NC0024392_Regional Office Historical File Pre 2018 (6)

Du Po R Go d
P.O. Box 33189
cxARLoTTE, x.c. 28242 'I
TE)U
�•ktiIa ):
r 28, 198
Paul, Wilms, Director
n of Environmental Management
ent of Natural Resources and
mmunty Development
ox 2`I687
NC 27611.
McGuire Nuclear Station
Renewal of NPDES Permit NCO024392
File: MC-702.13
Wilms:
e subject permit require submittal of an a
5t 180 clays prior to expiration.
ybject; permit and a check (no 158304) for $200.00 for
sine fee. We request notification that the application
you have any questions or desire additional info at
t R. T. Simril [(704) 373--2310 ] .
ely,
£C'u kr, ice President
r Production Department
/rhm
ores
Document Control Desk

r C1Li l NJ7iAw:%
W*dwvia Bank a Trust Company P.O. $OIL 33
Chadoae, N.C. CHARLOTTE, NORTH C.
DATE
12/21/88
PAY 00%
rO T14E
„ ., .._. 3F ATUK L RC URC
3 i D ELBPMENT
7
NC 27611
-.%J PA.NY BECK i
19 158
FtOI INA 28242
PAY ******200.00

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=RONT
leaks, or spills, are any of the discharges described In Items II -A or 8 intermittent or seasonal?
:te the folic wmg table)
NO lgri to Section 1111
3, FREQUENCY
A. FLOW
2, OPERATION(Si
a, FLOW RATE
8 DAYS b. MONTHS a,mgd)
I
b, TOTAL VOLUME
(specify with wnits,i c� OUR-
:ONTRIBUTING FLOW
PER W EEK PER YEAR - --------
- ATiON
fsp�,Cf% MAXIMUM
ai,craz, 11 1. 1 DAILY
1� LONG TERM
AVERAGE
21 ..Xlmum
I DAILY Iin daysl
al metal cleaning
Frequency and durationicannot lie
predi
ted from past.
as necessary. Various
Need based on the theroal-hydraulic
performance.
systems cleaned/flushed'
any of the following:
hydrazine, citric acid,�
saris acid, oxalic acid,'
ium phosphate, soda ash
ascription of chemical
ng.)
Cooling Systems drain-'
The sy4tems ma drained individually
for note-routin
ontains nitrite,borax
maintel'ance . M i:urn irdividual
system volume *'s 30,00
riazole corrosion
gallon
ations in the applicable effluent guideline expressed in terms of production for other memne of operatiorill?
S fcomptete Ite"I 111-C) NO (go to Section IV')
`red "yes" to Item 111.8, list the quantity which represents an actual measurement of your level of production, expressed in the terms and units
3pplicallite effluent guideline, and indicate the affected outfalls.
1. AVERAGE DAILY PRODUCTION Z.AFFECTED
MATERIAL, CTC. OUTFALLS
A DAY ti, u-Ts SURE C, OPER^T flint outtall numbers)
OF MEASURE
-P you tow required by any Federal, State or local author ty to meet any .mplementatron schedule for the construction, upgrading or operation of waste -
ilea treatment equipment or practices or any other environmental programs which may affect the discharges described in thts application? This includes,
it is not limited to, permit conditions, administrative or enforcement orders, enforcement compliance schedule letters, stipulations, court orders, and grant
loan conditions.
..�Yes icomplete the following table) No (00 to Item IV-B)
1 1 14AMA OF CONDITION. 2. AFFECTED OUTF^LLS I I P614. AMr. GATE
AGREEMENT, ETC, 3. BRIEF DESCRIPTION OF PROJECT
a. NO. to souac or eau i......� a. Re- t7 P*01.
N/A
ITIONAL: You may attacm additional sheets clescribmig any additional water pollution control programs (or other environmental projects which may affect
ur discharges) you now have underway or which yoj plan. Indicate whether each program is now underway or planned, and Inoicate your actual or
inned schedules for construcvon, ]MARK "X"IF DESCRIPTION OF ADDITIONAL CONTROL PROGRAMS IS ATTACHED
arm 3510-2C (Rev. 2-857 PAGE 2 OF 4 CONTINUE ON PAGE

[Dyes (list all such pollu tan ts below) :21NO (go to Item VI-B)
PAGE 3 OF 4 CONT

SM1tSWP JLRAINFALL
NOFF
-LAKE LOW LEVEL
1' I
NSW ' 200
NORMAN
INTAKE
SYSTEM
� t
La r
CW
1727100
SYSTEM
CONY. 6600'
LPSW
SYSTEM
OUTFALL
--
FILTERED
250
DEMIh.
REACTOR
LIQUID
1763808
LAKE
1734000
WATER
WATER
COOLANT
RADWASTE
SYSTEM
SYSTEM
SYSTEM
PROCESSING
NORMAN
BACKWASH REGENERATIVE
O iTFALL-
WASTE
t 001
FIRE
ISO
SECONDARY
PROTECTION
& AUX,
1
COOLANT
200
SYSTEMS
LAKE
LPS
SANITARY
STEAM GEN.
BLOWDOWN
TURBINE
CONY,
NORMA
INTAKE
POTABLE
WATER
BUILDING
SUMPS
WASTE
WATER
LEAKAGE R
— -
TREATMENT
DRAINAGE
14
INTAKE
METAL CLN.
SCREEN
WASTES
GUTFALL
BACKWASH
GOND.
002
OEMIN,
BACKWASht
COWANS FORD
TREATMENT
DIG SUMPS
DAM UNDERDRAIN
SYSTEM
DISCHARGE
L����SEWAGE
OUTFALL
2$2
0
003'
2E3
OUTFAL:L
WWCB
16t#B
005
CATAWBA
RIVER
RAINFALL
102
RUNOFF
NOTE. ALL FLOWS ARE IN GPM
DUKE POWER COMPANY
FOR AVERAGED CONDITIONS.
MCGUIRE NUCLEAR STATION
EVAP, &
00 NORMAL FLOWPATH
SEEPAGE
WATER :FLOWSCHEMATIC'
— -- i ALTERNATE FLOWPATH

NPDES
Supplemental Information
for
McGuire Nuclear Station
December 22, 198

TABLE OF CONTENTS
Page
STATION INTAKE
3
Surface Intake -
3"
Subsurface Intake
3
NUCLEAR SERVICE WATER
Containment Spray Meat Exchangers
CONVENTIONAL LOW PRESSURE SERVICE WATER
5
FIRE PROTECTION 'SYSTEM
5
Condenser Cooling Water
OUTFALL 002
Water Treatment Room Sump
8
Filtered Water System
8
Drinking Water System
g
ieminerali ed Water System
Turbine Building Sump
S
Diesel Generator Room Sumps
10
Lab Drains
10
Floor Wash
10
Condensate Polisher Backwash
10
Condensate Polisher Element Cleaning
11
Wet Lay-up
11''
Auxiliary Electric Boiler Blowdown
12
Groundwater Drainage System
12
CCW System Unwatering
12
Standby Shutdown Facility/Closed Cooling Systems
12
Stearn Generator Cleaning
13
Miscellaneous System/Component Cleaning'
13
OUTFALL 003
1
OUTFALL 004
15
Floor, Equipment, and Laundry Drains
16
Ventilation Unit... Drains
17
Chemical Volume and Control System
1.7
Standby Nuclear Service Water Pond
18'
Sanitary Waste Treatment System
18
Lab and Floor brains
18
Administrative Building drains
18
CCW System Unwatering
18
Yard Drains
19
COWANS FORD DAM UNDERDRAIN SYSTEM
1
APPENDIX: Boren Use and Control
20
2

The McGuire Nuclear" Station is a two ( unit nuclear fission steam
electric generating station. It is owned and operated by Due Power
Company. Each unit is a four loop pressurized water reactor.: Reactor fuel
is zircaloy clad sintered uranium oxide pellets. Reactor heat absorbed by
the Reactor Coolant System produces steam in four (4) steam generators
sufficient to drive a turbine generator unit with a design net electrical
rating of 1180 megawatts.
The nuclear ruction is controlled by control rods and chemical neutron
absorption. Boric acid is used as a chemical neutron absorber and to
provide borated water for safety injection. During reactor operation,
changes are made in the reactor coolant boron concentration. Appended is a
description of how boron concentration changesare implemented.
schematic diagram of water use and discharges indicating average rates of
flow for individual wastestreams of McGuire Nuclear Station is attached.
Actual flows through individual systems may vary significantly depending on
operational needs and meteorological conditions. Normally, liquid radio-
active waste are discharged only -;.through Outfall 004. However, it is
possible for any of the discharges to be contaminated by low levels of
radioactivity. All discharges of radioactivity are regulated by the Nuclear
Regulatory Commission in accordance to 10 CFR Part 20 and 10 CFR Part 50.
The following is a brief description of the major systems.
STATION INTAKE
All water for McGuire Nuclear Station is withdrawn from Lake Norman through
a duel intake system - a surface and a subsurface system. These systems
supply the lain Condenser Cooling Water (CW), Conventional Low Pressure"
Service Water, Nuclear Service Water, Fire Protection System, and Filtered
Water Make-up.
Surface Intake
McGuire Nuclear Station has two (2) power generating units with four
(4) CCW pumps per unit. There are two (2) intake screens per pump for
a total of 16 screens. The intake screens are backwashed on an
intermittent basis to prevent pressure differential buildup across the
intake screens. The frequency of cleaning is determined by the amount
of debris on the screens. The normal frequency is daily. Approximately
8,500 gallons of water are used to backwash each screen.` The water is
returned to Lake Norman at the intake bay. The debris collected from
:the screens is placed in sanitary containers and transported to a
licensed sanitary landfill. No chemicals are used in the "backwash
water.
Subsurface Intake
The subsurface lint ( Low Level Intake) is located near' the bottom of
Lake Norman at Cowans Ford Dam. There are six (6) low` level intake
pumps with a capacity of 150,000 gpm each. This pump system pumps cool
water` from the lake hypolimnion and mixes it with the warmerwater in
the surface intake structure during times of high lake surface water
3

temperatures. The Low Level intake is also the primary source of water
for the Containment Ventilation Cooling Water System and the Nuclear
Service Water System.
NUCLEAR SERVICE WATER
The Nuclear Service Water System is a safety related once -through non -
contact cooling water system. The Nuclear Service Water System supplies
cooling water to various heat loads in both the primary and secondary
portions of each unit. There are two (2) pumps per unit (four (4) pumps
total) that are capable of delivering 17,500 gpm per pump. The water supply
is f rom Lake Norman or the Standby Nuclear Service Water Pond. Water from
Lake Norman can be supplied by the main condenser circulating water system
from the surface intake or by the Low Level Intake. The normal source of
water is the Low Level Intake system. The normal discharge is to Lake
Norman through Outfall 001.
The Standby Nuclear Service Water Pond (SNSWP) is a 34.9 acre pond designed
to provide water for the safe shutdown of the station in the unlikely event
that Cowans Ford Dam is lost. The level in the pond is maintained, per
requirements of the McGuire Nuclear Station Operating License Technical
Specifications, by pumping water from Lake Norman into the pond. The pond
overflows to the Catawba River via the Wastewater Collection Basin (WWCB,
Discharge 005). The pond also receives runoff from a drainage area of 171
acres. When the Nuclear Service Water System is aligned to take suction
from the SNSWP, discharge is back to the SNSWP. This recirculation mode is
normally implemented for three (3) hours every six (6) weeks. This testing
frequency can change based on the results of the test.
As a result of accelerated corrosion of the nuclear service water system
piping, a corrosion inhibitor program is being considered. Corrosion
inhibitors under evaluation include zinc, nitrites, polyphosphates,
phosphates, borateslysilicates, molybdates, benzotriazole (BZT),
toyltriazole (TT), and mercaptobenzothiazole (MBT). Low levels of one or
two of these corrosion inhibitors will be discharged at environmentally
acceptable levels. Macrofouling by Corbicula (Asiatic clams) can impact the
safe operation of the station; microbial influenced corrosion (MIC) has
caused failures of piping and heat exchanger tubing due to pitting. Non -
oxidizing biocides or chlorine (or sodium hypochlorite) will be used at
concentrations that result in environmentally acceptable discharge levels
to address macrofouling and MIC.
Containment S]2r!ly Heat Exchangers
As part of normal heat exchanger maintenance, one (1) of four (4) heat
exchangers per month is treated with an alkaline flush. These flushes
may consist of 1-2% sodium hydroxide, 1-2% sodium metasilicate, 1-2%
sodium carbonate, 1-3% trisodium phosphate, and 1% surfactant, solution
and an approved biocide. The waste volume is approximately 5000
gallons per cleaning. Approved biocides (sodium hypochlorite and
organic biocides) are used to control biological growth in these heat
exchangers. The flush water may be discharged via the Condenser
Cooling Water (CCW) System or the Standby Nuclear Service Water Pond
(SNSWP). Alternative flushes may be performed using mild organic acids
4

(citric, oxalic, or formic) if< needed to remove excessive corrosion
deposits or Corbicula. In this case, if treatment is necessary, the
waste can be directed to the Conventional Wastewater Treatment (WC)
system.
in order to mitigate corrosion of the carbon steel, wet lay-up systems
are being installed. Various corrosion inhibitor solutions including
zinc, ortho-phosphates, polyphosphates, polysilicat es, nitrites,
boraces, and molybdates may be used. organic biocides or sodium
hypochlorite (chlorine) will be added for biofouling control. The
corrosion inhibitor solution will be released during the flow balance
and heat exchanger performance testing.
CONVENTIONAL LOW PRESSURE SERVICE WATER
The Conventional Low Pressure Service Water System supplies low pressure
cooling water for various functions on the secondary side of the station.
The system takes suction from the condenser cooling water cross -over lines
and supplies cooling water to various motor bearings, seals, Tube oil
coolers, vacuum breaker valves, and blowdown separator. Discharge is back
into the condenser cooling water system. The Low Pressure Service Water
System is the supply for process water.
FIRE PROTECTION SYSTEM
The Fire Protection System provides the plant site with protection from
postulated fires. The system is equipped with two (2) 200 gpm jockey pumps
which take suction from the Condenser Cooling Water System. One pump is
capable of maintaining system pressure; however, the second pump is used to
supplement the jockey pump system capacity. In the event the jockey pumps
can no longer supply enough water to maintain system pressure, the three
(3) 2500 gpm main fire pumps will start sequentially. The fire protection
system is continuously chlorinated to a concentration of approximately 1-3
ppm to assure that Corbicula are not present in the system's piping. The
fire protection system is used as the source of water for bearing
lubrication and gland seal on the low level intake pumps.
System operability is demonstrated by periodically performing specific
tests on the system. A summary of the current testing schedule follows.
Monthly, the main fire pumps are started, then stopped, to assure
operability. Very little, if any, water is discharged during this
test. Each valve on each hydrant is stroked annually to assure proper
operation; no water is discharged. At this same time, each hydrant is
opened and flushed to verify flow. Very little water is discharged;
any water discharged flows across paved lots, dirt, or grass to yard
drains from which it discharges to the SNSWP or Wastewater Collection
Basin (WWCB). Generally twice per month, a valve at the farthest point
from chlorine injection in the system is opened, flushed, and the
water tested for chlorine to assure the system is properly
chlorinated. Administrative procedures are in'place to assure that the
water flows across dirt or grass to yard drains. This 'test is
performed only if the system is being chlorinated (i.e., the jockey
pumps are operating and the chlorine cylinders are open).
5

The transformer emulsifier system is tested annually. The transformers
are subjected to a wet or dry test, whichever is appropriate for that
particular transformer. Any water discharged flows across paved lots,
dirt, or grass to yard drains.
Also annually, the head curve for =each of the three (3) main fire
pumps is verified. For the test, each pump is isolated; the flow path
is from the lake, through the pump and a test header, and discharged
back to the lake. No chlorine is in the water since the pump is
isolated from the fire protection loop.
Every 18 months, the system is tested to verify sequential starts of
the pumps and automatic valve actuation. The water that is discharged
during the test flows across paved lots, dirt, or grass to the yard
drain system.
Every three (3) years, flow through the hydrant loop in the station
yard is evaluated to assure the hydrants maintain the proper pressure
and flow. The water discharged flows across paved lots, dirt, or grass
to the yard drain system.
There is a non -routine test performed at the discretion of the system
coordinator. During the test, several hydrants are opened
simultaneously to verify the velocity and chlorination level. The
water discharged flows across paved lots, dirt, or grass to the yard
drain system, and hence to the SNSWP or WWCB. Any chlorine residual
present should be dissipated by the chlorine demand of the water in
the SNSWP or WWCB.
Additional testing is performed on the system. These tests, however,
do not discharge any water. These tests include visual inspections of
the system to verify flow path by verifying valve alignment and to
verify the condition of the system and/or equipment. Other tests
include simulating conditions that will actuate alarms.
OUTFALL 001
Outfall 001 is comprised of the main Condenser Cooling Water (CCW),
Conventional Low Pressure Service Water, Nuclear Service Water, and Liquid
Radioactive Waste (Radwaste). Outfall 001 discharges into Lake Norman.
Condenser Cooling Water
The CCW System is a once -through non -contact cooling water system that
removes heat rejected from the main and feedwater pump turbine
condensers and other selected heat exchangers. Each of the two (2)
power generating units has four (4) CCW pumps for a total of eight (8)
pumps. The flow for each unit depends on the number of pumps operating
as shown by the following table.
Number of Pumps 22eratin2 Total Flow Unit (gpm)
1 254,000
2 640,000
3 867,000
4 1,016,000
6

The operational schedule of the pumps of each unit is a function of
the intake water temperature and the unit load. At 100 per cent load
and the intake temperature near its summer high, three and sometimes
four CCW pumps are used. When the unit load is less than 100 per cent
and intake temperatures are lower, fewer pumps may be needed.
Condenser cleaning is by mechanical means (trade name "Amertap"). This
system circulates small sponge rubber balls through the condenser
continuously. It may become necessary to institute chemical control
for macroinvertebrate infestation, general corrosion, and
microbiologically induced corrosion (MIC). Chemicals anticipated to be
added include chlorine (sodium or calcium hypochlorite), organic
biocides, dispersants, and corrosion inhibitors. The corrosion
inhibitors may include zinc, nitrite, polyphosphates, phosphates,
borates, silicates, and molybdates. Discharge concentrations will be
maintained below approved discharge levels.
A 316(a) study was submitted August 9, 1985 and a 316(a) variance was
granted October 18,1985. Plant operating conditions and load factors
are unchanged and are expected to remain so for' the term of the
reissued permit. A Lake Norman aquatic environment maintenance
monitoring program was implemented July 8, 1987. Duke Power Company is
not aware of any changes to plant discharges or other discharges in
the plant site area which could interact with the thermal discharge or
to the biotic community of Lake Norman. Duke therefore requests a
continuation of the existing 316(a) variance, or as modified by the
outstanding 316(a) permit modification request.
OUTFALL 002
Outfall 002 discharges treated wastewater from the Conventional Wastewater
Treatment (WC) System through a Parshall flume to the Catawba River below
Cowans Ford Dam. The WC system consists of a concrete lined initial holdup
pond (IHP, 200,000 gallons), two (2) parallel clay -lined settling ponds
(2.5 million gallons each), and a concrete lined final holdup pond (FHP, 1
million gallons). Normally, inputs are received in the IHP but can be
routed directly to an in-service settling pond. The IHP serves as a common
mixing point for all wastewater, a surge -dampening function to the
remainder of the system, and allows the heavy solids to settle for periodic
removal. Retention time in the IHP is 12 to 24 hours. Solids removed from
the IHP are dewatered and disposed of on a State licensed land arm or
landfill.
Flow is directed to the in-service settling pond through the chemical
addition building where caustic, acid, and/or other chemicals may be
injected into the water by a metering pump. Sulfuric acid and sodium
hydroxide are added for PH control or to precipitate various chemical
compounds. Coagulants may be added to facilitate the settling of lighter
solids. Additional treatment may include chemical oxidation with
hypochlorite (calcium or sodium) or catalyzed hydrogen peroxide. Retention
time for each, of the settling ponds range between 6 and 12 days. The
settling ponds can discharge to the FHP or directly to the Catawba River.
Treatment and discharge are normally on a batch basis.
7

The FHP is aerated and is used to remove any persistent oxygen demand or to
provide additional holdup capacity. The FHP retention time is 1 to 2 days.
The capability is available for recirculation intra- or inter -basin. Flow
to the Catawba River may be by gravity at a rate of approximately 200 gpm
or be pumped at a rate of approximately 500 gpm. The pH of the discharge
from the WC system is adjusted by the automatically controlled addition of
carbon dioxide.
The WC system accepts all nonradioactive plant waste except sanitary
sewage. The inputs can be contaminated with very low levels of
radioactivity. Any discharges of radioactivity are monitored and accounted
for, being regulated by the Nuclear Regulatory Commission (NRC). Inputs to
the system are from the turbine building sumps, water treatment room sump,
condensate demineralizer backwashes, standby shutdown facility (SF'), and
laboratory drains. Steam generator blowdown, wet lay-up, and the unwatering
pump discharges may be routed through this system.
Water Treatment Room S2M
Inputs to the Water Treatment Room Sump consist of drainage from all
equipment including pump seal le off and bearing cooling water
located in the Water Treatment Room. Other inputs include the
Diatomaceous Earth (DE) Slurry Tank drain, acid and caustic day -tank
storage overflow drains, carbon filter backwash and sluice, pressure
filter backwash, demineralizer regeneration waste, and backflow
preventer drains. In addition, floor wash and sample line flush water
are routed to this sump. Antifoaming agents and wax strippers are
routinely present in this waste stream. The drains in the plant
"boiler room" are also routed to this sump. The drains contain sodium
nitrite/borax/benzotriazole (BIT) corrosion inhibitor and microbiocide
due to lea off and sample purging from the HVAC systems.
Filtered Water Svstern
Water from Lake Norman is treated for both process and potable use.
Filtration is performed by DE filters. Water from the Low Pressure
Service Water System is treated with chlorine for disinfection
purposes and polyelectrolytes to coagulate colloidal material. The
water is filtered through one (1) 750 gpm DE filter while a second
filter is on standby. The filtered water is stored in three (3) 42,500
gallon Filtered Water Storage Tanks. When the administratively
determined pressure differential across the filter is achieved, the
filter is backwashed thereby removing the filter cake. The system
utilizes approximately 100 pounds of DE and 16 ounces of
polyelectrolyte per day. Backwashing requires approximately 3,000
gallons of water per day. Approximately every 2-5 years, citric acid
is used to clean the filter elements because of tube fouling. The
approximately 110 gallons per year of waste citric acid is collected
in drums -and treated with caustic to adjust the pH and precipitate any
metals that may be present. The waste is then discharged to the WC
system.
8

Drinking Water System
The Drinking Water System takes suction from the filtered Water
System and pumps it to the 5,000 gallon Drinking Water Storage
Tank. ;
Deminerali ed Water S stem.
The Demineralized Water System provides high purity water for
make --up to the primary and secondary systems and for laboratory
usage. There are two (2) carbon filters and two (2) mixed bed
regenerative demneraliers with a system design flowrate of 475
m. Normally, two (2) carbon bens and one (1) demineralizer is
in use while the other is being regenerated or is on standby.
The Demineralized Water System takes suction from the Filtered
Water System. The carbon filters remove organic substances and
any residual chlorine. These filters may be cleaned by
backwashing, steam cleaning, and rinsing. The cleaning occurs
twice per months 15,000 gallons of waster are used for the
cleaning. Each carbon bed is replenished every six to twelve
months.
With normal demineralied water requirements, regeneration of one
deminerali er occurs approximately every fire (5) days. To
regenerate the resins, sulfuric acid and sodium hydroxide are
flushed through; the: bed. At the ;present time, each normal
regeneration takes approximately 90 gallons of sulfuric acid,
400 gallons of 5 % sodium hydroxide, and 75,000 gallons of water.
The amounts of required acid and caustic will Crary as dictated by
operational requirements. ;The demineralier beds are surfactant
cleaned approximately two to four times per year, caustic soaked
annually, and brine soaked as necessary to remove foul is from
the resin. The frequency of cleaning may vary depending on the
need as determined by the quality of the water produced. The
deminerali er beds are sluiced and replenished approximately
every four () to seven (7) years.
Turbine SLiM
The Turbine Building Sumps receive inputs from leakage, drainage, and
liquid wastes from equipment and floor drains located in the Turbine
Building. inputs include Groundwater Drainage Sump, Auxiliary Electric
Boiler Blowdown, Steam Generator Blowdown, filter air handling units,
Diesel Generator Room Sumps, lab drains, ;floor washes, and condensate
polisher backwashes. dither possible inputs include CCW Un atering, and
steam generator wet lay --up. Chemicals that may be in this flow include
the following:
ammonia
hydrazine
morpholine (planned for future use)
nitrite bor- /ben otria ole (B T) corrosion inhibitor
m crobiocide
industrial cleaning products
laboratory chemicals
9

The Turbine Building Sumps normally are routed to the WC System.
However, if radioactivity limits are exceeded, these sumps can be
routed through,Radwaste or to the radwa to discharge point depending
on the treatment needed. Very low levels of radioactivity can be
routed to the WC System. All radioactivity is; accounted for and
regulated by the NRC.
Diesel C,enerator Room S s
The Diesel generator Room Sumps receive; inputs from leakage or
draining the diesel generator engine cooling water, fuel oil, and
lubrication systems. Each diesel generator room has two 2)
s ps . The smaller sump has a volume of 600 gallons and one (l )
pump with a capacity of 25 gpm. The Larger sump has a volume of
approximately 4,000 gallons, two 2) pumps with a capacity of 450
pm, and a third pump with a capacity of 50 gpm.
The diesel generator engine coaling water systems :have a volume
of 800 gallons each. The systems are treated with a mixture of
sodium nitrite, borax (sodium tetr orate), sodium bicarbonate,
and sodium mercaptobenothiaole (' Tto maintain a minimum
concentration of 2000 mg/1 nitrite. The system is drained and
flushed to the WC System approximately once per year.
Additionally, the fuel oil contains residualbiocide to reduce
bacterial breakdown of the oil..
Lab Drains
'here are several laboratories that provide analyses on the
processes within the plant and which drain to sumps that
discharge to the WC system. The discharges contain the standard
and typical laboratory chemicals used in analytical procedures
performed to verify the quality of process streams.
Floor Wash
The floors throughout the station are maintained by a contract
vendor. Products used to clean and maintain the floors consist of
the typical commercial products.
Condensate Polisher Backwash
Over time, trace impurities in the condensate system increase in
concentration. In carder to maintain the integrity of the
condensate system, the condensate is processed through powdered
.ion exchange resin. A condensate polisher is backwashed on an
average of once per day. The backwash contains approximately'
1 -20 cubic feet of resin, 120 milliliters of polymer, and
requires approximately 10,000 gallons of water. The resin may
contain trace quantities of radioactivity from primary to
secondary leaks. The NRC-approved Technical Specifications
specify whether the resin is to be treated in the WC System or by
Radwaste based on the amount of radioactivity present.
10

Condensate Polisher Element Cleanin
The stainless steel filter elements used in the Condensate
Polisher tube bundles will be acid washed to clean any
fouled elements. ]wring the cleaning process, the elements
will be placed in an acid bath consisting either of
phosphoric acid, oxalic acid, citric acid or self is acid.
Initially, ;because of its effectiveness, a twenty (0)
percent phosphoric acid solution will be used although the
option is available for switching to any of the ether three
() acids. Elements washed, with acid will be placed in a
rinse tank to remove the :bulk, of the acid adhered' to the
elements. From the rinse tank, the elements are backwashed
at a flaw rate of approximately 60 gpm can a, flush stand.
With 1218 elements per bundle, approximately 2400 gallons of
flush water will be generated monthly assuming one bundle is
cleaned each month. Wastewater from the acid and rinse tanks
will be routed to two () 500-gallon treatment tanks for pH
adjustment or metal precipitation utilizing a dilute sodium
hydroxide solution. Wastewater from the flush stand can be
routed to a holding tank of approximately 4000 gallons
before discharge. All waste will be discharged via a turbine
building sump to the WC System or Eadwaste depending on the
presence of radioactive contamination.
Wet Lau
Each of the four (4) steam generators per unit has a volume of
`0,000 gallons. Each unit is provided with a Steam Generator
Hlowdown Recycle System, Steam generator'blowdown is continuous
at a rate of approximately 5000 gallons per hour to maintain
acceptable steam generator water chemistry. The blowdown is
directed to either the condensate polisher demineralizer or to
the steam generator bl.owdown dexineralizer. If the blowdo n water
quality is unacceptable, it is discharged. It can be discharged
to the WC system or to radwste depending on whether it is
contaminated with radioactivity.
During normal operation hydrazine is added to the condensate
system for oxygen scavenging. The hydrazine concentration' is
maintained within a concentration range of 25- 200 ppb. Ammonia is
added for phi control. The steam generators and hotwell are placed
in wet lay-up if a unit is to be in cold shutdown for two days or
more; Each unit is normally shutdown on a 10 month cycle for
refueling.
Wet lay-up is the method used for protecting the steam generators
against corrosive attack during inactive periods. Chemical
additions are made up in a 150 gallon Conventional Condensate
Addition System tank. Normally, 55 gallons of 54 hydrazine and
0 gallons of aqua ammonia are made up for transfer to the steam
generators. Any remaining chemical solution is drained to the WC
system via the turbine building sump. prior to returning the unit
11

to operation, this wet lay-up solution (75- 50 ppm hydrazine) is
drained to the WC System or Radwaste via the turbine building
sump.
The hotwell on each unit has a volume of approximately 250,000
gallons. During each unit shutdown that is two days or more in
length, the hotwell is placed in vet lay-up. Maximum chemical
concentrations should be approximately 50 mg/l hydrazine with the
B adjusted to 10.2 with ammonium hydroxide.- Prior to returning
the unit to operation, this wet lay -pup solution is drained to the
WC system or Radwaste via the turbine building sump.
AuxiliaLy Electric Broiler Blowdown
The Auxiliary Electric Boiler; is supplied feedwdter from the
'condensate system which contains hydrazine and ammonia. Trisodium
phosphate is added as an electrolyte. The blowdown from the
boiler contains these three chemicals and approximately
1, 000- , 0 0 ppb suspended solids. Blowdown is routed to the WC
System via the Turbine Building, Sump. The system is used
approximately 10 claim per year.
Groundwater Drainage_ System
The Groundwater Drainage System is designed to relieve hydro-
static pressure from the Reactor and Auxiliary Buildings by
discharging groundwater collected in sumps to either a yard drain
or the turbine building sumps. There are three (3) groundwater
sumps with two () 2 }- m sump pumps each. Two; of the sumps
'discharge to the turbine building sumps hi;.e the third sump
discharges to a'yard drain that is routed to the SNSWP.
CCW Unwate in
The CCW system for each of the two () units has a volume o
approximately 2 million gallons. Whenever a' unit is scheduled
down for refueling, periodically during rather shutdowns, and for
condenser tube leaks, the system must be unwatered for
maintenance purposes. The water is essentially lake water. The
principle discharge route is through the Wastewater Collection
Basis ( ), but it can: be routed through the WC System for
short periods of time.
Standby Shutdown FacilityZClosed Cochin stem
The Standby Shutdown Facility (SSF) is an alternate and
independent means to shutdown the station during emergencies
should the need arise. The independent power supply for the SS
is a diesel generator system. The S F contains a sump to collect
system leakage, floor wash, and drainage of the equipment for
maintenance. The coaling system for the- diesel generator system
is a closed cooling system. The coaling system is maintained at
approximately 2000 to 3000 ppm of a sodium nitrite/sodium
tetraborate/soda benotriaol.e (BZT) corrosion inhibitor. The
91

cooling system is flushed to the WC system annually to maintain
efficiency.
There are approximately 10 to 15 closed cooling systems within
the station. The largest system has a volume of approximately
0,000 gallons. The main portions of these systems are
constructed of carbon steel. A sodium nitrite (2 00 mg/l)/borax
(sodium tetraborate)/sod ben atria ole (BZT) corrosion
inhibitor is added to control corrosion. An organic biocide is
added to control biofouling. These systems may need to be
drained, individually, for non` -routine maintenance.. should this
occur, these systems would, be drained to the CCW discharge, WC
System, or Radwaste if contaminated with radioactivity.
Steam generator 21±Aninq
Each electrical generating unit contains four (4) steam
generators that have a capacity of approximately 40,€00 gallons
each. There have been no chemical cleaning of the steam
venerators to date. However, whenever a chemicalcleaning is
performed, all four steam generators will be cleaned based on
need as determined by the the al -hydraulic performance. One
possible cleaning solution, based on previous experience,
consists of 15ammoniated ethylene diamine tetracetic acid
(EDTA), 1% CCI 80/. (a proprietary corrosion inhibitor), l
hydrazine and ammonium hydroxide fear pH adjustment. The spent
solvent may contain radioactivity, iron, and other metals in
trace quantities. It will possibly be treated by demineralization
and neutralization/ ; precipitation. Treatment will be either
performed in Radwaste' or the WC System depending on the level of
radioactivity. Additionally, rinse/passiv tion'( 00 ppm Hydrazine
with the pH adjusted to 10.2 with ammonium hydroxide) water will
be required. The rinse water will be: processed' followed by
neutralization/precipitation in the WC System. The process may be
modified for each cleaning depending on the scale deposited
within the steam generators. Other solutions may be utilized; in
the cleaning.
Miscellaneous System/Component CleaniE2
Other systems may need to be; cleaned periodically because o
scaling or plugging. Other components will be cleaned a
necessary for various fouling problems. Solutions utilised will
be these used in standard chemical cleaning methodologies.
Chemicals utilized by these methodologies, alone or in
combination, include the following.
Alkaline Boilout Solutions
non -:ionic surfactants
anionic surfactants
cationic surfactants
sodium hydroxide
soda ash
13

trisodium phosphate
sodium metasilicate
disodium phosphate
monosodium phosphate
sodium bicarbonate
Acid Solutions
hydrochloric acid
sulfuric acid
phosphoric acid
formic acid
hydro acetic acid
self is acid
citric acid
nitric acid
Acid Solution Additives
thiourea
ammonium bifluoride
oxalic acid
EDTA Compounds and HE TA
pH adjusted tetra -ammonium EDTA
tetra -ammonium EDTA
di -ammonium EDTA
hydro xyethylenediaminetriacetic acid
tetra -sodium EDTA
Miscellaneous g2Mp2unds
chlorothene
sodium chloride
potassium permanganate
aqua ammonia
ammonium persulfate
sodium nitrite
antifoam
sodium sulfite
chlorine
corrosion inhibitors(e.g., phosphates,
borax -nitrite, silicates, etc.)
organic biocides
These solutions are described in the Devel2pment Document for
Effluent Limitations, Guidelines and New Source Performance
Standards for the Steam Electric Power Generatinq Point Source
Cateqory (Development Document).
The spent solvents from these cleanings will be treated in the WC
System or the Radwaste System. The acid compounds will be
14

neutralized; the other compounds will be mixed, oxidized, and/or-
precipitated as necessary for treatment.
OUTFALL 003
Outfall 003 discharges treated sanitary waste from the Sanitary Waste
Treatment System to the WWCB. The Sanitary Waste Treatment System is a four
() cell aerated lagoon system. The system was designed to process domestic
sewage from rest rooms, showers, lab drains,, and station cafeteria. The
lagoon provides a 5-day retention time and will allow for variable level
discharge. The wastewater effluent from the aerated lagoon flows through
chlorinators, a chlorine contact chamber and a Parshall flume
before discharging to the WWCB.
The lagoon is lined with a flexible synthetic material such as h alon it
is divided into four (4) cells by a curtain material such as a polymer
coated polyester with a weighted chain ballast and floatation collar. The
first: cell provides for a two day retention time and is kept in complete
suspension by surface mechanical aerators. The second and third cells are
kept partially suspended providing for partial settling. Each of these two
cells has a retention time of one day. The final cell is the settling cell
with a retention time of one day. The surface of this cell is'kept slightly
agitated to minimize algal, growth. If it becomes necessary to control algae
growth, an algicide, such as CUTRINF-PLUS, may be added to the lagoon. From
the final cell, the wastewater discharges to a chlorination installation.
After passing through the chlorinators, a retention time in excess of 30
minutes is provided by a contact chamber before being discharged to the
CB.
The sewage lagoon has a multiple level discharge capability at 5 1/2,
and 8 feet. At each of these different levels of operation, the lagoon is
le to provide a 5-day retention time for influent wastewater flaw rates
of 40,000 gpd, 52,000 gpd, and 64,000 gpd, respectively.
Accumulated solids are removed from the lagoon approximately every 12 to 18
months to facilitate removal of non -biodegradable material and to optimize
the treatment process. The sludge bottoms are +dewatered utilizing a filter
press or other suitable method. The solids are treated with lime and
disposed of in a State licensed landfill or landfarm. The filtrate is
returned: to the sewage lagoon or is treated by neutralization and carbon
adsorption or other suitable methods when released directly to the WWCB. An
alternative method of sludge disposal is to tank it to a municipal sewage
treatment system.
OUTFALL 004
Outfall 004 discharges flow from the liquid radwaste system. This flow
combines with the C before discharging through the concrete discharge
structure (Outfall 001) into Lake Norman. All radioactive and potentially
radioactive liquids are collected, segregated and processed prior to
release. 'These effluents are classified as recyclable or non -recyclable
liquids. Recyclable liquids are recirculated Haack to the process streams.
Non -recyclable liquids are collected and processed to Nuclear Regulatory
Commission (NRC) requirements (8 CFR Part 20 and 10 CFR Part 58) prior to
1

release with the type of processing depending on the type of waste. The
maximum discharge rate from radwaste is '150 qpm. The discharge flow for a
Taste Monitor 'lank release is a function of activity level, the number of
C:CwW pumps in operation, and the resultant boron concentration in Lake
Norman.
The liquid radwaste system collects waste in, three () sub -systems (floor
and equipment drains, laundry waste, and ventilation unit drains).
Chemicals that may be present in the liquid radwaste system include:
boric acid
borax
nitrate
Sonia
morpholine (planned for future use)
lithium hydroxide
ethylene glycol
benotriaole (ZT)
nitrite/borax corrosion inhibitor
hydrazine
chlorine/hypochlorite
hydrogen peroxide
ethylene diamine tetracet.c acid (EDTA)_
containment spray heat exchanger lair -up chemicals
pump bearing cleaning chemicals
laboratory chemicals
detergents
surfactants
olyelectrolytes
:industrial cleaning products
chemical metals cleaning waste
The Turbine Building Sump; can become contaminated with radioactivity. When
this occurs, it can be pumped to the :door Drain. Tank ( ') or to the
Radwate release paint in the CCW crossover line. The decision: on the
method of treatment depends on the amount of radioactivity in the waste
stream. Any chemicals listed as being in the Turbine Building Sump may be
in Radwaste when the waste stream is routed to Rad aste. Any solids
generated in the treatment process are solidified or dewatered and
transported to a State and NRC licensed low level' radioactive waste
disposal facility.
Floor,,EqLiipment, and Laundr Trains
All floor drains in the auxiliary building, drains from all equipment
(pumps, tanks, heat exchangers, etc,) which process aerated
radioactive waste, waste from showers in the change rooms and washing
equipment which is used to decontaminate protective clothing, and
waste from the Unit 1 and Unit 2 containment floor and equipment sumps
are routed to the Floor Drain Tank (FDT), Waste Evaporator Feed ".Dank
(WEFT), Auxiliary Floor gain Tank ( DT), Auxiliary Waste Evaporator
Feed 'Tank (A FT) , <and/or Laundry and riot Shower Tank (LMST) . The
total tank' volume is 125,000 gallons. "These collection tanks are used
16

ri
interchangeably and/or as backup and surge capacity for waste
collection upstream of processing.
Waste from these collection tanks is then processed using filters
and/or demineral.izers. The processed effluent is collected in waste
niter tanks for sampling and analysis prior to release. Release i
to Lake Norman via the CCW crossover line.
Ventilation Unit Drains
The Ventilation Unit Condensate Drain Tanks (VUCDT) collect condensate
from air handling units from each reactor building. Each VUCDT has a
volume of 4,000 gallons:
This waste typically has little radionuclide contamination and no
chemical contamination. The waste is sampled for radionuclide
contamination. If this sampling indicates the need, the VUCDT contents
are transferred to the FDT for processing. If no need for processing
is indicated, the waste is released from the VUCDT via the CCW to Lake
Norman.
Twice per year 'a portion of the ice in, the 'annulus in the reactor
building is melted and drained to the VUCDT. The VUCDT could contain
boric 'acid from the ice melt,
Chemical Volume and Control System
The Chemical Volume and Control System regulates the concentration o
chemical neutron absorber in the Reactor Coolant System to control
reactivity changes and maintain the required water inventory in the
Reactor Coolant System.. Soren is used as the chemical neutron
absorber. Appended is a description of the changes in the boron
concentration.
Other control elements introduced into the Reactor Coolant System by
e Chemical Volume and Control' System include lithium and hydrazine.
Approximately 120 pounds of lithium hydroxide monohydrate are used in
each unit per year for pH control. The lithium is removed by
demineralizers in the Reactor Coolant System of the liquid radwate
system. During cold shutdown, hydrazine is used as an oxygen
scavenging agent. It is removed during start up and is not used at any
other time. During shutdown, hydrogen peroxide is added to the Reactor
Coolant System to facilitate the removal of activated corrosion
products.
OUTFALL 00
Dutfall 005 discharges flow from the Wastewater Collection Basin ( C ).
The WWCB is a 13.4 acre collection basin having a total capacity of
approximately 40 million gallons, drawdown capacity is approximately 11
million gallons. Discharge from the basin ranges from 0 to 20,000, gpm. If
the Standby Nuclear Service Water Pend (SNS ) is being flushed, no holdup
of the WWCB is possible; otherwise,_holdup is minimal. The WWCB provides
17

sedimentation, natural neutralization, and skimming. The overflow from the
WWCB mixes with the discharge from the WC System (Discharge 002) in a
concrete apron and is discharged to the Catawba River downstream of Cowans,
Ford Dam. An algicide, such as CUTRINE-PLUS, may be needed to control algae
growth in the pond.
Inputs into the basin include overflow from the SNSWP, treated sanitary
waste effluent, yard drains, a lab sink and floor drains, miscellaneous
Administrative Building drains, and CCW system unwatering.
Standby Nuclear Service Water Pond
The SNSWP is a 34.9 acre pond designed to provide water for the safe
shutdown of the station in the unlikely event that Cowans Ford Dam is
lost. The level in the pond is maintained, per requirements of the
McGuire Nuclear Station Operating License Technical Specifications, by
pumping water from Lake Norman into the pond. The pond will receive
runoff from a drainage area of 171 acres. The containment spray heat
exchanger cleaning solutions may occasionally be routed to the SNSWP.
Sanitary Waste Treaeat stern
The sanitary waste treatments system is a four (4) cell aerated lagoon
system. It provides approximately 5 days retention and allows for
variable level discharge. The effluent flows through chlorinators, a
chlorine contact chamber, and a Parshall flume before discharging into
the WWCB. The sanitary waste treatment system is regulated as
Discharge 003.
Lab and Floor Drains
The lab sink and floor drains discharge approximately three (3) liters
of chemical waste per month. These chemicals are standard and typical
laboratory chemicals used in analytical procedures performed to verify
the quality of process streams. Flow from these drains go to a
groundwater sump then to the SNSWP and then to the C.
Administrative Buildin2 Drains
The Administrative Building drains include an HVAC sump, floor drains,
hot water boiler and chilled water system discharge. Any chemicals in
the drains would include the typical commercial products used to clean
and maintain the floors as well as sodium nitrite/borax/benzatria zole
corrosion inhibitor, phosphate corrosion inhibitor, and microbiocide
from leakage/drainage of the HVAC systems.
CCW System Unwaterin2
The CCW System for each of the two (2) units has a volume of
approximately 2 million gallons. Whenever a unit is scheduled down for
refueling, periodically during other shutdowns, and for condenser tube
leaks, the system must be unwatered for purposes of maintenance.
Unwatering must continue while maintenance is performed because of
leakage by the valves in the approximately 11-foot diameter CCW
18

piping. The maximum unwatering rate is approximately 2000 m; the
water; is essentially lake'water. Discharge is via the turbine building
sumps. Administrative controls are in palace, however, to restrict
inputs to the sumps during unwatering. Treated liquid radioactive
waste effluent (Discharge 0 ) discharges into a crossover line
between the CCW system of the two units. During unwatering, the
possibility exists for trace amounts of radioactivity to be released
into the water from the unwatering process because of isolation valve
leaf -by. All radioactivity is accounted for and regulates by the NRC.
The principle discharge route of the unwatering is through the WWCB.
However, it may be routed through the WC System for short periods` of
time.
Yard Train
Most yard drains discharge to the WWCB or SNSWP. The drainage area for
the plant site is approximately 250 acres.
COWANS FORD DAM UNDERDRAIN SYSTEM
The Cowans Ford Dam underdrain system discharges flaw to a ravine that
leads to the Catawba` River. prior to the construction of Cowans Ford Dam
and McGuire Nuclear Station, there were indigenous springs in the area.
When the dam, and subsequently the station, were constructed, the dam
underdrain system and the springs/groundwater in the vicinity of the Low
Level Intake Pump structure were collected and piped assay from the area.
Part of the water was piped to a ravine. The water is believed to be lake
or groundwater based on the quality of the water as demonstrated by the
Fart i analyses: Fire protection water is used as bearing lubrication and
gland seal water for the Low bevel Intake pumps. This water is processed by
cyclone separators to remove any silt or sediment that could damage the
pumps. The drains from the separators discharge into the underdrain system.
Yard drains in the area discharge through this systems
19

APPENDIX
Boron Use and Control
Boric acid is used as a chemical neutron absorber in the reactor coolant
system scar;; reactivity control and to provide water for safety injection.
During reactor operation, changes are made in the reactor coolant boron
concentration for the following conditions:
Reactor start-up - baron concentration must be decreased from shutdown
concentration.
Load followboron concentration must be either increased or
decreased following a change in load.:,
Fuel burn -lap - boron concentration must be; decreased to compensate
for fuel burn-up and the buildup of fission
products in the fuel.
Cold shutdown - baron concentration must be increased to the cold
shutdown concentration..
The concentration of boron in the Reactor Coolant System varies from g to
2500 ppm depending on core life.
The boron concentration is controlled through the Chemical and Volume
Control System. The boric acid is stored in the Concentrated Boric Acid
:storage Tank at a concentration of 7C}00 -' ,"700 ppm boron. The boron
concentration in the Reactor Coolant System is varied by blending reactor
makeup water from the Reactor Makeup Water Storage lank and boric acid from
the Boric Acid Storage Tank as needed to reach the desired concentration.
Excess liquid effluents from the reactor coolant system which contains 0 to
2500 ppm boron are diverted (or letdown) to the Recycle Holdup Tanks in the
Boron Recycle System, Water from the Recycle Holdup Tanks can be processed
as a batch through the boric acid evaporators where the boron is recovered
and recycled to the boric acid tanks.'Any boric acid that is not of
sufficient quality to be recycled is processed further in the Radwate
System. It is further concentrated, solidified, and transported to a State
and Nuclear Regulatory Commission C)licensed love level radioactive
landfill. The distillate: from the evaporators is ;either returned to the
Recycle Water Holdup Tank or transferred to the ReactorMake-up Water
Storage Tank.
Water containing boron can also be released to the monitor tanks for
discharge as a result of system leakage and flushing operations. The
maximum concentration of boron that can be present in the liquid radwaste
system discharge is estimated to be 200 ppm. The maximum release rate from
the liquid radwaste system is approximately 150 gpm. The liquid radwaste
system discharges through a valve" which is controlled by a radiation
monitor and flow meter. This valve is designed as an interlocking device
which will not open unless the radioactivity is within limits specified' by
the Nuclear Regulatory Commission in lg C"R Part 20 and a minimum flow rate
is established in the CCW System so that the offsite dose will be within
2

limits specified in 10 CFR Part 50. The resulting concentration in Lake
Norman is Less than 0.75 ppm as specified by the Administrative Limits.
1

`(Ti-M V-0 CONTINUED FROM FRONT I 'MCI a-0 1
I> POLLUT-
2. MAfaft
3, EFFLUENT
4, UNITS
S. INTAKE (irk titan d)
ANT AND
AS NO
a, r�#c
1e[v C'.
i.4.xe . ._..
L##.VYh a, MAXIMUM L'f AiLY
.. .. ,....
YAC�C,iE
ii MAXIM M 3,q{ p {y��Y' VAC.I.JE C.C. C. '�+p- V A UE
(a( fPt#fii2Cbi?fC.' : {iF #Ii!dX1fCl 4r�' f1. NCi Cif 8. G"QNC �S+i�'
:
a YANG re"M
A4ii E.F�l�IFV VAL.. 4i E.
"
4 NCA. Of"
fit aiaaddabia)
ro r#.
s e«r
An- ...., ._....w.»...
# r r
t <.11FY"t N'NtiiA�:tt4N
........._._.,.....
r
Flk !e#K!n i5
_ ..._ �........w ...._. ANAL,
—1-1—N Fi'i MASB #SOW %1-111T11— # WY R±i4 Y4'f, �h
TO TION
h, M ASS
,,.,�.. ,„.. ....... �.
C i•"c' nrt if hYixs.N !I Mp"«'4
ANAL,
/ Yf: .4 .
g. NItrogsn,
41,252
_....
...
_ .
Total Organic
t
CCi
/
I +
C . FJ
(as N)
_ ..
_
_ _
h. Off and
x
13 w
1,627
1
lb/Day
.13 ,
i. are
�
f
yya0 yP)yy, Tottalal
x
< a
1�
m
l
< . 0 <
1
). Radioactivity
Total I1
Ci/L
X
<a4 X
(2) Bata,
Total X <2 }( 1 pCi/L X2.1+.6 X 1
(3) Radium,
Total { 0.'9±. 2 X 1 pCi/L X <1.5' X 1
(4) Radium
226. Total x .3±. 2 x 1 i /L X 1.4±.4 X 1
Sulfate
( $04) X 9.2 115,161 -1 mg/L 1 b/D,aiy 9.6 187,462 1 1
. i5u)fklw'
(419) X <1 <12, 51 1 m /L l b/Dav <1 <19. 527 1 1
-
x
<2
<25,035
1
m /L
lb/D y
<2
<39,055 1
3)
". Surfactlertt
X
<.2
< ,50
1
1b/Day
<.2
<3,905 1
X
72
9,013
1
±mg/L
l b/Daa--15)61
11,912 1
P.
Total
(1440-; -)
X
02
250
l
m j L
l b/11i y
.02
390 1
.ran
Total
(7440-4 -a)
X
. 09
1,126
1 :
mg/L
1 b/Day
,11
2,14 1
Total 4is4)
X
<.1
<1,252
1
mg/ L
lb/Day
<,1
<1,953 1
a. Iron, Total
("743+3.89)
x
44
5f 50
1
m /L
1b/Da
.3
5,058
1
Total
X
1.2
15,021
1
mg/L
1 b/Day
1.2
23,433
1
u. Molybdenum,
Total
X
.09
1,1 6
1
m /L
l b/Day
. 07
1,367
1
(7439-91i:-)
i
Total ax
.04
501
1
mg L
l b/Day
390
1
(7439.96-5)
.02
W. tin, Total
44a .) 1.3 16,273 1 mg/L 1b/Day 1.2 13,433 1
x. T tan tam,
Total X .02 250 1 mg/L 1 b/Day .02 390 1
(7440.32-5)
1-
EPA Form 3510-2C (Rev. 2-85) PAGE'V-Z CONTINUEON PAGE V .3

EPA I.D. NUMBER (curry frarin Beer 7 Of Porto i) i>ti'Y"1.�ALL NUMBER
Fcsrrri Approved
CO0 4392 001 OM8 No 2040,0086
gxtaaxrvrrt expires 7 31.88
CONTINUED FROM feAE" OF FORM� .
PART C - If you are a primary industry and this outfall contains process wastewater, refer to Tabte c-2 in the instructions to determine which of the GC/MS fractions you mast test for, Mark .. "• in column
-a for all scach GC/MSGC/MS fractions that apply to your industry and for ALL toxic metals, cyanides, and total ()barrels. If you are not required to mark column 2•a (secondary industries, no"priocess
wastewater outfafls, anti tronrequired taL`1MS fractions). mark "X" in column -h for each pollutant: you kno or have reason to believe is present, Mark "X" in column -c for each pollutant you
believe rs absent. If youmark column a for any pollutant, You must provide the results of at least one analysis for that pollutant. If you mark column 2b for any pollutant, you must provide the results
of at least one analysis for that pollutant if you know or have reason to believe it will be discharged in concentrations of 10 pptr or greater. If you mark column 2b for <acrolem acrylonitrile, 2.4
door ophenol, or 2 -methyl-4, 6 dinitrophenot, you toast :provide the results of at least one analysis for each of those pollutants which you kirow or have reason to believe that you discharge In
cuncenn ahons calf pf,b or greater, Otherwise, for pollutants for whali you trrark column 2b, you must either submit ;at least one analysis ur br e;fly describe the reasons the pollutant is expected to
bar tltsc:lrar tied !Vote than there ate 7 pages to this part-, please review c ach carefully- Complete one table fall? pages/ for each outfall. See Instructions for additional dettails and requirements.
I, POLLUTANT L MA+4K 'sc 3. EFFLUENT 4, UNITS S. INTAKE foritionattj
AND CAS
: _p..
NiltvlL3E r'i a sr t>. +a c u+.- .MAXIMUM OAtL,r VALUE t3. MAr{rMtaM 3t! tF Y VALUE tit e.LCiNG T{" M }�j G, 6rAitrE rr. Nc?.Cit 8. LONGTERM
ka rt:? C
a ". +. c __.... ..„,.m„...,,.,. (it aval ,rt+0) f+1t ueiatr`kp tad0 _R d CONCEN ik.,�" VALUE
...... _... _,»..._.__ ._.. ,. ..__,.:. ._ ANAL.- Li,MASS ANAL -
fit
-te'atllalble) �. a++ ae `+ s+i'�r++ !+l tal MAlb l+l ttl. MA.0 ysus TRA'TIONl+l catae1ia- lzl MAUS YSES-
:. k..6.., ....,.._ M"t. N't NTRATION fit MASS CS71Y♦ tNT+ AtI." a. t.tNC E'N a• HAIfoF �.._ TRATme
METALS, CYANIDE, AND TOTAL PHENOLS
IAntimony,
Tc tall (7440.36 O) X <. 6 <7510 1 mg/L l b/Day <.-6 <11, 716 1
2M. Arsenic
17440 38 2I' Trust } <1 <12 1 pg/L lb/Day <1 <20 1
3 . Beryllium , . 002 25 1 mg/L l b/Day Total, 744p 41 7l .002 39
4M. Cadmium,
Total f744043-1 X .01 125 1 L l b/Day .01 195 1
SM. al (Chromium,7.3) X . 04 501 1 mg/L lb/Day .04 781 1
W CoWer, Total
(7440.60.8) X .04 501 1 mg/L lb/Day .03 586 1.
IM, IAW,Total y
17439-92-1l .08 m._1001 1 m /L lb/Da e.08 <1,562 1
of Skit, s t` Total X < 1 <1 1 pg L lb/Day < 1. <2
t. Nickel, TotalX <.0 <501. 1 /L lb/Da <.8 < 81 1
f7�t40-02o-oa of y
To al (778 Seleniva9'2l X <2 < 5 Mfg/L lb/Daye < 9 1
(7' t Silver, Total X <. 04 <501 1 m /L l b/Day <. 04 <781 1
1 M. Thallium, . 5 < 25 1 m L lb/Da <.5 <9 764 1
Total f7440- •ol 0 s
13M. Zinc, Total X009 113 1 m /L lb/Day .02 390 1
17440-66.61
14M, Cyanide,
X <.02 <250 _.1_ /L__. lb/Da <.02 <390 1
Total 15a7 1 5l 0
5M.Phenol$, X <.005 <62 1 m /L lb/Da <.005 <98 1
Total g
DIOXIN
*. .�3 7estY«5 C?ESGRIDE RESULTST _ �......__.._.._....�.:........_...........v.,:.._.__......:...__._....:..........._..�._ u.®...,.......w...:..:
cr luraa+rllaatalaaa tk X -
0tovin It7640161 NEG
ATIVE
EPA Form 510-2 (Rev, 2- S+I PAGE V•3 ; CONTINUE ON REVERSE

CONTINUED FROM THE FRONT MN a-001
1. POLLUTANT
AND CA
z> MAIMS
3. EFFLUENT
4, UNITIS
3, INTAKE f'raptionaf)
NtAECR
rN:* AriR4iY; 0J*vr
. Y
Mc vAcuE ccaN YMr�tVALUE d. NoloF
t#fa
CONCEN•b,
siri
VALUE
T�E9}�
b, NO.OF
ffp ###Ba
Aw<
FAt Fait
6ON+c ENtrNtl bN
($)MASS
:
ANAE-a.
o "A%$ VSES
C@NC Jffi NtMA tkt}N CONC C MtFt At1L)M. .'::
tT
ION
MA'
tit ht9C}H
M�
A a
ANAL -
*Sea
G FAA&I6k- VOLATILE COMPOUNDS
IV, A f*h't
I1#I7:°
X
<5
<62
1
fag/L
1 b/Day
<5
<98
2U�,1� �irl5fl
.
X
< 5
<62
X
<1
<12
1
g/L
1b/Day
<1
<20
1
4V fs eChlo r
m'Xy1f Ether
{J�
/i"k
�{
Fl
}
}
ll
�[
�(
(04 438.1) ;
fl
i4
Jk
ffV,'8 F{}rm
(76.25.2)
X
<1
<12
1
Mfg/L
1 b/Day
<1
<20
1
8V. Cerbon
Totrach)orfd*
X
<1
<12
1
/L
1 b/Day
<1
<20
1
(fib-3*)
7V. Chfo nz*na
(1 -90-7)
X
<1
<12
1
g/L
1 b/Day
<1
<20
1
@V. Chfor " ).
(bromomo
124- 1t)hime
X
<1
<12
_.w..
1
g/L
1 b/Day
<1
<20
1
OV. Chfor hank
(76- -3)
X
<2
<25
1
pg/'L
1 b/Day
<2
< 9
1
1OV.-Chforo-
I*t ylviny )Ether
X
<1
<12
1
g/L
1 b/Day
<1
<20
1
11 V> Chloroform
(87• -3)
X
<1
<12
1
g/L
1 b/Day
<1
<20
1
12V..01ehloro*
brromo tjthene
X ,
<1
<12
1
Mfg/L
1 b/Day
<1
<20
1
1311. %?fohfdro-
dflluorometh*n*
X
A
X
X
X
X
x
X
X
I7fI714f)
14W,1,1-otchloro-
«ne (1"4.3)
X
<1
<12
1
g/L
1 b/Day
<1
<20
.�.�
1
1sv, 1,2-01chforo
*then* (107-06-2)
X
<1
<12
1
g/L
1 b/Day
<1.
<20
1
16v, 1,1-01chloro•
otftyl*n* (75-3 .4)
X
<1.
<12
1
pgtp L
1 b/Dad"
<1.
<20
1.
171f. t,2.l�fchforca-
prop*ne (7 -87-)
x
<1.
<12
1
} g/L
1 b/D f,y
<1
<20
1:
18V:13•fi 2- t54-76-ff)
X
< 1
< 12
1
fag/L
1b/Day
<1
<20
1
f1.dE'#h4y)f*nz*n*
X
<1
<12
1
g/L
1b/Day
<1
<20:
1
20*-M yl
4rfr+fde {i . s)
X
<2
<25
1
fag/L
1 b/Day
<2
<39
1
L:*;�ethylelf^ide (7 7*3)
X
<12
1
Mfg/L
1 b/Day
<1
<20
1
EPA Form 3510- (Rory. -85)
PAGE V•4
CONTINUE ON PAR 71'

CONTINUED OR
EPA 1.0. "U ER (copy from Itent I of For 1) OU rFALL NUM19EFt
NCO024392 001
Form Approved,
OA48 No 2040 0086
i I
PAGr- v_4
Approval expires
7-31-88
1,POL4.UTANT
ANDCAS
2. MA"K'A'
I NOW
3. EFFLUENT
4. UNITS
ml ., OWN
flonw)
NUMBER
ok. c-
14,44 #'LVK
a. MAXIMUM DAlt.Y VALUE
b. MAXIM M 3&R/kjY VALUE
00 e
soar
VALUE
CLONG Tl�tpM A d No. - or
8, LONG TERM
It 040 of
(it available I
Or, pft�- As-
**,my
Lu ,
It
caft'LN't E RAYI : 0"
, , :
Iz)
���
ANAL-
I YSES
TRATtON
b� MASS ---
I toweaft.
11) **A**
ANAL-
YSS*
GCIMS FRACTION VOLATILE COMPOUNDS (continued)
22V. Methylene
Chloride (75.09-2)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
23V. 1,1,2,2-Totm
chloroathane
(79.34-6)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
24V. Tstrechforo-
ethylene (127.18-4)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
25V. Toluene
(108-88-3)
—1,2Trans—
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
ifivi'
Dichloroethylene
(156-60-6)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
'T7_V. _10.1 __i7fl
chloroothano
(71.65-6)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
chloroathano
(7900_5)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
29V. TrIchloro-
ethylene (79.01-6)
x
<1
<12
1
pg/L
lb/Day
<1
<20
1
30V, Trichloro-
fluoromethane
(76-69,4)
X
N/A
x
x
x
x
x
x
x
31VVinyl
Chloride (75-01.4) -
x
<2
<25
1
pg/L
lb/Day
<2
<39
1
GCJM$ FRACTION — ACID COMPOUNDS
IA. 2-Chloropheno!
(95-57-8)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
2A. 2,4-01chloro-
Phenol (120-83-2)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
3A, 2,4�Dirnethyl,
phenol (105-67-9)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
4A. 4,6-Dinftro-o'
Crosol (534-52,1 j
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
5A. 2.4-01rntro-
phenol (51-28.5)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
6A. 2-Nitrophenof
(80-75-6)
<10
<125
1
pg/L
lb/Day
<10
<195
1
IA. 4-Nitrophonol
(100-027)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
8A, P-Chloro-M.
ctasof (59,50-7)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
9A: Pontschloro
Phervol (87,86-5)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
10. Phenol
t15 2)
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
chlorop6o
(88 06-2) not
x
<10
<125
pg/L
7b/Day
<10
<195
1

3.tVVLULNT —7—c UNITS
IVILK
IT
IitateJoil
ruo k7i;;
To;;-
1 00 10010 fit
I 00""a
It) ".st
vsfs
8, co"crw
TRATION
t,-M^SS
'414 A, 4,
yscs
RACTION — BASEINEUTRAL COMFCiUNDi
x
<10
<125
1
pq/L
1 b/D.ay
<10
< 195
1
x
<10
<125
1
_pg/L
jA/Day
<10
<195
1
x
<10
<125
1
<10
<195
1
plracane
Idlna
x
<20
<250
1
lb/p.
<20
< 390
1
o (a)
X
<10
<125
1
pg/L
1 b/Day
<10
<195
1
W-32A)
x
<10
<125
1
lb/Qy_
<10
<195
1
to no
x
<10
<125
1
Vg/L
1 /Day
<10
<195
1
o (Ohl)
2) -
x
<10
<125
I b/Day
<10
<195
1
f- foars"T
(207-08-9)
<10
<125
1
pg/L
lb/Day
<195
1
108. Dis (2-Chloro.
ethoxy) Methane
(11191.1} -
X
A
r
<10
<125
1
pg/L
I b/Day
—<10
<10
<195
1
- ---
I Z) a efs(2 c
ethyl) th4�h toro-
fill-44-4)
x
<10
< 125
1
pg/L
lb/Day
< 10
<195
1
12t ft f2-Chkroilto-
wW#EtfwfIO2-WI)
X
<10
<125
1
pg/L
lb/Day
<10
<195
1
----
hexyl)
(117-01-7)Phtholsto
x
<10
<125
1
pg/L
1 b/Day
<10
<195
1
148. 4-9romo-
ph#nVIPh*rvVI
Ethel, (101-55-31
—0-ty,
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
Bgnzyl
<10
< 125
1
/L
1 b/Day
<10
1 <195
1
lss7-Chloro-
nophtholotto
1
< 10
<125
1
pg/L
1 b/Day
<10
<195
1
4-Chloro-
pho"VI ' pb4nvl
Ether 171605-72,3)
X
<10
<125
<10
<195
1
188. Chryssne
(216,01-9)
x
<10
<125
pg/L
<10
<195
1
198. Dlbonzii
-I
—lb/Day
Aothrocono
(63-70-3)
x
<10
<125
1
Wg/L
lb/Day
<10
<195
1
208.1,2-Dichloto-
benzene (95-50-1)
x
<10—
<125
1
pg/L
-lb/Day-
<10
<195
-F---F-
1
2M 1,3-Dichloro-
F1.8; I .4.3-Dl.jhl7-r-
_ 3_;
bonz*rnt (541-73-1
x
<10
<125
1
pg/L
lb/Day
<10
<195
1
EPA Form 3510-2C (Rev. 2-85)
PAGE V-6
CONTINUE ON PAGE V

• • VM Of
•
II :
..
n
e
1 •
(111-84�0)
IF a. Haxi-
tiltiorobutadlene
•
t.
t s
8
i
!!

C(11+iT)Nl1ECt FROM THE FRONT
1. !'C?L UTANT ' 2. r#v rr+t ^x*
3. EFFLUENT
. UNITS
5. INTAKE (f)iatiattatj
AND CAS
N l.i M i2 A ♦e •w iA ae C. wC.-
3WYn 3R.V#E# 4BMl+F
,_� _ _
at. DAILY V,t4LUiz.
�..;aXtMcMtv'a��u
f itL+ftt tt C
_.
c twcrnr Mi
F A8trt7t tt # P ff NO t9F
tf iiu
a. t t>rt��r*W
:A 4k'?N t: t r t'tM
t rt E
k'4 !� 4 C...Y.. 8- t,1,
Ix fat'# CAB'
�r
{tP iit3r d�94�' �t M. 9t NY *w"T
aat.....
.«.MAXIMUM_M. _......,. _.. ._
# f �i� MRhi
# l%t#NfA#AT#Ca�
_ „, ,_r!..,......-.-...,_...w,.;
t#� �i�:M A4±.
#33:WY1#AftdLN
_
_ .�......,� nrant.
tf� ( �- naU •®.•,• Ydet :Y:
C433akC itiA9F33M
�i����t�R*a
it ateici
�d� r'. A tit �.li MAY%
#ttA3tEY.f
xr+na
h'$rs
GC FRACTION -- BASEINEUTRAL COMPOUNDS UNDS (r#srA ismett)
WNW*-
li
d�y. gqhtytvi#yisrnfre
<10
<125
1
g/L
l b/Day
<10 <195
1
"0. Phoosothrone
(85=01.8)
<1.0
<125
1
g/L
l b/Day
<10 <195
1
no
i 29 P o x
<10
<125
1
dig/L
l b/Day
<10 <195
1
. 1,2,4 - TO-
x
<10
<125
1 -
g /L
lb/Day<10
<195
1
(12 2-1
QCNS FRACTION - PESTICIDES
1P. Aidrin
}
(-2)
2P. 4.9HC
1319.84-5) x
x
(1 -85.7)
4P�.t 1{jy}yBHC x
aP. 8.8HC °..,
x
(319.88 8) .
5P. Chiordsne
x
(67.74-9)
7P3.yy 4yy�,4*-- DT y]{}
8P. 4,4'.DDE
}
(72-55.9)
9P, 4,43-OOO
(72-54-8)
IOP, Wotdrin
x
(60.57-1)
11P. it•8ndorutfon
115-29.7)
i
12P. -8 osuifen
(115-29.7) x
12P.8ndosuifan
Suifoto
(1 1.07-8)
14P. Endrin
._
P
(72-2 )
15P.5ndrit
Aidohydo
(7421-93.4)
18p. Hootsehior
x
(7'6-44.5)
EPA Form 3610- C (Rev. 2-55)
PAGE -8
CONTINUE ON PAGE -9

ITIM V-0 CONTINUED FROM FRONT
MNS-002
I. PoLwr-
2� MA"*!I'X'
3, EFFLbENT
4, UNITS
5, INTAKE (t,11thowtj
ANT AND
CAS NO
wwVCcLW"" MAXIMUM MAILY VALUE
b MA I 'PAY VALUE VALUE
(11 W1011.
0010 LION It '�-
--�
a CONCEW
tl� MAS%
A t� EY2^NtC;r.'TVVA"LM1J E
Of
ANAL. -
P*V- 11
---,--T -
'T
-
tPI -�ASS
TT' --- -- - ANAI,
14-j MA�S 111-1) =- 111 '
"T'F4 ACT 10 N
1 111-
:I
Total Organic
fas N1
x
.57
3
1
mg/L
1 b/Day
<. 08
<1,562
--i
h� Off and
x
.33 1 .22 .5 2
mg/ L
1 b/Day
.13
2,538
1
W-
(A# r), Total
(7723-14,0)
x
08
4
1
mg/L
lb/Day
<.02
<390
1
1. RedloactivitV
(1) Alpha,
Total
x
<.9
x
I
pCi/L
x
<.4
x
1
(2) gout,
Total
x
5±1.4
x
1
pCi/L
x
2. 1±. 6
x
1
(3) Radium,
Total
<.5
x
1
pCi/L
x
<1. 5
x
1
(4) Radium
226, Total
x
<.1
x
1
pCi/L
x
1.4±. 4
x
1
x
430
2,225
1
mg/L
I b/Day
9.6
187,462
1
1. Suffide,
loot g)
x
< 1
< 5
1
mg/L
I b/Day
< 1
<19,527
1
x
< 2
<10
I
mg/L
I b/Day
< 2
<39,055
1
n. suffeatents
x
<.2
<1
I
mg/L
I b/Day
<.2
<3,905
1
0. Aluminum.
Total
(7429-90-5)
x
1
5
1
mg/L
.61
11,912
1-
WT
P To- U-M.
-lb/Day
Total
47440-39-3)
x
.04
.2
1
mg/L
I b/Day
.02
390
1
Total
(14010-42-8)
x
.34
2
1
mg/L
I b/Day
11
2,148
1
Total
17440-48-4)
x
5
1
mg/L
I b/Day
1
< 1, 953
1
a. Iron, Total
X
.3
2
1
mg/L
I b/Day
.3
5,858
1
Total.
(74" 05-4)
x
1.8
9
1
mg/L
lb/Day
1.2
23,433
1
U� Molybdonum,
Total
(1439-98-7)
x
.14
.7
1
mg/L
lb/Day
.07
1,367
1
v.
Total
(741111-915-15)
x
.07
.4
1
mg/L
lb/Day
.02
390
1
w. Tin. Total
(7440�31-5)
x
2.5
13
1
mg/L
lb/Day
1.2
23,433
1
x. Titan um,
Total
(7440-32-6)
x
.04
2
1
mg/L
lb/ Day
.0 2,
3 90 1
1 1
EPA Form 3510-2C (Rev, 2-85)
PAGE�V-Z
CONTINUE ON PAGE V - 3

CONTINUED FROM PAGE 3 OF FORM 2-C
:PA I.D. NUMBER (copy front lle»t 1 of Forth 1) OUTFALL NUMBER
Torn: Approved
t7M8 Atca 2040 0086
NCO024392 002 Approval expires 7 1.88
ran I k, - It you are apt omary mctusiry ano ttus outtait contains process wastewater, tefer to Talale 2c-2 in the instructions to determine' hi h of the GC/MS fractions you mustiest for. Mark'X mcolumn
2 a for all such GC/MS fractions that apply to your industry and for ALL toxic; metals, cyanides, and total phenols. If you are not required to mark column 2-a fsecondary industries. nonprocess
wastewater outtalls, and nonre uared taf~I MS fractions),` mark -X- in cotutrin 2-b for each pollutant you know or have reason to believe IS present. Mark "X" in column -c for each pollutant you
believe is absent. If you mark column 2a for any pollutant, you must provide the results of at teast one analysis for that pollutant; If you mark column 2b for any pollutant, you must provide the results
of at least one analysis for that pollutant if you know of have reason to believe it will be discharged in concentrations of 10 ppta or greater. If you mark column 2b for acrolein, acrylonittile, 2,4
dinitiophertrtl, or 2-methyl-4, fa dinittophenoi, you mist provide the results of at least one analysis for each (if these pollutants which you know or have reason to believe that you discharge in
concenti ations of 100ppbor greater. Otherwise, for pollutants for whtch you mark column 2b, you must either submit at least one analysis of briefly desrritte the reasons the pollutant is expected to
be dischatgwl Note that there are 7 pages to this part; please review each carefully. Complete one table (all 7 pages) for each outtalt. See instructions for additional' details and requirements.
t. FOLLUTANT Hamra 'X'
3a:N. EFFLUENT _ 4. UNITS Tit i\Tla. ANIN
TAKE (opthmal/
At -ID CA
NUMB b. MAXIMyM I?VALUE C,1-0NCTki VALUE . LONG TERM
[--
_ua ,MCK.Cta ii, 140
Cw 7 yc.". it CONCEN ANAL
acrtrla) a i°-HNA4TRATIOri t. MR55 Irp ccNcarNin a Its mAss rs M. teI MAU6 VSES
LL-1, - t""ATatN
METALS,
CYANIDE, AND TOTAL PHENOLS
i all ( Antimony, of X <. 6 <3 1 mg/L lb/Day < 6 <11,71 1
2M, Arsenic, Total
(7440 38 2) X 1. .006 1 erg/L lb/Day <1 <2( 1
3M. 8ary l l iu rn,
Total, 7440-4t-7) X .003 .02 1 mg/L 1 b/Day .002 1
AM. Cadmium
Total (7440 ci ) X .02 1 1 g/L 1 b/Day .01 19 1
5M. Chromium,
Total (744047-3) X .08 .4 1 /L 1 b/Day .04 781 1
(7440�60.8) Total X .1 1 mg/L 1 b/Day .03 586 11W Used, '
(7439«I X .18 - .9 1 mg/L 1b/Day <.08 <1,562 1
8M, Mercury, Total'
(7439.97-6) X <.1 <.0005 1 Ng/L 1b/Day <.1 <2 1
( 440--0Nickel,Total X < . 0 .5 1 m /L 1 b/D y < . 04 <781 1.
to . selenium (7782.4s� 2) <2 <. 01 1:.. pg/L lb/Day <2 <39 1.
7 sa lver Total
_X <.0 1 g;/L 1b ay <. 04 < 781 1
um
Total (7442. 0 a of X <. 5 <2 1. m /L 1b/Day . 5 <9,764 1:
13M. Zinc, Total
(7 40-5fa 6) X .03 .2 1 g/L 1 b/Day .02 390 1
t 4M. Cyanide,
Total(57.12-5} X <.02 .1 1 mg/L 1b/Day <' 02 <390 1
Total nia
�hats,
lX .005 .02 1Mg/L 1b/Day <:005 98 1
DIOXIN
tetra T TQESCRISE RESULTSw.
ciztoroUittc+rtcea i'
to as Tilt (1764 01 tit X NCGA 1 6
EPA Forn 3510-2C (Rev. 2.8 ) PAGE; V-3 CONTINUE ON REVERSE

CONTINUED FkIOM THE FRONT M[NS-00
1. POLLUTANT T
AND +GAS
2. M rtK 1x*
3 FFLUEN '
4. UNITS X
S. INTAKE fi)pti fsalj
F1l,tM iI
4,rant •c^ C. •a•
P» .rat
&. tk�AXIMUM DAILY VALU1�`
neat M317A.� VALUE c.c es� t y VALUE
ai at ittrm ah „.: �f. t�tCt. tt�
e, LONG TERM rM1
!> Ni?.C7i
5i( Oihl� lO ti dF
Out*- #*r#v **#4T
it)
C iXNC. #_##TMAT00N
(41 MA%%
`i� (1) Nf% tw� ¢t� MA'.Y Y5�
GONG 6#.TN A'Y##W cc#ivc R:rvrq ATPir#1
TPA`�ION
�A� corsc tw �X} atl +%i•
r#CATt0"
vSrs
Q S FRACTION VOLATILE COMPOUNDS
Zvi r1h
C1t17 .s .
X
<5
<. 02
1
M'g //{1.
•.
lb/Day
"�
Q
\ Cl
'1
Llg/L
lb/Day
<5
<90
1
<1
<. 005
1
�1g/L
lb/Day
.
<20
1
},�#rr
erce ryl
Fx
Ggttw
N/A
+e
IY
}
ii
ft
(155.z)
X
<1
<.005
1
pg/L
l b/Day
<1
<20
1
BV,CarbonTotrochlo
t 0 lrldo
<1
<.005
1
g/L
lb/Day
<1
<20
1 _
7V. Chloro naons
11 t 71
j�jj
x
<1
p�(g
<.005
1
g/L
lb/Day
<1
<20
1
8V. Chlorodi>
m
bro thboo
tf4,t1 11
t
<1
<.005
1
.........«... ..
Fig/L
....
lb/Day
<1
<20
1
gV, Chkt pent
l76 31
x
<2
<.01
�..
1
.._..... .».. _
pg/L
w..._ ««.
lb/Day
.»
<2
<39
1
IOV. •Chloro-
t0110-7B-81 Ether
<1
<.005
1
pg/L
lb/Day
<1
<20
1
11V. Chloroform
(87- -3)
X
<1
<.005
1
g/L
lb/Day
<1
<20
1
12V. Dleli
bra thane
116-27.41
x
<1
<.005
1
g/L
lb/Day
<1
<20
1
13V. Dichloro^
dlfluoromathime,
t711»71.8)
,
(
}
}
}(
}i
}(
14V. 1#1.01*hloro
aft (75• 3)
x
<1
<.005
1
pg L
l b/Day
<1
<20
1
*the" (107.06-2)
x
<1
<.005
1
Llg1L
lb/Day
<1
<20
1
othyl (7-3FX.41
x
<1
<.005
1
pg/L
lb/Day
<1
<20
1
17V. i#2-DIchtaro-
pr n.17 . 7-h1
x
<1
<.005
1
Llg/L
lb/Day
<1
<20
1
48Y.1.3- bran
( -15-$)
x
<1
<.005
1
pg/L
lb/Day
<1
<20
1
19V. Ethyl "zone'
(1 41-4)
x
<1
<.005
1
g/L
lb/Day
<1
<20
1
20*Mothyl
0 ►.t7 3.0
X
<2
<. 01
1
g/L
l b/Day
<2
< 9
1
21 Methyl
Ch t7 7-31
x
<1
<.005
1
g L
lb/Day
<1
<20
1
EPA For 10- C (Rev. .86)
PAGE V-4
CONTINUE ON PAGE

t_.,...
jL .
ErSA i.i3. NUMB is (copy from If4>tn 1 of Form !) dater aGt u eE
korro Approved,
OMB No 040 0086
CGNTINtIED FROM
PAGF VA
NC 24392 00Z
Approval expires 7 l •88
!.POLLUTANT
2, MAr+et 'ac"
L iIEiVT
. EFFLUENT
4, UNITS
S. INTAKE (optional)
NI..fMbFt
fB,aase
YNYw
Ikrit• Cu'u-
r�..wa 1.isva
e, MA?tiMClMC1AEL"Y VAL.Ui't.
p A
# MAXIM M 9, Y VALU C.LONG T M VALUE
bt j! cd Nli',. 6iF
i tit#tit it t) t oucsila c
A. L.ikNC. TENM
�� A
(a%'oud»$Jcrbldt)
NC•
ac.#w-
NAY k.^ A®1•
tANr i*Nt
t#I
co,L NTNATY+JN
Ik) MAY&{
ANAL-
#kI::MAma t#} l2):"^Us Y�tES
GONG k. N#TNhT#GYN CidNCQN7HATktlH
e LQINCEN-
TRATION
b, MASS
t#I conertw ..
TN.sI'!"tQM
is) Y%YnN
a�
Y*9111
GC/MS FRACTION- VOLATILE COMPOUNDS (cuithatted)
22V. e(76ene
Chloride i76-05-2)
-
<1�
<.005
1
pg/L
lb/Day
<1
<20
1
23 V. 1,1,272-Tetra•
.........
,»::.........«.,v......
.. �.....:.:. ..:,........... .:. .....
(7-3A-6)ene
X
<1
<.005
1
g/L
lb/Day
<1
<20
1
ethylene (127-18.4)
X
<1
<.005
1
pg/L
l b/Day
<1
<20
1
25V. Toluene
f1 -88.3)
X
<1
<m005
1
pg/L
lb/Day
<1
<20
1
Dichloroethylene
x
<1.
<. 005
1
/L
l b/Da y
<1
<20
1
(156.60.5)
27 . 1,1,1 •Trt•
chloroathane
X
<1
<. 005
1
}Ig/L
_
lb/Day
<1
<20
t11.65.6I
X
<1
<.005
1
pg/L
lb/Day
<1
<20
1
(7 0 5)ene
2 V. Trichloro-
ethylene t79-01.6)
X
<1
<.005
1
pg/L
l b/Day
<1
<20
1
flooromethane
}
N/A
x
x
x
X
X
X
x
(75-68..4)
31V, VIny I
Chforlde(75.01.4)
X'
<2
<.01
1
pg/L
lb/Day
<2
< 9
1
GC/MS FRACTION -- ACID COMPOUNDS
itloropftenaa
(9I18-6-67-57.8)
X
<10
<.05
1
pg/L
lb/Day
<10
<19
1
2A. 2,4-Dichloro-
phenol (I20.83-2)
X
<10"
<.05
1
pgl/L
lb/Day
<10
<195
1
3A.2,4.00nethyl•
phenol t105-67. )
X
<10
<.05
_
1
pg/L
lb/Daylb/Day
<10
<195
1
4A: 4,6• 34-5r
Cresol (534.52-1) .1)
X
<10
<.05
,.
pg/L
lb/Da
<10
<19
1
5A. 2,4-01riltro-
phenol (51-28-5)
X
<10
<.05
1
pg/L
lb/Daylb/Day
<10
<195
1
6A.2-itrophenot
18845.5)
X
<10
<.05
1
Ng L
lb/Day
<10
<195
1
(100,02t7) tthenot
X
<10
.05
1
pg/L
lb/Day
<10
<195
1
8A. P-Chloro-M-
Cresot (59-5€ -7)
X
<10
<.05
1
pg/L
lb/Day
<10
<195
1 '
Pentec6-5 ph
faereol (87 86.5)
X
<10
<.05
1
g/L
l b/Da
< 10
<195
1
t1 5 2) 10A. Phenol
X
<10
<.05
1
pg/L
lb/Daylb/Day
<10
<195
1
iticrrrala#ianc
X
<10
<.05
1
/ L
lb/Daylb/Day
<10
<195
1
ttt8 06- i

ONTINOEA FROM
THE
FRONT
MNS-002
1. POLLUTANT
ANC}: A
z.
MARN
`xx
3.
EFFLUENT
_
4. UNITS
5, INTAKE
foptional)
�_.«.._.
NUMBER
strati
0-0
O&W*w
;ta. ram�A:W,
r-
a, MAXIMUM
DAtt:V VALUE
-
MAXI M 3.
....,... a7lat
pp V VAL.UV
9 bre
a C
C„LONG °t' jF t4Y
t #:ViB
I
Joy} VAC.0
i(3 P N
! 7!
ct. rfo� or
. CGBN, tit.
W LONG
TERM
tt, Alo} '.
fita t, +g
fitovallakte)
01#414M•
*W"I"
t
Bad
C#NC "12 A� Y4#N
e
�!! MM4i
...�...»,.......:............
iF�
d:#HCCF•T4tA8A#N
eHt M l}
,_......
�a�
Y„iS d4'CCN6NN1t tr:5N
..___ Y
�ip Mn3C
JRNAO„.-
YS�Y�
r�A�t#ti
tf. MASS
...
fit CYtR4CEM
TWATi#N
..
t
jr) MAO*
wANA:
YS
C3 /M5 FRACTION
-- BASEINEUTRAL
COMPOUNDS
..___.:. .,._..... _.......
w.:..,..
®..._....,:«._.... .. ...«.:....
.,...... ._..._.. .....w_
mow.
1B. Acenephthene
(83-32.9)
X
<10
<.05
1
L
1 b/Da
<10
<195
1
28. AconaphtViene
(2t1B•B-a)
X
<10
<. 05
1
/L
1 /Da
<10
<195
1
39. Anthrecene
d12a12}
X
<10
<:0
1
q!L
lb/Da
<10
<195
1
48. BenzIdine
(2 s7)
x
<0
<.1
b/Da
<0
<90
1
6. Benzes (a)
Anthrecene
56- }
�{
< 10
< . 05
pg/L
1 b/Day
<10
<195
1
68. Benzes (a)
yrene lso 3z 1
}(
<10
<; 05
1
/L
1 b/ ay
<10_V
< 195
1
70. 3.4-8enzo=
__w
_
#tuorenthene
(205.99. )
X
<10
<. 05
1
pg/L
1b/Day
<10
<195
1
B. Remo (ght)
Perytene
(191t24-}
X
<10
<. 05
1
Fig/L
1b/Day
<10
<195
1
90. Sent* (k)
F luorenthene
(207• • )
X m
<10
<.05
1
pg/L
lb/Day"—<10
<195
1
108. Bls(2•Chloro-
,ethoxy) Methane
X
<10
05
1
pg/L
-lb/Day
<10
<1 5
1
118. Bis (2-Chloro
—<.
ethyl) Ether
1111.44.4)
X
<10
<. 05
1
pg L
1b/Day
<10
<195
1
126, Bic t2-E o-
Ettw(102-eat)
}
<10
<. 05
1
Dg/L
1 b/Day
<10
<195
1
138. Bit (-�Sthyl-
�_...
___
_.
hexyt) Phthelate
1117 B1•/}
X
<10
<. 05
1:
pg/L
lb/Day
<10
<195
1
phenylPhenyt
Ether (101.55-3)
X
<10
<. 05
1
pg L
1 b/Day
<10
< 195
1
168. Butyl Benzyt
Phtheleta (85- 7
.. 10_
05_.�<10
<195
1
1'BB. 2-Chloro.
naphthateine
{ 1.58,7)
<10
<. 0 ._- ._
.
_
.__ ..__
w
/L
1 b/Da
<10
<195
1
178. 4-Chloro-
_ _
_.._1_
phenyl Phenyl
Ether (7005�72 3)
X
<10
<. 05
_ _
_.
_ _
_.._
L
1 b/Da
<10
<195
1;
108, Chrysena
(21B.a1 )
X
<10
<_. 05
/Da
<10
<1
i
10B. Cilh�nzo (o.)
_
_
_
_
-.
. _
Anthracene
(3.70.3)
X
<10 „
<. 05
_
1
/L
_Lb /Day_
<10
<195
r 1
208. 1.2-Utchloro-
tsenzena (85.50.1)
X
<10
<. 05
_
_.
/L
1 b/Dam
<10
<195
1
18.1,3- 1chtorp-
nxene t541-73-
X
<10
< 05
1
pg/L
lb/Daylb/Day
<10 ,
<195
1
EPA Form 3510-
C (Rev.
-85)
PAGE;
it-6
CONTINUE
ON
PAGE

,298 otyll
0
1 b/Day
Phtfil
I b/Day
31 B� F luoranthene—T
<
<. 05
1
1 b/Day
(206-"-0)
3213 Fluorens
x
<10
<. 05
1
1 b/Day
<10
< 195
(86-�3-7�
3M. no
X
<10
<. 05
1
pg/L
Ilb/Day
<10
< 195
34E,7H.-a—,
--x
<10
<. 05
1
pg/L
Ilb/Day
< 10
< 195
358. Hexachforo-
v
� "
<10
<. 05
1
pg/L
Ib/Day
<10
< 195
cyolopental
(77-47-4)
368. Haxachloro-
x
<10
<. 05
1
pg/L
lb/Day
<10
< 195
*thmm (67-72-1)
--i7-0-. Indono
x
<10
<. 05
I
pg/L
b/Day
<1 0
<195
(1.2.3-ed) Py one
"
(193-39-5)
380. Isophorons,
X
<10
<. 05
1
pg/L
lb/Day
<10
<195
398, Naphthalene
X
<10
<. 05
1
pg/L
lb/Day
<10
< 195
(91-20-3�
408, Nitrobenzetle
X
<10
<. 05
1
pg/L
Ib/Day
<10
<195
(98-95-3)
4M N-Nitro,
x
<10
<. 05
1
pg/L
Ib/Day
<10
< 195
sodimethylarnino
428, N-Nitrosodil
X
<10
<. 05
1
Pg/L
Ib/Day
<10
<195
N-PrOPYISMins
14521-64-7)
L

MNS-002
CONTINUED FROM THE FRONT
I, POLLUTANT t MArttt 'x
3
EF'F"F U;LN1
4 UNt
FS
5 tN VAKF:
(optional}
AND CAS x —
DAILY
VALUE.':
Fd "ytA7itM, M 3
Y VAVUL
#: Gs?N r'
G VALUE UE.
dT tars c)#
X0. N n k
i#. {QR{Ct r'{_rd
trtA"t1caty
I o Rp A 5'a
# t r#nti,
3 # $4Rp J"A
sERMAXIMUM
liL
1a+x #rx tTMix txp rax
� f xnxtenxxar+d
idi�».,+`�
nxtr,«'
idt �
rax+�nx,�dry
i'i
,d.
_ _
GC11 .+ FRItiC`TIOPI 13A EINEUTRAi COMPOUNDS
tr'tfrttfrridrri!
438. N Nitro-
-
aodiphanyiarnina <
449.. Pherwilthrons.
(6a•o1 6) X <10
<. 05
1
nd
7
460 Pyrww
(129 11) x <'10
<. 05
1
1,2,4.Tri-
sane <10
<. 05
QCAN FRACTION - PE TICIGiE
1P. Atdrin
$ -2)
2P, f1.8HC-
(319-84-6)
P. SHC
(3111i5 7)
4P, 8HC
( 9 9)(
SP. S- HC
1319.864) }(
6P. Chiordna
(67-74-) - (
7P. 4,4'-DO 1'
(0-29-) }(
8P: 4,4'-DDE
(7 65-9) (
9P, 4,4'-DDD
(72 }(
10P, Diaidrin
(60.57-1) }(
I IP. a-Endotutta##
(11-29-7) -{
12P+. Q-Enddautfan
}
9uifata
(1 17.8):
14P. Endrin
(72-20-8)
16P. Endrin'
Ai ydo
(7 1.93,4)
16P. Holptachlor
x
(7 8)
EPA Form 3510-2C (Rev, 2-86)
PAGE
V-8
CONTINUE
ON PAGE
VW9

:ONTTINUE' 3 FROM PAGE V-8
t. Pd�at1 PANT x wt crrc tx
AND G AS b
se Nr sr wt {rp wanes : (xd; w+n s5 :a=• (t0 wan�.s TSE *a:: r"i •. •.••, '" itR rWw;f TiG *j
___ _ __ C{YWGi Neu Jett iYaN ¢ 4'tWY 6Wt ri dN T #5wC! WritntJa W. t#YRr(drN
dCi MS Fii. C&60N -- PESTICIDES (continued)
17P. Hop2echlor
E pox ids
(1 24-67-3) }(
18P. PCB-1242
(53469- 1-9)
19P. PCB-1254
(11097.69.1 )
20P. PCB-1221
Zip. PCB-1232
(11141-16>
22P, PCB,1248
(12672 29. )
P. PC13-1260
(11 9-82.5)
2 P. PCB 1016
(1274-11-2)
2 P. ToxePhene
(8 1.35-2)
PAGE V-

ITEM Y.1) CONTINUED
I o POLLiJT-
-ANT Anici
CAS rii.C3.
dl+'<Kli®i8i�jPw7
g. Nitrogen,
{asTotal NlCirganlc
2, MARK'X'
8, err:-
acne;
PRO^
%
X
FROM
I?, ea F.-
t<pp_vrsa
A"-
bt.:wv
FRONT
.r.• ..�._
8. MAXIMUM ITAILY
_.... .....
�r�..,.....
424
89 _
...._.�. ......_..®.
VALUE
^.......®..._....._....._
..._ !
TeAi"
113
2
3.
b MAXIM M 3r}
iti cJJ+ndtni)
.._
f„„#»wr Y..w Yren (,rsiy
EFFLUENT
p Y: VAC.0
..0 t
i#I. hi ltSS
C.LC?N + T M
AI <l .A.eIFIT.
....�a
: !
t TtY kirt r!rTw
t'C1H t
VAI..UE
.....�. y. .
l?I.!#e 1455
Ef, ha to C>t
ANAL,::
Y�rE C
1
4, UNITS
a. CONC1EN_
3"#'7 nr.'T Rt'p h#
mg/L
m L__
: Ie. MASS
l b/Day
W i b/Day
MN -003'
5. INTAKE
8 I t7NC
Ae/Etint
_.,...
"� ._'__
� (r'�ll.e rtt A#:n TtteN
<. 08
� .13
(ipri aFr,d)
Tt: 6xM
c Wnt.ltE
Y...ff _
"""`
i ) "A-
<1, 562
2,538
ANAL.
Y„`I. s
....
1
1
h. tiff and
Gromos
X
I. PhoaAhtlrus
-"
^
io�t72 t Total
X
7.0
1
mg/L
- -
lb/Day
<.02
<390
1
J. Radioactivity
_
-----
TotallPbat
X
<.3
X
1
pC1/L
X
<.4
X
1.
Tot*(
X
1 .2+3. 6
X
1
pCi/L
X
2.1-!~<
X
1
(3I Radium,
Total
X
X
1
pC1/L
X
<1.5
X
1
2) Radius'
X
<.1
X
1
pCi/L
X,
1.4±..4
X
1
(804)
X
29
8
1
m /L
lb/Day
9.6
187,462
1
iiMpq--7918)
1. fed $)fiid#
X
<1
<.3
1
mg/L
lb/Day
<1
<19, 527
1
itit. $U
r.cs
X
3
8
1`
m /L
g
lb/Da y
<
<39,05
(14285.45-3)
to. surt nts
X
<.2
<.05
1
mg/L
lb/Day
<.2
<3,905
1
o. Aluminum,
- --_
Total
X
66
2
1
mg/L
l b/Day
11,912
1
(7429-90-5)
.61
arum.Total
~-
X
.04
.01
1
mg/L
l b/Day
390
1
(7440 3)
.02
q• orcm,
t otat
X
.91
.2
1.
m /L
-
l b/Day
.11
2,148
1
•tx)
_
Totaal #'
X
I <.1
<.03i
v
1
Ong/L
1b/Day
v___
<.1
.
<1,9
1
a iron. Total
trams ss
.51
1
1
mg/L
1 b/Day
.3
5,858urn
1
~total
X
3.6
1
1
m/L
l b/Day
1.2
23,433
1
(7439.95-4)
v
u. Molybdenum.
Total
X
.08
.02
1
mg/L
l b/Day
.07
1,367
1
a�
v.
Totain°erlasa>
X
04
.01.
1
mg /L
1b/Day
.02
390
1
(74 -sly-s)
w. Tin. Total
(7440-31-5) X 2.0 5 1 g/L 1b/Day 1.2 23,433 1
x. Titanitini,
ono 'si X . 0 008 1 m /L 1 b/Day . 02 1: 0
EPA Form 810-2C (Rev. -85) PACE W-7 CONTINUE ON PAGE it -

EPA LCL NUMBER (COPY front Item I otporm 1) OUTFALL NUMBER form Approved
NCO024392 003 OM8 No, 2040-0086
CONTINUED FROM PAGE 3 OF FORM 2-C Aripjrovidexprres 7 31-88
PART C - Ifyou are a primary industry andilosoutfall contains process wastewater, refer to Table 2c-2 in the instructions redetermine which of the GC/MS fractions you must test for. Mark "X" incolumn
2-a for all such GC/MS fractions that apply to your industry and tot ALL toxic metals, cyanides, and total phonols. If you are not required to mark column 2-a I'secondalry indUSItte.l. nonptocOSS
wastewater outfalls, andnonrequited 6CIA4S fractions), mark "X" in column 2-b for each pollutant you know or have reason to believe is present, Mark "X'* in column 2,c for each pollutant you
believe is absent� If you mark column 2a forany pollutant, you must provide the results of at least one analysis for that pollutant. if you ma(kcolumn 2bfor any pollutant, you must provide the results
of at least orre analysis for that pollutant if you know or have reason to believe it will be discharged in concentrations of 10 ppl) or greater, Ifyou mark colunin 2b for acrolem, acrylonitrile, 2,4
dinittophonol, or 2-methyl-4, 6 dinitrophenol, you must provide the results of at least one analysis for each of these pollutants whichyou know o( have reason to believe thatyou discharge in
cunceno abortsof 100ppbor greater, Otherwise, forpollutants forwhich you tuarli,column 2b, you must either submit at least one analystsof brieflydescttbe the reasons thepollutant isexpectedto
budischaiqud Note that there are 7 pages to this part; please review each carefully. Complete one table rall 7tragesi for each outialt, See instructions for additional details and requirements.
I.POLLUTANTJ MARK 'X* 3. EFFLUENT 4. UNITS 5. INTAKE foptional)
AND CAS lu. MAXiMPM 3? C,LONG T G V ALUE a� LONG TE14M
at MAXIMUM OAILY VALUE Y VALUE t NO.Or tl)� NO 0
ANAL, Li, M ASS —LU —E A N A L
NUM p eI d CONCEW
(it atmilable) —6-F YSES TRATION M.us YSES
METALS, CYANIDE, AND TOTAL PHENOLS
1tvi Antimony,
Total (7440-36 0) X
2M. Arsenic, Total
(7440�38-2I X
3M. Sorylliur",
Total, 7440-41-7)
AM. Cadmium,
Total (7440,43-9) X
— ------- --
5M, Chromium,
Total (7440A7-3) X
6W Ccm Total
I � a
7440- -8) X
7M. Load, Total
(7439-92-1) X
illyl. Mercury, Total
(7439-97-6) X
9M. Nickel, Total
(7440-02-0) X
I OM. Selenium.
Total (7782-49�2) X
I I M, Silver, Total
(7440-22-4) X
12M. Thallium, X
Total (7440-28-0)
13M. Zinc, Total X
(7440-666)
14M. Cyanide,
Total (57-12-5r
ISM, Phervots,
Total
— -------------
DIOXIN
ESCRISE RESULTS
lorodit)fmzo t
ox iii (1764 0' X NEGATIVE
EPA Form 3510-2C (Rev, 2-85) PAGE V- CONTINUE ON REVERSE

an" rue ectnadlr MN -003
a
LUTANT
1 CAS
vr8�R
:AACrION—
2,
at�eat
+ajt
wa•
et++w+
VOLATWE
MARK
% r�•
+ava.
p«�.
ittn+t
W
c.+ee-
a.+Iva
��,
ow"T
COMPOUNDS
S. MAXIMUM CSw9i VALUE
(c} (a) #+nss
C#t+C i.N$MJ1teOM+
3.
, MXX6 M
+8t�f61�Qd1@
:r+r
YC KkfiC aENtN AtiiaN
EFFLUENT
p at. VALUE
q/►
(ar'e+wss
gd �g g�
C.Lot4G T VALUE
1 #trOtdQ &E
rar r�r
Gi+MC KNtIq lAtlON
t8. NO.c?r'
ANAG.-
vsEs
C UNITS
S. Ci GEN-
TRATION
b MASS
S. INTAKE
a LONG
(®I eawCa±ra
T+PAt+Q14
fopticsrall
tER O
b. NO.ti
i» ANAL;
rar �+x.. yeas
xr
motor,"
r
on
x
)ride
rob*nzons
V
fl
7)
rthene
t }`
rootbane
! ,,
hroro-
--
rt Ether
i}
drotor
Moro;
wthene
r-
i`
•D)ohroro-
PS- . }
-Olchroro-
107.06-2 j
(76•35-4)
s7-1i7-5}
(khkwo-
642.76.41
ey(benrone
a}
^thyl
(7a•s.9)
�thr
anr_c
to®x
Ct)NTINUE
ON
PAGE I

CONTINUED OROM PAGF-V-141
I.POLLUTANT
,129V. Trfthforo-
othylone (1 -01-6)
SA� 2 4-Dinkro-
phon�l (51-28-5)
'6A. 2-Nitroph -=
anot i
SA� P.Chloro.M.
(69-50-7)
I OA, Pheno
0 08-95 2)
W-
S. MAXIMUM DAILY VALUE
b.MAXIMIM3, 0,LONGT M#,Vr
apa?a?,�)V VALUE ova
�VALUE
0
W
Cali"
--Eoftck"THATION
POUNDS (continued)
NOS
toved
7S
4 MASS
1I.INTAKE
S, LON
--A-VAIL"
fit Coke*"-
(optional)
TERM
Lug
fit
bmo,o
ANAL -
Yoe*

CONTINOED-FROM T14E FRONT MNS-003
1. POLLUTANT
2-MARK'X'
3. CFrLUENT
4, UNITS
5. INTAKE loptionall
ANDCAS
NUM BIER
&ire* �J�
%. I -
$r. MAXIMUM DAILY VALUE
M YVA
au o e
CZ5NE VALVE
I No ' or
0, LONG
TERM
b - No ' 0
040
". I o"..
*W."r
I
I OWN*
^"A$--
F.
VS S
4� CONCEW
T"ATION
b� M^$S
—AVAU"Ag
W9--
(of Mkos
ANAL-
YSES
GCIMS FRACTION
— FIASENEUTRAL
COMPOUNDS
IW Aconsphthens
(83-32-9)
20. Atonaphtylone
(200-96-8)
38. Anthrecone
(120-12-7)
49. SontIdIne
(92-87-5)
SW Sonzo (a)
Anthrocano
(56-56-3)
as. sanzo (a)
Pyrone (50-3243)
78. 3,4-Senzo-
fluoranthane
(205-99-21
I
as, sonzo (ghf)
perylons,
(191-24-2)
90. sonzo Fk—)
F tuorenthone
(207-08-9)
108. at$ (Fc—hl.ro-
othoxy) Methane
1113. 819 (2-Chloro-
ethyl) Ether
(111-44-4)
l2w sit p-ChAarmo.
pwyV Ether (102-WI)
138. Bit (2-Sthyl-
hexyl) Phtholato
(117-81-7)
phonylPhonyt
Ether (101-55-3)
Ise. Flutyl senryl
Phtholate (85-68-71,
168. 2-Chloro-
naphthalene
(91-58-7)
178. 4-Chloro-
phonylPhonVi
Ether (7005-72 3)
108. Chryseoe
(2111-01-9)
X
lw-wbenzo-
Art,threcone
J53-70-3)
200.1,2-Dichloro-
benzene (95-50-1)
218.1,3-01chloro-
bonrono (541-73-1
16�
EPA Form 3510-2C (Rev, 2-85)
PAGE V-6
CONTINUE ON PAGE V

foon Ap>puazved �..
"EPA #105 NUMSE# (copy ; front Item I of Form I) DUTFAL:L NUMBER
OM11 No 2040 8:
NC4
Apparrrvalexjxres 7 31-88
CONTINUED FROM PAGE V-6
t. PCILLU'TANT z MARK x,
3; EFFLUENT ENT
. UNITS
5. INTAKE toptsonal/
ANDCAS
NUMBER area exr
ir.: ar-
+�. ra
a. MAXIMUM DAILY` VALUE
li.'M XIM 9`I LAj1.Y VALUE
8
aurxect a
c.i. NC. f M iil� tAl U
at+ Uie
tl.i r,c>,ct
a CONCEN'
a r,.rsw
t'�raM
tlre4
(if available) crc°re+wta
aav�
arae
aA•V•
•nax
_
I'} Ix1 *seas
co,r rash wwtijN
iel
cure*.. a,:wswesevra
la} ee s
�`}
c. aaea&erarsanroeone:.
la} wet
ANaL-
YSt=S
TRATION
te. A4
tt} c teca w-
YFt eetreAra
ANAL'
Itl wsxsa YRE
GC' FRACTION — 8
_
E/NEUTRAL
COMPOUNDS (continued'
228, I A-Dichloro-
borexene (1; .7
_
23W 3,3'-Dichloro
banzld[n*
(91-94.1)
248, Diethyl
Phthalate
(84.66-2)
258. Dimethyl
Phthalate
(131-11 3)
28. DI-N-Butyl
Phthalate
j
(84.74 2)
jt
278. 2,4-DAnitro-
toluene (11.14.2 )
}{
288, 2,6-Dinitro-
toluene (606 20.2)(
298. DA-N-CFctyi
Phthalate
x
tl176401
308. 1,24)iphanyi-
hydrazine fas Azo-
x
benzene) 022.661
31 B. F luoranthena
t2 .gip
328, Fluorena
x
(86-73-7)
nxarr
i11.7a.tA
3,i8 Fiexm
chlot utrtlrr adiane
(87.68 3)'
358. liexachtoro,
cyclopentediene
(77.41.4)
8. Nexechloro-
}(
*then* (67-72-1)
370.Ind®no
(,2,3-cd) Pyri n t
1193.39-5)
8.lsophoroe
x
(78 59.1)
398, Naphthalene
(91- 0-3)'
408 Nltrobenzell
ag
(98 95 3) ,
R
418, N-Nitro-
sodiAnethylaroina
(62-75 9)
428. N-Nitrosucii-
N •Propylarnina
(621-64 7)

CONiINUEtir FROM THE FRONT
I. POLLUTA9NT 2 MArrK 'X'
3 EI`I`I_Ui:N7
4 UNITS
. _ ,:-_
5 1N I
AKL-
, _,:
AND CAS :. -,...-._. _.... _. ._... _ ..
NUMBEF2 Fxx+er b wt t rbe A. MAXOMOM DAILY
._ ._
VALCJ 6.
1, MAXIM M�3
f9 (#9 {li
gypp Y VALLrr:
£dax'
Y i't i
_ Ji
C LONG tk, M I4
(7 f1#�d#li4t
F
......
G. VALOC
f' /
it racy xsi
.._,...
r+ COWL N
..
.t 9 ON .
/ V4ilF +.t
It 9aaee
V RLt1k
t
tlA+. L6PN00 dfF 4Px
we ♦ixa nrr
Ir(#J#�otlable) �,++ a x •rtix l k {
l,l„nM
I i
I$i
+i w+yn>
'}
AN Ai
r
r#rArr«r#
it F1Ati*`
a
' (
( E
y'A
GCANS FRACTION — BASK/NEUTRAL COMPOUNOS+ Ix'+rr+ldrtJer+il
438. N Nitro-
rodiphenviernine
(88 30-6)
S.
(n rtho"nthrene:
458. Pyrsns
TO-
chloroboort
WAA FRACTION -- PESTICIOES
1P. Aldrin
i '. -2I
2P. -8HC
i319- - }
3P. •BHC
(31i -885 7)
4P. 8HC
(be 9-91
SP. 6>8HC
(319.86-8) }
6P Chlordeoe
(61-74 9) }(
7P. 4,4'-ODT
(72.66-9)
9P; 4,4 -000
(72-64.8) }�
lop, Dieldrin
Ill
11P. a Endorulten
(115-29. 7) i{
12P. P-EndosuIten
i 11-29-71{
1 )'. Endosuliere
uiirtt(
I1_ 1-07 81
14P. Endriti
}�
(72.20.8)
15P. Endrin
Aidehyde }(
47421.03-41
1SP. Hopt hior
(76.44-81
EPA Form 3510-2C (Rev. 2.85)
PAGE
Va8
CONTINUE
ON PAGE
V-3'

forin Apprt
orn Itent I of Forin OUTFALL NUi�OEW­­ OMH No 21
M
App oval e,
2 003
4. UN#TS
L
Epoxide
x
18P, PCB- 1242
(53469-21.9)
19P. PC B- 1254
x
(11097-69-1)
20P. PCB-1221
x
(11104-28-2)
2 IP, PCO, 1232
x
22P, PC8-1248
x
(12672-29-6)
23PPCB-1260
x
(11090-82-5)
24P. PCB,1016
x
(12674-11-2)
P. Taxaph-2 ..
x
(8006 3 1-
PAGE V-9

MNS-004
NTINUED FROM
FRONT
1. POLLUT- 2. MARK
3,
CFFLbrNT
4, UNITS
5, INTAKE
(tphotfal)
ANT AND 4, -8 W
CAS N0. fMVCCLWVf,0
at MAXIMUM 0AILY
-
VALUE
b MAXI
Y 'VALUE
(TIP.,
M
j� No 0 F
ANAL,
CONCEN.
A
hMASS
VIR,"t I E
6, Noov.
ANAL -
pot* 0-
fitavallable) S T f, I � N
.......
III MASS
Y.;t
Ttl A I t (IN
[F14
9. Nitrogen,
Total Organic x
1.3
.06
1
mg/L
I b/Day <. 08
<1,562
1
h. and
ax
5
1
mg/L
I b/Day .13
2,538
1
area"
.2
1. Phospho u
(as Pl. Total x
1
.005
1
mg/L
1 b/Day <. 02
<390
1
(7723-14,0)
). Radioactivity
t I) alpha,
X
11000±640
X
1
pCi/L
x <.4
x
1
Total
(2) sots,
Total x
600000±3700
X
1
pCi/L
x 2.1±.6
x
1
(3) Radium,
33±3
x
1
pCi/L
x <1.5
x
Total
(4) Ascifur"
x
13.2±6.6
x
1
pCi/L
x 1.4±.4
x
1
226, Total
fat $yyy04) x
<1
<.05
1
mg/L
lb/Day 9.6
187,462
1
1. glgl.iii x
<1
<.05
1
mg/L
lb/Day <1
<19,527
1
(at SO,?) x
<2
<.1
1
mg/L
lb/Day <2
<39,055
1
(142§5-45-3)
n. Surfactants x
<.1
<.005
1
mg/L
lb/Day <.2
<3,905
1
o. Aluminum,
Total x
<.4
<.02
1
mg/L
lb/Day .61
11,912
1
(7429-60-5)
P. Ts-rTu-i".
Total x
<.1
<.005
1
mg/L
lb/Day .02
390
1
(7440-39-3)
q. on, Total x
5.3
.3
1
mg/L
lb/Day .11
2,148
1
(7"0-424)
r. CO
Total ME, x
<.05
<.002
1
mg/L
lb/Day <A
<1,953
1
(7"0-48-4)
a. Iran, Total
1
mg/L
lb/Day .3
5,858
1
.3
.02
Total x
.15
.008
1
mg/L
lb/Day 1.2
23,433
1
t7439-95-4)
u. MolVbdonum,
Total X
<.2
<.01
1
mg/L
lb/Day .07
1,367
1
(7439-98-7)
Total x
<.02
<.001
1
mg/L
lb/Day .02
390
1
17439-96-5)
x
<1
<.05
1
mg/L
lb/Day 1.2
23,433
1
urn,
Total
x Total x
[E(7440�312-6)
--
<1
<.
< - 0
1
mg/L
lb/Day A2
7177�3
90
1
I
:.�
EPA Form 3510-2C (Rev.
2.85)
PAGEV-z
CONTINUE
ON PAGE
V

EPA t.D : NUMBER (copy jrutrt Item 1 of Forrit t) OUTFALL NUMBER
Fctrnt Approved
N0024392 �4 �or�Itt tv�t expires t �e�
CONTINUED FROM PAGE OF FORM -C
M
u are a primary industryand this outfall contains process wastewater, refer to Table 2cm2 in the instructions to determine which of the GCJMS fractions you mast test fear. Mark"X" its column
ear all such GC/MS fractions that apply to your industry and fur ALL toxic ntetaals, cyanides, and total phenols. If you are not requ red to mark column 2-a(secondary industries. nonprocesewatr;r oratfalls, ant!nonre uiredGCIAA tractions), tnark "X' in column 2-ta for each pollutant you know or have reason to believe is present. Mark -X- in column -c for each pollutant you
ve is absent. If you mark column 2a for any pollutant, you rrtust f trovide the results of at least one aanalysis fear that pollutant. if yoga mark colutnn 2b for any pollutant, you must provide the results
least cane analysis for that pollutant if you know cat have reason to believe it will be discharged in concentrations of 1€} ppl, or greater Ifyou mark column 2b for acrotern, acrylonitrite, 2,of henol, or 2-methyt-4, 6 dinitrophenot, you must provide the results of at least one analysis for each of these pollutants which you know or have reason to believe that you discharge in
cuncenti abonsof 100ppbor greater. Otherwise, for pollutants for which you rtrark eolumn 2b, you must either submit at least one analysis or hrrefly desctibe the reasons the pollutant is expected tp
be dischauycad Note that there are 7 pages to this part; please teviow each carefully. Complete one table iaa11 pages) for each o uttalP See instructions for additional details and requirements,
t. P01..LUTANT -4 �. MARK 'X' 3, EFFLUENT 4. UNITS 5. INTAKE (iiptfutialj
AND CAS - __ " " ba MA11tiM4,Nr 3 µ'Y VALUE C.LO G"B_ Nr. G..VA-t�ue Ar,N<).a�r a. LONG TERM tt.NCa r3F
+t �[ St t5 Nt t�, ial War.�MAxirar.rM DAILY StALta.
NUMBER auee .t via _ _ (ij ,atirttlt d D fd urv,tid riite'$ " CONCIEN A—
y . ANAL' tt MASS """'�" ANAL-.
(itavaitutil 1 `a ` '"`+<t ltl (41 MASu l'1 (,} All (A} (.} uSt S TRATION it) cortcxr,- t } txas YSES
� tc)ka..i taYN)t7tbtd £t5 tr rl ttckN .a NC el Y'HAtAV+*+ Ttrt ARRICSM
METALS, CYANIDE, AND TOTAL PHENOLS
t43Toaf(74os of X ;. <.01 1 m /L lb/Day <. 6 <11 716 1
(74do-` Total
3B 2}X <10 <.0005 1 g/L l b/Day <1 <20 1
3M. BervIlluin,
Total, 744o- 17I X <.01 < 0005 1 mg/L lb/Day .002 39 1
Toall17440 -9) X a01 < 0005 1 m /L lb/Day .01 195 1
Chromium, a .3) <. 05 < 002 1 m /L l b/Day 04 781 1
BM: Copper, Total
(7 4o-50.0) X .03 001. 1 mt /L lb/Day .03 586 1
tal
4 Load, 1) X <. <-01 1 mg L lb/Day <.08 <1,562 1
SM. Mercury, Total
tX <. 0000 1 pg/L lb/Day <. I <2 1.
t744a'aa0I.Total X <.05 <.002 1 mg/L lb/Day <.04 <781 1
72410M.o (7si;2) X <10 <. 0005 1 pg/L l b/Day <2 <39 ,1
(7 Silver, T�atel X <.01 < 0005 1 mtg/L lb/Day <.04 <781 1.
Tote (744utn, .1 <.005 , 1 ` m /L lb/Da <.5 <9,764 1
Total f7aaU�28 0l J y
13M
(744 6-6)Total X 09 00 1 m /L l b/Da 0 390 1
(7+tC0-i3�Bl � Y
14 .Cyanide, Total (57.12.6) X 2 01 1 mg/L lb/Day <.02 <390 1
ISM, Pltenrit , X < m 001 < . 00005 1 mg/L l b/Day <.005 < 8 1
TCriai
DIOXIN
t, ,7,8 Tetra CiE SCRIDE RESULTS
sitioresulburazo it
tatrixin (17640, al X NEGATIVE
EPA Form 3510-2C tRev. 2-85) PAGE v-3 CONTINUE ON REVERSE

CONTINUED FROM THE FRONT
MNS-004
1.POLLUTANT
2.MAOK W
3. EFFLUENT
4� UNITS
S. INTAKE (op4tionall
AND CAS
NUMB
aTxrT to r4K• G Wit-
, rasa serve
1"a
a. MA iMUM DAILY VALUE
° M! l pp Y'VALUE
atta6ab�
C.LONG T M A t VALUE.
aStaiicr 0
cS. NCi.itiS`
ANAL-
a �f#GEN•
b, MASS
W LONGTERM
:
to Net.c>f
ANAL-
yyp.
.§p! �pAR
♦Mr• wbW
'OAUdN• 1&t9#T t MT
a
14
GOHC'E MTr ATIatY
It) MASS
f
co"es"THAyloft
�I� MARt
:
�f 8� Mh4Y
GtiMNCr NTNAT1iEM
s
PATION
�1` Ci`nNC 'N-
TNATt€AN
�8� MA6►
-----
Y ES '
OCAM FRACTION —VOLATILE C UND$
_
.4,,
X
<5
<.0002
1
g/L
1 /Day
<5
<98
1
2*1
1iYl*,ta:
1
g/L
1 b/Day
<5
90
1
3�1,W9
X
<1
<.00005
1
pg/L
1b/Day
<1
<20
1
o u
ro
dYs�yl p e
X
N & 9
PO
x
x
x
x
x
(540 •1)
(M 2)oform
X
1
.00005
1
fag/L
1b/Day
<1
<20
1
TV. Carbon
etroohlorlde
X
<1
<.00 05
1
pg/L
1 /Day
<1
<20
1
{68-23.5)
V. Chloro mans
(1 -90.7)
X
<1
<.00005
1
pg L
1b/Day
<1
<20
1
$V. Chlorodl-
brdmomethane
X
<1
<.00005
1
g/pL
1b/Day
<1
<20
1
(1 4-4$-1)
$V.Chlo ane .b
{ .`
X
<2
<.0001
1
pg/L
1b/Day
<2
<3
1 OV, 2-Chloro
othyhrloyl Ether
x
<1
<. 0000
1
pg L
1 b/Day
<1
<20
1
41 Iti-75-$)
_
__ _
{$ Chloroform
X
<1
<.00005
1
pg/L
1b/Day
<1
<20
1.
12V. - lthforo-
broom athane
X
<1
<.00005
1
g L
1b/Day
<1
<20
1
{7s•2ia4)
13 i. Dlehfero•
enunethane
/A
}
}
x{
}
x
xdifl
14V.1,1-Olchloro'
X
<1
<.`00005
1
pg/L
1b/Day
<1
<20
1
• (75-34-3)
16V. t42-Dlchlr
1
<.00005
1
it /L
1b/D
<1
<20
1
oth" (17-0-2)
hloro-
X
<1
<.00005;
1
erg/L
1 b/Day
<1
<20'
1
wthvia'nee {1.° sat
4.2-Dlc87-5)
X
<1
<. 00005.
1
g /L
1 b/Da y
<1
<20
1
aarapono (78-�t7-5)
rop
lNV.Ww( ` c�iz-��-a)
v�
<1
<.00005
1
g�/L
1b/Day
<1
<20
1
4)l ten:anr
X
<1
<. 00005
1
pgf L
1 b/Day
< 1.
<20
1
(100 i
20*Moth l
flraIvItft t14-$3-9)
X
<`2
<.0001
1
g/L
1b/Day
< 2
< 9
vl
3)
X
.
1
g/LCh
1 b/Day
<1
<20
1
01
EPA Form 510- D (Rev. 2-86)
PAGE V-
CONTINUE ON PAGE V

1,1,2,2-Tetra-
rroathane
4-5 )
Tetrachloro-
lona (127-18-41
M 1,1,1-Tri-
eloroothane
p1-Cs5^6)
9V; 1,1,2^Tri»
iloroathane
P9.00.6)
9V, Trlchloro-
thylana (79.01.6)
6A. 2-N i tropheo0l
(8-75.5)
torm Approved
EPA 9.0, NUMBER (COPY 1'rorn IlCol I of Form 1) OU rF'ALt- HUM BAR OMB No 2040-0086
P AC F v a N0002492 Q0 Approval expires 7.3I.88
x, MAR *X' 3. EFFLUENT 4. UNITS S. INTAKE (Op#fts»�lj
r},sr
kN4
b aI-
4k.Vi
C Ae•
4.irVii
#•MA�t.tMttM.t`AtL
"VALt6E
b. MAXIM M 5�iy
a i2tMEitQblf')
dr�1y/� tY t6At UE
c.LOiVG T M
o.,.,larbld"
Ay }p�' ,VALUE
allo,oF�
CONCEW
e. �aNCs
TERM
b,tio,or
Re:-
fiklOR•
wRmw
♦#NT
Aw..
ffi6NT
g
(4)
G CTN&4.NYR ATiUN
lE):MATrY
1:41
GiJNCk NYRATk4N
ii)MAbo
(.tl)
GIiN&CN7RAT#0N
($l ►oAYt
ANAL-
YJES
TRAT#094
b. MASSY
p
{e) CG}}eC AM�
FRA reON
(g) keAif
AMAL-
Yse*
VOLATILE
COMPOUNDS
(Continued)
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1.
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
<1
<.00005
1pg/L
lb/Day
<1
<0
1
X
<1
<.00005
1
pg/L
lb/Day
<1
<20
1
X
N/A
X
*1...
X
X
X.
X
X
X
1
<2
<.0001
1
pg/L
lb/Day
<2
< 9
1
ACID
COMPOUNDS
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1.
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1pg/L
lb/Day
<10
<195
1
X
<10
<.000
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<.0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<,0005
1
pg/L
lb/Day
<10
<195
1
X
<10
<}0005
1 A
1194
1b%Da
<10
<195
1

YTINOEn FROM THE FRONT MNS-004
ARMSIMARMILK
Mom M1111-00. ME m
Aconsphthono
1-32-9)
x
<10
<. 0005
1
_Lb/D jy_
<10
< 195
1
AcensphtVIons
0-964)
x
<10
<. 0005
--1
_tq/L
jt/Day
<10
<195----"
Anthrocens
;0-12_7)
x
<10
<. 0005
lb/D,av
—<10
<195
1
sonzidine
x
<20
<. 001
1
1 b
<20
<9
30
1
so"Zo
-co, throcon"
x
<10
<. 0005
1
pg/L
1 b/Day
< 10
<195
1
Benno (a)
,one (60-32-8)
x
<10
<. 0005
1
pg/L
I b/D f
<10
<195
1
orantheme
M-99-2)
x
<10
<. 0005
1
pg/L
I b/Day
< 10
<195
1
Senzo (ehl)
lon*
11-24-2)
x
--
--
—
<10
-- —
<. 0005
—
1
pg/L
I b/Day
<10
<195
1
, sionto Fkj—
----
---- -
---
-
---
—
lorenthon"
x
<10
<. 0005
1
pg/L
I b/Day
<10
<195
1
81# (2-Chloro-
bxy) Mothano
<10
<. 0005
1
pg/L
I b/Day
<10
<195
1
3. sit afhlowo-
�I) Sthor
1-44-4)
x
<10
<. 0005
1pg/L
1 b/Day
< 10
<195
1
Bit f2-ctdwv*#-
YljEftw(IO2-WI)
x
<.0005
1—
pg/L
1 b/Day
<10
<195
1
5. Bit (2-Fthyl-
--<10
ryl) phtholate
x
<10
<. 0005
1
pg/L
I b/Day
<10
<195
1
R. 4-aromo-
onyl phonyl
for (101-55-3)
x
<10
<. 0005
1
pg/L
I b/Day
<10
<195
1
0. Butyl senzyl
tholate (86.68-7
x
<10
< - 0005
1
A
1 b/Day
<10
<195
1
x
<10
<. 0005
1
pg/L
jA/Da
<10
< 195
1
B. 4-Chloto-
NnyfPhonyt
lot (70M72-3)
x
<10
<. 0005"
<10
<195
1
B. Chrysene
IR-01.9)
x
<10
<. 000
1<10
<195
1
S. Wbonzo (a,h)
F
1-10-3)ithrecono
x
<10
— -,-, - I,------.,--
<. 0005
—
1
A
/Da
<10
<195
1
B. 1,2-0;cbloro-
_—
—
nZeno (95-50-1)
x
<10
<. 0005
/L
_11b/Day
<10
<195
1
S. 1,3-01chloro-
1
nz I isno (541-73-1
x
<10
<. 0005
1
pg/L
lb/Day
<10
1 <195
1
k Form 3510-2C
(Rev.
2-85)
PAGE
V-6
CONTINUE
ON
PAGE V

I
ml
ON*INUfU FROM THE FRONT
I. POLLUTANT
2, MA"K 'X'
3, EFFLUENT
4, UNITS
AND CAS
N UMBER
h .. L WE'
h- *-- , "�
iw.0 V IF r
ILY VALUE MAXIMlymp 3,?,o Y VALUE 'PAt:
*.MAXIMUM0A Pat C
A N A
b, MASS
(it
"&I W
A I
E-ri:
yl�lf
GC/MS FRACTION
— BASE/NEUTRAL
COMPOUNDS
(cmitimsed)
438. N-NItro-
todiph*ny#emfno
f86*30-6)
440, Phonenthrone
185-01-8)
458. Pyrono
(129-MO)
yy
460. 1,2,4 - Fr—l-
thforobonsono
_t120-82-1)_
QC/MS FRACTION
— PESTICIDES
IP. Aldrin
(309-00-2)
2p. a-amC
319-84-6)
lb/T),qv
3PlqHC
(31 -85-7)—IhLDAY-
4P.1-SHC
(So 0-9)
1
jWdL
lb/Day
5P. S-Omc
019-86.8)'
6P. Chlordone
(61-74-9)
X
<20
<
I
uR/L
lb/Dav
7P. 4.4*-DDT
f50-29-3)
x
<20
OP. 4,4'-DDE
(72-65-9)
9P. 4,4'-000
(72-64-8)
<20
<. 001
lb Da
10P01oldrin
(60-57-1)
--X—
--<20--
—K-01—
'I IP, a-Endoswulfan
V
12P. P-Enclosuffen
(115.29-7)
<
13P. EndosurFf—s;n—
Su0sto
(1031-07-8)
Y
<20
< ou-
14P. endrin
(12-20a)
--<-2D-
--<,-0-0-1-.
15P. Endrin
Aldohvdo
47421.93-4)
I op> Hoptochlor
�(16-44-8)
EPA Form 3510-2C
(Rev.
2-85)
PAGE
V-0
CONTINUE
ON PAGE
V-9

s
s t • '"r: «7.« 'Y:rl :.. ""+MAY"
e e r
:. «•
a
OWN
i
_•
fff
B-1016
flit
i
PAGE V.g

MN fEPA #s ' Wu M 615 R (Copy trom lie"I i tr%Fc>rrrr tj for Approved WWC1
CHARGE
POLLUTANT
2.EFFLUENT
MAXIMUM DAILY ALUE
0 LON
----M-455; --TrrER VAL Irm a t, JIM
a.
'Wbirink)
TU14—M
b, No, OF
1.
a�
-1 ova
e)
If
(1, NO, OF
ANALYSES
a, CONCEW ASS
b. m
(2) MASS
ANALYSES
(2) AS.
lel
M A—
TRATION
CONOC.".AT§01S
W.
—0.0chernical
Oxygen Demand
2.0
20
1
mg/L lb/Day
1 19 527
1
b, Chemical
Oxygen Demand
8.4
84
1
mg/L lb/Day
<5 <97,636
1
c. Total Organic
Carbon (7'()C)
2.6
26
1
mg/L lb/Day
1.8 35,149
1
c[, Total Solids (TSS)Suspended
<4
<40
1
mg/L lb/Day
<4 <78,109
1
9. Ammonia (as N)
.18
2
1
mg/L lb/Day
.07 1,367
1
VALUE
VALUE
VALUE
VALkV
I. Flow
1.2
2
MGD X
2,340
CR
9. Temperature
0C
VALUE
(winter)
h. Temperature
VALUE
'VALUE
0C
VALUE
21
faurnmert
MINIMUM
IMAXIMUM
MINIMUM—
i. pH
1 00.2
PARTS- Mark ""X" in column 2-a for each pollutant you know or an
which is limited either directly, or indirectly
but expressly,hich ark
column 2a, you must provide quantitative data or an exptaraation of their presence it youi discharge. Complete one table for each outfall. See the instructions for<additionai details and nts.
I.POLLUT- 2, MARK 'X'
3, EFFLUENT
A. UNITS
5, INTAKE (optional)
ANT AND a,
—a
. MAXIMUM DAILY VALUE
b. MAXIM M 3,?,
(11 aval,
VjAY VALUE
a e
C.LONG T M VALUE
aVa a
("O� OF
a, LONCEW
b, MASS
AVERAGE VALUE
—
--TZT-
tX NO. OF
ANA L-
CAS NO LIEV�L
(if available*)
(2) MASS
CONC*.NTAATWON
(Z) MASS
MASS
ANAL-
YSES
-$;t^TlOr4
CONCENTR^TtON
MASS
YSES
CONCENTRATION
a. Bromide
X
<1
1
mg/L
lb/Day
<.I
<1,953
1
(24969-67-9)
b, Chlroeine
X
1
mg/L
lb/Day
.05
976
1
Total Frvl�ual
.05
.5
t. Color X
5
X
I
PCU
X
<5
X
1
No./
d. Fecal
X
5
X
1
X
5
X
1
Coliform
e, F'l u For i d a
�8..
X
<1
1
mg/L
lb/Day
<.1
<1,953
1
169B4 48-SY
( '9
If. Nitrate —
X
2
1
mg/L
1'b/Day
1
1,953
1
Nitrite (as N)
.21
EPA Form 3510-2C (Rev. 2-85)
PAGE V-1
CONTINUE ON REVERSE

"TFM V-6 CONTINUED FROM FRONT
MNS -00
I.L T
+t hi rt we �
3 I" F" F L it F• tU t
._
....... :. . ......�,.. _ .,-.......;. ___._ :.....
AWT A
GA'F
.
MAXIMUM DAILY VALUE0.
"YALU t v> t`I5 (4(
Rttl`C.l.�ixl. tf r(., m ANl
.a PS!.`fFrlea !P }
:`
...N_t...+.i_.tt.
Ft,i Fc.N.
a
(if ovailable)
fia•Preer±n t .em4 e5 tf
{ .
!Yh f M
_{....., q:
A .�
#�fSt
"k i } Y
,1
Total Organicx
(as NJ
31 3
y
1
f
y
b D
iJ/ I,I C
. LJG?
08
y 2
..[. y G.
y
.L
and
h, Groom
(fir
.13
1
1
mg/L
i b/Day
.13
2,538
1
i, Ix),rhorus
fog T Total
. 06
1
m / L
1 b/Da y
< » 02
< 390
1
17 73 14 Ol
1. Radioactivity
(1 ) Alpha,
Total
x
<. 8
x
1
pCin
x
<. 4
x
1
Tottaleta,
x
3. 9±1. 2
x
1
07 %
x
2.1±.
x
1
Total Radium,
< . 5
X
1
01 /
x
<1. 5
x
1
6, t l'
x<.1x
1
pCiA
x
1» 4±.
4 x
1
So
r` 04)
x
6.9
69
1
g/L
lb/Day
9.6
187,462
1
R 14St1S-7J•t1l
1. Sulfide
r)
x
<1
<10
1
mg/L
lb/Day
<1
<19,527
1
c7ex
<2
<20
1
m /L
g
lb/Day<2
<39,055
1
(14 65-46-3)
n. Surfactonts
x
<.2
<2
1
mg/L
lb/Day
<.2
<3,905
1
b. A Uin nuara,
Total
x
47
5
1
m /L
g
i b/Da
.61
11,912
1
(74 9.90.5)
P.
Total
x
.02
.2
1
mg/L
lb/Day
.02
390
1
� 3t
..
...... _.._ ».__...
_ _. ..., _ _..
_.W __..v...
Total T
T
.19
1
mg/L
lb/Day
.11
2,148
1
(144t -8)
Total
x
<.1
<1
1
mg L
lb/Day
<.1
<1,9
1
(7 0-40-4)
R Iron, Total
t74"-811- >
»12
1
1
mg/L
lb/Day
,858
1
Total 'x
1.4
14
1
mg/Llb/Day
1.2
23,433
1
I r4�g-g11.41
u, Molybdenum,
Total
x
.08
.8
1
mg/L
lb/Day
.07
1,367
1
t743f1•98}
Total
x
.05
.5
1
mg/L
lb/Day
.02
390
1
C.743S-S•St
.. Tin, Total
(740-1•)
x
1..6
16
1
mg/L
lb/Day
1.2
23,433
x T turn,
�rtal
x
.02
.2
1
mg/L
lb/Day
.02
390
1
(1440- • )
EPA Farm- 3 10- C (Rev. - Si
PAGE V-2
CONTINUF ON PAGE V, 3

:EPA 1.0, NUMBER fetal y frwn Rein 1 trfform dI OUTFALL NUMBER
I in tt r A/alrrl
OMH No 2
NCO024 92 005 Apptovir€,
CONTINUED FROM PAGE 3 OF FORM .0
P""Poir51 t,.:_. re ytru ar�<s tx varrrsry tre+.st�.rey atrutccea cerrar:�ee
for ,,.uc t C C/`MS fractions that a 1 t to our tncto�h aria lot ALL toxic inet its, cyanides, and total Irfaknots If you area that rerfru ed to nook column 2-aa l'se tnotfeary industries, rtraraprocess
2 to � a 6 Kr Y Y Y
w^:Fastewatet eau€f<o'ls anti tionre wired tiCIMS fr7actolrisi, mark "X" to cobjern, 2 to fir ejc:h pollutant you know or have reason to beheve i, present Mark "X*' to column 2 v for each pollutant you
a a r n pollutant, oo nova lovide thrr rt s1 rlts ut tat #t za:.r ont3 <anaalysis for that pollutant It yott rrook € olumn 2b tart any pollutant, yo€s roust provide the results
!r ltev� as alh5t'.tit If you ta,atk coltaraar 2K for any 6 Y I
, know or huvt€ rt.a son to beliewe it will be dischatt ec it, t,:am,erntt ations> of 10 pule or grt ater If ycru mask COMM) 2ta for aactolerrt, act ylonitrile, 2,
r,€ at least trtae analysis for that pollutant at you � ,h- You dischargern
dinto o :heool or 2 rnetli I YI to dinitra henot, tics most provides the :ttt.ult" of it tt e yt 0;W analysis for each h of these pullutaantts which You kt, ow or have rt..ascm to believe t at r
I Y fa Y I
, r t «, l" ,r 4 him t least one antal %is ut Irr jefl dest,rttrt- the re asons tho ollutant is ext ected to
t,urt+.cart,.<atatara„,caf1t7C7p{>bran}rraraterCC?ttaerlse„ftatlacaflt.t,arltstorwtaactryt,aalrtastkc.trltattan,�kr,yeatraatrs.l.t c �ta to y y P
bu di,,-J a,t a;t9 Notethat there are 7 pages to this pall, fafe ase It�wt>vv n�,ec:t; { <art�tellly t"canapfc.ttt taratt i<Ibtr: t`trJf 7t`aaary"a:�,iJ ftrr ". aerie wrtfaafl See insrvoc- nons> for additional details and rerloirenaents
t. fr+:Jt..t..U-TA T trAetlt .x. t; F.VF1,11E N T 4 ItNIT 5. tNTfit{C {<arrn+air=rta
tltlta AS la. M.Ai ttv,�ti § 1� �AY`VALU1„ t:a.t3NC Ti t p} q' ir, -VAt'J ... LUNG T rtM tt NfJ (al
"it1MCiE:> t, a htlk}CtMUM pAitYVAt Itttt,xetet, r of e+e.ttFrs+l Nca cla
r t - e . _ ._...._. _ . _... - _.. -. ,. }'. N A t. A V R A L+ A _ ANAL
'(tt (zl rans�. r v,x new t it
rr.,., ri rt a7taar� ._e raxao, i enu„. -,.
R A71CiN
METALS, CYANIDEL AND TC)TAL PHENOLS
t'inal t1440 36W X 6 <6... 1- mg/L lb/Day <.6 <11,716 :.1
(. , t,tat
7440 38 2) X <1 <. 01 1 pg/L l b/Day <1 <20
M, Beryllium
Total, 7440 47 1) X .002 .02 1 m g/L l b/Day .002 39 1
4M. Cadmium
Total (7440 45 9) X : .01 .1 1 mg/L l b/Day 01 195 1
5M, Chromium
Total (7440 47 3) X .05 .5 1 m /L l b/Day .04 781 1
BM Copper, Total W
(7 s0-e) X .05 1 mg/L 1 b/Day .03 586 1
7M Load, Total
(74 9.92.1) X 1 mg/L l b/Day <. 08 <1,562 1
e 439.97 i Total X <. 001 1 ' peg/L Ib/Day <.1 <2 1
(7Mna0t02 0) Total X .05 .5 1 m /L 1 b/Day <. 04 <781 1
IMW Salenttttrr,
Total $778 �" 2# X < <.02 1 pg/L lb/Day <2 < 9 1
1ttwn.Silver, Total X .04� <. 1 /L lb/Da <.04 <781 1
t7a�t-22-�� y
12M.Thsltunl, X <.5 <5 1 m /L 1b/Dad < 5 <9,764 1
Total (7440 2S 0) y
1 44o Eta � � D 3� �tl,t=, Total
t7aa06 6 1 m /L l b/Da .02 390 1
14M(51 12 S}
Ico (yentae, X <.02 <.2 1 /L lb/Day <.02 < 90 1
Total
15PA,Plater [ale, X <.005 <.05 1Ong/L lb/Day < 005 <98 1
DIOXIN
3 it's tea rxt C)E.5Cttlat- RESULTS
c ii€urtata tlrtrieccr 1,
t.atraatt7t,ttt€ X NEOAfI1/6
EPA Fora' 3510 2C: (Rev 2-55) PAGL v-3 CONTINUE ON txL VEEtSE

t1NTINUFA FROM THE
FRONT
at
MNS7005
1. POLLUTANT 2.
MARK
`x'
3. EFFLUENT
k UNITS
S. INTAKE
(optionall
AND GAS
NItNIEIII R e rssc
vrtc:
t0. •c
icVre
"""
c's -
catvtt
a. MAXIMUM DAILY
VALUE
•`.V'�'
b. MAXIM M 3
ava#4Lat4
p,qV VALUE
..,.••.._, ---.--..
c.LONG T y7M
aX nticztHabdt')
pY VALUE
it No or
ANAL-
a. CONCEW
b. MASS
a LONG
TERM wm
17At {a,
tr NO QI
ANAI
of
{tF tlabtel wawa-
rae-
ott"T
ass®
. «.
1+I
G ,iNCi Nia A7:1 Ci9M
:l MASS :
1,t
<: C}iVGH Nj$ AT44N
Irl A 5
1
C.Ir N+. RNTN AYaCJN
Itti A..�
rsk
TRATION
{vlr v.rrrs».
CiT ATix}N
ITI « sf
sEs
P t —VOLATILE
COMPOUNDS
IV*
t1 #
<5
.05
1
pg/L
1b/Day
5
<00
1
R A F
<5
<, 0
1 _
g/L
1 b/Day
<5
<98
1
pg L
: 1 b/Da
<1
<20
1
iz
ja
-
_
6.2ffiA21atoF
<1
<. 01
1tg/L
1/Day
<1
<20
1
<1
<.01.
1
g/L
1b/Day
<1
<2
1
he
FC-h#*rodi-
<1
<.01
1
D/L
1b/day
<1
<20
1
.
x
<1
<,01
1
ICJ/L
lb/Clay
<1
<20
1
4 6 3) hhaaT
<2
<. 02 '
1
l+g/L
1 b/Clay
<2
<30
1
ttIV,2-Mora-
ethyWInYEther
<_1
<.01
_ . _..
1
/L
1/Day
<1
<20
1
{11ih7l
'7-" Chloroform
6
<1
<«01
1
pg/L
lb/Day
<1
<20
1
bro thane x<1
<.01
1:
pg/L
lb/Day
<1
<20
1
1711.27•d�
31V, Olchloro-
difluoroma'thane
X
N/A
x
x
x
x
x
x
x
4V. 1,11-DICITIoro-
othant 175- t x
<1
<.01
1
leg/L
lb/Day
<1
<20
1
ISV. 1,2-Ellchloro-
of tr 7- t
1
<.01
1
N /L
lb/Day
<1
<20
1
16V. 1.1•Dichloro-
x
<1
<.01
1
pg/L
lb/Day
<1
<20
1
ethvle {76-35.4)
"17V. 1,2-010hloro-
x
<1
<.01
1
pg/L
lb/Day
<1
<20
1
propane(78.87- )
i$V.1,3-o a-
tsax-7ffi s► x
<1
<.01
1
pg/L
lb/Day
<1
<20
1
19V.. ethylbe"Zone
<1
<.01
1
pg/L
lb/Day
<1
<20
1 a
(1 41.41
t iya�.9I
<
<.02
1
leg/L
lb/Day
<2
<0
1
171 7-,
<1
<a01
1tg/L
lb/Day
<1
<20
1
EPA IFUFIrt 3510=2 (Rev,
-81
PAGE
V-4
CONTINUE
ON
PANE'

A'Lta, NUMBER
f(70PV fr(oll
IN'ttl I of Form
OMS No 2040
0086
Appt oval expires
7 31-88
CONTINUED FROM PAGE
V-4
I.POLLUTA, NT 2.
MARK
'A'
3, EFFLUENT
4. UNITS
5 INTAKE:
(optiona, I
AND CAS
NUMBER
a, MAXIMUM DAILY
VALUE
b. MAXIM, M 3,?
at,
Y VALUE
C
a? ,�A
cJ-ONG T M
ava
VALUE
M
No,
a. CONCEW
b,MASS
ANAL
tat:*
(if opurlabic) "to
put,.-
or
^&-
MASS
MASS
0)
T..To,
(If MASS
ANAL
TRATION
(s) co"cwkw
141 YSIES
GEMS FRACTION VOLATILE
1�- A I
COMPOUNDS (coutinuciff
t. ONC!�!IT!,tAl!0N
22V. Methylene
x
<1
<.01
pg/L
lb/Day
<1
<20 1
Chloride t75-O9-2)
23V. 1.1,2,2-Tatra-
chloroothane x
<1
<.01
I
pg/L
lb/Day
<1
<20 1
(79-34-5)
24V. Tstrachlorct-
x
<1
<.01
1
pg/L
lb/Day
<1
<20 1
ethylene (127 18 4)
25V. Tolue
110888-3)ne x
<1
<.01
1
pg/L
lb/Day
<1
<20 1
26V, 1,2-Trans -
Dichloroethylene x
<1
<.01
I
pg/L
lb/Day
<1
<20 1
(156-60-5)
1.1,1 Tti-
chloroothane x
<1
<.01
I
pg/L
lb/Day
<1
<20 1
(71.55-6)
--
chloroethane x
<1
<.01
1
pg/L
lb/Day
<1
<20 1
(79,00-5 )--
29V, Trichloro-
x
<1
<.01
I
pg/L
lb/Day
<1
<20 1
ethylene (79-01-6)
-iC\i-- foro-
. Tr7j.h-
fluoromethane
x N/A
<.01
x
x
x
x
x x
(75-69 4)
31V. Vinyl(75-01 x
<2
<.02
1
pg/L
lb/Day
<2
<39 1
Chloride
GC/MS FRACTION — ACID
COMPOUNDS
I A, 2-Chlorophenol
x
<10
<.1
I
pg/L
lb/Day
<10
<195 1
(95-67-8)
2A2,4-Dichlora V
A
<10
<.1
1
pg/L
lb/Day
<10
<195 1
phonof (120-83-2)
3A 2,4 Doricthyl V
A
<10
<.1
1
pg/L
lb/Day
<10
<195 1
phonol (105-67 9)
4A, 4,6-Dinitto 0 V
<10
<.1
I
pg/L
lb/Day
<10
<195 1
Cresol (534-52-1i
SA, 2,4-01rdtro-
<10
< .1
1
pg/L
lb/Day
<10
<195 1
Phenol (51-28-5)
6A, 2-Nitrophanol
x
<10
<.1
1
pg/L
lb/Day
<10
<195 1
(88-75-6)
7A, 4 Nitrophenof
x
<10
<.I
I
pg/L
lb/Day
<10
<195 1
000-02 7)
8A.p-Cfiloro-ML
x
<10
pg/L
lb/Day
<10
<195
CreSof (59 50-7)
4A,Pentachloro
<10
<.I
I
pg/L
lb/Day
<10
<195 1
i
phenol (87 86 5)
10A.-Phenol
<10
1
pg/L
lb/Day
<10
<195 1
(108952)
cMoro ph 01 x
<10
<.1
1
pg/L
lb/Day
<10
<195 1
(88-06-2)

Ct NTINUEP FROM THE
FRONT
i1 'tJ05
I,POLLUTANT a.
MAPK
`X'
UVVLU4.NT
4, ITS
_-._. _
, INTAKE (z/+rrzzrtfalf
.,.... ,.h�
AND AS
NUMBER v�
aaailehir
«r
V
•rwt
.MAXIMUMC9All
� }
crx �+c r.ann„ri+5
y VAt )1.
lt} wrnsa
_ _p
(7 M-AX IM,
Irasraxc
rt+rve. a. re+wtrtartr
..•.. Y VAC tll•
pp
l>i
C. C. C7 ril C� 7 M a4
fit�a
._ (zfr,�rtz,drCera
.._
verMr ta+ �¢«xan: «�
�`
x- V,'t L.t,a 6: sl
(:{ rrn s�
ac? ry r"
t C?
AwA.P.>.
Y ,r�"�
ar
M,asSfit
W_mt KaN (:. iC. i7
4 vAi.tt.__
vrxwt a
N43 OF
ANAC
GC/MS FRACTION -- BASElNEUTRAL
_
COMPOUNDS
1R. Acenephthena
(83 32.9)
28. Acenaphtylana
(206-96-6) x
<10_�
R, Anthracena
(120-12-7) x
<10
<. 1
a
g ( WTay
y (y #
48. Remidina
( 2- 7-)
< 0
<. 2j
g yp /gy
j} py
Anthracene
( 6- ► _
---w
- <10 _-_
<..1 ..
_
l
1 w
_fag/L lb/Day
<10 <195-
l
6R. RanXo (o)
Pyreno (50- 2- }
{
/L lb/D /
<10 <195
_..._
78, 3,4-Renzo-
tluoranthena
(2 -99.2) _
_. .
_ .
_.<10 . _
_
1 .
!O L. _lb/Day #
ci <i _._
_:. ._ _
Be. 6anzo (I)hi):..
Parylena
(191-24-) � . _.
_ _
.__._
_10 _
.1.
1__ .
FAD L 1b/D4y
<10 _.._<1 _.
-1-n
W Renzo (h)
Fluorenthena
(207.OR-9>
<10 .__.
_ .., ,
-D'—m _1/DaY
w <10 _ 15
1
108. Rig (2-Chlaro-
ethoxy) Methane
(111-911 _.
__.
<10
_ _._ .. _
_ _ . ..
1..__.,
_N_ /L lb/Day
.,.m<10. _. <1
—__l
1R. Ris(2-Chlarfa-
+ethyl) Ether
(111-44.4) x _.
g/Llb/Day
<10.. .__.<195
mil_,
126, 81e(2-GH�(10-2-$D.
Ether
<10
<.1
1
pg/L 1b/Day
<10 <1 5
113R.
Rig (hexyl)
PhV
A
<10
<.1
1
pg/L lb/Day
<10 <195
1,
phenyl Phenyl
Ether (101-55.3) X
<10
<.1
1
pg/L lb/Day
<10 <195
1
1513. outyl Renzyl
Pltthalato (85-M-71 X
<10
.1
1
. /L 1
<10 <195
1
1 CIR. 2-C'ti lore.
(91an#h58_7)
<10
<.1
1
g/L lb/Da
<10 <195
1
17R, 4-Chloro-
phenylPhonyl
<10
< 1
1
/L l b/Day
<195
?
Ether (7005.72 3)
_
_.:.._
_,..... ,
_ ...__.._ _
...,.<10
198. Chrysone
(21R 01 9) x<10
<.1
1
g/L lb/Day
<10 <195
1
198. Dibenzo (a,h)
Anthrecene
(53-70.3) x
<10
<.1
..
_...____.._ w.
1
p�iL lb/Day
<10 <195
1
208. 1,2-Dich loro-
benzene(95.50,1,)
<10
<.1
1
pg/L lb/Day,
._.. 10_ _:. _<195
1
21 R. 1,3-pichloro-
nzene(541,731 x
<10
<A
1
Dg/L lb/Day
<10 <195
1
EPA Farm 3510- C (Rev.
-85)
PAGE
-5
CONTINUE N INUE ON
PAGE L

forin Approved
I.D. NUMBER (COPY frOM Ileat I of Form 1)
OUTFALL NUMBER
OMB No, 2040.0086
J'EPA
Approval expires 7-31-88
CONTINUED FROM PAGE V-6
I.POLLUTANT
2, MARK 'X'
EFFLUENT
4, UNITS
S. INTAKE fop -
AND CAS
NUMBER .jb,
*E-
r- OIL-
lrmve,
8M^XjMUM DAILY VALUE
-3,
b, MAXI M 3,?,R/kY VALUE
e
-=a. 0 e
C.I. ONGT M
au
VALUE
4 NO OF
a CONCEW
b, MASS
A. L014G
TERM
b r4O,d`F
0 -
(it available) Alopt",
Pat,
**NY
11-1---- t4
YSES
TRATION
(1)
YSES
OCAM FRACTION - BASENEUTRAL
COMPOUNDS (continued,
228.1,4-Dichloro-
benzene (106-46-71
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
238. 3,T-Dichloro.
bonzidins
X
<20
<.2
1
pg/L
lb/Day
<20
<390
1
(91-94-1)
248. Dlathyl
Phthatate
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(84-66-2)
258.Dim Wt-hVl---
Phthalate
X
<10
<A
1
pg/L
lb/Day
<10
<195
1
(131-11-3)
268. DI-N-Butyl
Phthalate
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
(84-74-2)
2M 2,4-Dinitro-
toluene (121-14-2)
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
288, 2,6-Dinitro-
toluene (606-20-2)
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
29B. Di-N-Octyl
Phthalate
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(117-84-0)
308.1,2-Olphonyt-
hydrazine (as Azo-
X
<10
<A
1
pg/L
lb/Day
<10
<195
1
benzene) (122-66-71
31 BF
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(206-44-0)luoranthene
328. Fluorene
(86-73-7)
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
338, He"chlorebenzene
x
<10
<.1
1
pg/L
lb/Day
<10
<195
1
thlorobutadiene
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(87-68-3)
358. Hexachloro-
cyolopentediene
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(77
368. Hexachloto-
ethano (67-72-1)
V
A
<10
<.1
1
pg/L
lb/Day
<10
<195
1
378. Indeno
(1,Z3-cd) I'Vrene
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
(193-39-5)
386. loophn oroo
(78-59-1)
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
398. Naphthalene
X
<10
<.1
1
pg/L
lb/Day
<10
<195
1
(91-20-3)
408 hrobenzene
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
5-3)
sodimethylamine
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
(62.75-9)
-428.
N-Nitrosodi-
N-Propylarnine
X
<10
<.1
I
pg/L
lb/Day
<10
<195
1
t (621-64,7)
J
I
a
t'ONTIN(IF ON REVEr,

MNS-005
C6NT#NU1E FR THE FRONT
1,POL.LUTA4NT � MA"11 x.
1. UVrL,i;fi NI
d UNITi
� fNT1AKf-_ p,j,: xre=ail
AND CAS _ ...
:a ra at is er, G ion-
NUMBER
..
4, MAXIMUM 0ACLY t ALRt C"
i, MAX#' 3 �yqY tTALfis 6: C 4"?Nfia 'Y � iA K/C. P4 V AAC 4Pi"..
, y €t j
it tli: St)Ll k4' IF{tf! FI VIl
eJP
,t COW C N
;r t matt.. t c ftM
6A.V t,.la ,�= I,s i. Uf4LQfi�
d� ra r:s f#f
tNt+ 1.iE YFY dkk'vM
fit ii{rMi iabit+f +J t♦ 'f ?Y..I+Y
i
�.E wx w.. ^.
Ic
f
fxf nx ei .• i F' „
+l hi fi l..
"«d x
rti A4, TtttN
K� M.RA ry
( } a
A04ft6
L.i�iPa
.
tMt fY It YY{
GC/MS FRACTION -- BASE/NEUTRAL
COMPOUNOS [t`t)'Ihwfvdf
S
=438, N'Nitto-
iiP nylamine
B.Phenanthrene
(85-01-8)
FL !" �y y
. . 1t2, - Tri-
yy�
ma�ftt o r.
61F ' ! :.:<10
QC#A FRACTION -- PESTICIDE
2P. a-11H1
(19-8 -6)
3P, -8HC
t31E1S'7 y }
4P„ 8HC
d -9) x
SPY 8.8HC
(319.86-S)
hfor Brie
(67-74-9 )
(50.29.3)
SP:4,4'-D E
(72-SS-9 )
iP. +4r4'-00
(12.54-8)
-----
10P. Dieidrin
(60-57.1 )
11P, a.Frdosulfsn
f 115-29.7)
�. ..m— �.
_.,....-....»,...»..,..... _........_._
....., ._..»., ,,...»...„.„_„
._...».._.. ,._ .,,_.... .. ate .... .. .. ..:.... .. ...._,,.. ..>...., ....,.. _...,. <. �
.wWa. u.=.„.>.n
.....,. ., ....,......, _..,
.... .._
1 P. -Ender ifan
1116.29.7i
6uifate
}�
{ 1 i?31-ti7-8►
_ .....
drirt
}}1r+�4qP.E.p
16P+ Endlri
Ai vde
#7 1-93*wa
t1
EPA Form 3510-2C {Rev. 2•86}
PAGE v*8
CONTINUE ON PAGE V-9

HEM
(it
'67cWs-fi'�A�c�iiiN — PESTICIDES (continued)
7P Heptachlor
Epoxide
(1024.57-3)
lap, PCB-1242
(53469-21-9)
19P. PCB-1254
(11097-69-1)
20P. PCB-1221
(11104-28-2)
21P, PCB-1232
(11141.16-5)
22P. PCB-1248
(12672-29-6)
23P, PCB-1260
(11096-82-5)
24P. PCB-1016
(.12674-11-2)
25P. TOXOPhone
(8001-36-2) -L-
PAGE V-9

M a'- UN E iN
ITEM V-.0 CO--
1 PC LLuT'-
ANTAND
:.: N
($/atxailable)
. N1tt
TotalyC>reanlc
INUEI7 FROM FRUN t
2. MAttK
.,... v.d-.,..
a. m ' tr.{es' a. MR. ttMiJM #.roA4LW
#eevC xx.ueRx
P:w at - A tw" q-
arNr array $*�-..F_...®•,..••..
y„ixN{;p N11}A YYkN
a if
1'
_
VAL.t4E.
..M..... ,_..«-„».-
$t4.PAws
<w 06
_ 06
* 4
3.
h tatAMIN# M 9
( # tx#a#tx
TT
f{trN�aAYN&CPatN
6 FL ENT
.p.,.R...»�.....,.........�
bt Y VAI.tAI :
4:
$xl..AeAs•
c"L R-47':
# #t#Rr#a
....a.,.
cove{s•���3nr„xN.
+w+.
G. 1tq,�t9.c4,
a #r
:
$xlr:sAco
NO Hsu'
ANR#
VStK
1
1.._
4. UNITS
a. CONCEN-
7 ## A 1 I #"r N
/L
mg/L
m/L
tP, ttiASxa
µ Ib/Day
lb/Day
l b/Day
S. INTAKE (dPryr##tf#ud)
a rA G tf '.aM tr
A6ft, Ba :E A#.UE
�.e-t•oYYaASP:,N $<4MA+4
<. 06 <1,
w13 2,538
_ <. 02 <390
Nti:or
ANrAL-
Y�aE"
1
1
1
h:Off Sod
I. Photphotua
(at P). Total
17123-14401
!. Redloactiv$ty
1,1t Alpha.
Total
<
_
1
pC i/ L
x
< w 4
(2) secs,
! e
1
pCi/L
2w 1±. 6
Ax,
Total
<.
1
_ pCi/L
x
<1. 5
(3) Raulµ
Total
(4) Rattlu#n
<*
1
pCi/L
1.4±.4
228e Total
k. Su aca
1
m/L
1 b/Day
9.6 187,462
1
#sat apt. 041
14 '79-8l
<
<.
1
mg/L
l /Day
<1 <1 ,527
1
1. ulf1dor.x
,S�y.a�
< `�`
<T
1
mg/L
lb/D.ay
< <3 ,05
1
(w oj)
(14286.46-3)
�<w
<.1
1
mg/ L
lb/Day
<.2 <3,905
1
n.8utf enta
a.A r#urn
,5
.3
1
mg/L
lb/D:ay
.61- 11,912
1
$1429-90-5)
_
p. K
03
02
1
mg/L
1b/Day
.02 390
1
Total
(7440.39-3)
4. orb"'
m 07
D4
1
mg/ L
1 b/Day
.11 2,148
1
Total
<. 06
1
m /L
l /Day
<.1 <1,953
1
Total
11440.48.41
1
mg/L
1b/Day
.3 5,858
1
a. Iron, Tyotal
e1
1
mg/ L
1 b/Day
1.2 23,433
1
Total
$7439.98-41
47 -Molybdenum
.09
.06
1
m/L
1b/Day
.07 1,367
1
jTotal
y y
u. lingon000,
Tot a�ly
l
1
mg/L
l b/Day
.02 390
1
yyg y
. Tln* Total
37'64
—
1
1
mg/L
l b/Day
1.2 23,43
1
$744
A. T4ta#l{t,;_
T allot
C m
Cl
-
1
m/L
lb/Day
.0 0
1
4 1440 32 61
.., ... .._ , .
:.
f
.
.
�..
. _
.
.
.
-
.»
Vr"c a-r

Y jrutwt fta:ttt t of': orrrk t) OUTFALL NUMaER
farnt.4pprova
24392 N/A UNDER?) IN Omit No 2040,0086
FAtt) C It sat# ate a to onto mildly ano Hills, unit art contains process wastewater, rekrtat to k alit" 4%.•re ,tr ,tin is raft, uc,ru,ra rar-- „ .. rvm.:.,rra, —
Y
a fur all S.tt2tk GCMha4twtins that apply to your tntiiistry and for ALL liiwttsC mf#[all`a', cyakdits, and )rate) pnEkngl. If you a#8 not rest#artwtl to )nark Ct>)ttntrk 2 •al'sa'i:skndry inristriiys, nonprrkces
wa,stellil ;r outill antinonreyuiretst GCIM.S tractions). mark " C°` in cotumn 2-t7 tot each pollutant you know or have reason to believe is present, Mark "" to column 2-c for each pollutant You
believe wa. absent, it you mark column 2a for any pollutant, you must loovkdu the results of at least one analysts fist that; pollutant, It you mark cofuum 2b fat any pollutant, you mustprovide the results
of at')trast one analysis for that pollutant if you; know or have ru sctn to believe it will be discharged in concentrations of Ili Plitt or greater, If you mark cotoom 2b for acrolem, actylortktrile. 2,4
thothop hcsrtot; or 2-methyl•4, 6 dtnilrophenol, you must Provide the results of at least one analysis for each of these pollutants which you kneor w Have reason to believe that you discharge in
cunr.ckrtlkatwsk+is stf t b f)
p of rcwatstr, Otherwise, fttl fkoll}ttantafor which you ,slm,ta
ats column 2b, you us, either submit at least analysis or briefly describe the Mesons the pollutant is expected to
p
tasty stisk.hnttyt,sil Note that ,bete art# 7 pages to this part, Ttl,;askt ra:vtktw ustcla carefully Complete one table )'aff iwaes for each uutfalt See instructions for additional details and requirements,
I.POLLUTANTI AitK `x' 3. Er FLU ENT' j}{� 3 4. UNITS tit INTAKE or tion tf
A td t A ...^_ ,._...._ _®. __t
_ _..,,. ,"".. '•..." ir. A.kM tAM 9(�y,q�Y idALUE C. i.QNG T M .t $t#a`AG V It. 6.0NGK TERM
NUMBER d t x, it r,t c l,. aMAXIMUM DAI Y 4tAi.VL lit rttiattt Pd.'1 ftduw.trct ,a #JN6ENYi crt, ,:c ul.._ _...........: .. .„.... a.. —.,.--._ 4^ ANAL, t1 MASS ANAk
rtr xn+ttGtttr# ! _ TRATkCiN )rlrtcrwM
'" fa)MAtrtw ) 1 lal >. )Y1 let .ems. rYSiS )*)Y!iAtrit YE'S
t.t:r.. t#t,a al t xa a, r IYTN Atia}N 4e),t .. N,d Ri.;ai Ply.... .._.........�."m".„�.{L°titN a,Ft)ri w......+.w.m...�. ...«..®.
METALS,: CYANIDE, AND TOTAL PHENOLS
INA Antlrnony,.
Tutat 47440air Ol
ZM, Ateanic, 1 otol
x
(t440 2)
3M, Britylliton,
Total, 7440 41 7)
4M_ Cadailum.
R
T otal ) 7440 43 9)
M. Chromium,
x
Toted 17440 47t
6M Coppial Testa
)7 •64.8)
7 . Tiara)
17439.92.11
8M. Mercury. Total
1e439.97.61
N. Nicked, Total
st
1440-02-0)
i M. etsnium,
xoral
(7782-49 2)
1M. Silver, Total
x
r440-22.4)
M. Thaltium,
��r€
A
oral (7440-2 0)
..� _ ....._ _..._.�__ _ ......
3M. Zinc. Total{
. _ _.._ ._....._. �. _..yam._ ......_
t44A 66.6)
'.((.ilk Y`..
AIM IVI
l nits .ti Cl Jk., xt tit 3xk
PA t•ornk 3b)ti 2C. )tiov Ai
t)b) VAs..,L v•s Ct)NTtNUE ON f11FVLftSk

form A7cgrrtrv*d
pTOU FA -FA LL NUM8W OMS So 2040- 6
CONTINUED FROM PAGF V-4
NGUtJ 4
N/A
UN DERDRAIN
Appr#uar#xWr#s
7•31-e6
I. POLLUTANT 2. "AMA '
3.IEFFL.UENT
4. UNITS
A. INTAKE optf
AND CAS
NUMBER ara er Lt ee- G aa^
b. MAXI Spp Ulf VALUE
a. MAXIMUM DAILY VALUE auel(able
cl-0#4 r T Vp VALUE
atr# aeb78
d NO, OF
a. L N+ TSMA Is N4.Ai1F
t rrrc. rkvrr rates
(r/avaita le) Areia- isNY Y2 Nt
(rl lr} MAIN (rl (4) a^*$
i
(rl (2} 4sY4
ANAL^
yeas
■ CQNcaN-
bL MA1$.
TwATtoN
ANAL-
(r} GOrrCatYr IJI wwae YSIKS
COamti pr.Nrrtar#fr.N is otac apYat ATrd9lM
CttrgGattYw Arit#tr:
Ta Y a«
GC/MS FA TION -tr VOLATILE COMPOUNDS
(condtnu#d)
22V. Mathylane
Chloride (76.09-2)
23V. 1,1.2,2-Tatra-
chleroethan#
(19.34-51
24V, Tatrachloro-
(
ethylene (127-18-4
25V. Toluene
(1-88.3)-
28V. 1,2-Tram.
Diehloroethylene
1166-60.6}
27V. 1.1,1-Tri-
chforoathane
(71.66.6} -
28Vr--
chlaroethono
(79.00-6}
29V. Trichloto•
}(
athylsne (79.01-6)
lluo(orriethan#
IM69 4}
31V. Vinyl
}(
Chloride (75.01-4)
GC' FRACTION
•- ACID
CDMPO4
IA. 2-Chloropheno
(9t1=67.8}
2A.2a4-Dlchrloro-
phsenol (120.83.2)
3A= 2,4 Diniettiyi
phenot (105-67 9}
4A: 4.6-01rietto,0
}
Cresol (634.52.1 )
6A 2.4•Din tro•
{
ph l (61-28.5}
6A. 2-Nitrophanol
}
7A 4-Nitrophanot
41 •02 7} 5
8A P-Chtoro-M-
/t
Cresol (69 60.7}
9APootachturo
irhaticr9 t87 86 5)
10A MrEa,ra s
::X
t ttut3 *,.rG 1!
itj
I I A 2.44 1 rF
ij

MNS-UNI R TN
CONTINUED FROM
THE
FRONT
r.-POL.t UTANT
t, MARK
'x
3; EFFLUENT
4. UNITS
, INTAKE (4 pNr44na1)
AND CAS
MAXIMUM Di4rtY vxcv
Mx%iM M Sp
Y VALUEe,L MGT t
p #I VRt...UE tr
P4olo
ctaevcE4a
• 8.t7t1 TERM re.�tC9.Ci�'
NUMBER
rear
b •e- G.r• a.
di4144o
6r _ cr4a4r4ate
-.^
ANA4-
, t4. MA$S
M ANAL
(r(
4aao
aivar tarvr
#<r,.
(r (rr
i,r �+�re
vsE
raa tesrwr% i+r wrr xsE�
coacrr+raaxtceaork
r, cars ce r.n%awere'a«
cTMu rrce«ea.w saw>rr>++
._:..,�.M.
,,:
t3 CTIQN
— SASEMEUTRAL.
C POUNDS
18. A4: hthrno
(93.32.9)
28. AtonoPhIV1600
{
(208.9Er�Et}
38. Antht no{
(120.12-1)
48. 8ontidino
(
(247•6)
_
98, 86020 (a)
Anthr w
88. 80nzo (o){
Pyrono (0-32.)
7B. X4-8+1"110-
4uorolthono
(3 •99.2)
88. 8+nto (gh))
PorYlons '
9e. 84020 (k)
fluoroothatm
(2- hroro-Mothano
r1l
(hamh)oro-
4
126. "(2-i m
}(
ET t107- T►
13e. Bra f2w8#riyi-
txy() Phthalate
-eromo-
tPraonyr
r148.
1101.56.34
44twl eonzyt
ato (88 -ee.2.
Iona-
nmphth*1*o*
17e. 4-Chforo-
phonyr Phonyr
Ether (7_ -72-3)
FX
Ise. Chr so
t21a e1•a
t e« p#hwnto (4. )
Anthr ns
63.10-3)
ta*nrsne (95 5ti 1ii
2t iR3Ca#cta#csrtr
CPA Fnt Th1t)-2C:
tRev.
2-05)
PAGE V-6
CONTINUE ON PAGE 1

MNTIr, UM FROM PAGE V4
1, POLLUTANT ` A.
ANDCAS
NUMBER Ta.T #a:.- rr-
,N�. ,$ 4t..
fitavado&te) a"fwa ffi we .� Nt
OCfin FRACTION IEME TIRAL
bonsono (1 -7
a. btwx#1Jw#t_y vw#.4#e
#'1 #al a.ac$$
C #NYC. m:.N TRATfVX
COMPOUNDS (eontenuedt
3. EFFLUENT
MAX# # x a �y V^I.u6
ava
#r# #l1 .ew$$
va"Ca NTNATooft
4. UNITS S. #NTAKE top �l
c.#. r#a V'a#.u6 , o, raraec e### #�
ap!#RW-
Aw��- Mir: ww
}®} to) •+aa$$ vi At#iCe }s! a«e w lot aowoa Y
aC csNC NTNa$ 9GON : MX t aT t
�
238. 3,T-D1chlora
naW#no
(9194-1 }
248. Dlothy#
Phtha#otat
(94 66-2}
268. D#othy#
Phtho#oto
(131.11.3)
268. COPN- uty#
Phtha#ot t
( -74- )
278. 2,4• D#na#tro-
to#ono (121.1-2)
288. 2.6-01nitra-
tofuono (6 -20.2)
298. Di-N-00ty#
hthx#ote
(117.84.0)
308. 1,•D#Shony#-
hydror#ns (" xo
hen ent) 11 2.66-7
n
_u
318. F #uorsnthena
(2 44.0)
. Fluarionto
(06.73-7)
330.
4msxs
r348L
orabutadiene
8. Ho%ochlora-
cyclopeot #wns
8. Ha%aCh#ora-
athww (67-72-1 )
3718. # d#a
yr
( ,2,3-cd) Pyrono
/#
(193-39.6)
388. Nophorona
(78-69.1) ;
8. Naphthalene
191.20-3)
408 Nitrobaniene
1$.98 9 2}
4$#S N N+i+dt
idJil atTS.9tt y:B.rrain.
«a Pranvlsra#nv
+!

MNS-UNDERDRAIN
FROM THE FRONT
1. POLLUTANT 2. MARK M°
3. EFFLUENT4. UNITS
SE ).#t#tt.t" 4aritQA tj
AND CAS
NUMBER
*,MAXIMUM QAti4VALUE
. v VALUE cLAriml tCt
tztut : ai ii
p!rrfftltCGm+a
.#NTA##
YENt CiACLl!
i.tl#"
#ea#:
4tl:-
#ijataltt#atr# OM"
tomaarms
akaa•
•o +v •ae«v
_,.:.##
1+! #aj �4.as
GYaiVitl WYaa#Ytak#'4
« ,......... ...,_.,._:: ._.. A"At#tFAS4
µ #}1 i'H:pQ tN
#,! ..4 i,1 *aa . r*t 5
444M8l n#NAa#4A#+t :. 4" Ma i.:MY#a dk Y4KAM .�..W ®. m. ....:. ..®. _.. _:; .,,.. ...m. _..„.„..
l## rnraK rx+
#a! �+••• x5e
•Np94U#sp ..®. ,.". »......... «-."
....-..: ..
GC FRACTION — BASE/NEUTRAI. COMPOUNDS (eett4l ttatrtt)
438, N-Nttro-
k* YI�ilna
jj
as
C�Il1�3RO-��
44a. R#ea " thrana
I815-o1°8)
468. PyrWW
029 0)
. 1,2. - Tr!-
aftwo r
y
x
1 -1
QCJAAS FRACTION P- PESTICIDES
1P: A1clt9ta
(2)
2P. 4-8k1
3P. -SHC
(3I1 •8 -7) �{
i 9.9) }f
OP. 8-0040
8P. Ohlordono
(67-14.9) }(
7P. 4.4'-CLOT
(60.29-31 }(
8P. 4a4'•006
9P. 4,4'-DDD
(12-64-9) }{
10P. 01oldr lwt
11P. a-Endosuf#an
12P.p-EndoWAtfaA
1116.29.1) }�
13P,
Endoaullan
Sulfate
(1 1
4)
14P. Endrin
(12.20'8)
11#P. E"dr#n
Atdahvdw
(7421 93 4)
16P, *4#pfaCtA10(
t76448i
EPA Form 3610-2 (Rev. 2-85)
PAGE V>8
C014TINUE ON PAGE V4

I I ^*- F- lot "^*a 1 441 M^** reaxsx9—n lot COMc *4#-1
coftet VOAI#
GC/MS FRACTION PESTICIDES icontloued)
I ?P. Hoptuhtor
epoxidoo
11024-67-31
18P. PCO-1242
(63469-21-9)
14P. PCO-1264
111097-69-1)
20P. PCO-1221
I 11104-28-21
21P. PCB-1232
(11141-16-61
221`, PCB-1240
(12672-"-6)
23P, PC9-1260
24P. PCB-1016
t-12674.11-21
26P. Tolicoophootea
18001-36-2)
PAGE V-9

Date: August 31, 1988
NPDES STAFF REPORT AND RECOMMENDATIONS
County: Mecklenburg
NPD S Permit No. NC 0024392
PART
I- GENERAL INFORMATION
1.
Facility and Address. Duke Power Company
McGuire Nuclear Station
Post Office Box`33189
Charlotte, North Carolina 28242
2.
Date of Investigation: N/A
3`.
Report Prepared By: J. Thurman Horne, P. E.
4.
Person Contacted and 'telephone Number: Mr. W. T. Griffin;
(704) 7-5764
5.
Directions to Site. From the intersection of Highway 1
and Highway 73 travel east on Highway 73 approximately 3.2
miles. The facility is on the left (north) side of Highway
73 on the southern share of Lake Norman.
6.
Discharge Point - 001 & 004 002t 003 & 005
Latitude. 3502611011 30 `251 4011
Longitude: 8005613011 8005712011
Attach a"USGS Map Extract and indicate treatment plant site
and discharge point on map.
USGS Quad No.: F 15 NW
74
Size (land available for expansion and upgrading): The
existing site encompasses approximately fifty (50) acres.
There is adequate land available to construct additional
treatment facilities and modifications.
8.
Topography (relationship to flood plain included): Mildly
rolling, slopes are generally less than 10. The existing
facilities do not appear to be within any flood plain.
9.
Location of Nearest Dwelling: None within'1000 feet
10.
Receiving Stream or Affected Surface Waters:
001 & 004 002, 003 & 005
a. Classification Lake Norman Catawba Raver
b. River Basin and WS III & B WS III
Subbasan No.: 0 -08-32 03- 8-33

Rage Two
C.
Describereceiving stream features and pertinent
downstream uses. Outfall 001 & 004: The receiving
water body (Lake Norman) is used extensively for
primary and secondary recreation and as a municipal
water supply. The nearest water intake is for the
Town of Huntersv,ille and is located approximately 3
miles northeast of the discharge. Outfall 002 003
005: The receiving river (Catawba River) is used
extensively for primary and secondary recreation and
as a municipal water supply. The nearest 'water intake
is :for the City of Charlotte and is located
approximately 10'miles downstream.
:CART II -
DESCRIPTION OF DISCHARGE AND TREATMENT WORT
1. Type
of wastewater:
001
002' 003 004 00
0
0 100 0 0.3 % Domestic
100
100 0 100 99.7 % Industrial
a.
Volume of Wastewater:
001 002 003 004 005
2525 .41 0.04 .014 7.2 MGD
b.
Types and quantities of industrial. wastewater:
Outfall 001 (Cooling Water Discharge): This discharge
.s a combination of condenser cooling water (1,727,100
gpm), conventional low pressure service water (6,500
gpm), nuclear service water (,20,000 gpm) and. *turbine
building sumps (70 gpm) .
**Outfall 002 (conventional treatment system
discharge) : This discharge consists of steam
generator blowdo n, condensate demineralier backwash,
water treatment system backwash, demineralier
backwash, building drains, metal cleaning wastes and
*turbine building s ps .
Outfall 003 (sanitary waste treatments stem): This
discharge consists of the domestic type waste
generated by plant personnel.
Outfall 004 (liquid radwaste treatmentsystem),: This
discharge consists of low level liquid raw to (8
gpm) from minor spills, leaks, etc. in the auxiliary
and reactor buildings

Page Three
Outfall 005 (wastewater collection basin, WWCB): The
basin �receives the effluent from the sanitary waste
treatment system (Outfall 003), overflow from the
emergency standby nuclear service water pond, a
laboratory sink and floor drains, miscellaneous
building drains and condenser cooling water system
unwatering (2000 gpm).
C. Prevalent toxic constituents in wastewater:
Outfall 001 ***Outfall 002
Biocides (see attached letter Low level radio -
dated 2/28/86) low level radio- activity hydrazine
activity, chlorine, sodium
hydroxide, lithium hydroxide,
monohydrate, sulfuric acid,
boric acid, hydrazine.
Outfall 003 Outfall 004
None Low level radio-
activity hydrazine
Outfall 005
Low level radioactivity
d. Pretreatment Program (POTWs only): N/A
2. Production Rates (industrial discharges only) in Pounds:
I]
ri
r,
N
C
C
>plicable CFR Part and Subpart: 40 CFR Part 423 - steam
.ectric Power Generation
rpe of Treatment (specify whether proposed or existing):
itfall 001: None other than a discharge canal
)proximately 200 feet wide and 2,500 feet long for the
irpose of heat dissipation.
itfall 002: Wastewater is treated in the plant's existing
>nventi-onal wastewater treatment system which consists of
200,000 gallon initial holding pond, two (2) settling
)nds (in parallel) each with 2.5 million gallon capacity,
1 million gallon final holding pond (aerated -diffused
_r) and effluent pH adjustment consisting of automated CO 2
idition.

pa.gc
`our
The initial holding pond act
This pond may be bypassed, c
wastewater. The two settlir
one pond remains In standby.
the addition of coagulant as
ponds.
•I■
•
5. Slu
by
ai,.. art
as a flog equalization basin.
?ending on the nature of the
ponds are operated such that
Treatment can be enhanced by
and pH adjustment in these
ponds may be discharged
aam via outfall 002 or it may
pond. Effluent from the
--hargd through outfall 002 or
sands depending upon effluent
aitary wastewater treatment
alar aerated -:facultative
amber (tablet), and a parshall
.dlephone from Mr. W. T. Griffin on /2/).
,all 001 • None
:all 002: Sludges are disposed' by l.andfarming at
.mated on -site disposal area. This disposal is
Utted by ITEM Permit No. 741R2.
:all 00:3: ;Mudge is periodically removed from the
agoon and disposed at a municipal wastewater treatment
plant. Currently', the disposal is made at CMU r McDowel
Creek Wastewater 'Treatment Plant.
Outfall 00 : Sludges which accumulate in the liquid
radw ste system are disposed as low level radioactive
wastes at approved repositories such as Barnwell, South
Carolina.

Pagi
6.
**T
Five
L11 k1%-111t-1:CLJ.
OTHER PERTINENT
DTION
-ucted with Construction
ia.-s ,syUQ.L.L.Lt:" _L11 kw= Va.11CLL X-UL"-LJNZA-J--1
Specifications and Environmental Statement for the McGuire
Nuclear Station.
Additional effluent limits request: In accordance with
Duke's request, the current administrative limit for
hydrazine (.06 mg/l instream) should be included in the
Permit. X

Page Six
Outfall 005 (WWCB Basin) has previously been included as a
permitted outfall. It was removed years ago, but now is
proposed to be reinstated due to changes that have occurred
in Duke's operations. When this discharge was previously
permitted, Duke had considerable difficulty complying with
the maximum pH limitation (9.0 s.u.) during summer months.
The elevated pH was attributed to increased photosynthetic
activity in the WWCB.
Through conversations with Mr. Trevor Clements, Technical
Services, the MRO is aware that there are new or revised
modeling procedures that can be used where appropriate to
define the required pH limitations. Considering the large
dilution ratio of the receiving stream as compared to the
discharge volume, it is suggested that Technical Services
consider whether a relaxed pH limitation is appropriate.
PART IV - EVALUATION AND RECOMMENDATIONS
over the past several months, Duke has submitted several
requests for permit modifications, deletions of requests for
modifications, etc. From discussions with Dale Overcash, it is
our understanding that Duke has requested that we temporarily
withhold consideration of all requests except:
1. Request to include the discharge from the WWCB as a
separate permitted outfall (005).
2. Request that the Permit indicate that radioactive
releases be conducted in accordance with and under the
auspices of the NRC.
3. That the current administrative limitation for release
of hydrazine be incorporated directly into the PDES
Permit.
ecommend their approval.
Attached is a copy of the NRC requirements pertaining to
active Release at this facility.
S"4na-fure of Report Prepar er
vii—ter Quarity Re final Supervisor

/Ramp
Tr -ad r
Park Marna t
r
s 14 t
T Q' Manna c
x71
Creek
Ampgrol
C) 1 /
trra
�"" f '+,� =' E ' *'- --•:J bra} f"t,
'li r __--� . (I � �.i 1, 4 '^�"✓ /�'! � l� k � (�1 �9� 'ice .. � "�d`� a,� ��, � py,�.`�, .:
} t
i
rir8 `,'.'7i0 ..�
% r
4uwerpLB t
\31
rth
t'}lii t. � ,+*`X,• i �._- �\y "� �-..... � •r \ t�i: � �" � �`�• � e � f ,� 4 V"'�
Ba
kr
i' 00
seta

Y ,✓z a � �y � of p
RECEIVED
OF
rj
Cacilina Department of Human Resources
Division of Facility Services
UWAM cow
701 Barhotir Drive Raleigh, N, ( , ? 7603- 00
Jarnes t . Maiti , Governor a 0. Wilkerson, Jr., Director
David 'L Flaherty, `secretary Telephone [phone]
Tanury 27, 190
Thurman an Horn
Natural Resources anity velopt rrt
P. o x 950
Mooresville, N. C. 28115
Dear Mr. Horne:
This is in response to your telephone conversation of January 15, 1988 with
Dayne Brown, Chid of thee Radiation Protection ' Section regarding iquid
effluents containing radioactivity discharged rr the McGuire Nuclear Power
Station into Lake Nonnan and/car ti-te CatawbaRiver. Fc l se , please find copies
of relevant information t we obtained through the searching of; volumes of the
Final Safety Analysis tie (' ) , Technical Specifications and Environuental
Statement froto the McGuire Nuclear Station.
We dope that you will find this information helpful. If you have any further
questions, please feel free to calf me.
Sincerely yours,
,t
p
S. W. (Felix) Fong, Ph.I , Head
Nuclear ear 'acilities and Environmental
Radiation Surveillance Branch
'Radiation Protection Section
ao
Enclosures

Ar
WRCE TERMS
i-product inventory in the reactor core and the diffusion to the
cladding gap are discussed in Subsection 15.1.7.
ACTIVITIES IN THE REACTOR COOLANT
1 Fission Products
glil 111011111
cietermination OT anticipatea TIssion product activities are summarized
e 11.1.1-1, and the concentrations appear in Table 11.1.1-3.
Amum fission product activities in the reactor coolant during operation
iputed using the following differential equations (Ref. 1):
tient nuclides in the coolant,
dN wi = DV i N ci (xi + Rn i + 6 B1 B'0 IN wi
dt 0
ighter nuclides in the coolant,
dN Wi = DV.NQ - - ( x + RN + 81 N wj + N i N wi
3 B W
dt 0
N = nuclide population (atoms)
D = fraction of fuel having defective cladding
initial boron concentration (ppm)
B' = boron concentration reduction rate by feed and bleed (ppm per
second)
n = removal efficiency of purification cycle
X = radioactive decay constant (sec 1) -
V = escape rate coefficient for diffusion into coolant (sec 1)
t = time (sec)
Subscript c refers to core
Subscript w refers to coolant
Subscript i refers to parent nuclide
Subscript j refers to daughter nuclide
The results of the calculations are presented in Table 11.1.1-4. The fission
product inventory in the reactor core and the diffusion to the fuel pellet -
cladding gap are discussed in Section 15.1.
12/83

maximum fission product
ations. Experience to date
ie fuel defect for all operc-
zircaloy clad fuel -is con!
lure and burnup experience
`ission products (eg., xen(
do not take into account a
space which transports fi!
83MUMMEEM
Ift.t I.AfG V`Q7GM wit
Tritium
two principal contributors to tr
ly lower than this
;cussed in Chapter 4.
:ontinuous purge OT tne
Sion product gases to the
i.e.. Cr-51. Mn-54. Mn-56.
".5 ano are oasea on Lne-ju-5/
are included inn -Table
ith operating reactors.
duction within the PWR
4-VV t CXI IV. n%AU IV I VI IQ I a ItIQ If VV It&, I I LIM V IV I I Zi Q I K-. MQUI= MY L. I , L»f QIIU Mic7ul"Ut futil fit
the reactor water. Tritium production from different sources is shown in
Table 11.1.1-2. These sources are discussed below.
11.1.1.3.1 Fission Source
Tritium is formed within the fuel material and may
1. remain in the fuel rod uranium matrix,
2. diffuse into the cladding and become hydrided and fixed there,
3. diffuse through the clad into the primary coolant, or be
4. released to the coolant through microscopic cracks or failures in the
fuel cladding.
Previous Westinghouse design has conservatively assumed that the ratio of
fission tritium released into the coolant to the total fission tritium formed
was approximately 0.30 for zircaloy clad fuel. The operating experience at
the R. E. Ginna Plant of the Rochester Gas and Electric Company, and at other
operating reactors using zircaloy clad fuel, has shown that the tritium release
through the zircaloy fuel cladding is substantially less than the earlier
estimates used to predict. Consequently, the release fraction used is ten
percent as indicated in Table 11.1.1-2.
11.1.1.3.2 Control Rod Source
The full and part length rods for these units are zircaloy-clad silver -indium -
cadmium rather than boron. There are no "reactions in these absorber materials
which would produce tritium, thus eliminating any contribution from the control
rods.
11.1-2 12/83,

n
A direct contribution to the reactor coolant tritium concentration is made by
neutron reaction with the boron in solution. The concentration of boric acid
varies with core life and load follow so that this is a steadily decreasing
source during core life. The principal boron reactions are the B10,(n,20) H3
and B10 (n,a) Li reactions.
11.1.1.3.4 Burnable Shim Rod Source
These rods are*in the core only during the first operating cycle and potential
tritium contribution is only during this period as indicated in Table 11.1.1-2.
11.1.1.3.5 , Minor Sources
Lithium and deuterium reactions contribute only minor quantities to the tritium
inventory. The Liz reaction is controlled by limiting the overall lithium
concentration to approximately two ppm during operation. 06 is essentially
excluded from the system by utilizing 99.9 percent U7. Tritium generated from
these sources is shown in Table 11.1.1-2.
11.1.1.3.6 Reactor Coolant Tritium Concentration
The tritium concentration shown in Table 11.1.1-3 is the equilibrium result of
the source term in Table 11.1.1-2 and the releases in Table 11.2.6-1. It is
assumed that the tritium in the station is mixed in both reactor coolant
Mtn 16
cooled reactor, the hydrogen in the circulating water P
-.7u, f-l-v. 11, - =11117:6lull ul Per it! Gr-d I. i rig rdu-id-Li on are:
0-16 (n, p) N-16
0-17 (n, p) N-17
0-18 (n, X) N-19
The N-16 isotope decays with a half-life of 7.35 seconds, emitting high energ
gammas in 75 percent of the disintegrations (70 percent at 6.13 Mev and 5
percent at 7.11 Mev). The resulting reactor coolant activity is shown in Tab'
12.1.3-4.
11.1.2 SECONDARY COOLANT ACTIVITIES
Primary -to -secondary leakage will result in the buildup of activity in the
U-tube steam generators. The anticipated concentrations in Table 11.2.2-3 ari
11.1-3 12/81

tt- •t
« .t
.t
t t
t t t
t t t
Standard N237. Values of parameters utilized in
ble 11.1.1-1.
g secondary side steam activities are given in
used to obtain these- activities assumed primary
activity input to steam generator secondary side
y and steam generator blodown were assumed to be
team generator secondary water. The secondary'
2-2 are the equilibrium levels. All noble gases
e secondary system in steam leaks and via the air
si derd in Table 11.1`. 2-2.
NS-SL-653 of June 18, 1973 from R. Salvatori to
, Directorate of Licensing, USAEC.
2. Source Term Data for Westinghouse Pressurized hater Reactors, WCAP 8253,
May, 1974.
3. Locante, J. and Malinowski, D. D., "Tritium in Pressurized Water Reac-
tors," American Nuclear Soviet Transactions, Vol. 1.4, No. 1, 1971.
4. ANSI Standard N237-1976 "Source Term Specification," American Nuclear
Society, May, 1976.
5. Schreiker, R. E. and Lorii, J. A.', Operation Experiences with Westinghouse
Core, WCAP-8183, December, 1976.
11.1.-4 12/83

1.
Ultimate core thermal power, MWt
3636
2.
Clad defects, as a present of rated core thermal power being
generated by rods with clad defects
0.12
3.
Reactor coolant liquid mass, lbm
4.62 x
10 5
4.
Reactor coolant full power average temperature, F
590
S.
Purification flow rate (normal) gpm
75
6.
Effective cation demineralizer flow, gpm
3.0
7.
Volume contra A tank volumes
a. Vapor, ft 3
240
160
b. Liquid, ft
B.
Fission product escape rate_ioefficients:
1
a. Noble gas isotopes, sec -1
6.5 x,
1.3
1
b. Br, Rb, 1 and Cs sotopes, sec
x
c. Te isotopes, sec
1.0 x
9
d. Mo isotopes, sec
2.0 x
1
10 11
e. Sr and Ba isotopes, sec
1.0 x
12
f. Y, La, Ce, Pr isotopes, sec
1.6 x,10
9.
Mixed bed demineralizers decontamination factors:
a. Noble gases and Cs-134, 136, 137, Y-90, 91 and Mo-99
b. All other isotopes including corrosion products
10.
Cation bed demineralizer decontamination factors
*Escape rate coefficients are based on Westinghouse Fuel defect tests performed at
the Saxton reactor. Recent
experience at two plants operating with fuel rod defects has verified the listed
escape rate coefficients.

.t.L. gut "'Okf I6iLIT :UI tCUIN 11UUIU ydb b GT'1PPIfly Id(::.WT-t .
I rlt-0 o Stri ping Fraction
Kr--85 2.3 x 1_ 1
Kr-85m 2.7 x 10
Kr-87 6.0 x 10_1
Kr-88 4.3 x 10
X -131 m 1.0 x 1 r,
Xe-133 1.6 x 10
X -1. 3 3 m 3.7 x 10
X -135 1.8 x 10
X -135m 8.0 x 10 1
X-1381.0
12. Baron Concentration and Reduction Rates
a. B0 (initial cycled 85 ppm
B' (initial cycle) 2.1 ppm/day
b. 80 (equilibrium circle) 1080 ppr
' (equilibrium cycle). 3.9 ppmlday
13. Pressurizer Volumes
a. Vapor 720 ft3
b'. Liquid 1080 ft
14. Spray Line Flow 1.0 gpm
15. Pressurizer Stripping Fractions
a. Noble gases 1.
b. All other elements
Volume control tank purge rate is 0.7 scfm.
Volume control tarok stripping efficiency is 40 percent.
12/83

Table 111.1-
Desi
n Basis Tritium Production fur Ong
Unit
Expected Release
Total Produced
to Reactor Coolant
ritim Source
curies/yr)
(curies/yr)
ernary Fission
10500
1050
Wrnabl e Poison Rods'
;Initial Cycle)
120
152
Soluble Boron
,Initial Cycle)
222
222
'Equilibrium Cycle)
309
30
Lithium and Deuterium
reactions
110
110
Total Initial Cycle
12352
1540
Total Equilibrium Cycle 10919
1470
Basis:
Power Level
3555
MWt
Load Factor
0•B
Release Fraction from
Fuel
10
Release Fraction from
Burnable Portion Pods
10
Burnable Poison Rod B-10 Mass
6160
cdpm
Reactor Coolant: Boron
Concentration (Initial Cycle)
860
ppm
Reactor Coolant Boron
Concentration (Equilibrium Cycle)
1200
ppm
12/B3

Table 11.1.1-
Reator Coolant Fission and Corrosion Product Activities
During Normal Operation
Activity Activity
Isotope (Ci/ m) Istope (kci/ m
H-3 1.0 _ Cs-134 2.8 x 10-1
Br-83 5.9 10_3 I-135 2.3 x 10_2
Br-84 3.3 x 10_ -136 . x 10-2'
Br-85 3.8 10 Cs-137 2.0 x 10
Rb-86 9.5 x 10 Ba-137m 2.0 x10-9
Rb-88 2.5x 10 8a•-140 2.4 x 10-
Sr-89 3.7 x 10_ La-140 1.7 x 10 '
Sr-9 1.1 x 10_ Ce141 .4 x 10 5
Y-90 1. x 10_ e-143 4.4 x 10-5
Sr-91 7.6 x 10 Pr-143 5.3 x' 10
Y-91M 4.5 x 10 Ce-144 3.5 x 10
Y-91 6.8 x 10_5 Pr-144 4.2 x 10_3
-9 4.0 x 10 Cr�-51 .0 x 10
7r-95 6.4 x 10- Mn-54 3.3 x' 10
Nb-95 5.3 x 10_ e-55' 1.7 x 10�3
Mo-99 9.1 x 10_ Fe5 1.1 x 10-2
Tc-99m 5.7 x 10 Co-58 1.7 x 10
Ru-103 4.8 x 10 Co-60 2.1 x`10
Rb-103m 5.6 x 10 5 Kr-83m2.2 x 10
Ru-°106 1.1 x 10 Kr-85m 9.3 x 10
Rh-106 1.3 x 10 5 Kr-85 2.2 x 10_2
Te-125m 3.1 x 10 Kr-87 6.7 x 10
Te-127m 3.0 x 10- Kr-88 1.9 x 10-
Te-127 9.9 x 10 Kr-89 .3 x 10
Te�-129 2.0 x 10- e-131m 5.6 x 10
1-130 2.4 x 10 Xe-1m 4.1 x' 10
Te-131m 2.8 x 104 Xe-133 1.7 -2
Te-131 1.4 x 10 Xe-135m 1.6 x' 10
1-131. 2.9 x 10- Xe-135 2.2 x` 10
Te-132 2.9 x 10 Xe-137 1..1 x 10
1-132 1.2 x 10 Xe�138 5.4 x 10-2
1-133 4.3 x 10
1-134 5.9 x 10
12/83

Table 11.1.1-4
Reactor Coolant Fission and Corrosion Product Activities
During Normal Operation`
Activity Activity
Isotope Ci/) toe (EC i/ )
H-3 3.5 _ Cs-136 0.15
Br-84 4.3 x 10 C -137 1.5
Rb-88 3.7 _1 Cs-138 0.98 _3
Rb-89 1.1 x 10 Ba-140 43 x 111
Sr-89 3.3 x 10- L -140 1.5 x 10
Sr-90 1.7 x 10 C-144; 34 x 10
Sr-1 1.9 x '10_� Pr-144 3.4 x 10�4
Sr-92 7.4 x 10 -A Kr-85 88
Y-90 2.0 x 10_3 Kr-85m` 21
Y-91 6.1 x 10_Kr-87 1.2
Y-92 7.2 x 10_4 Kr-88 3.7
7r-95 7.0 x 10_4 Xe-131m 1.9 2
Nb-95 6.9 x_10 Xe-133 2.81 x 10
Mo-99 5.3 e-1 3 3.1
I-131 2.5 Xe°-135 63
-132 0.9 Xe-13m 0.7
1-133 4.0 Xe-138 0.
-134 0.6 C-51 2.0 x 10_
I-135 2.2 Mn-54 7.9 x 10_2
Te-132 0.26 Mn-56 3.0 x 10
e-13 2.9 x 10-2 Co-58 2.6 x lo-
s-134 0.3 Co-60 2.1 x 10
NOTE: Based on operation 'with 'defects in cladding of rods generating 1
percent of the core rated power and with the Waste Gas System remove
from service.
ti
/83

Table e 11
Parameters Used in Cal�olati
Fuel Defect Fraction
Primary to Secondary Leak Rate
0.12%
100 lbs/dav
Steam Generator Water Mass 88,000 lbs/generator
Steam Generator Blowdown Rate 45,000 lbs/hr.
Steam Generator Internal 0.01
Partition Factor for Iodine
Secondary System Demineralizer 10
Iodine Decontamination Factor (DO
12/83

Tab
Pain Steam Iodine
From Steam
1ste a
.
itions Rasuitina
1-131
9.7
x
10
1-132
2.9
x
10®8
1-133
1.3
x
10-7
1-134
9.8
x
10- 9
1-135
5.8
x
10-
12/83

Table 11.2.2-1 (Page 1 of 2)
Desi n Basis Source Strn the for Radioactiue Taste S'stems In ut Streams
The following list
is an explanation of source strengths identified on Figures
11.2.2-1., .1..2, - ,
11. . ~- , 1. . .2-4, 9. . -1, and . . -2 by alphabetical
flag designations as
follows:
Y
Y. Maximum anticipated nuclide concentration
X
. Normal 'operational nuclide concentration
Flag Letter
Source Strength
Reactor coolant containing fission and corrosion
products
B
Reactor coolant downstream of mixed -bed demineralizer
Reactor coolant downstream of mined -bed and cation -
bed demineraliers
D
Reactor coolant, demineralized, gas -stripped (see
Volume Control Tank Activities - Table 112.2-2)
F
Reactor coolant, fully degasses
F
Reactor coolant, fully degasses, diluted with other
leakage (drain header, dilution factor = 1/50)
Reactor coolant; dilated with other 'leakage (flush
header, factor = 1/50)
Reactor coolant, degassed, evaporated (DF = 1000)
I
Reactor coolant, degassed demineralized, diluted
1/4.8 (Refueling water storage tank)
,]
Reactor coolant, degassed, demineralized, diluted
1/4.8 (Refueling mode)
Reactor coolant, design basis LDCA sump
L
Reactor coolant, degassed, demineralized, diluted 1/8
(Fuel pool water)
Fuel Fool water, demineralized (Fuel Pool
eminraliers effluent)
N
Evaporator concentrates, nonreyclable (see Table
11.5.2-1 and fable 11.. .4-1, see Subsection 1.1..5.2'
for inputs)
12/83

Table 11.2.2-1 (Page ,2 of
Flack Letter
Source Strn th
Demineralizer resins (1 part combined resins plus 2
parts sluice water (spent resin cone. from Table
1.5.-1 divided by factor of 3, see Subsection
11..2 for inputs)
emineralizer resin sluice water return (equal to
Flag )
Waste Gas Tank (normal) (See Table 11.3.2-1 and
divide by tank volume of 600 F. for concentration)
Secondary side activity caused by steam generator
tube leak (See Table 11.2.2-)
Mixing and settling tank sludge (equal to Flag F)
T
Liquid waste systems tanks vent header (vapor);
U
Containment ventilation unit, condensate drains'
Spent resins (combined and decayed for 6 months
assuming demineralizer resins replaced once per year
See Table 11.5.-1 and Subsection 11.5.4)
Maximum activity allowed by Environmental Technical'
Specifications divided by tank volume of 600 ft. for
e
concentration
12/ 3

Table 112.-
Maximum Volume Control Tank Activities
t
(Based on parameters given in
Table 11.1.1-1)
Vapor Activity
(Curies)
*Stripping
Fractions with Assuming
Operations
Plant
Without
Isotope
WGS 02erating of
WCS
WGS
Kr-85
0.35 6.8 x
10-1
1.4
Kr-8 m
0.50 6.6
6.6
Kr-87
0.69 2.2
2.3
Kr°-
0.57 1.0 x
101
1.1
x 10
Xe-131m
0.39 1.4
9.8
Xe-133
0.40 4.1 x
102
1.4
x 10
Xe-133m
0.41 8.3
1.5
x 101
Xe-135
0.48 2.6 x
101
2.6
x 101
Xe-138
1.00 4.5 x
10-1
4.7
x 10-1
a
* Volume control tank purge rate is 0.7 scfm.
Stripping
efficiency is 100 percent.
12/83

Table 11. 2. 2-3
Steam Generator Blewdown Concentrations
Activity Activity
Isotope { Ci/ m) Isotope Ci/ m}
H-3 1.0 x 10 1-134 5.9 x 10-
Br-83 1.1 x 10 Cs-134 2.4 x 10
Br-84 2.3 x 100 I-135 5. x 10
Br-89 3.0 10 C-136 1.3 x 10
Rb-86 8.3 x 10 9 Cs-1371.8 x 10-
Rb-88 1.1 x 10.
_11 Ba-137m .4 x 10_8
Sr--89 3.4 x 10_ , Ba-140 .7 x 10
Sr-90 6.8 x 10_10 10 L -140 1.2 x'10-
Y-90; 1.4 0 Ce-141 6.8 x 10
Sr-91 3.4 x 10$ Ce-143 3.4 x 10
Y-91M 1.6 x 10_ r-143 3.4 x 10_
Y-91 5.1 x 10 Ce-144 3.4 x 10_16
Y-93° 1.7 x 10 Pr-144 1.5 x'10
Zr95 6.8 x 10- Cr-51 1.5 x 10_
Nb-95 6.8 x 10 Mn-54 3.4 x+ 10
Mo-99 6.8 x 10- Fe-55 .4 x' 10-7
Tc-99m 5.0 x 10 Fe-59 1.0 x'10
Ru-103 .4 10 Co-58 1.4 x' 10�
Rh-°183m 3.1 x 10 Co-60 .5 x' 10
Ru 106 .8 x 10-10 r-83 .6 x" 10-
R 196 6.0 x 10 Kr-85m 2.4 x 10 10
e-125m 1.7 10-8 Kr-85 5.6 x 10-
Te127m 1.7 x 10 Kr-87 .6 x 10
Te�-1.7 5.1 x 108 r-88 4.9 x 10_
Te-19m 1.0 x 10 Kr-89 1.6 x 10
Te-129 9.5 x 10-g Xe-1 1m 1.5 x 10-
1-130 6.9 x 10 Xe-1 3m 1.1 xi 10
Te-131m 1.7 x 10_ Xe-133 4.4 x 10_
Te-131 3.1 x 10 Xe-15m 4>1 x 10
1-131 9.7 10 Xe-135 5.6 10� 0
Te-132 1.7 10 Xe-137 2.9 x 10
1-132 2.9 x 10 Xe-1 8 1.4 x 10-8
1-13 1.3 x 10
12/83

Table 12.1.-
Reactor Coolant System nitro en-16 Actiuit
N-16
Component Ci/cam
Reactor Vessel, Core 95
Reactor Vessel, Upper Region 125
Reactor Outlet Pipe 113
Steam Generator 92
Coolant Pump 69
Reactor Inlet Pipe 65
12/3

14 IJ io
3-39
XIOACTIVE WASTE SYSTEMS
Iiiveccluter ��, � i�� t i) are useo
systems(.
F 11 l'i 111,
- r-- -- 11- "CAJ-V-ill 1:,Va-LU41-J-VL1
Lscussion of the radioactive
I,--- --- —1— . ----- ------
lear power plants consistent with keeping radioactivity in effluents
resultant radiation exposures to levels which are as low as practicable.
.1 Liouid Waste
liquid radioactive waste treatment system will consist of the tanks,
in, pumps, evaporators, process equipment, and instrumentation necessary
collect, process, store, analyze, monitor, and discharge any potentially
ioactive wastes from the plant. Although the liquid waste will be collected

}
1'
-0
continuously, the process and storage systems will be sized so that proeesE
of this waste will be done on a periodic basis. Thus, treated liquid waste
to be released will be handled on a batch basis as required, permitting
optimum control measures and reducing the chancre for an inadvertent discha
of radioactive liquid in excess of release limits. Prior to release of any
treated liquid wastes, samples will be analyzed to determine the amount o
radioactivity in the 'batch to assure conformance with release limits.
diation monitors will automatically terminate liquid waste discharges if
-high radiation levels are detected in the discharge line.
'the bulk of the radioactive liquids that will be released from the reactor
coolant system will be processed and recycled through use of the baron
recycle system (see dig. .1). The function of the boron recycle system
will be to process part of the reactor coolant letdown for reuse of the
baron and purified water, but a small portion of this water will be dis-
charged for plant tritium control.
The boron recycle system for the McGuire plant is not designed to process
reactor i-nni not` cat-,4^, 4 » 1 --A C— t I ___s
is ! � • � �:> 9! .y �.
is to be di
ran be
ated react'
Lant .
A
processed liquids will normally be recycled to the reactor makeup water
storage tank or the baron recycle holdup tank for reuse in the plant.
Operating e` evi nce at `other si ilar,!planto.<ha ,'sho x,that,=it-will b E
n c asa y tc discharge' tritium at ° th Iarrata,, 01 eix=2000c' Qi/yea r,from
the' plant'"pr'ir cool "t systems ins.;circlet� preVent ru desi;rabl.y', h Lgh
tri.ti acc " 3:ationt' °thin ' the t:pl tl; This is accomplished by occasional
release of treated tritiated water from Channel A to the condenser cooling
water discharge instead of returning it to the reactor makeup water storage
tank or the boron recycle holdup t k'for reuse in the primary coolant
system.

S
TEAM TURBINES
REACTORS
STEAM
GENERATORS
CONDENSATE
CONDENSERS
tS uoon
VOLUME
CONTROL
BORON THERMAL
REGENERATION
LETDOWN
TO PRIMARY
COOLANT LOOPS
TANK
SYSTEM
DEMINERALIZERS
CONDENSATE
REACTOR MAKEUP
: .STORAGE
:..WATER
STORAGE
TANK
�
DEAERATED TRITIATED
STEAM
WATER:
GENERATOR
"BORON RECYCLE
SLOWDOWN
FLANGE LEAKOF`.fS, VALVE
LEAKOFFs, PUMP SEAS
REACTOR COOLANT
BORON RECYCLE
EVAPORATOR
CONDENSATE
:TANK
LExKQFFS,
DRAIN TANKS
I
HOLDUP TANK
'..bEMfNERALdZER
I
STEAM
1.
BORON: RECYCLE
BORON RECYCLE
GENERATOR
I..
EVAPORATOR
EVAPORATOR
SLOWDOWN
I
FEED
GAS STRIPPER
DEMINERALIZER
I
I
DEMINERALIZER:
PACKAGE
AERATED TRITIATED
----- ^-�----------
WASTE: (CHANNEL Ad
EQUIPMENT LEAKS AND DRAINS
VALVE LEAKOFFS, POMP SEAL
WASTE HOLDUP
WASTE
WAS!:
WASTE
EVAPORATOR
CONDENSATE
RECYCLE
(
LEAKOFFS,TAIaaOVERFLOWS,
OTHER SOURCES.:
I
DEMINERALIZER
MONITOR
l
AERATED NONTRITIATED
WASTE (CHANNEL B)
1
FLOOR DRAINS, SINK DRAINS,
SOME.. EQUIPMENT DRAINS,.
FLOOR :DRAIN
MIXING AND
SETT G
WASTE I
MONITOR
WASTE
MONITOR
OTHER SOURCES
TANK
TANK
DEMINERALIZER
TANKS
LAUNDRY AND SHOWER
LAUNDRY AND
WASTE.. WATER.:
SHOWER
TANK
2.,900 cos:
SPENT RESINS, .EVAPORATOR
WASTE
ON -SITE
OFF -SITE
9OTTOMS, MISCELLANEOUS
DRUMMING
--°—
STORAGE
DISPOSAL
SOLID WASTES
ROOM
DISCHARGE
INTAKE
STRUCTURE �:;-.-• STRUCTURE
--_-- ALTERNATE
y
t
EA_W{ i0j� ara
zz
Figure
3.16 Liquid waste disposal system.

3-42
Channel B will be designed to handle low -purity waste (nontritiated)
from the laundry and personnel shower drain tanks (normally the largest
volume sources) and the floor drain tanks. This waste will normally have
low activity. The waste treatment equipment provided in Channel B will
include a mixing and settling ;tank for the laundry and shower drain waste,
filters, a waste monitor carbon filter, and waste monitor demineralizer.
Interconnections (not shown in Fig. 3.16) will be provided with the waste
evaporator in Channel A so that Channel. B wastes can be processed through
the waste evaporator in the event of an unexpected high level of 'activity.
In addition to the Channel A and Channel B liquid waste subsystems,
the applicant will incorporate a steam generator blowdown recycle system
to treat the blowdo' (water periodically flushed from the secondary coolant
system to maintain chemical purity of the secondary coolant) should steam
generator tube leakage result in the presence of radioactivity in the
secondary side. The steam generator blowdown water, when contaminated
with radioactivity, will be processed by the steam genexator blowdown
recycle system and reused in the plant.
The applicant has stated that there will be significant design
margin in the liquid waste treatment system to feceive and ocess liquid
AO
waste. For instance, the applicant has estimated that 163gal of
reactor coolant per; year will be treated by the liquid waste treatment
system, although the capacity of the 5- pm waste ev poratwor at a 25% load
factor is 657,00 gal (four times the estimated input). From our review
of the liquid waste disposal system in the plant, there appears t be
sufficient capacity, redundancy, and flexibility to assure that, ;under
any reasonably expected conditions, the plant can be operated so that the
radioactivity concentrations in liquid effluents :can be held to a small
fraction of the limits defined by 10 CFR Fart. 20 and that these concen-
trations may be said to be as low as practicable in accordance with 10
CFR Part 5.
In the absenceof a firm commitment from Duke Power Company And a horough'
engineering evaluation by the staff at the construction permit stage of
the concentration doses and environmental effe is of radioae Ye'releases
from the McGuire Station. The average expect d annual rele for each
nuclide is given in Column 2 of Table 3.13.
41,1111
Column 3, headed "initial concentration in discharge canal," is the
expected annual release diluted by the annual volume of water flowing
through the condenser cooling w t r di'harge canal. This is normally the
maximum concentration of nuclides eleaxed to a beady of water from a PWR
power plaint. In the present case, however, it appears that, under reason-
ably expected conditions, a fraction'of the activity entering Lake

�y in liquid eMuents from MGi,, Units I and 2
'large canal 2.9 x 103 efir
met 2.6 x I or efir
2,9 x to, cis
net 10 x to' its
I'll X 108 ft3
barge canal -'"initial concentration"
concentration in channel
Annual
concentration"
Steady-state(PCIMI)
Radionuclide
release
in discharge
Assuming no
dilution by lake
-con-ft"a"On
Assuming dilution by take
(0/year)
canal
(Acvml)
Channel
Pool
Channel:
Pont
86 Re
0.0026
1.0 x to-"
1.1 X 10-"
Ll X 102
LO x 10-12
2.o x 16-11
99 Sr
0.0024
9.3 x 10-11
I'll x to-,,
20 x 10-12
l'o x to -12
2.0 x to-, 2
90 St
C000080
3.1 x 10-14
3.5 X 10-"
65 X 10-14
3,5 x 10-14
6.5 X 10-14
OAMI 1
4.2 x 10-"
IS X 10-14
6.5 X to-14
3,5 X 10-14
6.5 x 10-14
91
0.50
L9 x 10-18
2,2 x 10-'o
4A X 10-10
2A X 10-10
4.0 X 10-'0
45 75
0,00040
1.5 x to-13
LI X 10-"
3.3 X 10-13
1.7 x 10-13
3,2 x lo-13
9s Nb
000040
1.5 x Ut-"
1,7 x 10"
33 x 10-13
L7 X 10-13
3,2 X 10-"
99 Me
0.20
7,7 x to-,,
8,6 X 10-"
L6 x 100
5,5 x lo'"
1,2 x 10-10
103 it.
0.00028
I'l x to-,'
1.2 X 10-"
2.3 X 10-13
1.2 X 10-t3
2.3X 10-11
tot, Ru
01000078
3.0 x to-,,
3A X 10-14
6.4 x 10-44
3.4 x 10-14
6A x 10-"
loatep,
0.00028
1.1 x to-,,
1,2 x to-"
2,1 x to -13
1,2 x to -13
2.3 x to-,,
OS Rh
0,000046
l,8 x 10-11
2,0 X 10-14
3.9 x j0-14
93 x 10-15
2.3 x 104
125 so
0X)"26
I'l x to-,,
1.2 x 10-"
2.3 x 10"s
1,0 x 10-15
2.1 x 10-"
127 Sb
0,000015
5.8 x to-"
&S x 10-"
1,2 X 10-t4
4.6 x 10-15
9,7 x 10-11
Mm 7t
0,00024
93 x 10-"
1.0 X It)-"
2,0 X W"
1.0 x 10-11
l.q x 10-11
12?. Te
0LO019
7.3 x 10-13
8.2 x W"
L6 X 102
8'1 X 10-t3
I "'i x to-,,
121 Te
1 0,0019
73 x 10-"
8,2 x 10-"
E6 x 10-12
8, X j0-t3
1_6 X 10-11
129. Te
0.20
7.7 x 10-"
8 6 x 10'
1 6 x 10'
83 x 10-"
1.6 x lo-10
a29 Te
0.20
7.7 x 10-"
8.6 x to-,,
1.6 x 10"
83 x W"
1-6 x 100
131. Te
0M28
1.1 x to-,,
1 2 x 10-"
2.3 x 10-12
5.1 x to-13
I'l X 10-12
M TV
0.00052
2', X 10-13
23 x 10-"
4A x 10-"
9.7 X 10-14
2.5 x 10-13
132 To
0A94
3,6 x W"
4.1 X 10-' '
7.7 x W"
2,7 x W"
5,9 x to _tj
431 1
0.54
2.1 x 100
13 x U)_'O
4-4 x 10-10
IA x 10-10
19 x 10-' 0
134 (7%
2.2
8's x 10-10
9.5 x 10-10
1,$ x 10-9
9,5 X 10-"
1-8 x 10-4
t36c,
0.74
In x 10-'o
3.2 x 10'
6.0 X 100
2,9 x 10-'o
5.6 x 10-'o
137 Cs
0.12
4,6 x 10-"
5,2 x to-,,
9'8 x to -11
5.2 x 10'11
9.8 x to-,,
137. Ha
0.14
SA X W"
5.2 x W"
9,8 X 10-1'
5,2 x 10-"
9.8 x 10-"
t40 0.
0,0026
I�o x to-,,
I'l x in-,,
2:1 x 10-11
1.() X Io-12
2, X 10-11
t40 L.
0,0022
&S x to-,,
1.3 X W"
2.4 X W"
1.2 x 10-11
2.3 x to-,"
14 IC,
0M04 2
L6 x 10-"
1.8 x I0_13
3A x 10-t3
117 x W"
33 x 10 -13
a43
0.000062
2A X 10-"
2.7 X Io-"
S', X 10-14
1,2 X 10-11
3.0 X 10-14
144 cc
(100024
9,3 X 10-14
1.0 x to-,,
2'(1 x to -4
1.0 x 10- t
2.0 x to-,,
143 of
0.00034
1,3 X 10-13
LS x 10-"
2 8 X 10"
1.3 x 10-"
2,6 x 10-"
147 No
0M014
SA X W"
6,0 x 10-14
I'l X jo-l3
5.3 X 10-14
I'd X 10-11
W47pm
0.000026
1.0 X 10-14
1', X 10-14
2, X 10-11
I8 X 10-14
2,1 X 10-14
149PM
O.ODOIO
3.9 X 10-14
43 X 10-14
8,2 X 10-14
IS x 10-14
5.6 x 10"
SiC,
0,08
341 X to-"
.1.5 X to-"
6,5 x 10-"
33 X 10'
63 X 10-"
54 Mn
0.12
4.6 x W"
52 x to-,'
9:8 x w"
5.2 x to-,,
9.8 x to-11
5 1 I�c
OA6
1,8 x to -,a
m x 10-10
m x 10`0
2,0 x to-10
3.8 x 10-11
$9 Fc
0.10
3.9 x to-,,
4-3 x 10-"
8,2 X 10-"
4,2 x 10-"
8,0 x to-"
58 (70
4.2
1,6 x to,
1.8 x to,
3A x 10­9
1.$ x to-,
3A X 10-9
60C.
0.12
4.6 X 10-''
_;,;
5,2 x to-,,
9.8 x to-"
5.2 x to-"
9.8 x 10 -11
Total
10.0 -
X to-
4.31 X 10 -
871 X to-
4.2 x to-
1,1 x M-
,U
2000
7,7 x 10-'
8.6 x 10-'
1.6 x to,
8.6 X 10-'
In X 10-*
3-43

Appendix
MODEL USED TO ESTIMATE RADIONUCLI
Liquid effluents will be released from
the discharge canal for the condenser
CONCENTRATIONS IN LAKES
McGuire Nuclear Station by
ing water. After release in
tially diluted by an annual rate
cis (see Sect. 3.3.3). The
Lake Norman in the old river
ections 11 and III) and discharged
to Lake 0 LL
L 01 Lhe SLatlon (sections T A
IV), as shown in Figs. 3.8 and 3.9. Water is returned to the channel from
the pool by one or more small outlets north of the station at the same
rate as the flow of condenser cooling water through the station.
Because the yearly average stream flow of the Catawba River into and out
of the channel portion of 2600 cfs (see Table 1-1) is smaller than the
flow of condenser cooling water through the station, the final dilution
in the channel is smaller than the initial dilution of liquid effluent in
the condenser cooling water. The final dilution of the condenser cooling
water and pool is also smaller because of recirculation of liquid effluent
from the channel to the pool in the condenser cooling water.
The model shown schematically in Fig. 1-1 was used to predict the
concentration of any radionuclides in the channel and pool portions of
Lake Norman near the station and in the downstream lakes of the Catawba
River system within a 50-mile radius of the station. The differential
equations describing the amount of activity in the different compartments
of the model as a function of time are:
dN P= Ne [N
dt P
— [A + R _V_ RPC + ANC
(1)
V� � P] P ]
dNC = Np� NC
— —Rpc-- �c-R,M+—R +XN (2)
dt VP [VC VC CP
dNm Nc NNE
—=—Rem --- V RMW+ANC
(3)
dt V': M I
dNw NM NW
—=—RV
gym —RWF+XNW(4)
dt Vm IW ]
dNF Nw NF
dt VW
RWF­ — Rog. + XN (5)
V
F

Table l-1. Data on Lake Norman and the downstream lakes of the Catawba River
system within SO miles of the McGuire Nuclear Station
Lake Area of lake` Volume of lakes' Flow of water from lake'
(acres) (fta) (cfs)
Lake Norman 3.25 x 104 4.76 X 10'0 2.60 X 103
Mountain Island lake 3.24 X 103 2.50 X 109 170 X 103
Lake Wylie 1,25 X 104 1.23 x 10§° 4.10 X 103
Fishing Creek Lake 137 X 103 2.61 X 109 4.86 x 103
aDuke Power Company, McGuire Nuclear Station, Units 1 and 2, Environmental Report, Fig. 2.4- , sect. 2
(Dec. 4, 1970).
bDuke Power Company, applicant's answer to ORNL question 1 of Past E.
1-2

I C
R pc
g,
CHANNEL OF LAKE
POOL OF LAKE
NORMAN NEAR STATION
Rcp,
NCRMAN NEAR STATION
,
Cc
V! Nc!)
(VP, Np, Cp),
RCM
n
A
MT. ISLAND LAKE
(Vm, Nm, Cm)
A
RATE OF DISCHARGE OF
RADIONUCLIDE FROM STATION
R
FLOW RATE OF WATER FROM
RMW
PC
CHANNEL TO POOL
R
FLOW RATE OF WATER FROM
3
cp
POOL TO CHANNEL
LAKE WYLIE
RIC
FLOW RATE OF WATER INTO
(Vw, Nw! Cw)
CHANNEL
RCM
FLOW RATE OF WATER FROM
CHANNEL TO MT. ISLAND LAKE
21
WF
ROF
FLOW RATE OF WATER OUT OF
FISHING CREEK LAKE
$�
N
C
CURIES OF RADIONUCLIDE IN
FISHING` CREEK LAKE
CHANNEL
000
,.
(VF! NF, F)
N
F
.
CURIES OF RADIONUCLIDE IN
at
FISHING CREEK LAKE;
V
VOLUME OF CHANNEL
R
VF
M •
VOLUME OF FISHING CREEK LAKE
Figure l-l. Model used to estimate radionuclide concentrations in lakes.
t_

5
1-4
with t = time and A = 0.693/Tl/2, where h is the decay constant and T1/
is the half-life of the radionuclide. Other symbols are defined in Fig.
I--l. These equations and models are similar to ones given in a Vir inia
Electric and Power Company report can the North Anna Nuclear Station
l and
in Peterson et al,
Equilibriumsolutions (dN/dt = 0) to these equations are used, since
all that is required in the estimates of dose to biota and man is the
concentration of the radionuclides averaged over the period of a year.
"these equilibrium solutions are:
C = ARCM + RCP + XVC)(b)
V (R + `R + V ) (R + AV ) - R
cpRpc
C Nc ARpc C1,Rpc ()
_—
VC (Rare + Rep +'XVc) (RPC + XVp) -- RcPRpc Rc + Rcp + XVp
N CCRc
CM _ V _ R + AV ()
mw
NW CMRMW
Cyy-VW Rye,F+?, � (9)
CF =VR �'=C�,R+hV (10)
r O F
where A is the yearly average rate of release of a radionuclide in liquid
effluents discharged at the station. The concentration of the radionuclide
in the discharge canal, CD, is
p R c i c
cp
where Cl = A/Rcp is the initial activity (or initial concentration) of the
radionuclide in the discharge canal.
If the half-life of the radionuclide is very large (the 'decay con-
stant is very small), the equilibrium solutions have the approximate for
Cp=C1+Cc— (1 )
pc

I-5
Rp (13)
Cc = Cl
RCM
RCM RPC (14)
CM =CcRM `Ct Raw
C _ RMw = CF RPac (1)
v, Cm RWr
: R
wF
Rw - R�,c
C = Cw r (16)
OF r
Equations 12) and (13) are also applicable when the mixing volumes of
the pool, V and the channel V , are very small. In this case, there are
k
,
no benefitspfrom the reduction of concentrations of radionuclides with
short half --laves by radioactive decay during large volume mixing.
The concentrations of radionuclides deposited on the shore areas
in the lower portions of Lake Norman and the downstream lakes were esti-
mated by the empirical equation3,4
CsHoxs = 100 V T1/2 CWATER (17)
where C is the concentration of the radionuclide per unit volume of
the waterwate al the specified location, T1/ is the if -life of the radio-
nuclide and C is the concentration of the radionuclide deposited per
7
unit area on tieore sore by sedimentation from the water.
Estimates of radionuclide concentrations in the channel and pool portions
of Lake Norman near the McGuire Nuclear Station are given in Table I-2
One set of estimatesgiven in the table was calculated by Eqs® (11),
(12), and (13), which assumes negligible or zero dilution volumes in
these portions, and another set was calculated by Eqs. 6) and (7) and
the assumption of dilution volumes of 3 108 and l x 108ft3 in the
channel and pool portions, respectively. These latter volumes, which
represent less than 2` of the total volume of Lake Norman, were used b
the applicant in estimating the radionuclide concentrations in the lake
near the station.5 The differences in the two sets of radionucl de con-
centration are small in most cases, but the choice of these small dilutlo:,
volumes is not a conservative one when the maximum drawdown of the lake
was indicated to be 735 ft msl.

FE
Table 1-2. Concentrations of radionuclides in the channe
of Lake Norman near the McGuire Nuclear!
F'low rate:
Discharge canal
2,9 x I
Channel
2,6 x I
Pool-
2,9 x I
Dilution volume:
Channel
3.0 x
Pool
1,0 x
Steady-state
concentration in discharge canal
= "initial
in discharge canal
plus concentration in char
"Initial
Steady-state
Annual
concentration"
Radionuclide
release
in discharge
Assuming no dilution
by I
(Ci/year)
canal
Channel
Pool
(Act MI)
3 H
2000
7.7 x 10-'
8.6 x 10-"
1,6 x 10
5 'Cr
0.08
31 X 10- 1 1
3.5 x to- 11
6.5 x 10
54Mn
OA2
4.6 x 10-' '
5.2 x 10-' '
9.8 x 10
SsFe
0.46
1.8 x 10-"
2.0 x 10-"
3.8 x 10
5917e
OAO
19 x 10-'
43 x 10-'
8.2 x 10
58CO
4.2
1.6 X 10-'
L8 x 10-'
3A x 10
60co
O. 12
4.6 x t0-11
5,2 x 10-'
9,8 x 10
86 Rb
0,0026
1.0 X 10-12
1,1 x to-,,
2.1 x 10
89sr
0.0024
93 x 10-"
I.o x to-,,
2,0 x 10
90 Sr
0.000080
3.1 x to-,'
3,5 x 10-' 14
6.5 x 10
90Y
0.0001 1
4.2 x> 10-14
3,5 x 10-14
6,5 x 10
91 Y
0,50
1.9 x to- to
2,2 x 10-10
4.1 x 10
95 Zr
0.00040
1.5 x to-,,
1.7 x 10-13
3.3 x 10
95Nb
0.00040
1.5 X 10-13
1.7 x 10-13
33 x 10
99NIO
0.20
7,7 x to- 1
&6 x 10-' '
1.6 x 10
99 mTcd
9's x 10-11
1,8 x 10
103 Ru
0.00028
1.1 x to- 13
1.2 x 10-"
23 x 10
I
and pool portions
to tion
), efs
)3 Co,
)3 CfS
)11 ft3
)11 ft,
oncentration"
net
oncentration ()Xi/ml)
ke Assuming dilution by lake
Channel
Pool
8.6 x 10-"
1.6 x 10'
it
33 x 10-"
63 x 10-"
11
5.2 x 10-"
9.8 x 10-"
to
2,0 X 10- to
3,8 x to-10
It
4.2 x 10-"
8.0 x to-,,
9
1,8 x 10-9
3,4 X 10-'
11
5,2 X 10-"
9.8 x to-,,
12
1,0 x 10 -11 -11
).O X ()-12
12
1.0 X 10-12
2,0 x 10-12
14
15 x 10-14
6.5 x 10-14
14
3,5 x 10-14
6,5 X 10-14
10
2.1 x 10-'0
4.0 x 10-'o
13
1.7 x 10- 13
3,2 x 10-"
13
1.7 x 10-"
3,2 x 10-13
10
5,5 x 10-"
1,2 x I0_10
,10
6,0 x 10-"
13 x 10-"
,13
1.2 x 10-13
23 x 10-"
lubRu
0,000078
10 X 10"
3A x 10-
6.4 x 10 "
3.4 X 10 * '
().4 X 1U -
103 .. Rh
0M028
I.l x 10-13
1.2X 10-"
23 x 10-13
1.2 x t0-13
2.3 X 10-13
Jos Rh
0.000046
1.8 X 10-14
2.0 X 10-14
3,8 X 10-14
93 x 10-15
13 x to- 14
106Rha
3A x 10-14
6A X 10-14
3.4 X 10-14
6.4 X 10-14
125 Sn
0.0000026
1.1 x 10-15
1.2 x 10-"
2.3x 10-"
1.0 x to-"
2A x 10-1s
12'Sb
0,000015
5.8 x to-,,
6.5 x 10-' '
1,2 x 10-14
4,6 x 10-"
9.7 x 10-'s
125 mTe
0.00024
93 x 10-14
1.0 X 10-13
2,0 X 10-13
I.o X 10-13
1.9 x 10-13
127 mTe
0,0019
7.3 x 10-13
8,2 x 10-13
1,6 x 10-12
8'1 X 10-13
1.6 x 10-"
127 Te
0.0019
7.3 x 10-13
8.2 x 10-12
1.6 x 10-"
8.1 x 10-'3
1.6 x 10- 12
129mTe
UO
7.7 x 10-11
8.6 x 10-"
1,6 x 10-10
8.3 x 10-11
1.6 X 10-10
129 Te
0.20
7.7 X 10-"
8.6 x 10-"
1.6 x 10-'0
8.3 X 10-"
1.6 X 10-10
131 ruTe
0:0028
1�1 x to-,,
1,2 x 10-"
23 x 10-'2
S', X 10-13
1.3 X 10-"'
131 Te
0.00052
2.1 x 10-13
23 x 10-13
4.4 X 10-13
9.7 X 10-14
2.5 X 10-13
132
Te
0.094
3.6 x 1_' I 0
4.1 X 10-11
I I
7.7 x 10-
2�7 X 10
_' I
5�9 x 10
1311
0,54
11 X 10-10
23 x I0_10
4A x to- to
2,0 x 10o
3,9 x 10-10
132ta
4.2 x 10-"
7,9 X 10-1'
2,8 x 10-"
6,0 x 10-"
134 CS
2,2
8.5 x 10-10
9.5 x 10-10
1.8 x to-'
9'5 x 10-10
1.8 x 10-9
1-6

,
m
Table 1-2 (continued)
Annual
"Initial
concentration"
Steady-state concentration (gCi/ml)
,
Radionuclide
release
in discharge
Assuming no dilution
by lake
Assuming dilution by lake
(Ci/year)
canal
Channel
Pool
Channel
Pool
b
Ouci/ml)
136Cs
0.74
2.9 x 10-10
3.2 x 10`'0
6.0 x 10`10
.9 x 10-'0
5.6 X 10-10
137Cs
0.12
4.6 x 10-' 1
5.2 X 10%11
9.8 x 10`t l
5.2 x 10`11
9.8 x 10`f t
137m0a
0.14
5.4 x 10-"
5,2 x 10-' �
9.8 x 10-11
5.2 x 10-1 t
9.8 x 10-11
140E
0.0026
1,0 X 10-12
1.1 x 10-12
2.1 x 102
t.O x 10-12
.0 x 10-12
140 La
0.0022
8. 10"��
1.3 x 10-"
2.4 X 102
1.2 x 10`-12
2.3 x 10'12
141
Cc
0.00042 `
1.fi X I0M13
1.8 x 10` 13
3,4 x 10-13
13
1.7 10`
i3
3.3 X 10�
143Ce
0.000062
2A x 10`14
2.7 x 10-14
.1 x 10'
1.2 x 10-"
3.0 X 10-14
144Cc
0.00024
9.3 x 10-14
1.0 X 10-13
.0 x 10%13
1.0 x 10-13
2.0 x 10-13
143Pr
0.00034
1,3 x 10`13
1.5 X 10-13
.8 x 10-13
1.3 x 10`-13
.6 x 10`13
144pru
1.0 X 10-13
2.0 x 10``13
1.0 x 10-13
2.0 x 10-13
147Nd
0.00014
5.4 X 10-14
6.0 x 10-14
1.1 x 10Mt2
5.3 x 10-14
1.0 x 1Ct"13
147Pm
0.00002
1.0 10-1#
1,1 x 10 14
2.1 X 10-14
1.1 X 10µ1`1
.1 x 10'14
14Pm
0.00010'
3.9 X 10 )`1
4.3 x 10 14
8.2 X 10-1a
.5 x 14 1�1
5.6 x 10`1a
°Radioactive daughter products not listed in anticipated releases of gaseous effluents.
7 4
vi
1
1-i ,

ro
1-8
Data: on volumes and flow rates used in estimating the radionuclide
concentrationsof downstream lakes of the Catawba River system within
a 0-mile radius of the station are given in Table I-1.
i

a.aK E NoRMAra
y x
. ,
I ,,.COwaNs fDRp UAM
�+' k ihTk NE
,~
X. / uCLE QR STATI" x
-CATAWBA RNER
Figure 3.8. Lake Norman in vicinity of McGuire Nuclear Station at full pond.

. .
'
. �:. .. ...
LEGAL MIXING ..
ZONE 4[MIT
1E
LAKE '
ca
/ NCaRMAN
`t SHALLOW
..._....AREA tIS5 la MSL7DISCHARGE
s
«+ v
y.
CANAL
^- — 20 t7 DROP
TORO DADA
(IOWANS
#
INTAKE
>
0 xs
MrGUIRE . r.
NUCLEAR STATION
CATAWBA RIVER
Figure 3.9. Lake Norman in vicinity of McGuire Nuclear Station at a lake drawdown of 10 ft and 20 ft.

3 `4.11 RADIOACTIVE EFFLUENTS
4.11.1 L.I UIU EFFLUENTS
CONCENTRATION
LIMITING CONDITION FOR OPERATION
.11.1.1; The concentration of radioactive material released from the site
,ration
shall
be
limited to 2
kILITY:
At
all
times.
:he above limits, immediat
limits.
,E REQUIREMENTS
n 2 for radionuclides other than dissolved`
lved_ r'entrained noble gases, the
x 10 microcurie/ml total activity.
material released from the site
ely restore the concentration to within
. �� I� I it {� � • w i
ntai ned within the l' imi'
within the limits of Specification 3.11.1.1.
•
IRE - UNIT 1 3/4 11-1

TABLE .11-1
RADIOACTIVE LI tllD
WASTE SAMPLING
AlD AIAI'SIS PROGRAM
Lower Limit
Minimum
of Detection
Liquid Release
Sampling
Analysis
Type of Activity
(LLD)
Type
Frequency
Frequency
Analysis
(pCi/ml)a
A. Batch Waste
P
P
Released
Each Batch
Each Batch
P incipa Gamma
5x1O_
Tanks
Emitters
1, Waste Monitor
I-131
1x1O-5
Tanks (2)
P
M
Dissolved and
1x10-5
2. Recycle
One BtchM
Entrained uses
Monitor
(Gamma emitters)
Tanks ()
P
M
-3
110-'S
Each Batch
b
Composite
Gross Alpha
1x1O 7
r
P-32
1x1O-5
P
Q
Sr-89, Sr-90
5xlO_
Each Batch
b
Composite
Fe•- 5
1x1O-6
B. Continuous
e
W
Principal Gamma
5xlO�'
Releases
Continuousc
Composites
Emitters
1. Ventilation
Unit Conden-
I-131
1x10-
sate Drain
f�
Tank Line;
. Conventional
M
M
Dissolved and
1x10-5
Waste-
Grab Sample
Entrained Gases
Water
(Gamma Emitters)''
Treatment
Line
M
H-3
1xl0_ 1�
Continuous
Composites
Gross Alpha,
1x10
P-32
1x10_5
Q
Sr-89, r-90
5xlo-
c
Continuos
Composite c
Fe-55
1x10-Q
McGUIRE - UNIT 1
3/4 11-2
JtN 1981

t
TABLE .11-=
TABU l
a. The LLD is the smallest concentrat
concluding that a blank observation rep
For a particular measurement system (wh
separation):
4.66 sb
LLB = 2.22 x 10 , . e
Where:'
LLD is the "a priori" lower limit
(as microcurie per unit mass or vo
s is the standard deviation of th
to counting rate of a blank'sampl
minute),
E is the counting efficiency (as c
is the sample size (in units of!
.22 x 106 is the number of transf
Y is the fractional radiochemical
is the radioactive dewy conta
Hued)
y with % probability of falsely
seats a "real` signal.
h may include radiochemical
(-ant
detection as defined above
e),
background counting rate or of
as appropriate (as counts per
nts per transformation),
ions per minute
t t a ♦ .
counting rate or of the counting rate of the blank samples as
appropriate) rather than on an unverified theoretically predicted
variance. Typical 'values of E, V, Y, and At shall be used in the
calculation.;
RE - UNIT 1 3,4 1-3

ti nued
A
the method of
representative
C. To be represen
materals,in l
in proportion
analyses, all
mixed in order
effluent r±l p
batch relea
TABU 4. 11
TABLE'
AMMKIMISM"
. • . e
'or the composite sz
above nuclides, shall also be identified and reported.
cGUI E - UNIT 1 3/4 11--4

RADIOACTIVE EFFLUENTS
DOSE
LIMITING CONDITION FOR OPERATION
3.11.1.2 The dose or dose commitment to an
materials in liquid effluents released, from
(see Figure 5.1-4) shall be limited:
a. During any calendar quarter to les
total body and to less than or equ
b. During any calendar year to less t
total
body and to less tha
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose f
in liquid effluents exceed
an othpr rAnort rPntiirPH
idividual from radioactive
each reactor unit, from the site
,o 5 mrem to any organ, and
or enual to 3 mrPm to the
water supplies with regard to the requirements of 40 CFR 141, Safe
Drinking Water Act.
b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
4.11.1.2 Dose Calculations, Cumulative dose contributions from liquid effluents
shall be d-et-e-r-m--in-e-d--i"n -accordance with the ODCM at least once per 31 days.
Mc DIRE - UNIT 1 3/4 11-5

RADIOACTIVE EFFLUENTS
LIQUID WASTE TREATMENT
LIMITING CONDITION FOR OPERATION
3.11.1.3 The liquid radwaste treatment; system shall be OPERABLE. The appro-
priate portions of the system shall be used to reduce the radioactive materials
in liquid wastes prior to their discharge when the projected doses due to the
liquid effluent from the site (see Figure 5.1-4) when averaged over 31 days,
would exceed 0.05 mrem to the total body or 0.2 mrem to any organ.*
APPLICABILITY. At all times.
ACTION:
. With the liquid radwaste treatment; system inoperable for more than
31 days or with radioactive liquid waste being discharged without
treatment and in excess of the above limits, in lieu of any other
report required by Specification 69.1, prepare and submit to the
Commission within 30 days pursuant to Specification 6..2 a'Special
Report which includes the following information:
1. Identification of the inoperable equipment or subsystems and
the reason for inoperability,`
2. Action(s) taken to restore the inoperable equipment to
OPERABLE status, and
3. Summary description of action(s) taken to prevent a recurrence.
b. The provisions of Specifications 30.3 and 3.0.4 are not applicable.
SURVILLAECE RE UIRMENT
4.11.1.3.1 In, the event that the liquid radwaste treatment system is not
operating and liquid waste releases are being made, doses due to liquid releases
shall be projected at least once per 31'days, in accordance with the ODCM.
4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE
by operating the liquid radwaste treatment system equipment for at least 90
minutes at least once per 92 days unless the liquid radwaste system has been
utilized to processradioactive liquid effluents during the previous 92 days.
Per reactor unit.
McUIRE - UNIT 3/4 1-5

RADIOACTIVE EFFLUENTS
LIQUID HOLDUP TANKS
LIMITING CONDITION FOR OPERATION
3.11.1.4 The quantity of radioactive material contained in each outside
temporary tank shall be limited to less than or equal to 10 curies, excluding
tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
ACTION:
a. With the quantity of radioactive material in any outside temporary
tank exceeding the above limit, immediately suspend all additions of
radioactive material to the tank and within 40 hours reduce the tank
contents to withinthe ;limit,
b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
►tity of radioactive material contained in
radioactive materials are being added to the tank.
Mc UIRE - UNIT 1 3/4 11-7

RADIOACTIVE EFFLUENTS
CHEMICAL TREATMENT PONDS
LIMITING CONDITION FOR OPERATION
3.11.1. The quantity of radioactive material contained in each Chemical
Treatment Pend shall be limited by the following expression:
264 2 : �i < 1.0
V j C
excluding tritium and dissolved or entrained noble gases, where,
Aj = pond inventory limit for single radionuclide "j", in curies
C = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single
J radionuclide " ", microcurie ml
V = design volume of liquid and slurry in the pond, in gallons
264 = conversion unit, microcuriescurie per milliliter/gallon.
APPLICABILITY: At all times.
ACTION:
a. With the quantity of radioactive material in any o f the above listed
ponds exceeding the above limit, immediately suspend all additions of
radioactive material to the pond and within 48 hours reduce the pond
contents to within the limit,
b. The provisions of Specifications 3 0.3 and 3;0.4 are not applicable.
SURVEILLANCE RE UIREMENT
4.11..1.5 The quantity of radioactive material contained in each batch of
slurry (used powdex resin) to be transferred to the chemical treatment ponds
shall be determined to be within the above limit by analyzing a representative
sample of the slurry, and batches to be transferred to the chemical treatment
pond's shall be limited by the expression:
6. x 105 i/ m
ml
where
concentration of radioactive materials in wet, drained slurry (used
powdex resin) for radionuclide "j", excluding tritium, dissolved or
entrained noble gases, and radionuclides with greater than 8 day
half-life. The analysis shall include at least Ce-144, Cs-134,
Cs-13 , Co-58 and Co-60, in picocuries/gram. Estimates of the Sr-39
and.Sr-9t batch concentration shall be included based on the previous'
monthly composite analysis.
Cj = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single
radionuclide,"j", in microcuries/milliliter.
McGUIRE - UNIT 1 3/4 11-8

RADIOACTIVE EFFLUENTS
3/4.11.4 TOTAL DOSE
LIMITING CONDITION ,FOR OPERATION
3.11.4 The dose or dose commitment to any member of the public, due to releases
of radioactivity and radiation, from uranium fuel cycle sources shall be
limited to less than or equal to 23 mrem to the total body or any organ (except
the thyroid, which shall be limited to less than or equal to'75 mrem) over 1
consecutive months.
APPLICABILITY. At all times.
ACTION:
a. With the calculated doses from the release of radioactive materials
in l quid=or gaseous effluents exceeding twice the limits of;Specifica-
tion 3.11 1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or
3.112.3.b, inlieu of any other report required by Specification 5.9.1,
prepare and submit a Special Report to the Director, Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, within 30 days, which defines the corrective action to be taken
to reducesubsequent releases to prevent recurrence of 'exceeding the
limits of Specification 3.11.4. This Special Report shall include an
analysis which` estimates the radiation exposure (dose) to a member of
the public from uranium fuel cycle sources (including all effluent
pathways and direct radiation) for a 12-month consecutive period that
includes the release(s) covered by this report. If the estimated
dose(s) exceeds the limits of Specification 3.11.4, and if the release
condition resulting in violation of 40 CFR 190 has not already been
corrected,, the Special Report shall include a request for a variance
in accordance with the provisions of 40 CFR 190 and including the
specified information of § 190.11(). Submittal of the report is
considered a timely request, and a variance is granted until staff
action on the 'request is complete.' The variance only relates to the
limits of 40 CFR 190, and does not apply in any way to the requirements
for dose limitation of 10 CFR Part 20, as addressed in other sections'
of this technical specification:
b. The provisions of Specifications 3-.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS
4.11.4 Dose Calculations Cumulative close contributions from liquid and
gaseous effluents shall be determined in accordance with Specifications 4.11.1.,
4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.
McGUIRE - UNIT 1 /4 11-20

0. z
App. B
App. B
PART 20 STANDARDS FOR PROTECTION AGAINST RADIATION
APPENDIX A
Corvoirobv6sms
In Ab sad Wrmw About Natural background
tSee notes at end of appendix)
_
Teblo I
Table I1
Nomw (otamk numbod
Isotope
Column I
1
Column 2
Column I
Column 2
AIr
Watot
Ak
Water
/
Asfnlum(09)... _-------
At227
S
2XIO`U
6X10`$
1xW14
2XTO-°`
1
3X10_11
9X10-3
9x10'13
3XIO 1
At 228
5
4 X10`'
3 X10-3
3 x10"$
9 X10-1
I
2XIO-1
3x10`3
6XIO`10
9X10"41
Amwitlum (95)_._..m._..
Am 241
S
6 X10-12
1 X10-4
2'X10-13
4 XIO'"',
I
Ixto-s
SX10-1
4x10-12
3`X10-$
Am 242m
S
6 XIO-12
I XIO-
2 XIO`13
4 xTO"'
1
3X10_10;
3XTo-'
9X10'13
9XTO'1
Am 242
S
4 X 104
4 X TO'3
1 5C 10 *
1 X 10-4
1
5X10-4
410-3
X
2XIO-0
IX10-4
Am 243
S
6X10`1$'
1X10-4
2XIO-13
4XIO4
I
IX10"t0'
SX10-4
4-X10`13
3XIO`3
Am 244
S
4xI0`s
I X10`1
I xI0'F
5 X10`3
1
2X10-3
1XIO`t
4X10-7
3XIO-3
Antimony (31)__....__._
Sbt22
S
2X10-7
4X10-4
6x10`3
3XIO-$
1
1X10-7
SX10-4
5X10'0
3XIO`3'
Sb 124
S
2XIO-1
7xIO-4
3X10-1
2X10`f
p�
1
2 XIO"1
7 X10-4
7x1O-70
'. 2 XI0-'
td
Sb 125
S
5 X10-3
3X10-3
2 xIO-11
1 X10`4
t0
1
3 xlO-1
3 XIO 3
9 X10-F0
1 XIO-a::
:Argon (10).............
A 37
:. Sub3
6 X10-3
._. .__::...
1 X10`4
;:. ... ..:
A 41
Sub
2 x10-'
4 xIO-1
Arsontt(33).......:.....
As73
S
2x10`''
IX10-1
7X10-1
5X10`"4
1
4 XIO-1
1 X10`3
1 X10-1
5 X10`4 '
As 74
S
3 xl0'3
2 X10-1
I XIO-'
5 XTo-$
1
1XTo-?
2XTO-3
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December 30,1982tt }

( PROTECTION AGAINST RADIATION
Arf'EFi01X e
Contentratlons In Air and Water
wove Natural eatkWound—Contlnuod
CSoe . notes of end of o x)
table I
tokto 11
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Column 1 Column 2
Column t Column 2
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tc�f�7tuft}(,cf�t�fcll>
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8r 82
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oftember 30,1982(reset)
20-16

App. B
App.
PART 20 • STANDARDS FOR PROTECTION AGAINST RADIATION
APPENDIX B
Coneo am Its AM and
Above Natural Eaekvrovnd_C*mfnved
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Toblo 1 ;
Table If
somw { "Mono}
1 1
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j :Column 2 i
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�*W
Ak
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/
(27)
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20-17
December 30,1982(reset)

pp. B Appr
' PART 20 • STANDARDS FOR ' ROT CTIO AGAINST RADI TI ►
APPENDIX 9
Coneentrat(one In Air and Water Above Notwal Baekgravadr- Co"flnusd
(See notes at and of a rAx)
1
i
Element totemic number} I*otopt I Co1u
{
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9
Table It
nn 2 Column I :Column
t
1
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App. B
pp. B
PART 20 STANDARDS FOR PROTECTIONAGAINST RADIATION
APPENDIX 8
Concontrattans in AM
and Water
Abava Natural Background—Cansinvad
(See : not" at and Y1 apper4x3
Table 1 l
Tabta 0
Element (aromle number)
Isotope 1
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Column 2
Column l
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Air
Water
a/ Air
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f:
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y.
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1134
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Hp203
5
7Xl0'4
3X10`4
2X10-#
2Xl0'4
1
1 X10-1,
3 X10`1
4-X10i0
1 X10-4
Molybdenum (42).
Me 49
S
7 X10-1
5 X10'4
3X10'4
2 X1ti`4
1
2 X10`1
1 X10-1
7 X10",
4 X10'4
Neodymium (60) . , ... m
Nd 144
5
a X10-11
2 X10-1
3X10`12
7 Xt0`4-
1
3X10`10
2X10"4
1X10"11
axio-4
NO 147
S
4 X10®7
2 X10"4
1 X10"1
6 X10-5
1
2X10"/
2X10®1
4X10-t
6XtO'4
NO 149
S
2 X10-1
a X10`1
6 x10"4
3 X10`4
i
1 X10`1
a X10-1
3 X10'4
;: 3 X10-4"
0-19 i December 30,1982(r )

App. PART 20 + STANDARDS FOR PROT
APPE1i
Concentrations In Air and Water Abe
[Sae notes at end
Element (atomic number)
Isotopy a
Cato
t
�
t
(}CI
Neptunium (93) Np237
S
4 )
1
15
Np 239
S
6
1
c77
Nitkal (211)
Ni 59
S
" S'
8
Ni 63
S
6"#
1
3"
NI6S
S
9
f
1
S;
Nloblum
Nb 93m
S
I
(Columbium) (41).
NF 95
1
S
27
S
{ Nb 97
1
S
I:
6
cc Osmium (76)
Os TITS
S
S
i
U.
1
S
Os 191m
S
i 2
1
9.
S
1
�Os191
1
i 4
Os 193
S
II 4'
1
1 3
palladium (46)
1 Pa 103
S
I
Pd ld9
1
S
7"
6
1
4
Phosphorus (15)
! P 32
$
7
i
I
a
Platinum'(76)
# PI'191
S
a
1
6
1 Pt 193m
S
7
1
1
S
�}
l Pt I93
s
t
I
3
Pt 197m
S
6
PI 197
1
S
i S
4
1
6
Plutonium (94)
( P. 236
S
2
P. 239
1
S
i 3
2
t
4
Pu 240
S
2
1
4
P. 241
S
9
1
4
:TION AGAINST RADIATION Apt. B
e
iatural BatkOround—Continual
pe"KI
Table I Table It
n 1 Column 2 Column I Column 2
i
.Air Water
'ml),(Pci/mIj(PC /ml.} ( Ci/M )
1-1-1-
1
10-12 9 X10"4 I X10-I3 i 3 X10`6
0-10 9 XIn-4 4 X10-t2 , 3 XIO`5
10 1 I 4 X10"° 3 X10"® 1 X10""
in-7 I a VIA-1 h via-$ i 1 xtQ-.
2 X1O, 4 .
2 X 10-3
3 XIO"4
7 X10`1
1 XIO`4
A heV � ro.I eer
t Xt0"7 1 S-XIO'r I 4 XTO`'
3 X10-3
j 2 XIO-6 I
I XIO-4
3 X101
I 3X10-1
1 X10-1
3 X10-2
2 X10-1 '
9 X10-1
3X10`1
i1
2X10-7 '
9XIO''
2 X10`1
2 XIO-1 1
7 XIO-S
2X10'7
2XIO'r
7XIO-7
7X10"7
6X10-7
3XIO"3
7 XTO-7
3 XIO-7
2 XIO`7
5X10'4
4xTO`$ j
2XIO"
5X10-1
tX1O"s
2XIO"4
2 XW-3
I i X10-1 j
6 X14 1
2xl0_3
� 9XIO"° t
5X10-t
IX10'7
5:X10-6
3XIO1.
aX10-3
( 3XIO"4
3XIO'
3X10"3
2XI0 6
9XIO`'
2Xt0`7
I XIO s :
7X10'7
SX10"4
2XtO-9
2X10`§
7XIO'4
3xTO"r
2XIO
4XIO'3
3XIO'*
IX1O'
3 <10 '
4.­10 r
9 . 10 '
KtO r
S <10 t
I.y10 r i
2 .10 s
XIO`6
3XIO`7 r
2X107
IX107
xlO_4.
3 xTO`2 'i
2 X1O�7
:. 9 XiO'";
X1O`J
4 X10-1
3XIO ` i
1 X10'4
X10-1 1
3 XI#1 s
2XIO r j
I x10"r
X10-i1
I X10 4 j
7XI6 #a k
5X10 b.
X10-11 I
8XIO"' I
I XIO tl7
3X1O 5
Xto 12 i
1 X10 '
6X10"1'
S X10 6.
X10 If
a 0"'
1X20"I
3xt0 i
X1O-11'2 )
t XIO '
6X1O 14
S x1O a.
x10'
a x10 '
I XSO-Ix
3 .e10 $
x10 t4
7 x*O 1
'"3 x00 �7
2 xtO.':'.
X10-1
4 X"tO '
1 X10'r
I X10
riber 30,1982(reset) 20-20

App. B FART 20 *STANDARDS FOR
AP
C00,96ntrattnnt In Air
and Water
Isoo notes
}t
i
ilsmrnl (atemic: numhor) ::
Isotope
t
Plutonium (94)
Pu 242
s '
I
Pv 242
s
i
Pu 244 '
s
Nionlues (44)
Pa 210
$
I
Polasslvm (19)
K 42
s
I
prosoodymium (39)
Pr 142
1
1
Pr 143
s r
1
Pr othivm (611
Pm 147 "
1
1
Pm 149
s
U. Pr ettnlum (91)
Pa 230
I
s
�
Pe 231
I
3
I
Pe 233
s
I
Radium (Yi)
Re 223
3
I
Re 224
3
I
Re 226
3
I
Re 229
1
1
IOTECTI©N AGAINST ADIATIt, App.
ENDIX a
,bovo Natural Eaekpraand—Can#Hued
t 8n4 Of SMOMW
table I Tablo I1
1
� r
Column I I Column 2Column i Column 3
Air Water Air i Water
pCi/ 1)�(yC /M1)()l i/1111) (pa/mi)
2 XI0't2 1 7d10'' 1 6 XIO-14 3
4X10`1t 9X10:: 1 I110-1t 3X10`1
2X10+ IX10-t 6X10", 3X10`4
3XI0ry6 IX10- aX10- 3X10"'
2X10-12 1X10-1 6X10-1" 4X10 r
3 X10-11 3'X10"' 1 X10"11 1 X10`1
3X10-10 2Xt0-' 2X10"11 7X10"r
2X10-10 SX10"4 7XIO-12 3X10-1
2 X 10-4 9 X 10-2 7 X 10-1 3 X10-4
1X10`1 6X10-4 4X10"'1 2X10`'
2X10®r 9X10-1 7X10-# 3X10`3
2X20"1 9X10'' 3X10-w* 3X10`t
3 X10-1 I X10-1 1 X10-1 3 X10" 1
2X10-1 IX10-r ( 6X10`1 3X10`'
.^..
tX10`r
4A1V -
6X10 2
: 6A—
3X10-1
.A—
2X10`4
3 X10'2
I X10-1
1 X10`1
4 X10`1
2 X10"2
1 X10"2 +
6 X10-f
4 X10''
2X10"*
7X10-2
6X10`11
2X1 "r
EX10-10
7X10`2 i
3 X1011
2X11Y4
IX10-1t
3X10"$
4X10`1"
9X10"1
t vsh-:d III
a v1n-4
f v i —12 II
9 -In-$
Radon (Y6)
Re 2"
$
1 3 X
tin 2223.: *ws
**03 3
Rhonfam (73)
Re 163
1
3 X
1
2X
Re 1R6
S
6 X
1
2X
No 147
s
9 X:
1
3x
IN198
1
4 x
1
2X
Rhod v t (431
Rh 103m
s
! x
1
6
Rh 103
s
# x
1
3X
Rubldlum (37)
Rb $6
s
3 X
I
I
Rb 67
s
3 x
2 X 70'•:.. 1 1 X 14
6 X10`1 � I X10`1
6 X10`11 7 X10'r
6X1 -11 4X10-*
3 X 10'11
3 X 10u2
2Xt0 t
3X10`s
2 X10tr
3X101
I X10`ss
3 X10'1
I X 10,
3 X 10'1
9 X10`#
6 X10'"
e:
m
1
I 7 XI'0'° I S X10-1 I 2 X10`r I 2 X10"'
0-1 December 0, 1932{reset}

App. B PART 20 STANDARDS FOR PROTECTION IO AGAINST RADIATION App. B
APPENDIX s
Concentrations In Air and Water Above Natural Sockpround—ConNnNed
1 :motes at end of slut
Table I
i
Table If
Element (atomic number) Isotope,
Column I �(( Column 3
1
Column I
Column 2
Air {
wow
At
Water
t
(),gCif Mj- .(,p .'iiit1j�(pU/it11.
+ + B
( cihi1l).
Ruthenium (44)
Ro 97
S
2 x10_6 Y
1 X10-2 +
3 X10'1
4 xlO-'t
1
2x10-t
1X10`1
6X10-1
3X10-1
Ru 103
5
3 X10-1
2 x1O-1
2 x10-4
A xI0"S
I
ItX10-t
2x10"1
3XIO`t
6X10`t
Ito t0$
3
I X10`1
3 X10-1
2 X10`t
I X10-4
t
S X10-7
3 X10`'
2 X10-1
1 X10 4
Ro 106
s
! x10-t
4 x10-4
3 X10-t
1 X10-'
1
6 xw*
3 x10''
2 X10®16
I xio-s
Somodam (62)
Sm 141
S
7 xl0'tt
2 X10`1
2 xi0" t1
6 xI0''
1
3 xI0`10
2 X10-1
9 X10" t2
7 x10"'
Sm 151
S
6x10-9
1X10'1
2X10-9
4x10'
I
1 X10-1
I X10-1
3X10"9
4 xI0-4
Sm 133
3
S X10`7
2 XIO`1
2 XtO`t
It X10"'
1
4 x10-1
2 x10-3
1 X10-4
I1 x10-'
3candlum (21)
Sc 46
S
2 X10-) ,
1 X10-3 �
• X10`tt
4 xlO-$
1
2 x10
I X10-
t X10 a
4 X10
Sc47
S
6X10-1
3X10'-1
2X10-0
4x10-.'
�
t
f 5X10-1
3x10-'
�
2x1O-t
9X10-'
ut
i Se4•
S
2X10-1
6X10-4
6x10"t
3X10"3 .s
ra
F
1
¢ I X10-1
E X10-4 ;
S xI0 t
3 X10-1 t
Selenium (34)
St 73
s
I x10`t
9 x10 1
4 X10-t {
3 XIO 4
1
1 X10_7
it X10 1
4 X10-t f
3 X10`4
S11lcon (14)
$1 31
s
6 x10-t
3 X10-1
2 X10'1 P
9 XIo-,
I
1X10`1
6X10-3
3XI0.t r
2x10-4
$liver (47)
Ali 105
s
6 xI0-1
3 X10-1
2 XIO`t
I X10-1
I
i X10-1
3 X10`1
3 X10-r $
I X10-4
AS floor
S
I 2X10-7
9X10'"
7x1O`t
3X10`'
I
1X10`t
9X10-'
3X10-Ie
3X10`'
Ay M
S
3 X10-1
I x10-1
I xtO-t
4 X10-1
I
2 xl0`1
I X10-3
If x10`t
4 xIO-'
sodlum (11)
Na 22
3
2 x10'1
I X10"1
6 X10`t
4 x10-1
1
( 9X10`1
9x10-4
3xIO-10
3x10''
Na 24
S
I x10`t
6 XI0-a
4 X10-t S
2 X10-4
1
; 1 X10`1
8 X10`4
S X10-1 j
3 X10-°
Strontium (311)
St tam
S
4 X10'
2x10`r
1 X10-1
7 X10-1
I
3X10-5
2X10-1
IX10`4
7x10-1
sr Its
2XIO-1
aX10-3
8 X10-1
I xlo-.
I
1 X10 `1
S X10`3
4 X10-t
2 X10-4
Sr 49
S
2 x10-4
3 x10-4
3 x10-tt j
3 xlO'
I
i 4 X10`'
It X10-1 iii
I X10-1 ii
3 x10-'
Sr 90
S
I X10-9
I X10-'
3 X10-11
3 xI0'1
I
S X10`t
I X10-1
2 XIO-10
4 X10-5
St9I
S
4xt0`1
2x10®1
2X10-4
7X10"'
I
1
3910'1 (
I X10'3
9X10`t
S X10-1
f Sr 92
s
4 X10_7 i.
2 X10-3 '
2 X10-1
7 X10""1
t
3 xto-1 `
2 xto-)
I X10-0
6 X10-5
Sulfur (16)
' S 35
S
3 X10"1
2 X10-1
9 XIO-t
6 X10-3
!
( 3 xI0 1
S X10-1
9 x10-t
3 x10'4
tantalum (73)
to I92
S
! 4 XI0`t III
I X10''
I X10-0
4 x10`'
I
2X10-t
1XIO't
7xl(I-W
4XIO®1
December 30,1$82(reset)
20-22

` ''" PART 20 STANDARDS FOR I
Apt
Cow"oftotloas lot Air and Water
(Soo notes i
App
ROTECTION AGAINST DIATI+ N. "
N#X 6
bovs ►Aata# 6achgrouni-Csntinuod
"W Of opwdxl
Tout* 1 Tabb 11 .
!)omoM (atomic numborl Isotope A Column 1 l Column 2 ! Column 1 ; Column 2
i
} Air
}; Wow
Air
Water
t X10-3
TaehooNum (43)- _ Ts gam s
e X1o`6
4 X10-1
3 x10-6
1
3X10`6
3X10`'
1 X10'6
1 X10'2
Ts 3
6X10`1
3X10'1
2X10"*
1X10'*
1
2 X10"t
1X10"1
IX10"*
5X10 0
Ts 97m S
2 X10-*
I X10"1
4 X10"6
4 X10'4
1
2X10-7
3X10'3
3X10-*
2'X10-4
Tt 97 3
I X10'6
5X10`1
4XI0 t
2X10`6
1
3X10-7
2 X10`1
1 X1'0-6
4 X10";
Ts94m 3
4XI0_6
2X10`1
1X10-6
6X10'6
1
1X10-'6
4X10`t
IX10`1
3 X10-3
Ts99 3
2X10"*
IX10`1
7X0'-*
3X10",
1
6X10`6
3X10'1
2X10'-v
2X10-1
TstturlYm(321._... .-_ To123m 3
4Xl0`t
5X10"1
1X10"i
2Xl0`*
t
I X10"1
3 X10-I
4 XI®-*
I X10""
To 127m $
1 X10"t
2 X10`1
5 X1'0`r
6Xt0"6
1
4 X10-*
2 Xt0-6
I X10`*
5 X10`6
To 127 s
2X10-4
4Xt0-6
6XIO-1
3XI0`4
ii
1
9X10-7
5X10-S
3X10`6
2X10-1
u"
To 129m 5
4 Xt0'*
I X10`6<
3 X10`*
3 X10-3
N 1
3X10-6
6X10-1
1X10--r
2X10`6
To 129 3
S X10-4
: 2 X10'2
2 XIO-,'
I-'X10`*
1
4 X10`*
2 X10"1
1 X10-1,
I X10`4
To 131m s
4 XTO-?
2 X10"1
1 X10-1
6 X10`6
1
2 X10-7
I X10-1
6 X14'*
4 X10'6
To 132 S
2 X'10-1
9 X10`4
7 X10-9
3 X10_6
1
I X10`7
6 X10-4
4 X10-1
2 X10-1
T•rblum (63). _ .. � . _ "_ Th 160 s
I- X10-1
I X 10'1
I x to'-'
4 X 10"6
I
3 XI0""*
1 X#0®6
1 XTO-f
4 X10'6
Tha111um(4I1-_n_.-•.'--. it 200 3
3Xt0"'*
1X10-2
9XW"
1 4X10'6
#
1 X10-4
7 X#0 6.
1 4 X10"6
2 X10"*
n2Q1 3
2X10`6
9X10`6
7X10'6
3x10-1
I
9x10-7
3 X10`*;
3 X10'*
2 X10''
it 202 3
4 X10"7,
4 x10"'6:
3 X10"'* I
1 x10'*
1
2x10_7
2X10`6:
lX10 r
7x10-6
T# 204 3
6 X10')r
3 X10";.
2 xlO'*
I:x10"
1:
3X10`6
2X10`6.
9X10'A*
6:X10`6
Thsatuml90l-. ... + Th227 S
3X10"t*
SX10`4
1X10"
2X10`6
1..:
2X10"1*
$X10"°
$xio-'%
2X1006
Th228 s
SX10'76
2X10"1
3X10-cs
7x t0'6
1
6X10-11
4X10-4
2X1:0'16
1X10`6
To230 5
2X10`A2
5Xt0'$
SXIO-14
2X10'6
1..
:1Xt0'1A
:. SX10"1
3X10"la
3X10`6
♦ Th 231 :S
1X10`6
7X10-1
SX10`1
2X10`6
1
1Xt0-*
7Xt0"1
4X1.4 6
2X10-4
Th232 S
3X10`A°
$Xto`$
1X10`16
2Xto-,
1
3Xt0-1 9
1X10"6
1X10"A6.
4X10`6
¢s Thniluri/ S
6XTo'AA
6X10`g)
2X10"°91
2Xtd-6
6X10'IA
6X10"&
2X10`°6
2X10'6
0-23 December 30,198 {reset}

Apt B
App. B
PART 20 STANDARDS FOR PROTECTION AGAINST RADIATION
g
APPENDIX a
ij Cont#nkations to Air and Water Above Natural Background-»CuMinutd
[Soo testa* at and of appandO
...�
�_._.
Table, I
{
Table 11
Element (alamlx numbor) t Isotope, a
Column 1 wmLL Column 2 Column 1 Column 2
Air
Wat)®r
Ak
Water
i
t
f /M1)(}9�..�.#ti11)(vCi/it 1j (11cii/Ml.)
1�1�il.
Thorium (90)
Th 234
S
6 x10`*
3 x to--' �
2-XIO-`*
2 XID
I
3X10`'
3X10`'
1x10"*
2XIQ1
Tbaliam (69)
Tan 170
1
4 x10 °
1 XIO'1
t x10"+
S X10
1
3 x10"1
1 X10-1
I xIO'*
$Xt0 1
I'm 171
S
1 x10"1
1 X1 't
4 X10-f
S X10®1
'p
a
1
2 x10'7:
I XI0-1 iii
i.X10't
3 X10`^..
,Tin(30)
So 113
S
4X10.1 Y
2X103 a
1XIO'*
9x1O 1
1
3XIO"° Y
2X10-'1
2x10®*
3x101
fSo123
S
IX10_r
3x101 I
4x10`*
2X10`1
j
1
! *X10`4
5X10-1 a
3X10`* i
2XIO"1
Tungsten (Walfram) (74) 1 W lit
S
2x10-6
1X101 ;
sx10'* p
4XI0''
1
IX10`I
1X10-* i
4x10-* j
3x10'1
133
S
t X10®r
4 X10"1
3 XIO'*
I X10-1
I
I X10`?
3 X10`1
11 4X10-
I x10'"
1417
1
I 4X10-1
2X10`1 i2
X10-0
7X10-1
I
3X10'r i
2X10"1 j
1"X10`*
6x10"1
Uranium (92)
U 230
1
3 X10-#° '
I x10"' E
I xt0`At j
3 X10 4
I
t X10`10
I X1014
4X10"11
S XIO'*'
U 232
1
1 X10`1*
! XIG`1
3 xt0'12
3 xIo-,
ram+
1
3 X10-11 '
I X10-1
9 xto ,$ i
3 XIO-3;
U 233
S
3 XIO-14
9 x10-4
2X10"11 ' ;
3 X10-1
1
I
IX10-10I
9X10`4
4X10't1'
3XIO-"
**
U234
54
6XIO-10
9X10`1
2XIO"11
3X10-1
I
IX10-14 I
9xw,
4XIO-12
3X10`1
MsU
235
34
3XW14
3X10`1
2x10`11 ':
3X10-1"
s
I
IX10-441
aX10`1
4XW" i
3X10'5
U 236
S
6 X10-14 '
1 X10-1
2 X10-11
. XI*-$
i
1 X10`r4
1 X10`*
4 x10`12
3 X10-1
If*
U 213
34
7 X10-11
I X10'*
3 xw1*
�
4 x10`$
1
1 X10-14
I XW1
S X10-1,
III
4 XW$
C
U 240
S
2 X10"1
I X10"*
4 X10'*
3 X10..1
1
2X10-r
1X10`1
6X10"*
axt0-$
99
»naW t
S4
1 X10`14
I X10'1
SxI0'1*
3xto-$
1
1 X10-r4
I X10-1
SX10-41
3 X10'1
Vanadium(23)
v 48
S
2X10_r
9x10`1
6X10-4'
�
3X10-1
I
1
6X10'*
3X10`1
2XI*`
3X10`1
Xenon (34)
Xo 1311"
Sub
2 x10"1 &
4 X10`7
p
Xo 133
Sub
1 X10"1
3 XI0 '
i
Xa 133m
Sub
1 x10-°
3XIO 1
X• 133
Sub
4 xlO"*
I x10 1 a
Yttsrblum (70)
Yb US
S
7 XIO-1
3 x10`1
2 XIO'•
I X10-1
1
6X10'r
3x10-1
2XIO"*
1X10`4
YMrlum (39)
Y
S
I x I O `r
6 X10-1
4 X 10`*
2 X 10`*
t
1X1O'I
6X10`1
3X10'*
2X10'1
Y 91m
S
2x10'1
I X10-1
aX10'1
3X10"1
1
2 X10-1
I X10-1
6 x10"1
3 X10`1
Y 91
S
4 x10-1
3 10`"1
I X10`*
3 X10-t
1
3 x10-1
a X10-1
I X10-4
3 xto-$
Y92
S
,4X10'1
2x10"1
IX10'*
6XIO`1
1
3X10`1
2x10`1
IX10-4
6xlO"*
Y 93
S
2 XI0`7
$ X10-1
6 X10-9
3 x1O'1
t
IX10-1
4X10-1
3X10-1
3x10..1
December 30, 1 982{reset}
20- 4

Ap B
App. B PART 20 STANDARDS FOR PROTECTION AGAINST RADIATION
APPENDIX d
Concentrations In Air and Water Above Natural Background-Conttou*d
( } Tobto I Table It ,
i
Element (atomic number)
Isotope r Column I Column 2 Column I Column 2
j Air We. ; At,
i(u i/ (11Ci/ml)(-tC i /e111
( Water
(J}Ci/cal)
Zinc (S0)
Zn 65 S
( I X10'' 3 X10"3
d 4 X10"'s
I XIo '
1
6 Xid's S x10's
2 I0`s
2 X10`'
Zn 64m It
4 x10'1 2 XIo:"
± 1 Xtoo s
7 Xto-$
1
( '3 XI 'r 2 X10-2
( 1 X10`1
6 X10`3
Its 69 S
IX10`s l 3X10'2
2X10'7
I 2X10-3
1
9 X10-* 5 X10-1
3 X10'r
2 X10`1'
Zkconlum (40)
Zr 93 S
I X10-1 2 X10`t
4 X10"+
S X10-4
b'
1
3 X10'7 2 X10`2
1 X10-4
:3 X10-4
Zr95 S
IX10"r 2X10'1
4x10`t
6Xle`s
1
3 X10`4 2 X10-1
I X10 *
6 X10`s
Zr 47 5
I X10`7 S X10-1
4 X10'11
2 X10`"s
1
9X10's 5X10`'
3X10`s
y 2X10-1
tvAny single radionuclide
Sub
I X10"4 j
3 X10-s
f
net listed above with
I
decay made other than
j
alpha *mission or
spontaneous fission
t
and with radlaactiv*
I
j
hate -III* last then 2
hours.
j
Any single radionuclide
3 Xi0`s 9 X10-1
I X10-10
3 X10`6
net listed above with
l
decay mode other then
alpha •tttlsston or
spontaneous fission
and with radioactive
{
hall' -life grander than 2
hours.
Any single rodlonuelddo
6 X10'tt 4 XI0 t Y 2 XI0 t" t 3 X10-s
not If red above* which
1
decays by alpha *tuts-
I
sion or spontaneous
r i , •
'Soubit,(8);Insotubwit}.
,"Rub" moans lust values given *ro for submersion in a
*Amended 37 F'k 233t9.
t 4. $or soluble mixtures at XI-238, it-234 m:
, infinite cloud of airborne matennt.
and t7 285 In air chemical toxicity may ba the "Amended 39 YR 23990, footnote re-
ing factor. it the percent by weight (en- designated 40 Fit 50904.
si ent) at U-2$6 1* Ion than b, the eon. *"Amended 44 FK $0704.
*Themradon oonoentratious ap pri-
eentration valve for a 40-hour workweek,
Table r, Is 0.2 ntilligr um per cubic % to ended 38 b'k 29314.
eta for protection from radon-222 combined
meter, of air avenge. Vur any enrichment, $Amended 39 Fit 25463; redesignated
with Its short-lived daughters. Alternatively,
the product of the average oiancentetiitan and 40 I- k .50904.
the value In Table f may be replaced by one-
time of exposure during a 40-hour workweek
third ( ? "work level." (A ; "working
level°* 1s defined as any, bination of shorn*
sholinot fix 8 10-t �cCl-hriml,'whom
r
av the x fdc activity of kilo uranium in.
C lived radon-222 daughters, alum-218,
as lead-214* b ath-214 end po -214, In
M haled. The coneentristion value for Table it to
u. C007 MUIIV—uranium cnbie motor of
one Ilter of air. without regard to the degree*
per
U.
ibri the
o activity for natal uranium
that t la
to : on of S.3 xl(PNOV of alpha of
' ha
a Is 6.77X10-s U. specific '
pwUde e .) The le n value y Ins
ivitr for other mixtures at U-23E, 1U-235
1 replaced by tbirit ' (klw) of • "working
and-23; if not known, abs11 be:
I. The t on one Wens
- 3.0 10-* cur/gram, tT 1 -deq
In o y be on an an-
-(0A+0 X+0. W) 10-s Bzo.
noel *"rap.
where E Is the n by weight of 11-235.
{
i exp as porcenk
tit,,,......
20-25 December 30, 182(reset)

Alp. App.
` PART 24 • STANDARDS FOR PROTECTION AGAINST RADIATION
NOTE TO APPENDIX B 3. rf any of the conditions specified below
I;ors: In any where there is a mixture in air or are met, the corresponding values'specified
water of more than one rsdionuolide, the limiting values below may be used in lien of those soecMed
for Purposes of this Appendix should be determined w% in paragraph 2 abovc
foi}owst a. It the identity of a radionuclide in
i. If the Identlty and concentration of each radionu. the mixture is known but the conosntrat0
€lids in tits mixture are known, the limiting each
ran of one or more of the radionuclides in the
should be derived as"folloers. Determine, for each ra-
dionuclidein the mixture, the ratio bet weerthequantlty a Is not kno oon tion
ppresent In the mixture and the limit otherwise estsb• lfmit for the mixture is the t specified
lishad in Appendix B for the specific radfanuchde when Appendix for the radionuclide in ilea
m not to a mixture. The sum of such ratios for all tit€mixture 11a the lowest oOncGntraton
1L radionuclides in the mixture way not €xoe€$ '°i" (f.€.«
� °•nnitY"}.: u'limit,• or :
ry ErAxrtx: If radionuclides A B, and C are present9 b. If t^e identity of each onuende in
in concentrations CA, a, sn$ Glc, and it the applksble the is not known, but it is known
NPC"s« are NIPCA„ and NIPCs, and ?APCc respee- that certain r4diolluclides specified in Ap-
llvelY, then the concentrations shall be limited so that pendix ..B.. an not present in the ure,.
the to
relationship exists: the concentration limit for the mixture is
CA + OR CC 91 the lowest concentration limit Specified in
'a1PCA i1PCa i:PCc Appendix "A" for any radionuclide which is .
It either the xi 0"Ir 5r ttw rormntrw1"t, of any not known to be a nt from the
:or
ra Ilonv.-ilde i i ",i:a.ure G no. knu,vn, the luniting
cola€, for pur1K ,.' ,Avitendtx 13 shall be:
CC a. For purposes of Table I, Col. 1--S X 10-10
b. For purpo.es of "Table I. Cal, 2--4 X 10-1
p c, For purposes of "Table 11, Col. 1---2 X 10-1"
d. For purposes of Table U. Col. X 10-4
O
ta.
o. Element (stomio number) and isotope
Table I
Tabu 11
Air (AClhnl)
Air (ACffxdl)
Water
4Water)
(
If it Is known that Sr pl, 1 lie, 1 126, 1 129, 1 131, (1133,
11 At YaI231,t t23,
Ra 10, Th�'i3u,, Tb-
Ral2 Ac 227, PTh,g2,
nat, Cm 248, CI 254 and Pm 256 are not present .. ...........
It it is known that Sr 90,1 125, 1 126, 1120, it 131, 1 133,
...
9XI(t't
-------------
SX104
table It only) Ph 210 Po 210 Ra 223 RA 22d Re, 229,
m
Pa 231, T`h nat Cm 248 C(254 and Pm are not
present_ .. ....................
1 1131, table 11
__
$XI0 t
2XI04
If it 3a known that Sr 90 1129 (I t25 106,
only), Ph 210 Ra 226RA 228Cm 248 and Ct 254 are
not present ........:..... .:........
._......
2Xltt s
__- ._.........
axio r
if it is known that {1129 table 11 onty) Ra 220 and Ra'
,
228 are not present
._ .........
..............
Me
If It is known that alppha•emitters and Sr 90 1 129 Pb
210, Ao 22i Ra 228 Pa 230 Pu 24I and Bk 240 era not '.
.
3XI"
1XI0-1+
li 3t is known € and Pb 210 Ae
Ica 228, and Pu 24t are not nt........:........... .:
u 2 1 are t pros
3XI0^n
... ..........
1Xi0^11
..::..._.___.«
It It is known that alpha•omitters and At M an not
present-.,.. .... .-............ .. -
3XI0-n
1XI0`15
It it is known that At 227Th 230, Pa 231Pu 238 Pu
239, Pu 240« PU 242, Pu 244 Cm248. Of 249 and C f 25f
on not.. present.................................... ....
3XIO-0
--------------
IXI0--s
--------------
C If a mixture of radionuclides consists of
uranium and its daughters In ore dust prior
0 to chemical separation of the u um from
u7 the ore, the values specified below may be
u:usedfor uranium and its daughters through
radlurn-226, instead of those from paragmphs
1, 2, or 3.above.
a. Forp of Table 1, Col. 3-IX30-de
"Cl/ml gross alpha activity; or 6 X 10-- act/
mI msturst uranium; or 76 m1orogromax per
14 cubic meter of air natural uranlum.
tr b. For purposes of Table n, Col, 1--3 X 10-u
u. sCitml gross aephs, activity; or 2 X 10-u ACII
0 rel natural uranium.. or 8 micrograms per
(_ cubic meter of air natural urWUUUL
6. Far p of this *bit, a 10-;
nuclide y be considered as not present in
a mixture if (a) the ratio of the Miam mt"s-
tion of that radionuclide in the mixture
(CA) to the concentration limit for that:
radionuclide specified in Table It of Ap-
pendix 11 (6(P A) does not exceed Us
0C
U.(i.e, ' �) wad (b) the of such
MPCA -10
cv satos for all the radionuclides considered as
not present in Use mixture does not "toe
Y4
CA L"x °
+ ...
PCx. .JF
December 30,1982treset) 20-26

App. C
DART 20 tr STANDARDS FOR PROTECTION AGAINST
RADIATION
A noix c
rear
Any alpha omitting radionuclide
not listed, above or mixturseof
Material Microcurtes
lum-191rn
100
100
alpha smitters of unknown
kmerS€ium-241 -
Antimony-122
01
100
0amlum-101
0smium-19s ---.
100
position _._®- __ .01
tr Any rwilonuelldo other thanalpha
------------------
Antimony-124
10
Palladlum-103
100
U. emittingradionuclides, one listed
Antimony-126 _
10
Palladlum-109--,---._..-----------
100
above or'mixtum of bets a90t-
Arsenic.7s
1
Pla -__:_-----_- :-----
10
iari of unknown composition--- 1
"
Arsenic-74 _
Platinum-1912
Platinum-191 -
100
Arselai€ 76 __
Arsenic 77
10 ;
too
Platinum-193m - --
Platinum-198
100
too
its"
Now. —For purposes of 1 2"M where
_
$urn 131 ..
10
Platinum-197m _
too
t
; there is involved a1 b of to in
ttirium 13.t .,..
to
Platinum-197 --- _
Pluton$rn-210
t
01
«a
n'°, ; known amounts. limit t combination
Sarium-140
sti
Polonium-2t0 ,.. ..,.
0 1
should be derived a: follows. Determine, for
Bismuth-210 . _
I
Pot ium-42 _
10
p„
a each isotope to the comb►nati the ratio
Bromine-62 _
1I
Praseodymium-142 -
100
s. between: quantitythe tin the
Cadmium-100
Cadmium-115aax
10
10
Pray ymum-142 '-
100
combination and
file t otherwise
Cadmium-116 ------- -----------
Calclum-45 - _ -
100 100
10:
Promathlum-147_
Promethlum-14 -----------------
Radium-220 "`
10
10
01
0
established for the
in combination.
specific isotope when not
Tfie sum of such raliaas for all
Calcium-47 _"
10
_
Rhentum-166 """
1
the Isotopes in the combination may not
fK Y
____
Carbon-14 ___..
1iS0'
----
Rhenlum-1186 "''
1
exceed1"(i.e. ty"�
Cerium.143 -r
100
..,..._.
h um-108
l oo
-.----
Cerlii -144 _»
I
..->-_.->-.-_
Rh ium-t06----- ------------
110
Cesium-131 _ -
L
Rubidium-86 -
Rubidium
to
10
Cesium-1341n
100 ;
Ruthenlum 97
210
Cesium-134
"' -
1
------------------
Cesitga l35 .-.._______________:._..
10
Ruthenlum-108
Ruthenium-i05------------------
10
IQ
Cesium-136 ----------------------
10
Ruthenium -too -.--..------------
1
Cesium-137 -_--__--__®_---_-- _
10
Samartum-161 "_-"
10
Chlorine-36 _--_-
10-:
-.---_--
100
Chlorine- 8----------------------
10:Scandium-46
----- .-------------
10
Chromium-61 _— --------------
1,000
Scandium-47 --- ----
100
Cobalt-Sam10
-_- -
Scandl -48 .. _®._
10
Cobalt-$$ --- -------------------
10
Selenium-75 _---..-.----_-_--.__.
10
halt-60 ------------------- --
1
Silicon.31-_-.-------._-.- - _ --
100
Copper-64-m---------------------
100
Silver-106.......................
19
Dysprosium-1 5 -----------------
10
Silver-110m------ ----------------
I
Dysprosium-186 -----------------
100
Silver -III ___---------- ---...
100
Erbluin-169 _:-------------------
100Sodium-24
----------------------
10
Erbitim-171 ---------------------
100
Strontium-65-.--.-.--.-_ -_----
10
Europittin-152 0.2 b--------------
100
Strontium-89--------------------
1
ev
Ettrop}tim-152 13 yr _
i
Strontium-90
0.1
Etiropwin.i54 ________________;:__
I
Strontium-91 ...._.:_.___--------
to
Cc
Europlum.156 ___.,.-.. __._--_-_.
10
CC Strontium-92--------------------
10
u.
fluorine-18 - -------------------
1,000
w. Sulphur-35-.-..---.------------.
100
Gadolinium-153_________________
10
"Tantalum-182 ------------------
10
Gadolmitim-1 9-----------
I0wo
T chnetturn-96------------------
10
Galli tnl-72 __«_..----------------
10
Technetium-97m--.---__-- _-._.,
100
Germanium-71 ------------------
too
Techuati -97----------------
100
Gold-108 ----- -------------------
100
Technettum-99m ----------------
100
Gold-i99 ------------------------
100%
Technettum-99-.--_._--.----_--_
10
HariAltuaa-181--------------------
10
Tellurium-125m ®_:-_-_-_. ,._®__-
10
Holmium-166 ___________________
100
Tellurium-127m -----------------
10
Hydrogen-3 - ------------------
1,000
Tellurium-127-------- _----------
100
Indicant-)131n--------------------
100
Te}lurlorn-129m-----------------
10
111dimu-114m-.._.__.__r-____-.---
10
Telluriu -129 -------------------
100
Indium-115in _________________s_-
100
Tell urium-l3lm-----------------
to
Indium.115 _____________________
10
T"ellmlum-132 -..-._____- ----.
t0
Iodine-125 -- ---------------- -.
i
"Terbium-160--_---------_-----
t0
ludine-ate ______________________
1
'Thallium-200 --------------------
100
lvdalle-129......................
0::1
"Thathum-201 ....................
:too
Icdaaae-131 ----------------------
1
"Thallium-202 ------------------
100
lodine-132 .. ----------------------
10
"Thallium- 04 ____.u________ _____
10
lodino-133 ______________________
1
* orlum natural)x-_----:--__-.
Ste}
loduae-134 ----------------------
10
Thulitim-170 --------------------
10
lodine-1 5 ----------------------
to 10
°Thullum-171 --------------------
10
lrid}aim-192 ---------------------
10
Tin-113-----___.«-___m_-®------
10
Indium-194 ______________®_ ----
100
Tin-125 :W-----------------------
10
lnol-"55 _____-_--®--- ----------
100
'1'uuasten-lal--------------------
10
lrot­59 -------------------------
10
'Ttwg.ten-185 _-_-a__---_ -----------------
10
xr4ptola-as _« :
100
Ttingsten-187 __--- _ _..
100
Krypton-87 _____________________
10,
#Riiranlum ........
too
Lanthanum-140 __.._r.____._.- _
10
Uranwin-213-__:-.._------------
.01
Lutetium-177 -------------------
100
Ur.niuto- 34- Uranlum-235 ------
.01
Ala^aranese-52-®__-.-_.-_».--_ ---
10
Cian:aditim-48....................
10
Manganese-54 _------------------
10
fen 11-131ut »..------------------
1. 000
Man}ranese-56 --------------- :__
10
7 enon-1 2 _._ ._ --------------
too
Wer€tary-197m-------------------
100
Xenon.135 ----------------------
100
Alerciiry-197 ---------------------
100
Ytterblum-175.......::.........
100
Merc fry-203 _-._-____.>____-__- _
10
lttrinm-90 ___.--:__------------
10
Alntcbdentaln-99______________ __
100
Yttrium-91 ----------------------
10
N _______ __
gaxaStlm-147 ______
1tXt
Yttrium-92 _.__.:____._-.--___--
100
Neodcmium-149 ----
100
'Yttrium-93 _.____:® __.-- ___-_
Zinc-65 -.
100
10
rR on alpha dials lion rate of
on * of
Ut
Nicke4 59 _.-: _
Mekcl 63
too
10
------
Zinc-69m -_-
100
T11Jess, T and Chair daughter u.
6 p
__----------------------
Nickel-65
100
Zan€-69 -.. _____..:: ____.:-_.__>_.1;
1 $ on alpha disintegration rat* of
._.._:.___.
N}rihlciln-93m -__. ____.,_______-._
10
Zirconium-93 _____ ____________.._-
10
1I-238, U-234, and U-285.
Mohttam-95
10
Zirconium.-95 ::_.. _.__-::....______--
10
� Anieaitlo:d 36 FK 16899.
----------------------
Zir€ontum-97 --------------------
10
KK° Amended Jai VK 23990
0<mium-185____________________
10
20.27
December 30,1932iresetf

PART 20 • STANDARDS FOR PROTECTION AGAINST RADIATION
APPENDiX D,--UNiTED STATES NUCLEAR REGULATORY COMMISSION REGIONAL
OFFICES '
Adolresses
IT
(24 r8)
rAO- 1: oN1eCfim t; Delaware, Disbid at Columbia: Mains,
USNRC, $31 Park Averwo, King of
(215) 337-SM
Murylanda M kt9, shire, Now , Now
Pmmsia, PA 4
(FTS) 488-1000
Y Islanrt VarMont
m
ti. F , GOwgii, K i , North
USNAC, 101 Marietta Street NW,
[phone]
ua
RsM T ssoe, VVsr
Suite 29W Atlanta, GA 30323.
(FTS) 242-4
m
and wast veginik'
0:
ROOM Of' Gir ' Iowa n, tK Mmoun,
USNRC, 798 Roosvelt Road. Glen
(312) 790-
LL
OW. end Wisoonsin.
Ellyn, IL 60137.
(FTS)
Region IV*' K
RC, 611 Ryan Plau Drive, Suft
(817) 100
i
Moxiotl, ta, OkW=W SO4th
1000, Arlington, TX 76011.
(ITS) 7 100
Toxw Mak end WWnlng
'
Region IV: w. „;: ,..USNRC,
Region IV Ur R000very
) 236-2805
F' Office, 730 k
(ITS) 776-2805
P.O. Box 25W5, Denver, 00 W225.
Region V. ' a ak Nevada. Oregon,
USNRC, 1450 Maria Lww, Sift 210,
(415) 3700
Pacft Trw T W4 Wa
aMut Crook, CA 0459&
(FTS) 3700
October 31, 1986
20-28

cooling water. To enhance the detector perfori
ing it at a lower temperature, the continuous
of the component cooling water coolers. The r,
tive concentrations monitored is from approxim�
mately 1 x 10 2 pCi/ml. To preclude the relea
in the event of cooler leakage, an interlock f
a valve that normally vents the component cool
ance and reliability by operat-
amples are obtained downstream
ige of gamma emitting radioac-
tely 1 x 10 5 pCi/mI to approxi-
? of volatile fission products
)m the radiation monitor closes
ig water surge tank to the
11.4-5 12/83

source is incorporated to verify the operation of the monitor, Abnormal
conditions of high activity or loss of sample flow are alarmed in the Control
Room. The setpoint for high activity is adjustable over the full range of the
instrument. The operator has sufficient indication to determine heat exchanger
tube Failure and can isolate the defective heat exchanger before significant
activity is released.
11.4.2.1.8 Containment Ventilation Unit Condensate Drain Tank Monitor
The containment ventilation unit condensate drain tank monitor is provided to
continuously monitor the activity of liquids discharged from the CVUCDT to the
plant "discharge `header. The monitor consists of an off-line lead shielded Nai'
scintillation detector identical to the conventionalwaste water treatment
monitor.
The monitor is interlocked to chose a valve on the discharge of the drain pumps
o insure liquids will not be discharged with activities in excess of limita-
tion defined by Appendix B of 10CFR2 , including dilution. The receipt of an
alarm' will alert the operator to insure the discharge valve has shut and to
evaluate if processing by the liquid waste system is necessary. A flow propor-
tional sampler is also installed on the drain line of the CVUCDT. Thisar-
rangement permits monitoring of the flow as well as radioactivity of the
discharge.
11.4. .1.9 Boron Recycle Evaporator Condensate Monitor
The baron recycle evaporator condensate monitor is provided to continuously
monitor the boron recycle evaporator condensate downstream of the filter. "
Normally, the condensate will be routed to Reactor Makeup Water Storage
Tanks. On a high radiation alarm, valve 1NB219 will divert this flow to the
boron recycle holdup tank.
11.4.2.2 Airborne Monitorin
Airborne activity process radiation monitoring equipment (Table 11.4.2-2
summarizes continuous monitoring equipment that is available. By monitoring
ventilation systems, which remove air from locations where systems containing'
radioactivity are housed, for airborne activity, indications and alarms indica-
tive of a loss of integrity of these systems are provided. Monitors provide
Control Room information regarding personnel access limitation to areas within
the station during normal operation or anticipated operational occurrences.
These areas include Reactor Containment, Auxiliary Building, Spent Fuel Build-
ing and Control Room.` The monitors also provide information and alarms regard-
ing airborne activity releases from the station. Control of airborne activity
releases is based on laboratory analysis.
The Containment Purge, Containment Annulus Ventilation, Auxiliary Building
Ventilation, Condenser Air Ejector, Fuel Pool Ventilation, and other poten-
tially radioactive systems such as sample hoods discharge through the unit
vents. The unit: vents are continuously monitored for airborne radioactivity.
Effluent flow rate monitors installed on the unit vent stacks are used for
calculating discharge rates and/or total activities discharged as required by
Technical Specifications. The airborne process radiation monitoring equipment.
11.4-6 1984 L )d to

E`
TABLE I1.4.2-1
Page 1 of 2 I
LIQUID
PROCESS RADIATION MONITORING
E UIPMENT
DETECTOR
DETECTOR
TYPICAL
RANGE
DESIGN
NUMBER
IDENTIFICATION
LOCATION
FUNCTION
TYPE
SENSITIVITY
COUNTS/MINUTE SERVICE
1- MF-31
Conventional Wastewater
Turbine Bldg.
Monitor effluent to
Nat
Scint.
3x1O8
cpm per
101 -
107
Normal Operation
Treatment Monitor
EL 741
conventional waste-
pCml
Cs-137
Gross Gamma
I-C- 4-25
water treatment system.
Stop turbine room pumps
and terminate discharge
on high alarm when
turbine; room pump align
to conventional waste-
water treatment system.
I-EMF-32
Steam Generator Blowdown
EL 716
Monitor effluent and
Nat
Sant.
3x108
cpm per
101 -
107
Normal Operation
Recycle Demineralizer
FF, GG-3
terminate discharge on
pCi/ml
Cs-137
Gross Gamma
Effluent Monitor
high alarm
I-EMF-34
Steam Generator sample
EL 716
Detect Steam Generator
Nat
Sant.
3x108
cpm per
101 -
107
Normal Operation
FF-55,56
tube leak, and terminate
pCi/ml
Cs-137
*10' -
10e
Gross Gamma
sampling
I-EMF-44
Containment Ventilation
EL 716
Monitor effluent and
Nat
Scint.
3xlO8
cpm per
101 -
107
Normal Operation
Unit Condensate Monitor
BB 50
terminate discharge can
pCi/mI
Cs-1 7
*101 -
10e
Gross Gamma
high alarm
I-EMF-45A
Nuclear Service Water
EL 733
Detect Containment
Nal
Scint,
3xIO8
cpm per
101 _
107
Post LOU
1-EMF-4 B
Monitor
JJ-55
Spray Neat exchanger
pCi/ml
Cs-1 7
*101 -
106
Gross Gamma
tube failure
I- MF-46A
Component Cooling
EL 750
Detect Neat exchanger
Nat
Scint.
3x1O8
cpm per
101 -
107
Normal Operation
1-EMF-46B
Water Monitor
GG.56
leaks
pCi/ml
Cs-137
Gross Gamma
1-EMF-47
Boron Recycle
EL 733
Monitor and divert
Nat
Sant:
3x1O8
cpm per
101 -
107
Normal Operation
Evaporator Condensate
MM 56
evaporator condensate
pCi/mI
Cs-137
Gross Gamma
Monitor
I-EMF-48
Reactor Coolant Monitor
EL 716
Detect Fuel Clad
Nal
Scint
8x1O3
cpm per
101 -
107
Normal Operation
EE, FF-54
Failure
pCi/ml
F.P.
Gross Gamma
*High
Range
(Shielded)

Mf+P
TABLE 11.4.2-1
Page 2 of 2 l
LIQUID
PROCESS RADIATION MONITORING EQUIPMENT
DETECTOR
IDENTIFICATION
LOCATION'
FUNCTION
DETECTOR
TYPICAL
RANGE
DESIGN
NUMBER
TYPE
SENSITIVITY
CQUNTS/MINUTE
SERVICE
1-EMF- 9
Waste Liquid Monitor
EL
716
Monitor effluent and
Nal
Scant.
3x108 cpm per
101
_ 107
Normal Operation
KK,
LL-56,57
terminate discharge on
GM
pC1/ml Cs-137
*101
- 10e
Gross Gamma
high alarm
2-EMF-31
Condensate Wastewater
Turbine Bldg.
Monitor effluent to
Nal
Scant.
3xlO8 cpm per
101
_ 107
Normal Operation
Monitor
EL
741
conventional waste-
GM
pCi/ml Cs-137
Gross Gamma
U=28
water treatment system.
Stop turbine room pumps
on high level alarm
2-EMF-32
Steam Generator Blowdown
EL
716
Monitor effluent and
Nal
Scant.
3x10$ cpm per
101
_ 107
Normal Operation
recycle demineralizer
FF
GG-57
terminate discharge on
GM
pCi/ml Cs-137
Gross,Gamma
effluent monitor,
high alarm
2-EMF-34
Steam Generator Sample
EL
716
Detect Steam Generator
Nal
Sc'int.
3x1O8 cpm per
101
- 107
Normal Operation
monitor
EE,
FF-57,58
tube leak and terminate
GM
pCi/ml Cs-137
*101
- 106
Gross Gamma
sampling
2-EMF-44
Containment Ventilation
EL
716
Monitor effluent and
Nal
Saint.
3xJO8 cpm per
101
- 107'
Normal Operation
Unit Condensate Monitor
BB
62
terminate discharge on
GM
pCi/ml Cs-137
*101.-
106
Gross Gamma
high alarm
-EMF-45A
Nuclear Service Water
EL
733
Detect Containment
Nal
Scant.
3x1Q8 cpm per
101
- 107
Post LOCA
2-EMF- 5B
Monitor
JJ-57
Spray heat exchanger
GM
pCi/ml Cs-137
*101
- 10e
Gross Gamma
tube failure
2-EMF-46A
Component Cooling
EL
750
Detect heat 'exchanger
Nal
Scint.
3x108 cpm per
101
- 107
Normal Operation
2-EMF-468
Water Monitor
GG
56
leaks
WCi/ml Cs-137
Gross: Gamma
2-EMF-48
Reactor Coolant Monitor
EL
716
Detect Fuel Clad
NaI
Scant.
8x103 cpm per
101--
107
Normal Operation 4
EE,
FF-57,58
Failure
pCi/mI F.P.
Gross Gamma f
*Nigh Range (Shielded)

1. G OFFSITE RADIOLOGICAL MONITORING 'PROGRAM
During operation of McGuire Nuclear Station, small amounts of radioact
materials are released to the environment from releases of low level g
and liquid waste disposal ;operators make in accordance with NRC regula
and the Technical Specifications. The design and operation of the'rad
waste 'systems maintain the quantities of 'radioactive materials release
s reasonably achievable and within regulatory limits. The objective
m t• f .• i; f m• t» if f m
naturally occurr)*nQ radioactive materials in his own body, from food, water
and air intake):
The variations from time to time of the naturally occurring and the manmade
components of background dose (consisting of radioactivity in air and water)
are to be expected based on differences in area and local climatology inclu-
ding windspeed, temperature, barometric pressure, rainfall and runoff condi-
tions, etc. For example,: the concentrations of naturally occurring radio-
active radon gas may varyconsiderably at a given location depending on the
weather; the greater concentration being encountered during inversion
conditions:
The average of terrestrial gamma background measurements made at the McGuire
location indicates the variability from place to place:
11.6-1 183

Calculated whole
Distance
from
body gamma dose,
an (as designated in Table 11.6.3-2
Site
mrem/year
Within Site and Exclusion Area
44
Exclusion Area Boundary & Hwy 73
35
Ramsey Creek Access Area
3.4
miles NE
44
Westport, Golf Club
4.9
miles NNW
132
Cowan's Ford Country Club
1.1
miles WNW
70
Homes on Shore nears Discharge Area
0.5
mile E
38
Huntersville
6.2
miles ESE
35
Beatty's Ford Road
3.7
miles SSE
26
Lucia
4.8
miles SW
70
Cornelius
5.5
miles NE
53
Hick's Crossroads
1.8
miles ESE
53
ncentration of activity in the Catawba
River below the
station, from
1 and manmade sources, has been reported as
follows:
Gross Beta
on RtgaELed By
Dates
Activity
pCi/I
tte, N.C. N.C. Department of Human
Resources
1968
3.
Radiation Protection Branch
1969
<3.00
1970
<3.00
1971
<3.00
ncentrations of activity in milk samples near the site
have
been re -
as follows:
90
137
on Reported By
Dates
Sr
CS
pCi/1 FC i _71
tte, N.C. N.C. Department of Human
Re-
1968
10
12
sources
1969
12
12
Radiation Protection Branch
1970
12
12
1971
10
<17
t radioactivity from nuclear weapons and radioactivity from
other
installations contribute an extremely small fraction of the average
)n dose due to natural background radioactivity (for example, perhaps
as 0 ( 031 millirem per year is contributed from other nuclear
?s). 3
CRITICAL PATHWAYS
the amounts of radioactivity added to the environment from station
i are minimal and as low as practicable the possible critical exposure
to man have been evaluated in accordance with Regulatory Guide 1.109
to estimate the dose to the hypothetical maximum exposed individual,
as to establish the sampling requirements for the Offsite Radiological
)g Program. The pathways are:
11.6-2 12/83

1. Submersion in air (gaseous effl
2. Inhalation
3. Consuming milk and other dairy
gaseous waste effluents.
fts from locations affected by
'n areas or on feed affected by
ig along the shore of Lake Norman.
-ake Norman affected by radioactive
flrectly associated with this portion
? Norman affected by radioactive
i included in the Offsite Radio -
)cation 24 hours per day, 365 days per year.
PRE -OPERATIONAL RADIOLOGICAL MONITORING PROGRAM
?-operational phase of the Radiological Monitoring Program for McGuire
-
ng methods,- ------ ­z7_--
' frequ'ency of sampling, analytical procedures,and somewhat
ctly, laboratory instrumentation. This program provides surveillance of
itical exposure pathways to man and satisfies legitimate interests of
mpany, of the public, and of the state and federal agencies concerned
he environment. These agencies include the N.C. Department of Human
ces, Radiation Protection Section; the Environmental Protection Agency;
e U.S. Department of Interior, Fish, and Wildlife Service.
e-operational Radiological Monitoring Program is described in full
in the McGuire Environmental Report -Operating License Stage.
OPERATIONAL RADIOLOGICAL MONITORING PROGRAM
erational Radiological Monitoring Program provides surveillance and
support of detailed effluent monitoring which is necessary to evaluate
dual and population exposures and the ecological significance, if any,
11.6-3 12/83

of the contributions to the existing en
result from station operation.
This monitoring program is based on NRC
ized Radiological Effluent'Technical Sp
media,'! sampling locations, sampling metl
ticl sensitivitv requirements. This o
tal radiological levels that
al "Investigation of Natura
13(1960)
1959, pp. 11-12.
4 Y ! -1 MW to
,ith regar
RMATIMMUMM
California, Lawrence Radiation Laboratory,, October 1972.,
11.C- 13

Tabu 11.6.2-1
Estimated Doses Concerning Critical Pathways to
Man for Radion5c11Tdes Releases to the Environment
Airborne Related Pathways
mremlyr
1.
Submersion (all ages -skin)
0.75
2.
Inhalation (infant -thyroid)
0.58
3.
Milk (infant -thyroid)
1.7
4,
Vegetation (child -thyroid)
0.77
Water Related Pathways
5.
Lake and Shoreline Recreation
(teenager -whole body)
0.00
6.
Water (infant -thyroid)
0.53
7.
Fish (adult -liver)
0.59
12/86

Tables: 11. .3-1 (1 of 3 through 3 of 3)
11 > .`-2
11.6.3-3
DELETED
1985 Update

Table 11.6.6-1
ExaTples of Analytical Sensitivity Versus Permissible
and Discharge Cana]—Con-centrations
A. Releases
into Water
Discharge Caoal Con-
Caul
Concentration Permitted b
Sensitivity
—
by AEC Regulations
of Analysis
Radionuclides
pCi/ml
pCi/ml
PCi/mI
Tritium
1.9 x 10-6
3 x 10-3
2 x 10-9
Sr90
3.3 x 10-14
3 x,10-1
1 x 10-9
CS137
4.4 x 10-10
2 x 10-5
1 x 10-9
C060
1.5 x 10-12
5 x 10-5
1 x 10-8
1131
4.1 x 10-10
3 x 10-7
1 x 10-8
B. Releases
into Air
Radionuclide
1131
3.7 X 10-14
1 x 10-10
1 X 10-14
a See Table
11.2.8-1
b 10 CFR 20
Appendix B, Table II Limits
12/83

T""�Pc
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.1 MONITORING PROGRAM
LIMITING CONDITION FOR OPERATION
3.12.1 The radiological environmental�monitoring program shall be conducted
as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a. With the radiological environmental monitoring program not being
conducted as specified in Table 3.12-1, in lieu of any other report
required by Specification 6.9.1, prepare and submit to the Commission,
in the Annual Radiological Operating Report, a description of the
reasons for not conducting the program as required and the plans for
preventing a recurrence.
b. With the level of radioactivity in an environmental sampling medium
exceeding the reporting levels of Table 3.12-2 when averaged over
any calendar quarter, in lieu of any other report required by
Specification 6.9.1, prepare and submit to the Commission within
to Specification 6.9.1.13. When more than one of the radionuclides
in Table 3.12-2 are detected in the sampling medium, this report
shall be submitted if:
concentration (1) + concentration (2) + > 1.0
limit level limit lev-e--l--(-2-)--
3. Th

LANCE REQUIREMENTS
,al monitoring samples shall be collected
cations given in the table and figure in
cant to the requirements of Tables 3.12-1
d 4.1-1,
4c UIRE - UNIT 1 3 4 12-2

m
Number of 'Samples
Exposure Pathway
and
Sampling and
Type and Frequency***
and/or Sample
Sample Locations"
Collection Frequency
of Analysis
1. AIRBORNE
Radioiodine and
5 Locations
Continuous operation of
Radioiodine canister.
Particulates
sampler with sample col-
Gamma isotopic analysis_
lection as required by
for I-1.31 on each sample.
dust loading but at least
once per 7 days.
Particulate sampler.
Gamma isotopic analysis
on each sample.
. DIRECT RADIATION
40 Locations
Continuous integration
Gamma dose.
> 2 dosimeters or > 1
with collection at least
instrument for con-
once per 92 days.
tinuously measuring
and recording dose
rate at each
location.
Samp-- locations are
given on the figure and table in the`ODCM.
***Frequency of analysis
stated only if different
from collectionfrequency.

rn
Number of Samples
Exposure Pathway
and
Sampling and
Type and Frequency**
and/or Sample
Sample Locations *
Collection Frequency
of Anajyr
3. WATERBORNE
a. .Surface
3 Locations
Composite* sample collected
Gamma isotopic analysis
over a period of < 31 days.
of each composite sample.
Tritium analysis ofcom-
posite sample at least
once per 92 days.
b. Drinking
4 Locations
Composite* sample collected
Gross beta and gamma
over a period of;< 31 days.
isotopic analysis of
each composite sample.
Tritium analysis of
composite sample at least
once per 92 days.
c. Sediment from
3 Locations
At least once per 184 days.'
Gamma isotopic analysis
Shoreline
of each sample.
be collected by collecting an aliquot at intervals not
exceeding 2 hours.
Composite samples shall
**Sample locations are
shown on the figure in the
ODC .
***Frequency of analysis
stated only if different
from 'collection frequency.

TABLE 3.12-1; (Continued)
m
RADIOLOGICAL
ENVIRONMENTAL MONITORING PROGRAM
i
Number of Samples
Exposure Pathway
and/or Sample
and
Sampling and
Type
and Frequency***
Sample Locations**
Collection Fre uenc
of
Anajy i.
4. INGESTION
a. Milk
4'Locations
At least once per 15 days
Gamma
isotopic and
when animal are on pasture;
I-131
analysis
at least once per 31 days
at other times.
b. Fish and
Invertebrates
2 Locations
One sample in season, or at
Gamma
isotopic analysis
least once per 184 days if
on edible
portions on
not seasonal. One sample of
each
sample.
each of the following species:
1. Game Fish
2. Bottom Feeders
c. Broad Leaf
Vegetation
3 Locations
at least once per 31 days
Gamma
isotopic analysis.
Sample locations are
shown on the figure in
the ODCM.
**Frequency of analysis
stated only if different from collection frequency.

l AbLt
REPORTING LEVELS FOR
RADIOACTIVITY CONCENTRATIONS IN
ENVIRONMENTAL SAMPLES
Repo.
Levels
c
Broad Leaf
-,
Water Airborne
Particulate
Fish
Milk
Vegetation
Analysis
(pC%/1) or Gases
(pCi/ma)
(pCi/ g, wet)
(pCi/
(pCi/Kg, wet)
(a)
H-3
2 x 10
N.A.
N.A.
N.A.
N.A.
Mn-54'
1 x 103
N.A.
3 x I04
N.A.
N.A._,
Fe-5
4 x 102
N.A.
I x 104
N.A.
N.A. '
Co-58
I x 103
N.A.
3 x 104
N.A.
N.A.
41.
r
o-6
'x 10
N.A.
I x 104
N.A.
N.A.
Zn-65`
3 x 102
N.A.
2 x 104
N.A.
N.A.
Zr-Nb-95
4 x' 102
N.A.
N.A.
N.A.
N.A.
I-131
2b
1
N.A.
3
1 x 102
Cs-134
30
10
I x 103
60
1 x 103
Cs-137
50
20
2 x 103
70
2 x 103
Ba-La-140
2 x 102
N.A.
N.A.
3 x 10
N.A.
(a) For drinking water samples. This
is 40 CFR Part
141 value.;
(b); If low
level 1-131 analysis are performed.

TABU4.12-1
.,
MAXIMUM VALUES FOR THE
LOWER LIMITS OF
DETECTION
(LLD)"'
m
Airborne Particulate
Broad Leaf
Water
or Gas
Fish
Milk
Vegetation
Sediment
Analysis;
(pCi/1)
(pCi/ma)
(pCi/kg,wet)'
(Pci/1)
(pCi/kg, wet)
(pCi/kg, dry
gross beta
4
N.A.
N.A.
N.A.
N.A.
N.A.
H-3
2000
N.A
N.A.
N.A.
N.A.
N.A.
Mn-'54
15
N.A.
10
N.A.
N.A.
N.A.
Fe-59
30
N.A.
260
N.A.
N.A.
N.A.
Co-58, 60
15
N.A.
130
N.A.
N.A.
N.A.
,.a
Zn-65
30
N.A.
260
N.A.
N.A.
N.A.
r
Zr-95
30
N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95
15
N.A.
N.A.
N.A.
N.A.
N.A.
I-131
15b
7 X 10-2
N.A.
1
60
N.A.
s-134
15
5 X 10-2
130
15
60
10
Cs-137
18 -
6 X 10-2
150
18
80
180
Ba-140
60
N.A.
N.A.
60
N.A.
N.A.
La-1.40
15
N.A.
N.A.
15
N.A.
N.A.

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TABLE 4.1'
TABL
liter shall be at
ihtinued)
`ION
.1 in drinking water samples.
.ter will not be; routinely
Dr low level analyses of I-1.31
radionuclides; in Table 4.12-1 , shall be identified an `reported.
McGUIRE - UNIT 1 3/4 1.2-9 ;

RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.2 LAND USE CENSUS
LIMITING CONDITION FOR OPERATION
3.12.2 A land use census shall be conducted and shall identify the location
of the nearest milk animal and the nearest residence in each of the 16 meteoro-
logical sectors within'a distance of five miles. Broad leaf vegetation sampling
shall be performed at the site boundary in the direction sector with the
highest D/Q in lieu of the garden census.
APPLICABILITY: At all times.
ACTION:
a. With a land use census identifying a location(s) which yields a
calculated dose or dose commitment greater than the values currently
being calculated in Specification 4.11.2.3, in lieu of any other
report required by Specification 6.9.1., prepare and submit to the
Commission within 30 days, pursuant to Specification 6.9.2, a Special
Report which identifies the new location(s).
b. With a land use census identifying a location(s) which yields a
calculated dose or dose commitment (via the same exposure pathway)
20 percent greater than at a location from which samples are currently
being obtained in accordance with Specification 3.12.1, in lieu of
any other report required by Specification 6.9.1, prepare and submit
to the Commission within 30 days, pursuant to Specification 6.9.2, a
Special Report which identifies the new location. The new location
shall be added to the radiological environmental monitoring program
within 30 days. The sampling location, excluding the control station
the same exposure pathway) may be deleted from this monitoring
program after October 31 of the year in which this land use census
was conducted.
C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE -RE UIREENTS
4.12.2 The land use census shall be conducted at least once per 12 months
between the dates of June 1 and October I using that information which will
provide the best results, such as by a door-to-door survey, aerial survey, or
by consulting local agriculture authorities.
McGUIRE - UNIT 1 3/4 12-10

RADIOLOGICAL ENVIRONMENTAL MONITORING
3 4.12. 3 INTERLAB ORATORY COMPARISON PROGRAM
LIMITING CONDITION FOR OPERATION
3.123 Analyses shall be performed on radioactive materialssupplied as part
of an Interlaberatory Comparison Program which has been approved by the
Commission.
APPLICABILITY: At all times.
ACTION:
a. With analyses not being performed as required' above, report the
corrective actions taken to prevent a recurrence to the Commission
in the Annual Radiological Environmental; Operating Report.
b. The provisions of Specifications 3.0.3 and 3..4 are not applicable.
SURVEILLANCE REQUIREMENTS
4.12.3 A summery of the results obtained as part of the above required Inter -
in the tPA cro sche k program sha1( provide the LPA program code designation
for the unit) shall be included in the Annual Radiological Environmental
Operating Report.
Mc U RE -'UNIT 1 3/4 2-1

DT-TRE POWER C)O--4PA--,Y
P.o. Y3ox 331€ 9
C; .'.RLOTTE, :ti.c. 28242
HAL, B. TUCKER TELFPHON
vic y PRPSIDev-r [phone]
December 3, 1986
Mr. Harold R. Denton, Director
Office of Nuclear Reactor Regulation
,µ
U.S. Nuclear Regulatory Commission
Washington, D.C. 205
ATTENTION: Mr. B.J. Youngblood, s Director
PWR Project Directorate No. 4
Subject: McGuire Nuclear Station
Docket No. '0--69 and 50-370
Response to RFI Regarding
Radioactive Discharge From
Conventional Waste Streams
Dear Mr. Denton:
On March 19, 1986Duke Power submitted a proposed Technical Specification change
to allow slightly radioactive water to be discharged from. the Conventional Waste
(WC) system. By letter of October �6 1986, the Staff requested additional
information. Attached are ;the questions asked by the Staff, together with the
responses. For clarification purposes Figure 1'has been included to identify the
various' components of the WC system and adjacent water sources.
If the Staff desires additional information, please contact Duke through normal
Licensing channels.
Very truly yours,
Hal B. 'Tucker
SAG/4/gm
Attachments

:. Trenton
3, 1986
J. Nelson Grad., Regional Administrator
>. Nuclear Regulatory Commission - Region II
Marietta Street, Suite 2900
.at, Georgia" 3033
W.T. Orders
Lion Resident Inspector
wire Nuclear Station
Da. ne Brown, Chief
.iaton Protection Branch
'ision of Facility Services
artment of Human Resources
1. Box 12200
eigh, N.C. 2605

(AG4) ATTACHMENT
STAFF QUESTIONS AND RESPONSES
Premise For Questions Is Through if
Radioactive liquid effluents from theaMcGuire Nuclear Station are now sampled,
analyzed, and released by a monitored pathway. The radioactive liquids are
diluted by the circulating water and released to Lake Norman. The lake provides
additional dilution and delay before the radioactivity reaches the river.
Question la
The proposed new release pathway will not have the dilution and delay provided by
the lake. Discuss the provisions made for assuring that the radioactivity
concentrations are sufficiently low at the proposed point of release and 'provide a
comparative analysis of river concentrations for the: proposed and existing release
paints.
Response:
Radioactive releases from the existing monitored pathway are diluted by Condensate
Cooling Water (CCW) and released to Lake Norman. However, the
recirculation/buildup is included in Offsite Dose Calculation Manual (ODCM)
release; rate and dose calculations effectively reduces CCW dilution by a factor of
2.. Although Lade Norman provides additional delay before radionuclide releases
reach the Catawba River downstream of Cowas Ford Turn, ODCM release rate and dose
calculation procedures applicable to the existing monitored release point 'would be
unaffected by the proposed new release pathway; existing ODCM procedures are
applicable to maximum individual liquid pathways for Lake Norman adjacent to the
existing release point. Additionally, since the proposed new release point is
downstream of Cows s Ford Dam, radionuclide releases from the new release point
will not affect maximum individual pathways in Lake Norman.
The combined effect of radionuclide releases from both the existing release point
and the proposed new release points downstream of the new release point on Catawba
River maximum individuals shall be assessed in the future and compared to Lake
Norman maximum individual doses in accordance with revised ODCM Section B4.3.1
procedures. Only;maximum calculated close values (i.e., Lake Norman maximum
individual or downstream Catawba River maximum individual calculated doses) shall
be used for compliance or reporting purposes. Operational history has shown that
the maximum individual doses will continue to result from `Lake Norman pathways'.
The combined effect of both the existing release point and the proposed new
release point on procedures assuring radionuclide concentrations remain /
sufficiently low is addressed by revised ODCM Section B >1.3. Since
recirculation/buildup of radionuclides in Lake Norman is considered to increase
lake concentrations by as mach as a factor of 2.4, it can be sho th C^t wb
River o entry iJijil, L2111ILstream of Cowans yard Dam resultin from n release
point releases will not exceed S o x mum Permissible Concentration

Dre, ODCM Section B3.1.3 has been
e proposed new release paint to
3 to limit radionuclide releases
resulting in less than 41% of MPC
3 revision assures MPC values are
:he Catawba River due to the
release points.
=quation to Section 4.3.1 to
WC system to the Catawba River.
Like a'discharge to Lake Norman via
a. discharge to the river via WC.
>{ 1.0.
pursuant to
the releases are to be controlled spa the combined doses from both
is (existing and proposed) do not collectively exceed the Appen
in our response to la above, ODCM Section B4.3.1 has been nevi
educes to assure that the new release point in combination with
es shall be perfo d to assure only maximum dose values+
e and reporting purposes.
Lfications should require appropriate sampling and analy
from. the
:n Appendix % evaluations; the LLD for Cs-137 for releases from the
µ example, should be no greater than 0.1 pCill. discuss the various
ind analyses associated with the proposed action and .identify the
it sensitivity for the instruments to be used.
Specification 4.11.1.1.1, Fable .11-1 lists radioactive liquid'wast
.nd'analysis program requirements.. Each release through this release
.1 comply with these technical specification: requirements.

__
wm with a Germanium detector. The laboratory
red in; Specification .11..1.1 Table
t these requirements,for example, the
.uuu ror us- .5/ ror releases from the WC system shall be no greater than 0.1 pCi/l;
therefore no difficulty is anticipated.
Question Id:
Address the capability to obtain representative samples .from the Conventional
Wastewater Collection System.
Response
Prior to release the appropriate pond will be isolated and recirculated to ensure
thorough mixing for representative sampling.
Question le:'
Discuss the capability to prevent unmonitored releases to and from the
Conventional Wastewater Basin.
Response
To prevent unmonitored releases from turbine building sump to the conventional•
wastewater system there are radiation monitors installed on each Turbine Building
.LICj. = L.LJ Ci LIVWever, uney cannot detect very low levels of tritium
The station has implemented routine sampling and analyses for tritium
Lrbine Building sumps, in the WC system, in the Sanitary Waste Treatment
A in the: Standby Nuclear Service Water Pond.
Et unmonitored releases from the conventional waste water system, in
to the routine sampling program discussed above, a continuous composite
.s located at the discharge point to preclude unmonitored releases. Any
ctivity discovered` will be investigated immediately to determine the
correct the problem.
om Conventional Wastewater Treatment System (WC) are initially directed
ret-lined initial holdup pond where primary sedimentation occurs. This
allon capacity basin has a retention time of from 12 hours to 24 hours
as a surge tank to prevent overloading and subsequent degradation of
quality throughout the remainder of the system. This pond may be
depending on influent quality,

t
---
The initial holdup pond is followed by parallel stream settling ponds. These two
1.1 acre, 2#5 million gallon ponds are lined with tamped 'clay and are equipped for
recirculation. The ponds are operated such that one pond is in service while the
other is on'standby. Coagulent aids may be used for settling lighter solids along
with pH adjustment to neutralize or precipitate various chemical compounds.
Holdup time for each of these basins ranges from 6 to 12 days.
The wastewater then normally flaws by gravity to the final holdup pond where it is
aerated.; retention time for this basin is 5 days. This final holdup pond is used
to remove any persistent oxygen demand of the wastes. The pond has a capacity of
one million; gallons. Its contents may be ,pumped to the head of the settling
basins or back to its own inlet for recirculation if the effluent does not meet
the established discharge limits. The final holdup 'pond may be bypassed and the
discharge flows by gravity or is pumped to the river if the effluent is within
specifications.
NOTE: In as much as the WC system accepts influent from the turbine building;
sump, any primary to secondary leak may result in contamination of one of the
settling basins and possibly the initial hold-up pond.. In this case, the basin is
isolated to allow for dilution and radioactive decay as required by NRC Technical
Specifications. In addition, demineralizers and chemical additives may be used to
process the 'waste water. Releases from the pond will comply with McGuire
Technical Specifications.
Question If
Discuss the capabilities to determine the quantities to be released so they can be
reflected in dose calculations,
Response:
Representative samples will be taken and analyzed as discussed in the response to
Ic, above. From this the total curie content can be calculated for use in the
offsite dose equations given in response lb.
Question 2:
Address theaccumulation of radioactivity in the sludge in the Conventional
Wastewater Basin, the frequency and method of sludge removal and disposal, the
radiological concentrations and exposures projected for sludge control and
procedures used to maintain these exposures ALARA.
Response:
As shown in Figure 1, the Wastewater Collection Basin (formerly the Conventional
Wastewater Collection Basin) is not in the WC flow path. Therefore, this response
addresses sludge accumulation in the initial holdup pond, where the 'vast majority
of sludge accumulates.

The volume of waste being generated per year is projected to range from 8,000 t
• M.
i
ing of this sludge is projecte
table for landfilling where t1
l the sludge at a suitable site and incorporate it into the soil
The disposal procedures which are already approved for use b
.r Landfarming permit are as follows:
zo.rtation Procedure
To remove this sludge, the _;pond is drained and the sludge is dre
from the bottom and transferred by dump truck to the disposal si
The sludge will be transported to or from the disposal site in s'
that liquid or solid spills will be kept to a minimum.
accordance with station Health Physics procedures and stationT
directives.
oral Procedure
Turing and after the disposal process access to the proposed disposal
site will be controlled. Proper warnings will be maintained as
described in the Landfarming permit.
The waste sludge (water treatment residues) will be spread on the
surface of the proposed disposal site over an approximate area and dep'
of one acre and six inches, respectively.
The sludge will be incorporated approximately six inches into the soil'
after drying to the extent practical.' Because of water retention by t
resins, there will be no inhalation hazard from diatomaceous earth
particles.
A suitable year round vegetative cover will be established and
maintained after the waste has been incorporated and covered with
topsoil as needed, if necessary.
The workers handling the waste disposal will be properly dressed in
accordance with station Health :Physics procedures and station
directives.

Administration Procedure
o The waste volume of each batch'
and documented.
o For each batch of waste genera -
locations will be taken for rat
documented.
o The total waste volume and rad
and the total accumulating dos(
oThe disposal ragas will be lim:
inches/acre/year) .
;posed of will be properly estimated
a composite sample from different
.ogical analysis, and results will be
:tivity inventories will be documented,
.11 be periodically evaluated
to 500 cubic yards per year (6
to prevent wind erosion and surface
unozz from conveying poiiutants trom the waste material applicati
isposal area onto the adjacent property.
e (1) design changes to upgrade the capacity of the LRS,`and (2) oper,
Lions consistent with existing LRS capacity. Justify the proposed a
of available alternatives.
se:
cal Specifications 3/4.11 1.5 allow small < concentrations of radionucl
system. These may enter ,the system as a result ofprimary to second<
and may be present as radionuclides which cannot be removed (e.g. trig
ich will result in an insignificant increase in offsite dose. They m<
ionuclides which are at detectable concentrations, but cannot be
r-reduced by available plant processing equipment (ion exchange, filt
ich will result in an insignificant' increase in offsite dose commitmei
as include cesium--134 and 137 at less than 5E-07 microCi/ml.
Ling to route this 100 gpm waste source to the 20 gpm radwaste system
in reactor shutdown due to 'Turbine Building Hotwell Pit flooding. TI
ad amendment would allow the release of WC system radioactivity at
trations within the current Tech Spec limit if the calculated offsite`
trations and dose are within Tech Spec, 10 CFR 20, and 10 CFR 50 limi
:here will be no change to the health and safety to the public.

_-
ternatives examined included a) pumping the contents of a contaminated WC pond
(2 million gallons) back to the Turbine Building for portable Ion Exchange process
and then release to the CCW; b) Ion Exchange/filtration of trace quantities o
radionuclides in the 2 million gallon basin; and c) install increased LRS
capacity.
None of these options will significantly affect offsite dose due to tritium. None;
of the options would significantly reduce instantaneous effluent concentrations
for other nuclides.
Casts for the above options range from $250,000 for option a) to $8,000,000 for
option c) for an offsite dose reduction of less than: 0.3 /year®
Question 4:
Identify any waste stream otherthan that of the Conventional Wastewater Treatment
System that will also be released at the proposed alternate release point.
Discuss the measures taken to ensure' adequate control of releases via any such
other waste streams through this release point. Include sampling, analysis and
monitoring provisions for any such waste stream.
Response:
See figure 1.
Collection Basin (CB)
e Collection Basin receives treated sanitary effluent, yard drainage and
overflow from the Standby Nuclear Service Water Pond. The overflow from the
.. _ • " • • .. e • • IBM
11 003 discharges treated sanitary waste from the Sanitary Waste
ment System to the Collection Basin.
ante TreaLMnt System
anitary Waste Treatment System consists of an aerated -facultative
m which is a trapezoidal multicellular arrangement consisting of
etely suspended cell followed by -three partially suspended cells'
s. The lagoon provides an approximate 5-day retention time and to
for variable .flaw discharge. The wastewater effluent from the 4
flows through chlorinators, a -chlorine contact chamber ' d a"Fz
before discharging to the Collection Basin. Expansion space is
ded should a sand filter be required in the future.

lagoon is lined with a flexible
Tided into four cells by a curtaJ
_yester with a weighted chain ba'
elm.«� 1 1 0
tic material such as hypalon, it is;
ial such as a polymer coated
d floatation collar. The first
and is kept in complete suspension
d and third cells are kept
settling. Each of these two cells
ace of this cell is kept slightly
ae final cell, the wastewater
After passing; through the
f 30 minutes is provided by a
the Collection Basin.
;har e capability at=5, 6 , and 8
f operation, the lagoon is able to
t wastewater flow rates of 40,000
52,000 gpd, and 64,000 gpd, respectively.
analyses and monitoring programs to prevent unmonitored releases are
in, response to Question le

INITIAL
HOLDUP
WT
POND
INFT TFNT
SETTLING
PONDS
�'
A AND B
4 WT LAGOON
l
�
FINAL<
HOLDUP
h
POND
YARD
DRAINS
WT EFFLUENT
WC
(OUTFALL 002)
EFFLUENT
(OUTFALL 003)
STANDBY
NUCLEAR
S tr".RV I C: E'
WATER
CATAWBA
RIVER
WASTEWATER
Col,l,r TLON
BASIN
SITE
BOUNDARY
FIGURE' I:

11.2-2 1985; Updat

M,
.ste drain tank can
processing in this subsys
)ntamination area showers, hand washes, Auxiliary Building servifce
fecontamination sinks, and laundry machine effluent. The radioacti-
tanks should be below the level required for processing to reduce

)activity. However, in on
urging this liquid it is 1
D minimize the environmental effe
sled through the fallowing equipm
ral ner.
imary filter (A&B).
ondary filter.
pment the liquid is 'collected in
M i
M ! i' M M *•
11.®4

nthe contai
.nk Subsystem
.i 1 ati on units
s tank will b
adwaste+Portion)
ts'of the 50,000 gallon auxiliar
y waste evaporator feed tanka<.
t' • i i t t i • t -i
.2 Electrical Power Requirements
ectrically powered equipment in the liquid waste systems, with the
ion of the Residual Heat Removal and Containment Spray Room sump puml
plied from station non -vital buses,as it is not required to be oiler;
emergency conditions. No duplication of power supplies is made.
.3 Water Chemistry
ste evaporator distillate water chemistry for water suitable for rec
is as follows:
Electrical Conductivity 2.0 uho/cm @ 25 C
pH 4.0 to 0.`0
Oxygen (dissolved) <0.1 ppm
Chloride <0.15 ppm
Fluoride <0.15 pp
11.2-5 1

Particulates
it is used as a recycle e)
>ntration should rance bet
SYSTEM DESIGN
• 1s 1 W
<100 ppb (as iron oxide)
►rater, the waste evaporator feed boron
itration should range between 7,000
feat Tracing
design parameters of equipment in the liquid waste systems are (
1.2.3-1. The criteria used to establish the system design para�
relationship to key equipment in the system are discussed in th(
paragraphs.
Safety Classes and ASE Code Classes are given in Table 3.2.2-2.
ipment listed as ANS Class NNS (NRC Class D) have an absence of
gases, thus a failure of any NNS class equipment contributes nol
ite exposure since all liquids'are contained by the Auxiliary Bt
aaste evaporator and its associated pump and filter are listed
cause of their use as a backup to the boron recovery evaporator
11.2-6

,ion, both pumps
sign performanc
,e operated to meet
11.2- 121

udge Pump
i capacitv at 200 feet developed head is
this pump t(
ition Unit Cot
:ontents of the ven
s complete. Pump se,,
Waste Evaporator Feei
~
lump
)e pump capable of deliveri
Floor Drain Tank Pumps
,dwaste facility. These pumps are used to recirculate and transfer t
�ntents of the two 50,000 gallon radwaste facility tanks.
Mechanical Seal Cooling Water Pump
iis, small 60 psi @ 2 gpm pump is used to supply cooling water to the
faporator concentrates pump.
Reactor Coolant Drain Tank Heat Exchanger
ie heat exchanger meets the following requirements:
Maintains the RCDT fluid at 170OF or less with a nominal 10 gpm
of 600OF reactor coolant.
Maintains the RCDT fluid at 170'F or less with a 25 gpm flow frot
excess letdown exchanger during heatup or draining operations.
Cools the contents of the pressurizer relief tank from 200OF to
less than 8 hours.
ie heat exchanger is cooled by the Component Cooling System on the sl
Mechanical Seal Cooling Water Heat Exchanger
iis heat exchanger cools seal water to the waste evaporator concentr
t cools 2 gpm from 140'F to 1100F. This heat exchanger is cooled by
)mponent Cooling System on the shell side.
11.2-9

ictor
Coolant Drain Tank
'4-1, 4-
----4A—A
-F-- —,-k .-4+
Tk- mA�mr%ee
I M,
M a
?ed Tank
, valve and pump seal leakoffs (outside Containment), aj
ed water sources. The design bases for the required tai
itional margin to accept a 10 gpm leak from one unit fo,
gallons).
itional 200 gallon margin.
Tank
gn bases for the size are essentially the same as that for the wast
,or feed tank.
ycle Monitor Tanks
!sand gallons of tankage are provided to collect distillate from the
and waste evaporator. The size is sufficient to allow a 15 gpm eva
operate without interruption for an 8 hour period. Due to space
ons, two 5,000 gallon tanks are provided to meet the tankage requir
Each of these tanks is provided with a diaphragm to exclude air fro
,e condensate.
te Evaporator Reagent Tank
ik is provided to add chemicals to the evaporator liquid if requirec
11.2-10 12/8"

Floor Drain Tank
day surgecapacity
Tanks
ospheric tanks are
r ank 114 jAs
MEMM
'Aling Tank
M
W.
ided for liquid holdup and moni
provided for mixing specialty
,Patina lintjiri-, rnI1Prt_ArI in the
1985 Updat

1. Auxiliary Floor Drain Tank
This 50,000 gallon seismic tank is pa
for temporary storage of floor drain
is also used, where necessary, to che
M. Mechanical Seal tooling Water Ta
Filters
izer with :
the radwaste facility and is used
waste until it can be processed. It
ly adjust waste.
Ll i zer
-ycle this to the primary s
cystems. The deminerali
ve its apacity.
ze
20 ft3 of resin is used to process laundry.or fl(
- - 4.1-- -1 -* -- - - - I- I - - - .-1 --.: .1 -- A 1 11 t.! 1 1 - -- t- - Ai - -
-1-1 u — aar.t .ieY , I g . I 4IfV %.%JVIIIIV lTQ LGI I I I %UI I --wcx III
,cent of 5 microns or larger particles. Filters that retain 98 percent
microns or larger particles are as follows:
!ante evaporator feed filter
Paste evaporator condensate filter.
,aundry and hot shower tank primary filters (A&B).
Este monitor tank filter.
'loor drain tank filters (A&B).
11.2-12 12

ers
llowing strainers are provided in this system:
aundry and hot shower tank strainer.
loor drain tank strainers
loor drain tank pre -strainers.
,undry and hot shower tank strainers and the floor drain tank strainer
r larger from entering the floor drain tank. All sti
tainless steel.
ent
r
r is provided in the Liquid Waste Recycle System. &
- . - - _11 - J L - L__ ___ __ - .___ __ A .4-­
upon its origin. Evaporator bottoms are generally reclaimed in the or
Tanks.
b. Waste Evaporator Condensate Return Unit
�eheater and evaporator and returns the condensate to the condensate,
The unit consists of a 100 gallon receiver, two 25 qpm pumps, valv
instrumentation, and automatic controls.
ip is automatically started'when the receiver water reaches high leve
level in the receiver the pump is automatically stopped. In the nex
[n alternator switches control to the other pump.
operating pump cannot handle the,condensate load the standby pump is
.ically started on a high -high level signal..
(aporator Concentrate Lines Flush Tank
iter heater is used after the recycle or waste evaporator bottoms hav
imped through a concentration line to be drummed. The capacity is
ient to flush the full length of pipe from the waste evaporator to th
ig station. The flush water is taken from the W.E.F.T. and pumped by
C. pump.
Instrumentation Design
irm originating on the system panel is relayed to the common annuncia
Control Room.
11.2-13 1985 Upc

a . .
1111OP41V Il.
Coolant Dr
:em
ink Liquid Temperature.. This channel prc
n tank liquid temperature on the system
s'also provided.'
ink Pressure. This channel provides ind
';LIOW F.dI Wtl 644GLi.
170-Reactor Coolant Dr
ate locally the disch
mentation
.. r
e pressure of ROOT pumps A and E
1. This channel provides indic<
Wild
this
10'-This instrument indicates the total RCT pump flow at the system
A low -flow signal from this instrument automatically stops any?operat-
pump. m
RO'-This instrument indicates the recirculation flow to the RCDT`from the
it exchanger, at the system panel. A low -flow alarm is also provided to
se operator that recirculation flow has been lost.
-ain Tank Subsystem
I
ssure Instrumentation
10„ OWLPG5670-Waste Drain Tank Discharge Pressure -This instrument
is locally the di-scharge pressure of the waste drain tank pump.
11. 2-14 1.2f 8

Level Instrumentation
!vel-This instrument indicates the liqw
les high and low level alarms, and intei
.ank level so that the pump shuts off ai
suction when'the tank level falls beb
s furnished locally and at the system I
temperature of the tank on the liquid waste panel.
alarms on high temperature downstream of the rupture disc. The a
vaste evaporator panel alerts the operator that the rupture disc i
:-6370-Recycle Evaporator Rupture Disc Downstream Temperature - Thi
alarms on high temperature downstream of the rupture disc. The a
,ecycle evaporator panel alerts the operator that the rupture disc
:-6320-Seal Cooling Water Hx Outlet Temperature - This instrument i
exchanger outlet temperature locally and trips the concentrates F
Pressure Instrumentation
-15010, OWLPG5680-Waste Evaporator Feed Pump Discharge Pressure - 1
�ument indicates the discharge pressure of the waste evaporator fe
ie evaporator control panel.
'15020-Waste Evaporator Feed Filter Differential Pressure - This ir
:ates locally the differential pressure across filters A and B.
35040-Waste Evaporator Condensate Filter Differential Pressure - I
rument indicates locally the differential across the waste evaporz
?nsate filter.
36160-Vent Condenser Pressure - This instrument indicates the pre�
im downstream of the vent condenser locally.
36170-Feed Preheater Discharge Pressure - This instrument indicatE
iarge pressure of the feed preheater on the evaporator panel.
36180-Distillate Cooler Outlet Pressure - This instrument indicat(
iarge pressure of the distillate cooler on the evaporator panel.

al Cooling Wate
gal Cooling Wate
imp Suction Pressure - This instrument trips
suction pressure.
imp DischargePressure - This instrument ind
- the seal cooling water pump on the evapora
'Iter Differential Pressure - This instrumen
)ressure on the evaporator panel-
il Cooling Water Supply Pressure - This inst
seal water supply pressui
1.
ized Water Supply Pressui
ation
I
e - This instrument alarms
essure gets too low.
so
w a predetermined value. Indication is furnished locall
nel.
mentation
Evaporator Feed Pump Discharge Flow - This instrument pr
,-Concentrates Pump Discharge Flow - This instrument indicates and
concentrates discharge flow on the evaporator panel.
-Concentrates Pump Seal Water Supply - This instrument trips the
tes pump on low seal cooling water flow.
-Conductivity Analyzer Flow - This flow glass allows visual verifica-
low through the conductivity analyzer.
-Sodium Analyzer Flow - This flow glass allows visual verification of
ugh the sodium analyzer.
11.2-16 12/83

OWLF66260-Oxygen Analyzer 'Flow +- This flaw glass allows visual verification of
flow through the oxygen analyzer.
11. 2°-17 12/86

OWMLT5050-Floor Drain Level - This instrument indicates liquid level in ti
floor drain tank, both at the system panel and locally, the instrument al!
provides high and low level alarms at the system panel, and interlocks th(
floor drain tank pump with the tank level, so that the pump automatically
when the1evel falls below a predetermined value.
OWMLT5260-Mixing and Settling Tank Level - This instrument is used to conl
valve 1SM172 on the pump discharge and to provide local indication. The r
and settling tank pump is shutoff automatically on low level.
alarms on the WPS.Panel, and interlock the waste -mot
!vel, so that the pumps shut off automatically if the
letermined value. Level indicators are located on th(
.ntation
.40-Waste Monitor Tank A Pump Flow, Waste Monitor Tani
-uments indicate waste monitor pump flow on the systen
ow to Mixing and Settling Tank - This instrument proN
if waste flow to this tank.
;ubsy.Ltem
'.rumentation
60 and OWMPG5420-Floor Drain Tank Filter Diffarp-ntial
he floor tank filter. The AP across the filter at full flow may be
Jetermine filter cleanliness..
)-Floor Drain Tank Pump Discharge Pressure - This instrument provides
lication of the discharge pressure of the floor drain tank pump.
Derature Instrumentation
)-Floor Drain Tank Temperature - This instrument provides a computer
high temperature.
!on Unit Condensate Drain Tank Subsystem
;sure Instrumentation
1WLPG5630-Vent Unit Condensate Drain Tank Pump Discharge Pressure
trument provides local indication of the discharge pressure of the
?l Instrumentation
11.2-18 121E

r5590-Vent Unit Condensate Drain Tank Level - This instrument indic
id level of the ventilation unit condensate drain tank in the contr
instrument interlocks the ventilation unit condensate drain tank pu
tank level, so that the pump automatically shuts off when the level
N a predetermined value.
ante Facility S stem Subs
Pressure Instrumentation
6010 Auxiliary FDT Pump Discharge Pressure This instrument give
cation of pump discharge pressure.
6030 Auxiliary WEFT Pump Discharge Pressure This instrument giv
cation of pump discharge pressure.,
Level Instrumentation
T 6000 Auxiliary FDT Level - This instrument indicates tank level,
on to level and alarms on hi level.
T 6020 Auxiliary WEFT Level - This instrument indicates tank level,
on to level and alarms on hi level.
S 6040 Radwaste Facility Sump Level This instrument starts the su
i level and stops pump on to level.
Radwaste Facility Pipe Trench Sump A Level - This instrument, alarms
ump, level.
Radwaste Facility Pipe Trench Sump B Level - This instrument starts
ump on hi level, stops the pump on lo level and alarms on hi -hi
Radwaste Facility Pipe Trench Sump A Level - This instrument starts
ump on hi level and stops the pump on lo level.
Instrumentation
Auxiliary WEFT Pump Recirculation Flow - This instrument indicates
ecirculation flow to the tank remotely.
Auxiliary FDT Pump Recirculation Flow - This instrument indicates the
,culation flow to the tank remotely.
Auxiliary FDT'Pump to L&HST Filter Flow;- This instrument indicates
to the L&HST filter remotely.
11.2-19 12/83

OPERATING PROCEDURES
and alarm funciions to
aeration.,
rmal !22tLation
on except opera
The system 14
15��
6id Waste Monitor <and Disposal
e functions of the reactor coolant
11.2-20 1985 Update

nitrogen from the liquid collected in this tank. The procedure to
uipment in the systems listed above in order to exclude nitrogen fror
ids in this tank is as follows:
se all equipment isolation valves.
n the flush line from the reactor makeup water storage tank.
n the line to the waste drain tank and leave open until liquids with
rained fissi-on product gases have been flushed from the tank.
se the line to the waste drain tank.
se the flush line from the reactor makeup water storage tank.
n the equipment vent line.
n the equipment drain line to the waste evaporator feed tank.
ceure assures that no nitrogen gases enter the 'waste gas decay tank
no fission product gases are released to the environment. In many
s system maintenance occurs during refueling when systems are often
after circulating aerated reactor coolant. In these 'cases equipment'
directly to the waste evaporator feed tank and the above procedure is
tank is filled, the contents are pumped to one of the recycle holdup
r evaporation.'
hvdronpn 7S HiSfinlvpd in fha moor>tnr rnnlant a nnrtinn r*an hn avnar-+
11. - i 12/86

a Line up the standby waste gas compressor to the recycle holdup tank
eductur. Normally, the standby compressor feeds the other waste gas
compressor which is lined; up to a catalytic recomb ner and a high'ac
1
« • 1
. .e• • a -• . _. a my«•. • ..
he station. If radioactivity dictates that further process—A.w
1 .2-22 12 6

ing is required, the WM system demineralier
can be used. Water from the waste
circulating water at a rate
n'the Reactor Building deon-
Wer LdnK, d LWO TOOL Minimuit ievei
shower 'tank.
#
llaneuus chemical processing requirements.
4.2 Faults of Moderate Frequency
ystem is designed to handle the occurrence of equipment faults of moderat
envy such as.
Malfunction in the waste processing system.
Excessive leakage in Reactor Coolant System equipment.
Excessive leakage in auxiliary system equipment.
11. 2- 12 6

fiction in the Waste Processin System
fiction in this system could include such incidents as pump or valve
RA
not normally operate during a blackout.
Accident
iot required to operate during, or immediately following,
irted manually as required when electrical power is available.'
PERFORMANCE TESTS
1.1 Results of Initial Tests
J performance tests are performed to verify the operability of the
ients, instrumentation and control equipment and applicable alarms and
I setpoints.
lecific objectives are to demonstrate the following:
lumps are capable of producing flow and head as required.
11.2-24 1985 Update

.
Waste
filters are
capable of passing required flow.
C.
Waste
evaporator
is operable
nentati on, controllers and al
, pressures, and flow rates,
ad,
npli'ng points are available f
ration the system is u
ED RELEASES
ntities are largely dep
s capable of maintaining the temper-
ed n point.
to Anah"Z+a e #icf ^Fnr7ly +n
id indicate, record and alarm as
sampling.
?d at all times and hence is Conti'
�.M •. . i ® * . r r i r i`i •r ; . i *
i i r •. •. * « M ;:.r r i i • r : • * • ! :i
i i i it # ; r • r • *i ir# ;* . • +,
i .. ': «.. .. ! i ': w ! r' •... ! . r i ! ' i i r • *
A .: - r:. i r .. ,• `. * . a. ! : i r ,... i r i.: i .. ......
!* !• i . i!` r ! . i . it *i #i``r • r i r ` . ! r r
®. . . t. r i ! * r r `• i i i ii ! i :
! • ` • i ! i ! r •
r •

I of actual radioactive liquid releases from Westinghouse PWR Plants
in Table 11..6-4.
RELEASE POINTS
14A t.rne+11 i•n kn A4ee—knwrvnr% 'i*1% +kn nnwiv^mmnn+ -FI^we +kv+neenk n ft.4;!N+4^n
at ng waterf(R) system a
.
LUTION FACTORS
r
� :� ®� ! �I� • III * i.
*
The pathways used in
2.
Iratorl es , May 19/b.
condenser circulating water fl
Cowan's Ford Dam
result of radioactive liquid rel
6

lLn . uurK 'f'ar-v, DU F foully .L, U.J.- riuc lt::ci1 nt-vutawl y
11.2'-27