NC0024392_Regional Office Historical File Pre 2018 (5)

PERMIT NO.: NCOO
FACILITY NAME: Du ce
Facility Status:
(circle one)
Permit Status:
(circle one)
Major
Minor,
Pipe No: 5
Design Capacity (MGD):
Domestic (% of Flow):
Industrial (% of Flow):
Comments: ,e/r
ezvicr ho., /3G i / /1
RECEIVING STREAM:
Class:
Sub -Basin:
w
Reference USGS Quad:
County: MzeL/n.
Regional Office: As
(circle ens)
Requested By: ` o.
Prepared By:
Reviewed By:
Fa
NPDE WASTE L D ALLOCATION
ever
(please attach)
Wa Wi WS
Drainage Area (mil)
7410-(.cfs) SC-) Winter 7Q10 (cfs)
Toxicity Limits: IWC % (circle
Instream Monitoring:
Parameters
Upstream
Downstream
Effluent
Characterist
cs
BOD,L (mg/1)
NH3-N (mg/1)
D.O. (mg/I)
TSS (mg/I)
F. Col. (/ 100m1)
pH (SU)
Comments:
Location
Location
Avg. Streamflow (cfs):
`'`30Q2 (cfs)
cute

Peen it Number
Facility Name
Typecif Waste
Status
Receiv
Stream
3ubbas
rig Stream
Class
7ASTELCAD ALLOCATION APPROVAL FORM
N00024393
DUKE POWER-MCGUIRE
COLLECTION BASIN DI
EXISTING
CATAWBA RIVER
WSIII
0 30833
LENEURG
CHRIST
-7
HARGE
::]age Area
Average F'?
Summer 7010
Winter 7Q10
RECOMMENDED EFFLUENT LIM
0a
is
Location:
Location:
T#" 1 A MODIFICATION TO
3 ,iUTF4LL C 0S FROM THE
PERMITTED f F LL
ONA!`, WASTE
`. ..mac LIMIT i= O P
FLOW IS A
4,6
or
COMMENTS
Reviewed by:
Tech. Support
Regional
Permits
rvisor
rieeri
Request No. :433
AND INVOLVE- PERMITTING
. 0 6 4 MOD OF SANITARY
TFALL DO 1 (,411 AGD
OF O.v 'iREN``.,
00'2
RETURN TO TECHNICAL SERVICES BY QEC m03 1988

Facility Name T. N'%
Permit# t.9C o 2 q
CHRONIC TOXICITY MONITORING REQUIREMENT (QRTRLY)
The permittee shall conduct chronic toxicity tests using test procedures outlined in:
L) The North Carolina Ceriodaphnia chronic effluent bioassay procedure (North Carolina Chronic
Bioassay Procedure - Revised *February 1987) or subsequent versions.
The effluent concentration defined as treatment two in the North Carolina procedure document is
12%©. The permit holder shall perform Quarterjv monitoring using this procedure to establish
compliance with the permit condition. The first test will be performed after thirty days from
issuance of this permit during the months of --Co l — Effluent
sampling for this testing shall be performed at the NPD S permitted finale uent discharge below
all treatment processes.
All toxicity testing results required as part of this permit condition will be entered on the Effluent
Discharge Monitoring Form (MR-1) for the month in which it was performed, using the
appropriate parameter code. Additionally, DEM Form AT-1 (original) is to be sent to the following
address:
Attention: Technical Services Branch
North Carolina Division of
Environmental Management
P.O. Box 27687
Raleigh, N.C. 27611
Test data shal be complete and accurate and include all supporting chemical/physical measurements
performed in association with the toxicity tests, as well as all dose/response data. Total residual
chlorine of the effluent toxicity sample must be measured and reported if chlorine is employed for
disinfection of the waste stream.
Should any test data from this monitoring requirement or tests performed by the North Carolina
Division of Environmental Management indicate potential impacts to the receiving stream, this
permit may be re -opened and modified to include alternate monitoring requirements or limits.
NO 1'E: Failure to achieve test conditions as specified in the cited document, such as minimum
control organism survival and appropriate environmental controls, shall constitute an invalid test
and will require immediate retesting(within 30 days of initial monitoring event). Failure to submit
suitable test results will constitute a failure of permit condition.
7Q10 cfs
Perrnited Flow �.. Z MGD
1WC%© \
Basin & Sub -basin
Receiving Stream (bst
CountycAl`./.,..,
Recommended by:
**Chronic Toxicity (Cerio) Monitoring at l7_ %,
See Part ' , Condition G

NPDES Permit Modification #1
Application for
Re -Permitting Collection Basin
' roll,
'
OCT
G
OCT"T

Supplemental Information
System Description
Collection Basin (Wastewater Cc
Llding drains, and condenser
esigned to provide water ±for
The lab sink and floor drains discharge approximately three
liters of chemical waste per month. Flow from these drains
go to a groundwater sump then to the SNSWP then to the WWCB.
The Administrative Building drains include an HVAC sump,
floor drains, hot water boiler and chilled water system
discharge. Flow is to a yard drain which flows to the WWCB.
The Condenser Cooling Water (CCW) System for each of the two
(2) units has a volume of approximately 2 million gallons
each. 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 piping. The maximum

,x
unwatering rate is approximately 2000 gpm; the water is
essentially lake grater. Treated liquid radioactive waste
effluent (discharge 004) discharges into a crossover line
between the CCW system of the two units.inuring unwatering,
trace amounts of radioactivity can potentially be released
into the water from the unwatering process because of
leakage by a 54-inch isolation valve.
All yard drains discharge to the WWCB. The WWCB provides
sedimentation, natural neutralization, and skimming. inch. 'he
overflew from the WWCB mixes with the discharge from the
Conventional Wastewater Treatment (WC) system {discharge
002) in a concrete' apron and is discharged to the Catawba
River downstream of Cow ns Ford Dam

OMB No. 1000-0059
Approval e+pnes 11-31 -85
Pleasefprint or type in the unshaded arras only.
it;
„EPA
OUTFALL LOCATION
A. OUTrALt
NUMBER
(liar)
005
U.S. ENVIRONMENTAL PROTECTION AGILNCY
APPLICATION FOR PERMIT TO DISCHARGE WASTEWATER
EXISTING MANUFACTURING, COMMERCIAL,
A,, MININGG ND SILVICULTURAL OPERATIONS
ConsolidatedPermits
B. LATITUDE
f, Ogg.
35
Z. M#M,
25
1, sac.
59
s
an to the nearest 1
C. LONGITUDE
F. ©!G,
80
56
55
econds and the name of the receiving w
II. FLOWS, SOURCES OF POLLUTION, AND TREATMENT TECHNOLOGIES
A. Attach a line drawing showing the water flow through the facility. Indicate
and treatment units labeled to correspond to the more detailed descriptions i
flows between intakes, operations, treatment units, and outfalls. If a water
pictorial description of the nature and amount of any sources of water and any
D. RECEIVING WATER (name)
Catawba River
sources of intake water, operations contribut
n Itern B. Construct a water balance on the li
balance cannot be determined (e.©., for carol
collection or treatment measures.
B. For each outfall, provide a description of: (1) All operations contributing w
cooling water, and storm water runoff; (2) The average flow contributed by
on additional sheets if necessary. (Refer to Supplemental Inf
t, OUT-
FALLNOr
(lia I)
2. OPERATIONIS) CONTRIBUTING FLOW
a. OPERATION (liar)
b. AVERAGE
(include un
er to the effluent,
ing by showing average
hies), provide a
astewater to the effluent, including process wastewater, sanitary wastewater,
each operation; and (3) The treatment received by a wastewater. Continue
or-tttation for Additional Details
OW
005
Collection Basin
(Wastewater Collection Basin)
7.2 MGD
3. TREATMENT
a. DESCRIPTION
b. LIST CODES FROM
TABLE ZC•I
Sedimentation
Natural neutralization
Skimming
Discharge to Surface Waters
1-U
2-K
4- A
OFFICIAL USE ONLY (et 4fnt /uldelines aub•eateporlee)

CONTINUO FOM THE FRONT
C. E xort for stormr(jfl�ff Ieaks, or Spills, re any ot the dacharge describeddescrlbad n Items II -A or B intermittent or sessontll
; YES 'croupier(' MC follou•,ng tahIct
X NO (go to S(Cti0n11/)
1. OUTFALL
NUMBER
PRODUCTION
2. OPERATION(s)
CONTRIBUTING FLOW
A. )to Il1Wirrrrrrr •ir,rdellrrw rtr-nriorrr)n nrrrmulciatr.,
rce,rrroi.•tr
3. FREQUENCY
4. FLOW
a, DAYS
PER Wk.,FI4
b. MONTHS
PER VEAR
""'"
a FLOW RATE
(1,1 Ingd1
b. TOTAL VOLUME
(specify with units)
th4Le0 i tOtt.
ETA taidiii Section 304 of he Cit-ian W3tel Act apply to your tacitity?
NO firr t,r Sicl'rrrrr /11
c, DUR-
ATION
10 I 414.1.
Are the limitations i0 the appiicable effluent guideline expressed in 0:rtri5 ot production (or other measure of operation
] YES ,col,o0, (", NO /kr, Irr Sertiorr 11,t
C. f you answered -yeS'' tO inriWB. ],st the otuiputy h sentt, an actual measurement of your level of production, expressed
used m The applicable effluent 00oClrno P10 ncicate the af!ected ctatk
m' and UnitS
1 AVERAGE DAILY BRT,DUCTION
“TION„ evr-
2, AFFECTED
OUTFALLS
(list ewlfaN /11.1 FYI
A. Aol 1 d by any Federal, State Or 'hr.:al aurhor.ty 10 meal any implmnenlal,on schedule o the construction, upgrading or operation of waste
oi practices or any [Me, 1..r-rs,r,rwrilirrcrtat programs which, may affect the 0iiiiiuitarges described in this ouplication? This includes,
but 7)0,0 to, permit condit,ons, administrative or enforcement orders, enforcement compliance schedule letters, stipulations, court orders, and giant
Or 03/
y ES icontpleo, thc follow1,4 tahlet :-t.to (go lo nemV• I)1)
11,
. IDENTIFICATION OF corromo
AGREEMENT, ETC.
Z. AFFECTED OUTFALLS
orr.o. b„ souse* or 151.14C1A1441/t
3. BRIEF DESCRIPTION OF PROJECT
FINAL.r+FkiSE
OPTIONAL: You may attach additional sheets describing any additional water pollution control programs (or other environmental projects which may affect
your discharges) you now have underway or which you plan. Indicate whether each program is no underway or planned, and indicate yOur actual or
warmed schedules for constructon,
MARK "X" IF DESCRIPTION OF ADDITIONAL CONTROL PROGRAMS IS ATTACHED
Nmommlimmill&
CONTINUE ON PAGE 3,
r
-2C IRev. 2-851
PAGE 2 OF 4

CONTINit1ED FROM PAGE 2
V. $NTAKE AND EF
A, 8, & C: Sae instructions before proceeding — Complete one sat of tablet for t
NOTE: Tables V-A, V-8, end V C are included on separate sheets nu
to list any of the pollutants listed in Table 2c-3 of the instructions, which you know or have reason to believe is discharged or may be
outfell. For every pollutant you list, briefly describe the reasons you believe it to be present end report any analytical date in your
Supplemental Information for additional details)
SOURCE 1. POLLUTANT
Form Approved
OMB No. 2000-0059
Ae! exprres 12.31 -8
fall - Annotate the outtatt nu
V-1 through V.
D. Use the space below
discharged from any
possession. (See
1. POLLUTANT
Vi. POTENTIAL DISCHARGES NOT
Is any pollutant listed in Item V-C a substance or a component of a
byproduct?
OVERED BY ANALYSIS
ubstancewhich you currently useor manufactu
' YES iiis( aII ouch polls. toots below) X,No two to !fern VI-B)
SOURCE
or final product 0

TI'hUE4 FRIMTHE FRONT
po you have ert
receiving water i
knOWteC9e Or rea:t
rein;ion to your d
;t any biotc
the fart3 y
DIVES (identity the test(a) and describe their purposes below)
Fathead Minnow Flow -Through Acute Test
Ceriodaphnia Survival and Reproduction Test
or acute or chrome toxicity hat bean made on any of your ditch
n VIM
Tests were for informational purposes to determine whether the discharge showed any signs
of toxicity. No acute toxicity to fathead minnows was demonstrated during the 96-hour
test period. No effluent -related acute toxicity or chronic toxicity to Ceriodaphnia was
demonstrated during the 7 day test period.
e any of the analyses reported in item V performed by a contract laboratory or consulting ti
v ES analyzed (list the nae, address, and,
each such laboratory or
telephone
fnumber
rm below) and pollutants
B. ADDRES
A
A
NUS Corporation
Teledyne Isotopes
( Analyses perfo
o to Section IX)
0
1910 Cochran Road [phone]
Pittsburgh, PA 15220
50 Van Buren Avenue [phone]
Westwood, NJ 07675
D. POLLUTANTS ANALYZED
(list)
Item V; Part C
Parameters
Ra-226 & Total Ra
d in 1982; to be retested with renewal in 1989)
nder penalty of law that this document end al/ attachments war
at qusidled personnel properly gather and evaluate the informat,
sons directly responsible for gathering the information, the inforri
ra that there are significant penefties for submitting false info
Qred under my direction or supervision in accordance with a system designed to
submitted. Based on my inquiry of the person or persons who manage the system or
ion submitted is, to the best of my knowledge and belief, true, accurate, and complete•
anon, including the possibility of fine and imprisonment for knowing violations.
A. NAME & OFFICIAL TITLE ((ppe or print)
H.B. Tucker
Vice President, Nuclear Production
B PHONE N©. )urea coda & no.)
[phone]
D. DATE SIGNED
7
C. SIGNATURES
/
TGq Ladbit(cL,,

CART A ,
I. POLLUTANT
t» ctt4�tl.t ,1
C)..yytal t..'xtt.�ttti
c 141,1 Ou.j.::MiL
i,. t.rej
1. 7 0111fx ,.SGi'(ii:�.:.f
rr
1 Tt"t.,, tutu ram.
.1 1«A):11.11JM DAILY VALU
4.2
15
5.8
2.05
.20
V AL,. t1
311.75
(Analyses perfotiued in 1982; will be retested
for application in 1989).
fation Name Outfal'1 Number
McGuire Nuclear Station 005 ,
1. r/AXILIU\1
1.1
cor.rc r.r _ n
1113.39
430.51
151.43
14.84
8.90
V At_U:.
PAW'. : i.
1 1t f'..•c.
X
X
t,o..tat •
6.8
.1AX 1M U.L7
10.5
4.3
V A L UL
4.00
Y V U
v ALUC
VAL
U
14 AJ. I M UP1
v VALU..
319.17
A4"I4L%. VALUi.
_.__ (xl •n res '
VALU
2.46
VALUE
VALUC
r,4_. 3'� t�,t'.' v •}L 11Z 1 c. L. C1
ANAL YSE
astewater Collection Basin
t1.CONCEN-
TIIAl1Ur:
1
1
A59
b/day .91
mg/1
1
248
259
mg/1
mg/1
m9/1
1:) .nnss
18.67
lb/day 7.11
145.87
A
b/day 2.2
MGD
b/day 2.5
b/day .05
45.14
51.29 1
1.02 1
2.46 248
VALUe
4c
VALUE
No./100i
wg/1
Ts
lb/day
2
6
15.

T-
AN'I A
CAS N
J IIrPQan,
1a1 prunnr[
4
MARK'
U r
)AILY VALUC
1.4 103.92
CNT
A X I M U ht 31i (),A Y V A
**
.19 14.10
c
Alpha,
X
Total
X
4+.2
4.4+.
A k i i (: , V A L U
X
4) ftaoaum
25, Total
It, st
ray
1141t
1. Su
Write
4265,45-3)
u
X
5
4, UNITS
©NCCN•©. MASS
ATION
mg/1 lb/day
5. INTAKE:
At.)' A i tat,
<.1 2.05
X
NO t>t
A NA.1
vsl.s
mg/1 lb/day
.08
.64
1 pCi/1
X
X
X
o. AIutY (nut
T Deal
In,9 90 51
11atluffl,
�1a1
440 39.
X
10 742,26
X
X
0,4243)
Cut oI1,
uul
/44C 4.94)
Iron, Total
439 H9 6)
Total
11439 95 4)
yt)aenu
4
11n TPtal
440 31
X
X
X
X
.35 25.98
.02 1.48
1pCi/1
1 pCi/1
1 pCi/1
.43+.16
2.4+.28
8.5
.5
nr / 1 1 b/day
0 205.16
X
X
X
1 mq/1 lb day
1 mq/1 lb/day
.055 4.08
.36 26.72
5 259.79
.07 5.19
.01
.44
.01
1 mg/1 lb day
1 mg lb day
1 mg/1 lb/day
.02
X
.14
.2
X
.006
.20
.41
2.87 1
24.62
2

Part C
4�" u A
ANC) I:A�
rJU.1(1C1
1,1ArtK "X'
(Analyses performed in 1982;.will be retested
fear application in 1989).
s
a
IC uclear Station
MAXIMUM :DAILY V AL.Ui..
TALS. CYANIGE, AND TOTAL PIIENC)LS
1 r.1rLti.unV.
1 i,Ia1 ; /440
•
JL.1 0.11•Il.ipn,
u td 11 44t1 4 S 91
3r.1 Chrunni.,n
1 u1Jl (1440 41 31
nI Covnrr, TUtal
(J..0004)
)r.1. Lead, ru Lri
143:1 9 / 461
J l.I F.;ercury, TQtJI
14:490/10
1 u1J1
1 /440 02 0)
1 "LI41 11132 40 2)
111.1.50.e!„ ro14l
/440 22 4)
121'.1 1 haliunn
I utal (1440 211 0)
Jr..) Zinc, Tu[d1
144U 63, Co
1441. CY.nuh>,
Iuul;5/
I:.rst. Phenols,
I ..c..l
N
5.45
025
.1
,4
r.
.0001
01
04
1.94
07
.02
31,
86
07
.37
�FFLtJ NT
Ou
Number
astewater Collection Bas
4. UN1"1
. CONCCN
TF:ATK3N
r1 MASS
ug/1
ug/1
ug/1
ug/1
ug/1
ug/1
ug/1
ug/1
ug/1
mg/1
nib 1
d LC'r
A
lb/day <2
lb/day 3.7
lb/day <.001
lb/day <.2
1bfday
lb/day 4.7
lb/day 1.0
lb/dad ._.'w.
iP/day
b/ ._
WA
1b/day .03
lb/day ,:.001
lE,/LUy
TAK
4
<.00002
<.004
<.01
.10
.02
<.002
<.10
10
<.002
‹.02
.62
02
t+ r`t tl e•E
X

1. F'C`I..LUTANT
A N (1 C A 5
C!111,t11U. )7
ACTION)
111. AcettarllU,i*ni,
;83 32 9)
Acennphtylenc
I. 0U 96 0 )
39. Anthrecone
120127)
i (1. I3rnridine
92 87 5)
1lunro (a)
lnihracune
555531
iU. Ilenro (u)
'yrene (50 32 3)
10a. pis f -1l Chfur,,
y)
111-91-
'10 2-C1,1,,r0
It. y;) F thcr
111 44-4)
1211. Cis (2-Chl„ro
3.153),32 9)
30 O,s (2 Elhy).
".'1)) FlilLal]IC
117 81 7)
4 Ir0rn3-
;hcnylF'hrnyl
Inc) (101 55 3)
5il idyl Orntyl
hthalate I95.1,6-7)
2 C#;Ioto,,
,r. ntl.)1unc
'.I 1 58,7)
4 Ct.luro-
1•Ienyl
1)5 72-31
7U 3)
1,2 U,. hlorri
„t,na (95 GU 1 r
'11t 1.3 nicl,w,u-
,,<r�ut If,41 13 I
( r MAXI
1.1
c c
U liA4. CC)it QUNUS
<10 <.74
<10 • <.74
X <10 <.74
X <10 <. 74
X <10 <. 74
X <10 <. 74
X <10 <.74
X
<14__ <.74
1_0 _ =14.
<10 .74
<10
<10 �_..74
<10 <. 74
<l0 <.74
sl 0. _ _ ,_74
<l.a- _ sJ4
<10 <.74
s10 .74 _..
µ
<10__ `.._._4..___
10 < . 74
UF1 OAILV vr,Lur TNo. oL
_. y'
I 1 An 1 .�s
1
1
1
1
1
c 1_1NITS
n CONCrtr
T NATION
I+1 A55
5 INTAFKC:
• e 1. ().',C, '11 It r.1 .•
ug/1 lb/day <10
<.21
ug/1 1b/day < 10
ug/1 lb/day < 10
.2
.21
ug/1 lb/day < 10
< .21
ug/1 lb/day < 10
< .21
ug/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
uy/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
ucl/ l l b /day < 10
ug/1 lb/day < 10
ug/1 lb/day < 10
ug/1 lb/day 10
ug/1 lb/day 1Cl
u9/1 lb/dad 10
Il/1
.21
.21
.21
.2
< .2
.2
.21
.21
.21
.21
.21
.21
.21
.21
.21
1
1
1
1

1. POL,LLITAr1T
Alin CAS
Liu l„tuClt
MA#ttt
CTIO' - V
i2V, t.1..0 I ,,u
CI.Io,1.1u (75 09 21
i3V, 1„1 2,2 Tau('
I11,1:.IUlilnue
17) 14 5)
24V, TcIr:[:hluro.
uil.ylr..r. (127,1a-4)
25V, TCI[,cne
(100 Cd-a)
20V. 1,2 Trans
115G 00 51
X <10 <.74 1
HUL:Itdr JLdLIUlIw1® UU5_�a._
y• 7. LFF'l_1JL:14-T
MAXIMUM t]AILV VALUL 110. of
1.1 I11 M,as Analy j S
X <10 <.74 1
X <10 <.74
X <10 <.74
X <10 <.74
L7V, 1.1,1
_LV, 1,1.2Triu
u�:oror;:�anc
I)9,C05)
29V, Tr I1I ro
,,ny1 ,w 179 01 6)
�IOV TrLI.Icro,
() 1.9 41
)1v, Vinyl
[.lJ„r.r1r (75 01,4)
X <10 <.74 1
X <10 <.74
X
10 <.74 1
10 <.74 1
GC/;.3S f.IACTIO (- ACIO C
IA : Cr�[,rovl�rno
15slul
:.1A
1120 a3 2)
:. 2,4 LL n..rhyI
Itlus,iul I IU r G/ '..I
4A. 4,6 n,mirn 0
Crrf01 (Sa4 :i2 1)
..A 2.4 0.1ntr+r
1, t..•nr>t 1�1 23.5)
A 4 Iiur0lrllenul
I UJ U.2 1)
P CUI
0 7)
DC. 5)
X <10 <.74 1
X <10 <.74 1
<10 <.74
X <10 <.74
X <10 <.74
10 <.74 1
X <10 <.74 1
X <10 <.74
X <10 <.74
X <10 <.74
<10 <, 74
VdsL waLeI' LUI Itl LIUII DdSlll
tom'-n-a:.•araami ran- aaa/a QRrOK�s*4�1�a.
4, UNITS 5 I1'4TAi£k:
CONC'cN
THATION
,t 1 t.,r+t. Tr_ r rt.1
MA'5,5
1.0
ug/1
ug/1
lb/day < 10 < .21
lb/day <10 < .21
ug/1
Ir r.
A
Y Y`
b/day < 10 < .21
ug/1
lb/day <10 <.2
ug/1
ug/1
ug/1
ug/1
ug/1
ug/
ug/1
ug/1
lb/day <10
lb/day
1b/day
10 < .21
10
/day < 10
b/day < 10
b/ day < 10
lb/day <:0
lb/day
ug/1
ug/1
ug/1
ug/1
ug/1
ug/1
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9/1 lb/day <10 < .21
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(110
A44 1

Analyses performed in 1982; will be
retested for application in 1989).
. 1'Ot_LUTAN f MA4trt "A
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4. UNIT' 5 1NTAKt.
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4

OLLLITAWT
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CT
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4 1.1i11:;;;
ri
MA
. I N 1 1! 1'is

NPDES Permit Modification #2
Permission to
Release Radioactivity to the Catawba River

Release of Radioactivity to the Catawba River
Normally the McGuire Nuclear Station turbine building sumps
are discharged to the conventional wastewater treatment (WC)
system for treatment with chemical addition and aeration.
The treated wastes are discharged to the Catawba River
(discharge 002). Occasionally, the turbine building sumps
become contaminated with radioactivity by various means
including primary -to -secondary leaks and HVAC condensate
drains. Sump discharges may continue to be released to the
WC system, may be routed to the normal Liquid Radwaste
System discharge line for release to the condenser cooling
water (CCW), or may be routed to the Liquid Radwaste
Collection tanks for processing prior to release. The
selected path of release depends on the level of
radioactivity, volume of radioactive wastes, NRC Technical
Specification's processing requirements, potential for an
oil spill, and the need to process chemical wastes.
This permit modification request includes adding the
Collection Basin (Wastewater Collection Basin, WWCB) as a
permitted discharge point. One of the inputs to the WWCB is
the unwatering of the CCW system for maintenance purposes.
During the unwatering process, a 54-inch isolation valve
between the two units leaks. This leakage sometimes allows
processed liquid radwaste to contaminate the unwatering
flow. The liquid radwaste has been processed to effluent
limitations contained in 10CFR Part 20 and diluted by the
CCW flow; it is diluted farther by the unwatering flow and
the WWCB.
All radioactive releases will be made in accordance with
effluent release technical specifications. All
radioactivity released from the site will meet the
concentration and dose limitations specified in 10CFR Part
20, 10CFR Part 50, and McGuire Nuclear Station Operating
License Technical Specifications. Attached is the NRC
approval for releasing radioactivity to the Catawba River.
The addition of this requested release path will not
increase the quantity of radioactivity released from the
station. The dose due to radioactivity from this requested
release path (combination of the discharge from the WC and
WWCB) will be limited to 41% of the maximum permissible
concentration and will be added to the dose due to
radioactivity released from the present release path
(discharge 004). As such there will be no change to the
health and safety of any member of the public. The
additional release path will provide more flexibility to the
manner in which contaminated wastes can be treated and
released. The requested release path will not result in an
increase in the discharge of any NPDES regulated pollutant.

UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, 0. C. 20555
June 5, 1987
Docket Nos.: 50-369
and 50-370
Mr. H. B. Tucker, Vice President
Nuclear Production Cepartment
Duke Power Company
422 South Church Street
Charlotte, North Carolina 28242
Dear Mr. Tucker:
Subject: Issuance of Amendment No. 72to Facility Operating License NPF-9 and
Amendment No. 53to Facility Operating License NPF-17 - McGuire
Nuclear Station, Units 1 and 2 (TAGS 61179/61180)
The Nuclear Regulatory Commission has issued the enclosed Amendment No, 72 to
Facility Operating License NPF-9 and Amendment No. 53to Facility Operating
License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. These amend-
ments consist of changes to the Technical Specifications in response to
your application dated March 19, 1986, as supplemented December 3, 1986, and
June 4, 1987.
The amendments change Technical Specification Figure 5.1-4 to add another
discharge point from the Conventional Wastewater Basin into the Catawba River.
The amendments are effective as of their date of issuance.
A copy of the related safety evaluation supporting Amendment no.72 0 Operating
Facility Operating License NPF-9 and Amendment No. Facility p g
License NPF-17 is enclosed.
Notice of issuance of amendments will be included in the Commission's next
bi-weekly Federal Register notice.
Sincerely,
1,
Darl Hood, Project Manager
Project Directorate II-3
Division of Reactor Projects-I/II
Enclosures:
1. Amendment No. 72 to NPF-9
2. Amendment No.53 to NPF-17
3. Safety Evaluation
cc w/enclosures: See next page

Mr. H. B. Tucker
Duke Power Company
cc:
Mr. A.V. Carr, Esq.
Duke Power Company
P. 0. Box 33189
422 South Church Street
Charlotte, North Carolina
McGuire Nuclear Station
Dr. John M. Barry
Department of Environmental Health
Mecklenburg County
1200 Blythe Boulevard
28242 Charlotte, North Carolina 28203
County Manager of Mecklenburg County
720 East Fourth Street
Charlotte, North Carolina 28202
Mr. Robert Gill
Duke Power Company
Nuclear Production Department
P. 0. Box 33189
Charlotte, North Carolina 28242
J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell
and Reynolds
1200 Seventeenth Street, N.W.
Washington, D. C. 20036
Senior Resident Inspector
c/o U.S. Nuclear Regulatory Commission
Route 4, Box 529
Hunterville, North Carolina 22078
Regional Administrator, Region II
U.S. Nuclear Regulatory Commission,
101 Marietta Street, N.W. Suite 2900
Atlanta, Georgia 30323
L. L. Williams
Area Manager, Mid -South Area
ESSD Projects
Westinghouse Electric Corporation
MNC West Tower - Bay 239
P. 0. Box 355
Pittsburgh, Pennsylvania 15230
Chairman, North Carolina Utilities
Commission
Dobbs Building
430 North Salisbury Street
Raleigh, North Carolina 27602
Mr. Dayne H. Brown, Chief
Radiation Protection Branch
Division of Facility Services
Department of Human Resources
701 Barbour Drive
Raleigh, North Carolina 27603-2008

UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
DUKE POWER COMPANY
DOCKET NO. 50-369
McGUIRE NUCLEAR STATION, UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 72
License No. NPF-9
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station,
Unit 1 (the facility) Facility Operating License No. NPF-9 filed
by the Duke Power Company (the licensee) dated March 19, 1986, as
supplemented December 3, 1986 and June 4, 1987, complies with the
standards and requirements of the Atomic Energy Act of 1954, as
amended (the Act) and the Commission's rules and regulations as
set forth in 10 CFR Chapter I;
8. The facility will operate in conformity with the application, as
amended, the provisions of the Act, and the rules and regulations
of the Commission;
C. There is reasonable assurance (i) that the activities authorized by
this amendment can be conducted without endangering the health and
safety of the public, and (ii) that such activities will be conducted
in compliance with the Commission's regulations set forth in 10 CFR
Chapter I;
C. The issuance of this amendment will not be inimical to the common
defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51
of the Commission's regulations and all applicable requirements have
been satisfied.

Accordingly, the license is hereby amended by page changes to the Technical
Specifications as indicated in the attachments to this license amendment,
and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby
amended to read as follows:
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised
through Amendment No. 72 are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the
Technical Specifications and the Environmental Protection Plan.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
B. J. 'Youngblood, Director
Project Directorate II-3
Division of Reactor Projects-I/II
Attachment:
Technical Specification
Changes
Date of Issuance: June 5, 1987

UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGT©N, D. C. 20555
DUKE POWER COMPANY
DOCKET NO. 50-370
McGUIRE NUCLEAR STATION, UNIT 2
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 53
License No. NPF-17
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station,
Unit 2 (the facility) Facility Operating License No. NPF-17 filed
by the Duke Power Company (the licensee) dated March 19, 1986, as
supplemented December 3, 1986 and June 4, 1987, complies with the
standards and requirements of the Atomic Energy Act of 1954, as
amended (the Act) and the Commission's rules and regulations as
set forth in 10 CFR Chapter I.
B. The facility will operate in conformity with the application, as
amended, the provisions of the Act, and the rules and regulations
of the Commission;
C. There is reasonable assurance (i) that the activities authorized by
this amendment can be conducted without endangering the health and
safety of the public, and (ii) that such activities will be conducted
in compliance with the Commission's regulations set forth in 10 CFR
Chapter I;
!. The issuance of this amendment will not be inimical to the common
defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of
the Commission's regulations and all applicable requirements have been
satisfied.

2
Accordingly, the license is hereby amended by page changes to the Technical
Specifications as indicated in the attachments to this license amendment,
and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby
amended to read as follows:
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised
through Amendment No.53, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the
Technical Specifications and the Environmental Protection Plan.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(--41.4jer
oungblo d, Director
Pro?�ec Directorate II-3
Division of Reactor Projects-I/II
Attachment:
Technical Specification
Changes
Date of Issuance: June 5, 1987

ATTACHMENT TO LICENSE AMENDMENT NO. 72
FACILITY OPERATING LICENSE NO. NPF-9
DOCKET NO. 50-369
AND
TO LICENSE AMENDMENT NO. 53
FACILITY OPERATING LICENSE NO. NPF-17
DOCKET NO. 50-370
Replace the following page of the Appendix "A" Technical Specifications with
the enclosed page. The revised page is identified by Amendment number and
contains vertical lines indicating the area of change.
Amended
Page
5-5

FIGURE 5.1-4
SITE BOUNDARY FOR
LIQUID EFFLUENTS
GUIRE NUCLEAR STATION
McGUIRE - UNITS 1 and 2 ,5-5
Amendment No. 72 (Unit 1)
Amendment No. 53 (Unit 2)

UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NPF-9
AND AMENDMENT NO. 53 TO FACILITY OPERATING LICENSE NPF-17
DUKE POWER COMPANY
DOCKET NOS. 50-369 AND 50-370
McGUIRE NUCLEAR STATION, UNITS 1 AND 2
INTRODUCTION
Existing Technical Specification (TS) 3.11.1.1 and its referenced Figure 5.1-4,
"Site Boundary for Liquid Effluents" define the authorized discharge point for
radioactive material released in liquid effluents to unrestricted areas as being
only to Lake Norman, an upstream impoundment of the Catawba River. By letter
dated March 19, 1986, Duke Power Company (the licensee) requested a change to
the TSs for McGuire Nuclear Station, Units 1 and 2. This proposed change would
modify Figure 5.1-4 to add a new release point for radioactive liquids and
thereby permit the release of liquids containing trace quantities of radio-
activity into the Catawba River, via the conventional waste water treatment
system. The change would affect only the discharge location, and would not
increase existing TS limits regarding (1) the quantity of radioactive material
contained in the treatment pond, (2) allowable doses to the public from releases
to unrestricted areas, and would not decrease existing TS requirements regarding
liquid discharge monitoring. The licensee provided additional information to
support the request by letters dated December 3, 1986 and June 4, 1987.
The change would be accomplished by deleting from TS Figure 5.1-4 an existing,
obsolete footnote which authorized a one-time discharge to the Catawba River
on June 20, 1986, but retaining the existing arrow at the river and its label,
"Liquid Waste Discharge Point." (The existing arrow, label, and footnote were
added in response to a separate application by the licensee submitted subsequent
to the March 19, 1986 request.)
EVALUATION
The McGuire plant is designed to release radioactive liquid effluents to Lake
Norman and effluent controls are based on the concentrations of activity at
the point of release to Lake Norman. The outflow from Lake Norman is into the
Catawba River. Conventional ("non -radioactive") waste water is released through
another discharge point directly to the Catawba River.
Water from the turbine building sump is normally released through the conven-
tional wastewater treatment system. The quantity of radioactive material
contained in each treatment pond, and in each batch of slurry (used power
resins) to be transferred to the treatment ponds, is limited consistent with
10 CFR 20, Appendix B, Table II by existing TS 3/4.11.1.5 and is not changed

2
by these amendments. There are provisions for releasing turbine building sump
water through the liquid radwaste system if the sump water is contaminated
with radioactivity. The liquid radwaste system is capable of processing
27,500 gpd, whereas the turbine building sumps can add up to 120,000 gpd
during operation with primary to secondary leakage. Thus, the liquid radwaste
system is not capable of handling the turbine sump discharge on a continuing
basis as would be required by the present technical specifications if there
were small steam generator tube leaks. Furthermore, when low levels of
radioactivity are detected in a large pond (e.g., in one of the two 2.5
million gallon settling ponds of the conventional wastewater treatment system)
release through the liquid radwaste system is impracticable. The licensee
investigated several alternatives to the proposed additional release point and
concluded that other possible solutions were unduly costly and were unwarranted
in view of the low levels of radioactivity and doses involved. Therefore the
licensee requested approval to release low level liquid radwaste through the
conventional wastewater treatment system.
The TS change does not decrease the existing monitoring requirements (TS 3.3.3.8
and referenced TS Table 3.3-12) which assure that instantaneous radioactive
release rates remain within 10 CFR 20, Appendix B limits, and that radioactive
liquid effluent monitoring instrumentation remains operable or appropriate
compensatory action taken. There are provisions for sampling and monitoring
the water going into, and being released from, the conventional waste water
system. The licensee has committed to make these measurements with the
sensitivity necessary to assure that the concentrations are below the levels
needed for compliance with the dose design objectives of 10 CFR 50 Appendix I.
Specifically, the licensee committed to maintaining a lower limit of detection
of 0.1 pCi/L or less for Cs-137. These provisions satisfy General Design
Criterion 64 which require that a means be provided for monitoring effluent
discharge paths.
The dose or dose commitment to a member of the public from radioactive
materials in liquid effluents released from each McGuire unit is limited
consistent with 10 CFR 50, Appendix I by existing TS 3/4.11.1.2 and is not
changed by these amendments. The licensee has committed to ensuring that
the use of this new release point does not increase the total permitted
release from the station. To accomplish this, doses at both the new and
old release points will be added and the total will be maintained below
the limits of Technical Specification 3.11.1.2.
The concentration of radioactive material released in liquid effluents
to unrestricted areas is limited consistent with 10 CFR 10, Appendix B,
Table II by existing TS 3/4.11.1.1 and is not changed by these amendments.
The change also, will not increase the concentration of radioactivity in
the Catawba River. The radioactive material that is released to Lake
Norman reaches the Catawba River after some delay. Use of the new release
point is a more direct release path for some of the material into the River.
This will lower concentrations in Lake Norman without materially changing
the concentrations in the River. This is true because almost all of the
activity released by the new pathway will be relatively long lived (i.e.
tritium and Cs-137) which are not affected by the delay. Also in the low
concentrations permitted by the technical specifications the short lived
materials are inconsequential.

The staff concludes that this proposed technical specification change is in
accordance with release requirements of 10 CFR Part 50.36a, Part 50 Appendix I
and 10 CFR 20 Appendix B; and in accordance with 10 CFR Part 50 Appendix A,
General Design Criterion 64 requirements for monitoring radioactivity
releases. The change does not increase the liquid effluent release rates
or the annual dose resulting from station liquid effluent releases. Thus,
although the effluent release path is changed, neither the dose, quantity
nor concentration of radioactive effluent in the River is changed. Therefore
the proposed change is acceptable.
ENVIRONMENTAL CONSIDERATION
These amendments involve changes to the installation or use of facility com-
ponents located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase
in the amounts, and no significant change in the types, of any effluents that
may be released offsite and that there is no significant increase in individual
or cumulative occupational exposure. The NRC staff has made a determination
that the amendments involve no significant hazards consideration, and there
has been no public comment on such finding. Accordingly, the amendments meet
the eligibility criteria for categorical exclusion set forth in 10 CFR
51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or
environmental assessment need be prepared in connection with the issuance of
these amendments.
CONCLUSION
The Commission made a proposed determination that the amendments involve no
significant hazards consideration which was published in the Federal Re ister
(51 FR 36088) on October 8, 1986. The licensee's subsequent submitia s ate
December 3, 1986, and June 4, 1987, do not alter the scope of the licensee's
requested amendments as described in the October 8, 1986 Federal Rye ister; nor
do they affect the Commission's proposed no significant hazards cons ation
determination. The Commission consulted with the state of North Carolina. No
public continents were received, and the state of North Carolina did not have any
comments.
We have concluded, based on the considerations discussed above, that: (1)
there is reasonable assurance that the health and safety of the public will
not be endangered by operation in the proposed manner, and (2) such activities
will be conducted in compliance with the Commission's regulations, and the
issuance of these amendments will not be inimical to the common defense and
security or to the health and safety of the public.
Principal Contributors: D. Hood, PD#II-3
C. Willis, PRPB
Dated: June 5, 1987

NPDES Permit Modification #3
Application for
Clean Water Act Section 311 Exemption

Application for Clean Water Act Section 311 Exclusion
In relation to oil and hazardous substance liability, the
Clean Water Act Section 311 defines "discharge" as
"include[s] but is not limited to, any spilling, leaking,
pumping, pouring, emitting, emptying or dumping but excludes
... (B) discharges resulting from circumstances identified
and reviewed and made a part of the public record with
respect to a permit issued or modified under section 402 of
this Act, and subject to a condition in such permit ..."
[311 (a) (2) ] .
The implementing regulations promulgated by the
Environmental Protection Agency specifies "[a] discharge
results 'from circumstances identified...and subject to a
condition in such permit,' whether or not the discharge is
in compliance with the permit, where: (1) the permit
application, the permit, or another portion of the public
record contains documents that specifically identify: (i)
The substance and the amount of the substance; and (ii) the
origin and source of the substance; and (iii) The treatment
which is to be provided for the discharge either by:...(B) A
treatment system designed to treat the permittee's normal
discharge and which is additionally capable of treating the
identified amount of the identified substance...and (2) The
permit contains a requirement that the substance and amounts
of the substance...be treated...in the event of an on -site
release; and (3) The treatment to be provided is in place."
[40CFR117.12 (c)].
Following is a description of the treatment provided by each
of the McGuire Nuclear Station treatment systems and the
substances on site that will be treated by that system in
the event of an on -site release. Part of the substances are
maintained and used at multiple locations and therefore may
be released through more than one treatment system. The
inventory data system lists the total quantity of the
substance that is on site. Therefore, the total quantity of
the substance on site is listed for each treatment system
through which it can be discharged. In the event of a
spill, the total quantity listed will probably not be
released.

Discharge 001-Condenser Cooling Water (CCW, RC)
Condenser Cooling Water is drawn from Lake Norman. It is
pumped through the condensers and component heat exchangers
and discharged back into Lake Norman. In addition to
removing heat, it provides natural neutralization and
dilution. Oil booms are placed across the discharge canal
to prevent the discharge of oil. Maximum flow is 2.8
billion gallons per day. Attached are the chemical
substances that can be discharged via the condenser cooling
water.

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH RC
PRODUCT NAME
ACETONE, ACS GRADE; (P/N: A-184):
ARMSTRONG'S 520 ADHESIVE:
BRAWN:
CLOVER LAPPING COMPOUND:
CP-52 CHIL LAG:
CP-82 CHIL-STIX F-R-N:
CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556):
DIESEL FUEL OIL 12:
DYKEM STEEL BLUE; (P/N DX-100):
FOSTER 85-20; SPARK-FAS ADHESIVE:
GENERAL PURPOSE ADHESIVE ^77^:
HYDRAZINE SOLUTION (54%):
M & S STRIP -IT:
METAL POLISHING COMPOUND; (P/N 41500):
MOLYKOTE G-RAPID SPRAY; (P/N 87504-24):
MOLYKOTE PENE-LURE SPRAY; (AEROSOL):
MOLYKOTE 111:
MS-450 PROTECTIVE VARNISH:
NEVER-SEEZ PURE NICKEL SPECIAL NUCLEAR GRADE:
PAINT, 1200 PRIME COAT, RED:
PAINT, 1201 PRIMER:
PLACCO RA-6602:
RUGBEE SOIL RELEASE CONCENTRATE; (P/N 1368-001):
TAP MAGIC CUTTING FLUID:
TERESSTIC 32:
TERESSTIC 46:
VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574):
6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):
702 DIFFUSION PUMP FLUID:
704 DIFFUSION PUMP FLUID; (P/N 837-5):
AMOUNT
32.97 GAL
12.00 GAL
45.00 GAL
87.69 GAL
5.00 GAL
2.00 GAL
4.25 GAL
206000 GAL
7.79 GAL
3.00 GAL
5.00 GAL
992.80 GAL
220.00 GAL
3.30 GAL
0.11 GAL
75.79 GAL
39.28 LBS
5.63 GAL
80.00 LBS
0.21 GAL
0.13 GAL
2.00 GAL
135.00 GAL
147.66 GAL
60069 GAL
995.75 GAL
21.00 GAL
0.25 GAL
0.26 GAL
6.20 GAL

Discharge 002 - Conventional Wastewater Treatment System
(WC)
The Conventional Wastewater Treatment System treats waste
through a system of basins with chemical additions and
aeration. Wastes are initially directed to the initial
holdup pond where primary sedimentation occurs. This
200,000 gallon capacity basin has a retention time of 12 to
24 hours and acts as a surge tank to prevent overloading and
subsequent degradation of effluent quality throughout the
remainder of the system. This pond can be bypassed
depending on influent quality. The initial holdup pond is
followed by parallel settling ponds. These two 2.5 million
gallon ponds provide 6-12 day retention. 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. The wastewater then flows to
the final holdup pond where it is aerated. This pond has a
volume of one million gallons and a retention time of 5
days. The final holdup pond can be bypassed if the effluent
from the settling basins are within specifications. The
final effluent can flow by gravity or be pumped to the
Catawba River with the pH adjusted with an automatic CO
addition system. An oil trap is provided to prevent of
spills to the receiving water. The holding capacity and
recirculating capabilities designed into the treatment
facility assure a high quality effluent to the Catawba
River. Attached are the chemical substances that can be
discharged via the conventional wastewater treatment system.

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH WC
PRODUCT NAME
ACETIC ACID, GLACIAL; (FISHER P/N A-38): 9.35 GAL
ACETONE, ACS GRADE; (P/N: A-184): 32.97 GAL
ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOWS: 10.00
GALX
4.00
ALL CLIMATE HIGH VACUUM PUMP OIL: 16.11 LAS
AMMONIUM CHLORIDE; (P/N A-661):
AMMONIUM HYDROXIDE; (FISHER P/N A-669): 225.20 GAL
ARMSTRONG'S 520 ADHESIVE: 12.00 GAL
BELZONA MOLECULAR RELEASE AGENT: 0.19 GAL
BUFFER SOLUTION, PH 4.00; (P/N SO-B-99(CONC) & 50-B-101) 4.38 GAL
CL-371 LOW TEMPERATURE RADWASTE ANTIFOAM: 55.00 GAL
CLOVER LAPPING COMPOUND: 87.69 GAL
CP-52 CHIL LAG: 5.00 GAL
CP-82 CHIL-STIX F-R-N: 2.00 GAL
CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556): 4.25 © GAL
LAS
CS CORROSION INHIBITOR: 206000225GAL
DIESEL FUEL OIL 112:
DIGESTION SOLUTION FOR COD, 0-150 PPB RANGE; (P/N 21258 0.32
GAL
DYKEM STEEL BLUE; (P/N DX-100): 7.79
GAL
FEL-PRO N-5000 NUCLEAR GRADE; (PART NO. 51269): 487.00 LBS
FENSO 71; (P/N 390180 - 03746): 110.00 GAL
FERRIC CHLORIDE; (FISHER P/N I-88): 0.52 LBS
FIBRAX 370: 217.00 GAL
FIRE -PREP 8256: 5.00 GAL
FORMIC ACID; (P/N A-118): 0.38 GAL
FOSTER 85-20; SPARK-FAS ADHESIVE: 3.00 GAL
GEAR OIL; GX 85W-140: 97.00 GAL
GENERAL PURPOSE ADHESIVE "77": 5.00 GAL
HERMES CEMENT; (P/N 999-125): 9.38 GAL
HYDRAZINE SOLUTION (54%): 992.80 GAL
HYDROCHLORIC ACID; (FISHER P/N A-144): 11.311.88 GAL
01 GAL
KEROSENE; (P/N K10-1*FISHER): 345.00 GAL
KUTWELL 40; (P/N 350040 - 03777):
LEAD/ACID STORAGE BATTERY, ANTIMONY: 11780 LBS
LOW LEVEL SODIUM REAGENT; (P/N 15111/181153): 068 GAL
GAL
LYSOL LIQUID DISINFECTANT:72.00
M & S STRIP -IT: 220.00 GAL
MARVEL MYSTERY OIL: 24.80 GAL
METAL POLISHING COMPOUND; (P/N 41500): 3.30 GAL
METHANOL; (FISHER P/N A-4124): 5.98 GAL
METHYL ISOBUTYL KETONE; (P/N M-213): 5.64 GAL
MOBIL SHC 824: 5317.8 GAL
MOBIL 1 5W-30 OIL: 48.63 GAL
MOLECULAR N.F. CLEANER/DEGREASER: 0.73 GAL
MOLYKOTE G-RAPID SPRAY; (P/N 87504-24): 0.11 GAL
MOLYKOTE PENE-LUBE SPRAY; (AEROSOL): 75.79 GAL
MOLYKOTE 111: 39.28 LBS
MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79): 327.35 LBS
MOTOR OIL; 10W-40: 332.00 GAL
MS-450 PROTECTIVE VARNISH: 5.63 GAL
MULTI -PURPOSE CLEANER; (M 8 S P/N 4790): 110.00 GAL
NEOLUBE 12 DRY FILM CONDUCTIVE LUBRICANT: 302.10 GAL
NEVER-SEEZ PURE NICKEL SPECIAL NUCLEAR GRADE: 80.00 LBS
NITRAVER 6 NITRATE REAGENT; (P/N 14119): 100.00 PIL
NITRIC ACID (BAKER P/N 4801); (FISHER P/N A200S, A200, A 11.05 GAL
AMOUNT

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH WC
PRODUCT NAME
NUTO H-32 LUBRICANT; (P/N 363010-01335):
NUTO H-68:
PAINT, 1200 PRIME COAT, RED:
PAINT, 1201 PRIMER:
PHENYLARSINE OXIDE; (P/N 2205-16):
PLACCO RA-6602:
PLATINUM COBALT COLOR STANDARD; (P/N SO-P-120):
POTASSIUM CHROMATE; (FISHER P/N P-220, P-220-3):
POTASSIUM HYDROXIDE; (P/N P-250):
POTASSIUM PERMANGANATE; (P/N P-279):
PROPIONIC ACI➢; (P/N A-258):
PRUSSIAN BLUE; (P/N 35):
RANDO OIL HD 68; (P/N 01659):
REAGENT SOLUTION W/DIFFUSION; (P/N 15-17-11):
RED GAGE OIL; (P/N A103):
RIGID DARK CUTTING OIL:
RUGBEE SOIL RELEASE CONCENTRATE; (P/N 1368-001):
SANURIL 115 CHLORINE TABLETS:
SAVOGRAN STRYPEEZE SEMI PASTE:
SCOTCHKOTE ELECTRICAL COATING; (P/N 80-6100-3260-1):
SILVER NITRATE; (P/N 5-181):
SODIUM BISULFATE; (P/N S-654/FISHER):
SODIUM ELECTRODE RINSE SOLUTION; (P/N 15-11-13*18-11-40)
SODIUM FLUORIDE; (P/N S-299/FISHER):
SODIUM HYDROXIDE PELLETS; (P/N 5-318):
SODIUM HYDROXIDE 50% SOLUTION; (FISHER P/N SO-S-254):
SODIUM NITRITE; (P/N S-347/FISHER):
SODIUM REFERENCE STANDARD SOLUTION; (P/N 50-S-139):
SODIUM SULFHYDRATE; (P/N 5-423):
SPARTAN EP 460 OIL; (P/N 475375 - 05375):
SPARTAN EP-150 OIL:
SPARTAN EP-220 OIL:
SPARTAN EP-680 OIL:
SPINESSTIC 22 LUBRICANT; (P/N 372038-01125):
SULFURIC ACID (93%); (FISHER P/N A-300):
SURETT N-80K OIL; (PIN N-8K):
TAP MAGIC CUTTING FLUID:
TERESSTIC 100; (P/N 376045 - 01180):
TERESSTIC 150:
TERESSTIC 220:
TERESSTIC 32:
TERE55TIC 46:
TERESSTIC 68:
TOLUENE; (P/N T-3245/FISHER):
TRISODIUM PHOSPHATE; (P/N 5-377,5-376/FISHER):
UNIREX N2 LUBRICATING GREASE:
VACUUM PUMP PRECISION OIL; (CAT 1-69126):
VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574):
W-INCONEL WELDING ROD 182:
W-METCO 44 POWDER:
W-METCO 447 POWDER:
W-METCO 450 POWDER:
W-METCO 451 POWDER:
W-1/8 SIL FLO WIRE:
AMOUNT
70.00 GAL
627.00 GAL
0.21 GAL
0.13 GAL
1.75 GAL
2.00 GAL
0.13 GAL
766.00 LBS
19.14 LBS
16.60 LBS
0.13 GAL
39.60 LBS
15.00 GAL
0.45 GAL
0.53
44.00 GAL
135.00 GAL
855.00 LBS
9.00 GAL
1.29 GAL
2.10 GAL
15.20 LBS
0.13 GAL
5.50 LBS
14.80 LBS
6058.3 GAL
2091.3 LBS
0.51 GAL
2.53 LBS
401.85 GAL
785.00 GAL
33.00 GAL
74.00 GAL
40.00 GAL
10264 GAL
237.00 LBS
147.66 GAL
55.00 GAL
1162.2 GAL
275.25 GAL
60069 GAL
995.75 GAL
4038.3 GAL
5.60 GAL
1920 LBS
558.59 LBS
22.50 GAL
21.00 GAL
20.00 LBS
5.00 LBS
5.00 LBS
5.00 LBS
5.00 LBS
15.00 LBS

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH WC
PRODUCT NAME AMOUNT
W-3/32 SIL FLO WIRE:
XYLENE:
ZERICE 46 OIL; (P/N 386040 - 02970):
6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):
702 DIFFUSION PUMP FLUID:
704 DIFFUSION PUMP FLUID; (P/N 837-5):
15.00 LBS
12.00 GAL
665.00 GAL
0.25 GAL
0.26 GAL
6.20 GAL

Discharge 003 - Sanitary Waste Treatment System (WT)
The sanitary waste treatment system is a four (4) cell
aerated lagoon system. It provides approximately 5 day
retention and allows for variable level discharge. Maximum
volume (depth of 8 feet) is approximately 321,300 gallons.
The first cell provides a two day retention and is kept in
full suspension by surface mechanical aerators. The second
and third cells provide one day retention each and are kept
partially suspended providing for partial settling. The
final cell is the settling cell and has a one day retention.
Flow from the final cell is through a Sanuril chlorinator
and a chlorine contact chamber. Discharge is into the
Wastewater Collection Basin. Attached are the chemical
substances that can be discharged via the sanitary waste
treatment system.

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH WT
PRODUCT NAME AMOUNT
BRAWN:
CLOROX LIQUID BLEACH:
CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556):
KEPRO ETCHING SOLUTION; (KEPRO P/N E-1QT, E-1G, E-4G):
LYSOL LIQUID DISINFECTANT:
MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79):
MULTI -PURPOSE CLEANER; (M & 5 P/N 4790):
TAP MAGIC CUTTING FLUID:
45.00 GAL
2.00 GAL
4.25 GAL
0.50 GAL
72.00 GAL
327.35 LBS
110.00 GAL
147.66 GAL

Discharge 004 - Liquid Radwaste Treatment System (Radwaste,
WL)
The Liquid Radwaste Treatment system collects radioactively
contaminated water from equipment drains, spills, or leaks
within the auxiliary and reactor buildings. The system
utilizes filters, evaporators, and ion exchange
demineralizers for the treatment process. Releases are made
to assure compliance with 10CFR Part 20 and 10CFR Part 50.
Attached are substances that can be released via the Liquid
Radwaste Treatment System.

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH RADWASTE
PRODUCT NAME
ACETIC ACID, GLACIAL; (FISHER P/N A-38): 32.979.35 GAL
GAL
ACETONE, ACS GRADE; (P/N: A-184):
ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOWS: 10.00BOX
GAL
ALL CLIMATE HIGH VACUUM PUMP OIL: 4.00 LAS
AMMONIUM ACETATE CRYSTALS; (P/N C-64): 16.111LBS
AMMONIUM CHLORIDE; (P/N A-661):
AMMONIUM HYDROXIDE; (FISHER P/N A-669): 225.20 GAL
25.20 GAL
ARKALONE P; (LIQUID): 2.50 GAL
BENZENE; (P/N B-414, B-245):
BUFFER SOLUTION, PH 4.00; (P/N SO-B-99(CONC) & SO-B-101) 4.381.
GAL
211.0
CARBON TETRACHLORIDE: 0 GALAS
CAZAR 2 GREASE; 20000 LBS
CEMENT C-320: 1.50 GAL
CHROMERGE; (P/N C-577): 87.69 GAL
CLOVER LAPPING COMPOUND:
COPPER REFERENCE STANDARD SOLUTION; (P/N SO-C-194): 0.40
GALLBS
COPPER SULFATE; (P/N C-493, C-495):
CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556): 4.25 GAL GAL
DAG; (P/N154):
DESSICANT, INDICATING GEL; (P/N HDMI 103-6); 8.00 LBS
GAL
DYKEM STEEL BLUE; (P/N DX-100):
FEL-PRO N-5000 NUCLEAR GRADE; (PART NO. 51269): 48©.00 LBS
00 LBS
FERRIC CHLORIDE; (FISHER P/N I-88): 10.52 LBS
FERRIC NITRATE; (P/N I-110): 1.10 LBS
FERROUS AMMONIUM SULFATE; (P/N I-77): 217.00 GAL
FIBRAX 370: 97.00 GAL
GEAR OIL; GX 85W-140: GAL
4i
HERMES CEMENT; (P/N 999-125): 999.38.3GAL
HYDRAZINE SOLUTION (5):
HYDROCHLORIC ACID; (FISHER P/N A-144): 11.311.88 GAL
8 GAL
KEROSENE; (P/N K10-1*FISHER):
LEAD REFERENCE STANDARD SOLUTION; (P/N SO-L-21): 0.13 GAL
LEA➢/ACID STORAGE BATTERY, ANTIMONY: 11780 LBS
2.00 GAL
LYSOL LIQUID DISINFECTANT: 220.007GAL
M & S STRIP-IT:GAL
0.00
MARVEL MYSTERY OIL: 20.25 AS
MERCURIC CHLORIDE; (P/N M-155): 10.25 LBS
MERCURIC THIOCYANATE; (P/N M-197): 5.98 GAL
METHANOL; (FISHER P/N A-4124): 5.64 GAL
METHYL ISOBUTYL KETONE; (P/N M-213): 5354 GAL
31
MOBIL SHC 824: .8 GAL
4.63
MOBIL 1 5W-30 OIL:
MOLYKOTE PENE-LOBE SPRAY; (AEROSOL): 39.28 GALLAS
MOLYKOTE 111;
MOLYKOTE 33 GREASE (P/N'S 14770-79 AND 14770-99): 1.28 GAL
MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79): 332.35 LBS
35 GAL
MOTOR OIL; 10W-40: 302.10 GAL
NEOLUBE #2 DRY FILM CONDUCTIVE LUBRICANT:
NITRIC ACID (BAKER P/N 4801); (FISHER P/N A2005, A200, A 61105 GAL
.05 GAL
NUTO H-68: 8.10 GAL
PETROLEUM ETHER; (P/N E139-4, E-139-5): 0.50 GAL
PHOSPHORIC ACID; (P/N A-242):AL
PLATINIZING SOLUTION; 0.50 19.14 GALL
POTASSIUM HYDROXIDE; (P/N P-250):
AMOUNT

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH RADWASTE
PRODUCT NAME
POTASSIUM PERMANGANATE; (P/N P-279):
PRUSSIAN BLUE; (P/N 35):
RIGID DARK CUTTING OIL:
SCOTCHKOTE ELECTRICAL COATING; (P/N 80-6100-3260-1):
SILVER NITRATE; (P/N 5-181):
SILVER SULFATE;
SODIUM BISULFATE; (P/N S-654/FISHER):
SODIUM FLUORIDE; (P/N 5-299/FISHER):
SODIUM HYDROXIDE PELLETS; (P/N 5-318):
SODIUM HYDROXIDE 50% SOLUTION; (FISHER P/N SO-S-254):
SODIUM NITRITE; (P/N S-347/FISHER):
SODIUM REFERENCE STANDARD SOLUTION; (P/N 50-5-139):
SPARTAN EP 460 OIL; (P/N 475375 - 05375):
SPARTAN EP-150 OIL:
SPARTAN EP-220 OIL:
SPARTAN EP-680 OIL:
SULFURIC ACI➢ (93%); (FISHER P/N A-300):
SURETT N-80K OIL; (P/N N-8K):
SYNESSTIC 32 OIL; (P/N 343101 - 03101):
TAP MAGIC CUTTING FLUID:
TERESSTIC 100; (P/N 376045 - 01180):
TERESSTIC 150:
TERESSTIC 220:
TERESSTIC 32:
TERESSTIC 46:
TERESSTIC 68:
TOLUENE; (P/N T-3245/FISHER):
UNIREX N2 LUBRICATING GREASE:
URANYL NITRATE; (P/N U-7):
VACUUM PUMP PRECISION OIL; (CAT it-69126):
XYLENE:
AMOUNT
16.60 LBS
39.60 LBS
44.00 GAL
1.29 GAL
2.10 GAL
0.50 LBS
15.20 LBS
5.50 LBS
14.80 LBS
6058.3 GAL
2091.3 LBS
0.51 GAL
401.85 GAL
785.00 GAL
33.00 GAL
74.00 GAL
10264 GAL
237.00 LBS
322.00 GAL
147.66 GAL
55.00 GAL
1162.2 GAL
275.25 GAL
60069 GAL
995.75 GAL
4038.3 GAL
5.60 GAL
558.59 LBS
0.25 LBS
22.50 GAL
12.00 GAL

Discharge 005 - Wastewater Collection Basin (Collection
Basin, WWCB)
The Wastewater Collection Basin is a 13.4 acre collection
basin having a total capacity of approximately 40 million
gallons; drawdown capacity is approximately 11 million
gallons. The basin provides sedimentation, natural
neutralization and skimming. Flow from the basin ranges
from 0 to 15,000 gpm. Holdup is minimal; if the Standby
Nuclear Service Water Pond is being flushed, no holdup of
the basin is possible. The overflow from the basin mixes
with the discharge from the WC system in a concrete apron
and is discharged to the Catawba River downstream of Cowans
Ford Dam. Attached are the chemical substances that can be
discharged via the Wastewater Collection Basin.

MCGUIRE NUCLEAR STATION
POSSIBLE DISCHARGES THROUGH WWCB
PRODUCT NAME
ACETIC ACID, GLACIAL; (FISHER P/N A-38): 935 GAL
GAL
ACETONE, ACS GRADE; (P/N: A-184):32.97
ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOWS: 10.00 GALX
ALL CLIMATE HIGH VACUUM PUMP OIL:
AMMONIUM ACETATE CRYSTALS; (P/N C-64): 16.111.10 LBS
LBS
AMMONIUM CHLORIDE; (P/N A-661):
AMMONIUM HYDROXIDE; (FISHER P/N A-669): 225.20 GAL GAL
BENZENE; (P/N B-414, B-245):
BUFFER SOLUTION, PH 4.00; (P/N SO-B-99(CONC) 8 SO-B-101) 4.38 GAL
CARBON TETRACHLORIDE: 1.00 GAL
CHROMERGE; (P/N C-577): 1.50 GAL
COPPER REFERENCE STANDARD SOLUTION; (P/N SO-C-194): 0.40 GAL
COPPER SULFATE; (P/N C-493, C-495): 201.10 LBS
10 GAL
DIESEL FUEL OIL #2:
FERRIC CHLORIDE; (FISHER P/N I-88): 15.400.52 LBS
LBS
FERRIC NITRATE; (P/N I-110):1.10 LBS
FERROUS AMMONIUM SULFATE; (P/N I-77): GAL
GASOLINE, UNLEADED: 1100992.80 GAL
HYDRAZINE SOLUTION (547):
HYDROCHLORIC ACID; (FISHER P/N A-144): 11.311.88 GAL
01 GAL
KEROSENE; (P/N K10-1*FISHER):
LEAD REFERENCE STANDARD SOLUTION; (P/N SO-L-21): ©.13 3 GAL
LAS
MERCURIC CHLORIDE; (P/N M-155): 19.20 LBS
MERCURIC THIOCYANATE; (P/N M-197):5.98 GAL
METHANOL; (FISHER P/N A-4124): 5.64 GAL
METHYL ISOBUTYL KETONE; (P/N M-213):
NITRIC ACID (BAKER P/N 4801); (FISHER P/N A200S, A200, A 11.05 GAL
PETROLEUM ETHER; (P/N E139-4, E-139-S): 8.10 GAL GAL
PHOSPHORIC ACID; (P/N A-242): 0.180GAL
PLATINIZING SOLUTION:
POTASSIUM HYDROXIDE; (P/N P-250): 19.1,4 LBS
POTASSIUM PERMANGANATE; (P/N P-279): 16.60
SILVER NITRATE; (P/N S-181): 0.502GAL
AL LBS
SILVER SULFATE; 10.50 LBS
SODIUM BISULFATE; (P/N S-654/FISHER): 5.50 LBS
SODIUM FLUORIDE; (P/N S-299/FISHER): 14.80 LBS
SODIUM HYDROXIDE PELLETS; (P/N S-318):
SODIUM HYDROXIDE 50% SOLUTION; (FISHER P/N SO-S-254): 6058.3 GAL
SODIUM REFERENCE STANDARD SOLUTION; (P/N SO-S-139): 0.51 GAL
SULFURIC ACID (937..); (FISHER P/N A-300): 102110264 GAL
4 GAL
TERESSTIC 150: 1162.2 GAL
TERESSTIC 68:
TOLUENE; (P/N T-324S/FISHER): 5.60 GAL
URANYL NITRATE; (P/N U-7): 0.25 LBS
VACUUM PUMP PRECISION OIL; (CAT *-69126): 12.0022.50 GAL
GAL
XYLENE:
AMOUNT

Plot Plan
McGuire Nuclear Station
NPDES Discharge Locations

LAKE NORMAN
COWANSFORD DAM
CATAWBA RIVER
INTAK
ASTE WATER
COLLECTION BASIN
004
001
SCHARGE
WASTE RELEASE POINT
SNSW POND
*Requested modifications
McGUIRE NUCLEAR STATION
DISCHARGE POINTS

DUKE POWER COMPANY
P.O. sox 33188
cruom T 1 . N.G. 28242
HAL a. TI:GKER
'ICE ►AEAED W T
C^I. PIPDOCC1101.
September 29, 1987
Dr. George T. Everett, Chief
Water Quality Section
Division of Environmental Management
Department of Natural Resources and
Community Development
P.O. Box 27687
Raleigh, N.C. 27611
SUBJECT: McGuire Nuclear Station
NPDES Permit Modification
File: MC-702.13
Dear Sir:
TLLEPHONT
1704) :773-453I
On several occasions we have discussed various discharges
from our McGuire Nuclear Station with your staff. As a
result, we have decided to request that the McGuire NPDES
permit (NC0024392) be modified.
The modifications include (1) re -permitting the Collection
Basin and (2) allowing very low-level radioactivity to be
discharged into the Catawba River below Cowans Ford Dam, and
(3) applying for a Clean Water Act Section 311 exemption.
Attached is the information substantiating the request.
Re -permitting the Collection Basin will alleviate the
necessity of case -by -case approvals for condenser cooling
water system unwatering. Permitting very low-level
radioactivity to be discharged into the Catawba River will
result in no increase in the quantity or dose of
radioactivity released from the station; therefore the
health and safety of the public will not be impacted.
Enclosed please find a check (No. 311792) for $100.00 for
the permit processing. Also enclosed is a sketch of the
station showing all discharge locations.
We would appreciate the opportunity to discuss the specifics
of our request with you while you are developing the
modification. Should you have any questions or desire

additional information, please contact R.T. Simril ((704)
373-2310] or W.T. Griffin ([phone]].
Sincerely,
%
H.B. Tucker, Vice President
Nuclear Production Department
WTG/rhm
Attachment
xc: D.H. Brown, Department of Human Resources
Document Control Desk, NRC
bc: W.A. Haller E.O. McCraw
M.L. Birch J.C. Painter
R.W. taker D.W. Phillips
N.A. Rutherford M.E. Bridges
J.E. Lansche Staff
O.N. Hamilron MC-2002.02-01
W.M. Funderburke

DUKE POWER COMPANY.
NUCLEAR PRODUCMON DEPARTMENT
P.O. H©X 33189, 422 SOUTH CHURCH STREET
CHARLOTTE. N.C. 28242
[phone]
April 1, 1988
Mr. Charles Wakild, Chief
Water Quality Section
Division of Environmental Management
Department of Natural Resources and
Community Development
P. O. Box 27687
Raleigh, N. C. 27611
Attention: Mr. Dale Overcash
Subject: McGuire Nuclear Station
NPDES Permit Modification
File: MC-702.13
Dear Sir:
On September 29, 1987 we requested that the McGuire Nuclear Station NPDES permit
(NC0024392) be modified. The requested modifications included (1) re -permitting
the Collection Basin, (2) allowing very low-level radioactivity to be discharged
into the Catawba River below Cowans Ford Dam, and (3) applying for a Clean Water
Act Section 311 exemption. On November 17, 1987 we met with your personnel to
discuss our request. As a result of our discussion we desire to amend our
modification request.
With this letter, we withdraw part 2 of our modification request. Another in-
depth review of the regulations and additional discussions with our legal staff
indicated that radioactive waste releases regulated by the Nuclear Regulatory
Commission are not subject to state regulation under the water program, Northern
State Power Co. V. Minnesota, 447 F. 2d 1143 (1971), aff'd. 405 U.S. 1035, 92 S.
Ct. 1307, 31 L. Ed. 2d 576 (1972). In view of this regulatory interpretation and
the distinction between NRC and EPA/state authority, we withdraw the request for
your approval to allow very low-level radioactivity to be discharged into the
Catawba River below Cowans Ford Dam.
Additionally, in 1983 an instream administrative limitation was approved by the
Department of Natural Resources and Community Development for hydrazine. The
limitation was 0.06 mg/l. We desire to incorporate this currently approved
administrative limit into the NPDES permit. The limitation applies instream to
Lake Norman and the Catawba River below Cowans Ford Dam, depending on the release
pathway. Since 1983, the regulatory climate has changed and there are
overlapping regulatory requirements. It is for this reason that we request the
hydrazine administrative limitation be formally incorporated into Part III of the
NPDES permit. Procedures are in place to assure compliance with the above
mentioned limit. We will submit the procedures to you for your review should you
desire.

Mr. Charles Wakild, Chief
April 1, 1988
Page Two
Once completed, we would appreciate the opportunity to discuss the draft permit
with you prior to it going to public notice. Should you have any questions or
desire additional information, please contact R. T. Simril [[phone]] or M.
C. Griggs [[phone]].
Sincerely,
W. A. Haller, Manager
Nuclear Technical Services
WTG/1518/sbn
xc: D. H. Brown, Department of Human Resources
Document Control Desk
U. S. Nuclear Regulatory Commission
Washington, D. C. 20555

Mr. Charles Wakild, Chief
April 1, 1988
Page Three
bxc: R. E. Baker
G. M. Barker
S. Biswas
M. E. Bridges
C. C. Brown
R. W. Eaker
W. M. Funderburke
J. E. Lansche
E. 0. McCraw
D. W. Phillips
G. S. Rice
R. 0. Sharpe
Staff
MC-2002.02-01

State of North Carolina
Department of Natural Resources and Community Development
Division of Environmental Management
512 North Salisbury Street • Raleigh, North Carolina 27611
James G. Martin, Governor
S. Thomas Rhodes, Secieury
Mr. W. A. Haller, Manager
Nuclear Technical Service
Duke Power Company
P. O. Box 33189
Charlotte, NC 28242
Dear Mr. Haller:
May' 5, 1988
R. Paul Wilms
Director
SUBJECT: NPDES Permit No. NC0024392
Biocide Additives
Duke Power Company -McGuire Nuclear Station
Mecklenburg County
The Division of Environmental Management has reviewed the information in the
letter of April 11, 1988, concerning the use of chlorine (as sodium hypochlorite) in
the cooling water at your facility. Our review has found that the chlorine should be
appropriate for use in your application. Therefore, the Division of Environmental
Management grants approval to Duke Power Company for the use of the above mentioned
additive in its cooling water.
Should youplan to change to a different additive in the future, you should
contact this office and submit the appropriate information prior to the change.
If you have any questions, please contact Mr. Dale 0vercash at 919/733-5083.
cc : 0141.11110Miwak
Mr. Steve Tedder
Mr. Pale Overcash
Pollution Prerrntion Pay,
P.O. Box 27687, Raleigh, North Carolina 27611-7687 Telephone [phone]
An Eaual Opporruniry Affirmative Action Emolover

-LUTANT
•
r. UL.maila
2 rr: LUCHT
lb. MAXIMUM! 34,)
• 1.1.A.Y.Latua; DAILY v/ILLU
11
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74975.9
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2.5
20689.5
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992.3
1
22
62
May 7.11
lb/day
lb/day
lb/day
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20.3
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20.3
10.1
31
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00
311.14
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21.6
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•
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x
334
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"l0l•1
x
<.26
1
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.43±.16
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x
2.72+.29
1
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1
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1
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l u 1.1
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1
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X
.03
312.40
l
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l?440.40 4)
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1)43911961
x
34
3540.5
14
1158.6
10
11Iq%1
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McGuire Nuclear Su
2 t$AIiK 'i:•
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411440 20 01
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fA AYIi C.. VALUC f.0 G►
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10
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10
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41.38
41.38
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1
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52.06
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t_PY,
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DUKE POWER COMPANY
P.O. BOX 33189
CHARLOTTE. N.C. 28242
WILLIAM A. HALLER
MANAGER
NUCLEAR TECHNICAL SERVICES
(704) 373 S506
February 9, 1987
Operations Branc
Water Quality Section
Division of Environmental Management
Department of Natural Resources and
Community Development
P.O. Box 27687
Raleigh, NC 27611
ATTENTION: Mr. Dale Overcash
SUBJECT: Draft NPDES Permit
McGuire Nuclear Station - NC0024392
File: MC-702.13-1
Dear Sir:
Duke Power Company appreciates the opportunity to review the
draft permit for McGuire Nuclear Station. Attached are our
comments. Also attached is a copy of the permit as we would
like to see it. Should you desire additional information,
please contact R.T. Simril [phone] or W.T. Griffin
[phone].
Very truly yours
W.A. Hailer, Manager
Nuclear Technical Services
WTG/rhm
Attachment
xc: M.D. McIntosh w/o att M.L. Birch
H.B. Tucker w/o att J.E. Lansche
W.M. Funderburke w/att Staff
J.C. Painter MC-2002.02-07
R.W. Eaker

Comments on Draft NPDES Permit
McGuire Nuclear Station (Permit No. NC0024392)
Item 4 of the "Supplement to Permit Cover Sheet"
should be changed to read "[c]ontinue to discharge
condensate demineralizer backwash water, wafer
treatment system backwash water, deminera`lizer backwash
water, diesel generator sump water;; and tiirbine
building sump water (Outfall No. 002) into . . . " The
other flows, steam generator blowdown water and metal
cleaning wastes, constitute part of turbine building
sump water.
2. Item 5 of the "Supplement to Permit Cover Sheet" should
be changed to read " . treated domestic wastewater
(Outfall No. 003), via Collection Basin, into the
Catawba River . . . " The domestic wastewater does not
discharge directly to the Catawba River but into the
Collection Basin which discharges to the river.
Discharge 001 - Delete the statement "[a]dditional
monitoring to determine for its other power
plants." Duke Power performed a successful 316(a)
demonstration. (Attachment 1).
4. Discharge 001 - Add the phrase "outside of an area five
meters from the discharge point" at the end of the
statement "[t]here shall be no discharge of floating
solids or visible foam in other than trace amounts."
The added statement is in the current permit. The
statement should be added to all other discharge pages
as well.
5. Discharge 002 - Change daily maximum discharge
limitation for total suspended solids to 100mg/1.
Steam electric effluent limitations guidelines
(40CFR423) specify 100 mg/1 as the daily maximum
discharge limitation.
6. Discharge 004 - The statement concerning turbine
building sumps should be changed to read "[i]n the
event the turbine building sumps are discharged . . .
to the turbine building sump discharge." The work
"building" was omitted in two (2) places.
7. Part III G should be deleted. It is a duplication of
Part III E.
8. Part III J should be changed to 60 day notification.
The current permit specifies 60 days. There can be
situations when a biocide would be needed in which 60
day notice may be difficult to meet.

9. Change Part III S to read "[t]he Division of
Environmental Management has approved the submitted
316(a) demonstration and has concluded that the
existing thermal limits are sufficient to protect the
aquatic environment of Lake Norman." Duke Power
performed at successful 316(a) demonstration. (See item
3) .

Permit No. NC0024392
STATE OF NORTH CAROLINA
DEPARTMENT OF NATURAL RESOURCES & COMMUNITY DEVELOPMENT
DIVISION OF ENVIRONMENTAL MANAGEMENT
PER M IT
To Discharge Wastewater Under The
NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM
In compliance with the provisions of North Carolina General
Statute 143-215.1, other lawful standards and regulations promulgated
and adopted by the North Carolina Environmental Management Commission,
and the Federal Water Pollution Control Act, as amended,
Duke Power Company
is hereby authorized to discharge wastewater from facilities located
at
McGuire Nuclear Station
Mecklenburg County
to receiving waters designated as the Catawba River in the Catawba
River Basin
in accordance with effluent limitations, monitoring requirements, and
other conditions set forth in Parts I, II, and III hereof.
This permit shall be effective
This permit and the authorization to discharge shall expire at
midnight on August 31, 1989
Signed this day of
R. Paul Wilms, Director
Division of Environmental Management
By Authority of the Environmental
Management Commission

Permit No. NC0024392
SUPPLEMENT TO PERMIT COVER SHEET
Duke Power Company
is hereby authorized to:
1. After receiving an Authorization to Construct from the
Division of Environmental Management, construct and
operate additional wastewater treatment facilities
necessary to comply with the final effluent limitations
contained in this permit located at the McGuire Nuclear
Station (See Part III of this permit), and
2. Continue to discharge condenser cooling water,
conventional low pressure service water, and nuclear
service water (Outfall No. 001) into Lake Norman which
is classified Class "WS-III & B" waters in the Catawba
River Basin, and
Continue to discharge low level liquid radwaste and
turbine building sump water (Outfall No. 004) into the
condenser cooling water, conventional low pressure
service water, and nuclear service water discharge
(Outfall No. 001) which ultimately discharges into Lake.
Norman and is classified Class "WS-III & B" waters in
the Catawba River Basin.
4. Continue to discharge s't dt L i, immoiremPt
condensate demineralizer backwash water, water
3utreatmlent sstem backwash water, demineralizer backwash
ate`` ,'^� Ovand
turbine building sump water (Outfall No. 002) into the
Catawba River which is classified Class "WS-III" waters
in the Catawba River Basin, and
5. Continue to discharge 0.064 MGD
wastewater (Outfall No. 003 in
which is classified Class WS-I
Catawba River Basin.
treated domestic
o the Catawba River
I" waters in the
CO//«i, In 895/»

A. (
1). EFFLUENT LIMITATIONS AND MONITORING REQUIREMENTS Final
During the period beginning on the effective date of the permit and lasting until expiration, the
permittee is authorized to discharge from outfall(s) serial number(s). 001. Once through cooling water
Such discharges shall be limited and monitored by the permittee as specified below:
ffluent Characteristics
Flow
Discharge Limitations Monitoring Requirements
Kg/day (lbs/day) Other Units (Specify)
Daily Avg. Daily Max. Daily Avg. Daily Max.
Temperature 95 deg F
*Sample location for temperature is the discharge canal bridge.
Measurement Sample Sample
Frequency type Location
Daily Pump Log Influent
Daily Recorder
Radwaste system discharges are regulated, monitored and reported to the
Nuclear Regulatory Commission.
The pH shall not be less than n/a standard units nor greater than n/a standard units
and shall be monitored n/a.
There shall be no discharge of floating solids or visible foam in other than trace amounts
0 mrea

Daily Avg. Daily Max.
Flow
Oil and Grease
Total Suspended Solids
Total Copper**
Total Iron**
pH
A. (2). EFFLUENT LIMITATIONS AND MONITORING REQUIREMENTS Final
During the period beginningon the effective date of the permit and lasting until expiration, the
permittee 1s authorized to discharge from outfall(s) serial number(s). 002 Conventional Wastewater Treatment
Such discharges shall be limited and monitored by the permittee as specified below: Facility
affluent Characteristics Discharge Limitations Monitoring Requirements
Kg/day (lbs/day) Other Units (Specify)
Daily Avg. Daily Max.
/N. v
15.0 mg/1 ! 20.0 mg/1
30.0 mg/1 Aim mg/1
1000.0 u g/ 1 1000.0 u g/1
1000.0 ug/1 1000.0 ug/1
Measurement
Frequency
Weekly'
1/year***
1/year***
1/batch
1/batch
2/month
Sample
Type
Instantaneous
Grab
Grab
Grab
Grab
Grab
*Effluent sampling shall be conducted at the discharge prior to mixing with any other waste stream.
**Monitoring, analysis and reporting for iron and copper are required only when chemical metals
cleaning is performed.
***Sample frequency is based on demonstrated performance. Should additional sampling be indicated,
this permit shall be modified to include additional sampling for these parameters.
The pH shall not be less than 6.0 standard units nor greater than
and shall be monitored as indicated above.
9.0
standard units
* Sample
Location
Effluent
Effluent
Effluent
Effluent
Effluent
Effluent
Or
r♦
There shall be no discharge of floating solids or visible foam
Mk 1+7S yru"77 (JO ig13 rf,* C ::Y +;1 1
other than trace amounts),

w
E
TATIONS AND MONITORING REQUIREMENTS Final
During the period beginning on the effective date of the permitand lasting until expiration,
the permlttee 1s authorized to discharge from outfall(s) serial number(s) 003 Domestic wastewater treatment
Such discharges shall be limited and monitored by the permittee as specified below: plant
Effluent Characteristics
Discharge Limitations
Kg/day (lbs/day)
Monthly Avg. Weekly Avg.
Other -Units (Specify)
Monthly Avg. Weex ly Avg.
Flow
BOD,5Day,20°C 30.0 mg/1 45.0 mg/1
TSS 90.0 mg/1 135.0 mg/1
Fecal Coliform (geometric mean) 1000.0/100 ml 2000.0/100 ml
The pH shall not be less than n/a standard units nor greater
shall be monitored monthly at the effluent by grab sample.
There shall be no discharge of floating solids or visible foam
Monitoring Requirements
Measurement
Frequenq►
Monthly
Monthly
Monthly
Monthly
a��le S 11e_
Type Uxat on
Instantaneous Effluent
Grab Effluent
Grab Effluent
Grab Effluent
than n/a standard units and
in other than trace amounts.

A. (4). EFFLUENT LIMITATIONS AND MONITORING REQUIREMENTS Final
During the period beginning cn the effective date of the permit and lasting until expiration, the
permittee is authorized to discharge from outfall(s) serial number(s).004-Radwaste Processing System **
Such discharges shall be limited and monitored by the permittee as specified below:
.ffluent Characteristics
Kg/day (lbs/daY)
Daily Avg. Daily Max.
Flow
TSS
Oil & Grease
Discharge Limitations Monitoring Requirements
Other Units (Specify) Measurement Sample Sample
Daily Avg. Daily Max. Frequency Type Location
Annually Instantaneous Effluent
30.0 mg/1 100.0 mg/1 Annually Grab Effluent
15.0 mg/1 20.0 mg/1 Annually Grab Effluent
*Effluent - Monitoring will be required after radwaste treatment but prior to any dilution with
cooling water.
bo:Wof
**In the event the turbinAumps are discharged to Lake Norman and are not treated in the radwaste processing
system, the above discharge limitations and monitoring requirements shall also apply to the turbineomsump
discharge.
The pH shall not be less than n/a standard units nor greater than n/a standard units
and shall be monitored n/a.
There shall be no discharge of floating solids or visible foam in other than trace amounts.

Part III Continued
Permit No. NC0024342
Toxicity Reopener
This permit shall be modified, or revoked and reissued to
incorporate toxicity limitations and monitoring requirements in the
event toxicity testing or other studies conducted on the effluent
or
rcedvin8thestream
receivingindicate
streamthat
asdetrimental
ofeffects
may be
thisdischarge.
expecte
If the permittee, after monitoring for at least six months,
determines that he is consistently meeting the effluent limitations
contained herein, the permittee may request of the Director that
the monitoring requirements be reduced to a lesser frequency.
There shall be no discharge of polychlorinated biphenyl compounds
such as those commonly used for transformer fluid.
The permittee shall not use any biocides except these
approved in
conjunction with the permit application. The permittee
notify the Director in writing not later than ninety daps
prior to instituting use of any additional biocide used in cooling
systems which may be toxic to aquatic life other than those
previously reported to the Division of Environmental Management.
Such notification shall
locatinginclude
the dischargecompletion
pointBiocide
receivinget
Form 101 andP
stream.
Continued intake screen backwash discharge is permitted without
limitations or monitoring requirements.
Nothing contained in this permit shall beconstrued as a rued asrauwaiver by
the permittee or any right to a hearing it
may State or Federal Laws or regulations.
The term "low volume waste sourcesmeans the waste is taken
collectively as if from one source except those for which specific
limitations are otherwise established in this part. Low volume
wastes sources include but are not limited to: wastewaters from
wet scrubber air pollution control systems, ion exchange water
treatment system, water treatment evaporator blowdown, laboratory
and sampling streams, boiler blowdown, floor drains, cooling tower
house
ice water
basin ning tes, and and air conditioninggwastes are not systems. Sanitarynot included.
The term "metal cleaning waste" means any wastewater resulting
grom
cleaning (with or without chemical cleaning compounds)
any
metal
process equipment including, but not
limitedir pto,
uoil cltubeng.
cleaning, boiler fireside cleaning, a

Part III Continued
Permit No. NC0024392
0. It has been determined from information submitted that the plans
and procedures in place at McGuire Nuclear Station are equivalent
to that of a BMP.
P. Yard drains may be discharged without limitations or monitoring
requirements.
Q. "Upset" means an exceptional incident in which there is
unintentional and temporary noncompliance with technology based
permit effluent limitations because of factors beyond the
reasonable control of the permittee. An upset does not include
noncompliance to the extent caused by operational error, improperly
designed treatment facilities, inadequate treatment facilities,
lack of preventive maintenance, or careless or improper operations.
R. Collection basin may be discharged without limitations or
monitoring requirements.
S• The Division of Environmental Management has approved the submitted 316(a
demonstration and has concluded that the existing thermal limits are
sufficient to protect the aquatic environment of Lake Norman.
T. Mixing Zone
A mixing zone has been defined containing an area of no more than
3500 acres and lying upstream of the dam and south of a line
originating on the west bank of NC Coordinates E-1, 416,900 and
N-633,600 and extending south 70 -00 east intersecting the point
of land on the eastern shore.
U. The term "chemical metals cleaning waste" means any wastewater
resulting from the cleaning of any metal process equipment with
chemical compounds, including, but not limited to boiler tube
cleaning.

P4
RECEwE
State of North Carolina
Department of Natural Resources and Community Devel►p
Division of Environmental Management
512 North Salisbury Street • Raleigh, North Carolina 27611
James G. Martin, Governor
S. Thomas Rhodes, Secretary
October 18, 1985
Mr. H. B. Tucker, Vice President
Nuclear Production
Duke Power Company
P.O. Box 33189
Charlotte, North Carolina 28242
RE:
McGuire Nuclear Station
316(a) Demonstration
NPDES Permit No. NC0024392
Mecklenburg County
2 1985
r,•
ffe
ul Wilms
Director
Dear Mr. Tucker:
The report entitled "McGuire Nuclear Station, 316(a) Demonstration",
June 1985 has been received and evaluated by the staff of the Division of
Environmental Management.
The North Carolina Department of Natural Resources and Community
Development, Division © Environmental
Stativnt,agement effectivesMadrehP28s 19781andNo.
NC0024392 for the McGuire
re -issued this permit on September 1, 1984.
One of the conditions of the previously mentioned permit required
Duke Power to submit the resultThis requireme©tmwastration includedras per©Titletl5n
of best available technology.
NCAC 28.0204 of the State of North Carolina Administration Code. This
demonstration was to include open;aional effects
zovplanktonMcGuire
as©detailedwater ginlity,
fish, periphyton, benthos, phytopnkton,
Section 316(a) of the Federal Water Pollution Control Act and to address
interaction between the McGuire and Marshall power facilities located on
Lake Norman.
Pollution Prrm111irr>t Pay
P©. Box 27687, Raleigh, North Carolina 27611.7687 Telephone [phone]

Mr. H. B. Tucker
October 18, 1985
Page 2
The Division of Environmental Management has completed its review of
the submitted 316(a) Demonstration and has concluded that this submittal
sufficiently fulfills the requirements of the NPDES permit conditions. It
is the conclusion of the Division that the effects of the discharge from
the McGuire Nuclear Station is such that the protection and propagation of
a balanced indigenous aquatic community is assured in Lake Norman and that
interaction of the two thermal plumes of McGuire and Marshall do not occur.
The Division of Environmental Management, therefore, approves the sub-
mittal as a successful 316(a) Demonstration and that this demonstration
confirms that McGuire's existing NPDES thermal limits are sufficient to pro-
tect the aquatic environment of Lake Norman and that these limits are
approved.
The Division would like to acknowledge the exceptional efforts of the
Duke Power staff throughout this extensive study period and look forward to
continuation of such cooperation in the future.
Sinc ely,
cc: Mr. Jack Ravan
Mr. George T. Everett
Mr. Steve W. Tedder
Mr. Dick Hamilton
Mr. Dennis Ramsey

Date: September 4, 1986
NPDES STAFF REPORT AND RECOMMENDATIONS
County: Mecklenburg
NPDES Permit No. NC 0024392
PART I - GENERAL INFORMATION
1. Facility and Address: Duke Power Company
McGuire Nuclear Station
Post Office Box 33189
Charlotte, N. C. 28242
2. Date of Investigation: March 27, 1986
3. Report Prepared By: J. Thurman Horne, P. E.
4. Persons Contacted and Telephone Number: Mr. W. T. Griffin
[phone]
5. Directions to Site: From the intersection of Highway 16 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 shore of Lake Norman.
6. Discharge Point - 001 002 & 003
Latitude: 35°26'10" 35°25'40"
Longitude: 80°56'30" 80°57'20"
Attach a USGS Map Extract and indicate treatment plant site and discharge
point on map.
USGS Quad No. F15NW
7. 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: 001 002 & 003
Lake Norman Catawba River
WS III & B WS III
03-08-32 03-08-33
a. Classification:
b. River Basin and Subbasin No.:
c. Describe receiving stream features and pertinent downstream uses:
Outfall 001: 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 Huntersville and is located
approximately 3 miles northeast of the discharge.

-2-
0utfall 002 & 003: The receiving 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.
PART II - DESCRIPTION OF DISCHARGE AND TREATMENT WORKS
1. Type of wastewater: 001 002 003
0 0 100 % Domestic
100 100 0 % Industrial
a. Volume of Wastewater: 001 002 003
2525 .41 0.04 MGD (average daily)
(based on flow schematic attached to application)
b. Types and quantities of industrial wastewater:
0utfall 001 (Cooling Water Discharge): This discharge i a combination
of condenser cooling water (1,727,100 gpm), conventional low pressure
service water (6,500 gpm); nuclear service water (20,000 gpm), low level
liquid radwaste (8 gpm) and *turbine building sumps (70 gpm).
**0utfall 002 (conventional treatment system discharge): This discharge
consists of steam generator blowdown, condensate demineralizer backwash,
meter treatment_ systew ba kwasi% tdemineralizer backwash, building drains,
metal cleaning wastes and *turbine building sumps.
Outfall 003 (sanitary waste treatment system): This discharge consists
of the domestic type waste generated by plant personnel.
c. Prevalent toxic constituents in wastewater:
0utfall 001
***Outfall 002 0utfall 003
Biocides (see attached Low level radioactivity None
letter dated 2/28/86)
low level radioactivity)- ..
chlorine, sodium hydroxide,_.
lithium hydroxide ,„e.,.--..--�
monohydrate, sulfuric acid,
boric acid
d. Pretreatment Program (POTWs only): N/A.
2. Production rates (industrial discharges only) in pounds: Information not
available in any application submittals received by MRO. If information is
needed it should be requested from the applicant.
Description of industrial process (for industries only) and applicable CFR
Part and Subpart: 40 CFR Part 423 - Steam Electric Power Generation
4. Type of treatment (specify whether proposed or existing):.
0utfall 001
The existing liquid radwaste system consists of filters, evaporators and
demineralizers. (Note: this process treats only a small portion of the

total discharge of outfall 001). The combined wastewaters of outfall 001
flow into Lake Norman via a discharge canal approximately 2500 feet long and
200 feet wide. The canal is for the purpose of heat dissipation.
0utfall 002
Wastewater is treated in the plant's existing conventional wastewater treatment
system which consists of a 200,000 gallon initial holding pond, two (2) settling
ponds (in parallel) each with 2.5 million gallon capacity, a 1 million gallon
final holding pond (aerated -diffused air) and effluent pH adjustment consisting
of automated GO addition.
The initial holding pond acts as a flow equalization basin. This pond may be
bypassed, depending on the nature of the wastewater. The two settling ponds
are operated such that one pond remains in standby. Treatment can be enhanced
by the addition of coagulant aids and pH adjustment :in these ponds.
The effluent from the settling ponds may be discharged directly to the
receiving stream via outfall 002 or it may be routed to the final holding pond.
Effluent from the final holding pond may be discharged through outfall 002 or
recirculated to the settling ponds, depending upon effluent quality.
0utfall 003
The existing sanitary WWTP consists of a multicellular aerated -facultative
lagoon, a chlorine contact chamber (tablet), and a parshall flume. The discharge
from outfall 003 enters an impoundment which also receives area surface runoff.
The overflow from the impoundment•, combines with the discharge from outfall 002
prior to discharge into the Catawba -River. The sanitary WWTP is designed for a
maximum of 64,000 gpd.
5. Sludge handling and disposal scheme: (Information received by telephone from
Mr. W. T. Griffin on 8/26/86).
Outfall 001: Sludges which accumulate in the liquid radwaste system are
disposed as low level radioactive wastes at approved repositories such as
Barnwell, S. C.
0utfall 002: Sludges are disposed by landfarming at a designated on -site
disposal area. This disposal is permitted by DEM Permit No. 7641R2.
0utfall 003: Sludge is periodically removed from the lagoon and disposed
at a municipal WWTP. Currently, the disposal is made at CMUD's McDowell
Creek WWTP.
6. Treatment plant classification: Attached are copies of suggested revised
rating sheets being sent to John Campbell for consideration. If approved the
revised rating will be as follows: 0utfall 001: Class IV; 0utfall 002: Class
III, 0utfall 003: Class I
*Based on information given to the investigator during the inspection. Note:
The turbine building sump water will normally go to the conventional wastewater
treatment system for discharge thru outfall 002. However, in instances where the
radioactivity of the sump water is sufficiently low (within NRC requirements)
the water may be released directly thru outfall 001. If radioactivity level
exceeds NRC requirements, the sump water must first be routed to the liquid rad-
waste processing system prior to discharge thru outfall 001.

-4-
**The application does not provide sufficient information to ascertain specific
quantities for each type of wastewater included in this outfall (002). If this
information is necessary, it should be requested.
***Refer to information submitted by letter from Duke dated June 18, 1982 for
full listing of metals, etc. If a copy is not available in Central Files, please
contact MRO for a copy.
PART III - OTHER PERTINENT INFORMATION
1. Is this facility being constructed with Construction Grants Funds (municipals
only)? N/A.
2. Special monitoring requests: See Part IV
3. Additional effluent limits requests: None
4. Other: None
PART IV - EVALUATION AND RECOMMENDATIONS
Duke's application for amendment essentially covers three (3) changes to and
clarifications of operations at the plant that have occurred since last issuance
of the permit (9/1/84) as outlined below:
1. Duke has modified their operations such that turbine sump water may now
be discharged via outfall 001 (see part II * for detail). The manner of
release is reportedly governed by NRC approved plant procedures. Duke has
submitted a copy of these approved procedures (copy attached).
2. Duke has begun using biocides and chemical additives which are ultimately
discharged thru Outfall 001. (See attached report from Duke dated 2/28/86
for explanation and listing of materials used).
3. Duke has now placed the new multicellular aerated facultative lagoon WWTP
(sanitary treatment system) in service and has abandoned the previously
used package WWTPs.
As is typical with any such request for permit renewal or amendment, the
investigator has attempted to review the adequacy of the existing permit, least
we should continue any inadequacies in a new, revised permit. This review has
prompted serious concern with respect to the monitoring of possible radioactive
releases thru outfalls 001 and 002. We can find nothing in our file copy of
Duke's permit which provides any assurance that such releases>are being
monitored or that they are properly limited. In Duke's application documents
(for this latest modification and for applications in years past) Duke has
indicated that such releases are low level a and are in accordance with NRC
approved station operating procedures. Further, it is our understanding, thru
conversations with Duke personnel, that Duke submits reports regularly to NRC
with respect to the amounts and types of radiation released. If thisis the
case, then NRC is regulating the levels of radioactivity released thru DEM
permitted outlets (001 & 002). This is no problem if NRC is reviewing Duke's
releases in a responsible manner (and we are confident that they are) and that
the controls which they impose take into consideration DEM's concerns to protect
water quality (not just human health). Obviously the answer to this question
is not easily obtained and would appear to be a matter best resolved by a written

-5-
agreement between the NRC and DEM.
An agreement such as this would be advisable since NRC is obviously the more
qualified of our agencies for such a matter and this would merely be an official
acknowledgement that this is, in fact, their responsibility. DEM could then
ma* reference to such fact in the NPDES Permit and establish that the reporting
and procedures for radioactive releases will be done in accordance with NRC
requirements. Thus, if there should ever be a problem with such releases DEM
would have some avenue for action. Such an avenue does not exist in the current
permit.
eL
This matter has been discussed with Mr. Dayne Brown, NC-DHR-Radiological Unit and
Mr. Darrel Hood, NRC. Neither are aware of the existence of any such agreement
and both agree that this may be advisable and warrants further consideration.
We recommend that this matter be discussed with the Water Quality Section Chief
and that negotiations be initiated with NRC with the goal of developing an
inter -agency memorandum of understanding. We believe that this is in the best
interest of both DEM and NRC not just for the McGuire Station but for all nuclear
stations within the State.
Upon resolution of this matter, it is recommended that the NPDES Permit be
reissued with limitations and monitoring requirements appropriate for this
industrial category and for the revised class of each outfall.
Note: The permit should not be drafted until the proposed revised facility
rating has been reviewed and classifications assigned.
Signature of report preparer
Water Quality Regional Supervisor

C K -!L Alwil f
N. C. DEPT. OF NATURAL RESOURCES AND COMMUNITY DEV.
ENVIRONMENTAL MANAGEMENT COMMISSION
NAL POLLUTANT DISCHARGE ELIMINATION SYSTEM
\I CATION FOR PERMIT TO DISCHARGE WASTEW4TER
STANDARD FORM C — MANUFACTURING AND COMMERQ$L
,41
pia
SECTION I. APPLICANT AND FACILITY DESCRIPTION
Unless otherwise Spei cirAdhis form all Items are to be completed. If ari item Is not applicable Indicate INA.'
ADDITIONAL INSTRUCrIDNSTOR SELECTED ITEMS APPEAR IN SEPARATE INSTRUCTION BOOKLET AS INgiliCINVED. REFsfii\ TO
BOOKLET BEFORE FILLING OUT THESE ITEMS:
Legal Name of Applicant
(see Instructions)
Mailing Address of Applicant
(see instructions)
Number & Street
City
State
Zip Code
Applacant's Authorized Agent
(see Instructions)
Name and Title
Number & Street Address
City
State
Zip Code
Telephone
4. Previous Application
If a previous application for a
National or Federal discharge per-
mit has been made, give the date
of application. Use numeric
designation for date.
Please Print or Type
Duke Power Company
P.O. Box 33189
Charlotte
North Carolina
28242
H. B. Tucker
Vice President, Nuclear Production
P.O. Box 33189
Charlotte
North Carolina
28242
704 373-4531
Area
Code
Number
82 07 20
YR MO DAY
I certify that I am familiar with the information contained In this application and that to the best of my knowledge and belief such Information
Is true, complete, and accurate.
H. B. Tucker
Printed Name of Person Signing
Vice President, Nuclear Production
Title
YR MO DAY
Signature of Applicant or Authorized Agent Date Application Signed
North Carolina. General Statute 143-215.6(b) (2) provides that: Arty person who knfringly makes
any false statement representation, or certification in any application, record, report, plan,
or other document files or required to be maintained under Article 21 or regulations of the
Environmental Management Commission implementing that Article, or who falsifies, tampers with,
or knowly renders inaccurate any recording or monitoring device or method required to be
operated cr maintained under Article 21 or regulations of the Environmental Management Cowls it
implementing that Article, shall be guilty of a misdemeanor pin.ishahle by a fine not to exceed
$10,000, or by imprisonment not to exceed six months, or by both. (18 U.S.C. Section 1001 provi(
a punishment by a fine of not more than S10,000 or imprisonment not more than 5 years, Or both,
for a similar offense.)

f=aWiitY/Aettvtty (see InstruCtions)
Give the nama, ownership, and
Physical location of the plant or
other operating facility where dis-
charge(*) does or will occur.
Name
Ownership (Public, Private or
Both Public and Private)
Check block If Federal Facility
and glve GSA Inventory Control
Number
Location
Street & Number
City
County
State
Nature of Muslims State the
nature of the business conducted
at the plant or operating faclllty.
7. Facility Intake Water (see Instruc•
tions) Indicate water Intake volume
per day by sources. Estimate
average volume per day in thousand
gallons per day.
Municipal or private water system
Surface water
Groundwater
Other`
Total Item 7
"If there is Intake water from
'other,' specify the source.
Facility Water Use Estimate
average volume per day In thousand
gallons per day for the following
types of water usage at the facility.
(see Instructions)
Noncontact cooling water
Boller feed water
Process water (including contact
cooling water)
Sanitary water
Other*
Total Item 8
*If there+re•discharges to
'other,' specify.
If there Is 'Sanitary' water use, give
the number of people served.
McGuire Nuclear Station
UB ®PRV ©BPP
© FEO
Mecklenburg
Generation of electric power from nuclear fuel
NJA
thousand gallons per day
thousand gallons per day
thousand gallons per day
nd gallons per day
thousand gallons per day
N/A
thousand gallons per day
thousand gallons per day
thousand gallons per day
thousand gallons per day
thousand gallons per day
thousand gallons per day
Wople served
I-2

STANDARD FORM C — MANUFACTURING AND COMMERCIA
SECTIONU. BASIC DISCHARGE DESCRIPTION
Complete this section for each discharge indicated in Section I, Item 9, that is to surface waters, This includes discharges to municipal sewerage
systeMS in which the wastewater does not go through a treatment works prior to being discharged to surface waters, Discharges to wells must
be described where there are also dischargeS to surface waters from this facility. SEPARATE DESCRIPTIONS OF EACH DISCHARGE ARE
REQUIRED EVEN IF SEVERAL DISCHARGES ORIGINATE IN THE SAME FACILITY. All values for an existing discharge should be repre-
sentative of the twelve previous months of operation. If this is a proposed discharge, values should reflect best engineering estimates.
ADDITIONAL INSTRUCTIONS FOR SELECTED ITEMS APPEAR IN SEPARATE INSTRUCTION BOOKLET AS tNDICATED. REFER
TO BOOKLET BEFORE FI LING OUT THESE ITEMS,
1,, Discharge Serial No, and Name
a, Discharge Serial No,
(see instructions)
b. Discharge Name
Give name of discharge, if any.
(see instructions)
c, Previous Discharge Serial No.
II Previous permit application
was made or this discharge (see
item 4, ,iiiction I), provide Previ-
ous diqiiargo serial number.
Discharge Operating Dates
a. Discharge Began Date If the
discharge described below is in
operation, give the date (within
best estimate) the cliScharge
began,
h. Discharge to Begin Date If the
discharge has never occurred but
Is planned for sorne future date,
give the date (within best esti-
mate) the discharge will begin.
c. Discharge to End Date If dis-
charge is scheduled to be discon-
tinued within the next 5 years,
give the date (within best esti-
mate) the discharge win end.
3. Engineering Report Available
Check it 311 engineering report IS
available to roviewing ncy upon
request, (see instructi)ns)
4. Discharge Location Name the
political boundaries within which
the point of discharge is located,
State
County
(it applicable) City or Town
5, Discharge Point Description
Discharge is into (Check one):
(see inStiuctions)
Stream (includes ditches, arroyos,
and other intermittent watercourses)
Lake
Ocean
Municipal Sanitary Wastewater
Transport System
Municipal Combined Sanitary and
Storm Transpor t System
001
_Conc1enser Coolingyater
N/A
YR MO
MO
YR MO
North Carolina
Mecklenburg
TR
K E
DOCE
DMIS
DMC5
This t,kort re000i0,0 0

DISCHARGE SERIAL NUMBER
001
Municipal Storm Water Transport
System
Well (Injection)
Other
if 'other' is checked, specify
6. Discharge Point — Lat/Long Give
the precise location of the point
of discharge to the nearest second,
Latitude
Longitude
Discharge Receiving Water Name
Name the waterway at the point
of dlscharge,(see instructions)
tf the discharge Is through an out -
tact that ex tends beyond the shore -
tine or is below the mean low
water line, complete Item 8.
P STS
PWEL
POTH
2� 35 DEG 25 MIN 59SEC
24I _8DEG 56 MIN 55SEC
Offshore Discharge
a- Discharge Distance from Shore 20 k
b. Discharge Depth Below Water
Surface 20111b
Discharge Type and Occurrence
a. Type of Discharge Check
whether the discharge Is con-
tinuous or intermittent.
(see instructions)
b. Discharge Occurrence Days per
Week Enter the average num-
ber of days per week (during
periods of discharge) this dis-
charge occurs,
c. Discharge Occurrence —Months
if this discharge normally
operates (either intermittently,
or continuously) on less than
a year -around basis (excluding
shutdowns for routine mainte-
nance), check the months dur-
ing the year when the discharge
is operating. (see instructions)
ompiete items 10 and 11 if "Inter-
iittent" is checked in Item 9.a.
)iherwise, proceed to Item 12.
0, Intermittent Discharge Quantity
State the average volume per dis-
charge occurrence in thousands of
gallons,
It„ Intermittent Discharge Duration
and Frequency
a. Intermittent Discharge Duration
Per Day State the average
number of hours per day the
discharge is operating.
b. Intermittent Discharge
Frequency State the average
number of discharge occur-
rences per day during days
when discharging.
12, Maximum Flow Period Give the
time period in which the maximum
flow of this discharge occurs.
Lake Norman
feet
[(con) Continuous
0 (int) Intermittent
days per week
©JAN( DFEB OMAR DAPR
DMA 0JUN 0JUL ['AUG
PSEP POET ID NOV POEC
For Agency Use
303e
thousand gallons per discharge occurrence.
.hours per day
discharge occurrences pet day
From June to October
month month
n-s

DISCHARGE SERIAL NUMBER
nni
13. Activity °ascription Give a
narrative description of activity
producing thls discharge.(see
instructions)
14. Activity Causing Discharge For
each SIC Code which describes
the activity causing this discharge,
supply the type and maximum
amount of either the raw material
consumed (Item 14a) or the product
produced (Item 14b) in the units
specified in Table I of the Instruc-
tion Booklet. For SIC Codes not
listed in Table I, use raw material
or production units normally used
for measuring production.(5ee
instructions)
a, Raw Materials
SIC Code
213
General - Conversion of nuclear energy into
electrical energy
Specific - Condenser cooling water serving
steam condensers, plus blowdown
from steam ,generators, treated low-
level radioactive liquid wastes�W
N/A
Name
t2i
Maximum Unit
Shared Discharges
Amount/Day (See Table I) (Serial Number)
b„ Products
SIC Code
Name
Maximum Unit
Amount/Day (See Tabl
Shared Discharges
(Serial Number)
11-3

15. Waste Abatement
Waste Abatement Practices
tiev r b, the. waste abatement
tsar Fit es Tisch ,n, this discharge
with a brief narrative. (see
instructions)
b. Waste Abatement Codes
Using the cotes listed in Table
It of the Instruction Booklet,
describe the waste abatement
proccsscs for this discharge in
the order in which they occur
,1 In,t :rblr:.
DISCHARGE SERIAL NUMBER
001
Na„,, Condenser cooling water , drawn from Lake.hiarman,
pumped through the condenser and discharges back into Lake
Norman. Steam generator blowdown is monitored and then dis-
charged into the condenser cooling water or recycled for
cleanup if needed. Plant drains which may contain radio-
activity are collected in Liquid Radwaste System. The Liquid
Radwaste System collects all radioactively contaminated water
from the equipment drains, spills, or leaks within the
auxiliary and reactor buildings. The system is
onitored and o erated such that low level radioactive
(4)
(7)
PSCREE
ESURFA
RECOVE
((0) �1.F CdbS
(13) MTfNOY
(16)
(19)
(22)
(25)
ESEPAR.
(2)
(5) EMERGE
0) RECYCL
(3) ESEGRE
(6) EPTTMPS
LOCALS
00 TEVAPO ( t I ) TPR©CE
(14) ...„. (15)
(17) (18)
(20) (21)
(23) , (24)
waste may be released when its activity is below prescribed
limits or may be recycled to the Reactor Coolant System.
The system utilizes filters, evaporators, and demineral-
izers for the treatment process. All releases are regulated
by the Nuclear Regulatory Commission and are made to assure
compliance with 10 CFR 50 Appendix I. Maximum flow from
the system is 300 gpm.
NOTE: The turbine building sumps are normally routed to
the Conventional Wastewater Treatment System (WC). How-
ever, when the sump has radioactive contamination, its
discharge may continue to be released to the WC system,
may be routed to the normal Liquid Radwaste System
discharge ,line for release to the condenser circulat-
ing water or to the Liquid Radwaste Collection tanks
for processing prior to release. The release method
to be used depends on the level of radioactivity,
volume of wastes, other wastes to be processed, NRC
Technical Specifications processing requirements,
potential for an oil spill, and on the need to
process chemical wastes.
11-4

At r,4t,##m.
i)UKE POWER COMPANY
.EAR PRODUCTION DEPARTMENT
x 33189, 422 SOUTH CHURCH STREET
CHARLOTTE, N.C. 28242
(704) 373-401.1
February 28, 1986
Mr. D. Rex Gleason, Pf.E.
Water Quality Regional Engineer
North Carolina Department of Natural
Resources and Community Development
Division of Environmental Management
919 North Main Street
Mooresville, NC 28115
SUBJECT: McGuire Nuclear Station
Use of Biocide
Containment Spray Heat Exchanger
File: MN-208.38, 702.12, 730.65
Dear Sir:
On November 27, 1985, we requested permission to use a
biocide, Calgon H-106 in the containment spray (NS)
heat exchangers at McGuire Nuclear Station to assist in
cleaning the exchangers and to restore their efficiency
and ensure their operability. Should the efficiency
deteriorate excessively, the unit(s) would have to be
shut down.
In providing approval to use the biocide, you requested
a report on the chemical(s) used, the amount of the
chemical(s) used, and the discharge concentration.
Attached is a listing of the heat exchangers cleaned,
the chemicals used, the amount of the chemical, and the
maximum discharge concentration as well as flow rates.
Also attached is a short description of each chemical.
As can be seen, the biocide was used in only two (2) of
the heat exchangers. We found that equal or better
cleaning was obtained by using surfactants, penetrants,
and disperants for this particular fouling. Biocides
may be more effective on other types of fouling.
Only three of the four heat exchangers were cleaned at
this time. It may be necessary in the future to clean
the fourth heat exchanger and/or to reclean one that
was cleaned at this time. If a biocide is needed in a
future cleaning, we will contact you for approval.

Mr. D. Rex Gleason, P.E.
February 28, 1986
Page Two
Should you have any; questions or desire additional
information, please contact me at [phone].
Sincerely,
R. T. Simril, System Engineer
Nuclear Environmental Compliance
WTG:hj p
Attachments
cc:
W.A. Haller
R.W. Esker
P.W. Downing
W.M. Suslick
MN-2002.02
MN-2002.03-04

HEAT EXCHANGER CLEANINGS
Date Time
HX. # Chem. Flush Time Length CCW Flow Max. Dischg.
HX. Vol., Chemical Used. Rate, gpm of Disch. min. Rate, gpm Conc. ppm
gal.
12/12/85 1330 "lA" NS 4,000 H-106
12/12/85 2000 "lA" NS 4,000 PCL-2000
4.3 5,000
5.2 5,000
0.8
0.8
12/31/85 1430 "lA" NS 4,000 H-106 4.3 2,250 1.8
12/31/85 1430 "lA" NS 4,000 CL-361 4.5 2,250 1.8
1/6/86 2300 "lA" NS 4,000 CL-361 4.5 5,000 0.8
1/6/86 2300 "lA" NS 4,000 PCL-2000 10.4 5,000 0.8
2,032,000
2,032,000
2,032,000
2,032,000
2,032,000
2,032,000
0.32
0.38
0.14
0.15
0.33
0.77
1/14/86 1000 "lA" NS 4,000 TSP 150 33 120 1,883,000 0.079
1/14/86 1000 "lA" NS 4,000 Triton X-100 7.1 33 120 1,883,000 0.0037
1/14/86 1000 "lA" NS 4,000 PCL-2000 5.2 33 120 1,883,000 0.0027
1/27/86 0830 "2B" NS 4,000 TSP 150 200 20 2,032,000 0.44
1/27/86 0830 "2B" NS 4,000 Triton X-100 4.7 200 20 2,032,000 0.014
1/27/86 0830 "2B" NS 4,000 PCL-2000 5.2 200 20 2,032,000 0.015
2/5/86 0900 "2B" NS 4,000 TSP 150 33 120 2,032,000 0.073
2/5/86 0900 "2B" NS 4,000 Triton X-100 7.1 33 120 2,032,000 0.0035
2/5/86 0900 "2B" NS 4,000 PCL-2000 5.2 33 120 2,032,000 0.0025
2/12/86 0900 "2A" NS 4,000 TSP 150 33 120 1,948,000 0.076
2/12/86 0900 "2A" NS 4,000 Triton X-100 7.1 33 120 1,948,000 0.0036
2/12/86 0900 "2A" NS 4,000 PCL-2000 5.2 33 120 1,948,000 0.0026

Definition of Chemicals
H-106 - Calgon H-106 Microbiocide (a quaternary ammonium
biocide)
PCL-2000 - Calgon Powergaurd 2000 (an anionic, polyacyrlic
acid dispersant/scale inhibitor)
CL-361 - Calgon CL-361 Deposit Inhibitor (a blend of
penetrants, surfactants, and dispersants)
Triton X-100 - Rohm & Haas Triton X-100 (a non-ionic, poly -
ether alcohol surfactant/detergent)
TSP - Trisodium Phosphate

Date: September 4, 1986
NPDES STAFF REPORT AND RECOMMENDATIONS
County: Mecklenburg
NPDES Permit No. NC 0024392
PART I - GENERAL INFORMATION
1. Facility and Address: Duke Power Company
McGuire Nuclear Station
Post Office Box 33189
Charlotte, N. C. 28242
2. Date of Investigation: March 27, 1986
3. Report Prepared By: J. Thurman Horne, P. E.
4. Persons Contacted and Telephone Number: Mr. W. T. Griffin
[phone]
5. Directions to Site: From the intersection of Highway 16 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 shore of Lake Norman.
6. Discharge Point
001
Latitude: 35°26'10"
Longitude: 80°56'30"
002 & 003
35°25'40"
80°57'20"
Attach a USGS Map Extract and indicate treatment plant site and discharge
point on map.
USGS Quad No. F15NW
7. 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: 001 002 & 003
Lake Norman Catawba River
WS III & B WS III
03-08-32 03-08-33
a. Classification:
b. River Basin and Subbasin No.:
c. Describe receiving stream features and pertinent downstream uses:
0utfall 001: 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 Huntersville and is located
approximately 3 miles northeast of the discharge.

-2-
0utfall 002 & 003: The receiving 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.
PART II - DESCRIPTION OF DISCHARGE AND TREATMENT WORKS
1. Type of wastewater: 001 002 003
0 0 100 % Domestic
100 100 0 % Industrial
a. Volume of Wastewater: 001 002 003
2525 .41 0.04 MGD (average daily)
(based on flow schematic attached to application)
b. Types and quantities of industrial wastewater:
0utfall 001 (Cooling Water Discharge): This discharge is a combination
of condenser cooling water (1,727,100 gpm), conventional low pressure
service water (6,500 gpm), nuclear service water (20,000 gpm), low level
liquid radwaste (8 gpm) and *turbine building sumps (70 gpm).
**0utfall 002 (conventional treatment system discharge): This discharge
consists of steam generator blowdown, condensate demineralizer backwash,
water treatment system backwash, demineralizer backwash, building drains,
metal cleaning wastes and *turbine building sumps.
0utfall 003 (sanitary waste treatment system): This discharge consists
of the domestic type waste generated by plant personnel.
c. Prevalent toxic constituents in wastewater:
0utfall 001
***0utfall 002 Outfall 003
Biocides (see attached Low level radioactivity None
letter dated 2/28/86)
low level radioactivity,
chlorine, sodium hydroxide,
lithium hydroxide,
monohydrate, sulfuric acid,
boric acid
d. Pretreatment Program (POTWs only): N/A.
2. Production rates (industrial discharges only) in pounds: Information not
available in any application submittals received by MRO. If information is
needed it should be requested from the applicant.
Description of industrial process (for industries only) and applicable CFR
Part and Subpart: 40 CFR Part 423 - Steam Electric Power Generation
4. Type of treatment (specify whether proposed or existing):
0utfall 001
The existing liquid radwaste system consists of filters, evaporators and
demineralizers. (Note: this process treats only a small portion of the

total discharge of outfall 001). The combined wastewaters of outfall 001
flow into Lake Norman via a discharge canal approximately 2500 feet long and
200 feet wide. The canal is for the purpose of heat dissipation.
0utfall 002
Wastewater is treated in the plant's existing conventional wastewater treatment
system which consists of a 200,000 gallon initial holding pond, two (2) settling
ponds (in parallel) each with 2.5 million gallon capacity, a 1 million gallon
final holding pond (aerated -diffused air) and effluent pH adjustment consisting
of automated CO2 addition.
The initial holding pond acts as a flow equalization basin. This pond may be
bypassed, depending on the nature of the wastewater. The two settling ponds
are operated such that one pond remains in standby. Treatment can be enhanced
by the addition of coagulant aids and pH adjustmentin these ponds.
The effluent from the settling ponds may be discharged directly to the
receiving stream via outfall 002 or it may be routed to the final holding pond.
Effluent from the final holding pond may be discharged through outfall 002 or
recirculated to the settling ponds, depending upon effluent quality.
0utfall 003
The existing sanitary WWTP consists of a multicellular aerated -facultative
lagoon, a chlorine contact chamber (tablet), and a parshall flume. The discharge
from outfall 003 enters an impoundment which also receives area surface runoff.
The overflow from the impoundment combines with the discharge from outfall 002
prior to discharge into the Catawba River. The sanitary WWTP is designed for a
maximum of 64,000 gpd.
5. Sludge handling and disposal scheme: (Information received by telephone from
Mr. W. T. Griffin on 8/26/86).
0utfall 001: Sludges which accumulate in the liquid radwaste system are
disposed as low level radioactive wastes at approved repositories such as
Barnwell, S. C.
0utfall 002: Sludges are disposed by landfarming at a designated on -site
disposal area. This disposal is permitted by DEM Permit No. 7641R2.
0utfall 003: Sludge is periodically removed from the lagoon and disposed
at a municipal WWTP. Currently, the disposal is made at CMUD's McDowell
Creek WWTP.
6. Treatment plant classification: Attached are copies of suggested revised
rating sheets being sent to John Campbell for consideration. If approved the
revised rating will be as follows: 0utfall 001: Class IV; 0utfall 002: Class
III, 0utfall 003: Class I
*Based on information given to the investigator during the inspection. Note:
The turbine building sump water will normally go to the conventional wastewater
treatment system for discharge thru outfall 002. However, in instances where the
radioactivity of the sump water is sufficiently low (within NRC requirements)
the water may be released directly thru outfall 001. If radioactivity level
exceeds NRC requirements, the sump water must first be routed to the liquid rad-
waste processing system prior to discharge thru outfall 001.

-4-
**The application does not provide sufficient information to ascertain specific
quantities for each type of wastewater included in this outfall (002). If this
information is necessary, it should be requested.
***Refer to information submitted by letter from Duke dated June 18, 1982 for
full listing of metals, etc. If a copy is not available in Central Files, please
contact MR0 for a copy.
PART III - OTHER PERTINENT INFORMATION
1. Is this facility being constructed with Construction Grants Funds (municipals
only)? N/A.
2. Special monitoring requests: See Part IV
3. Additional effluent limits requests: None
4. Other: None
PART IV - EVALUATION AND RECOMMENDATIONS
Duke's application for amendment essentially covers three (3) changes to and
clarifications of operations at the plant that have occurred since last issuance
of the permit (9/1/84) as outlined below:
1. Duke has modified their operations such that turbine sump water may now
be discharged via outfall 001 (see part II * for detail). The manner of
release is reportedly governed by NRC approved plant procedures. Duke has
submitted a copy of these approved procedures (copy attached).
2. Duke has begun using biocides and chemical additives which are ultimately
discharged thru 0utfall 001. (See attached report from Duke dated 2/28/86
for explanation and listing of materials used).
3. Duke has now placed the new multicellular aerated facultative lagoon WWTP
(sanitary treatment system) in service and has abandoned the previously
used package WWTPs.
As is typical with any such request for permit renewal or amendment, the
investigator has attempted to review the adequacy of the existing permit, least
we should continue any inadequacies in ,a new, revised permit. This review has
prompted serious concern with respect to the monitoring of possible radioactive
releases thru outfalls 001 and 002. We can find nothing in our file copy of
Duke's permit which provides any assurance that such releases are being
monitored or that they are properly limited. In Duke's application documents
(for this latest modification and for applications in years past) Duke has
indicated that such releases are low level and are in accordance with NRC
approved station operating procedures. Further, it is our understanding, thru
conversations with Duke personnel, that Duke submits reports regularly to NRC
with respect to the amounts and types of radiation released. If this is the
case, then NRC is regulating the levels of radioactivity released thru DEM
permitted outlets (001 & 002). This is no problem if NRC is reviewing Duke's
releases in a responsible manner (and we are confident that they are) and that
the controls which they impose take into consideration DEM's concerns to protect
water quality (not just human health). Obviously the answer to this question
is not easily obtained and would appear to be a matter best resolved by a written

agreement between the NRC and DEM.
An agreement such as this would be advisable since NRC is obviously themore
qualified of our agencies for such a matter and this would merely be an official
acknowledgement that this is, in fact, their responsibility. DEM could then
makereference to such fact in the NPDES Permit and establish that the reporting
and procedures for radioactive releases will be done in accordance with NRC
requirements. Thus, if there should ever be a problem with such releases, DEM
would have some avenue for action. Such an avenue does not exist in the current
permit.
This matter has been discussed with Mr. Dayne Brown, NC-DHR-Radiological Unit and
Mr. Darrel Hood, NRC. Neither are aware of the existence of any such agreement
and both agree that this may be advisable and warrants further consideration.
We recommend that this matter be discussed with the Water Quality Section Chief
and that negotiations be initiated with NRC with the goal of developing an
inter -agency memorandum of understanding. We believe that this is in the best
interest of both DEM and NRC not just for the McGuire Station but for all nuclear
stations within the State.
Upon resolution of this matter, it is recommended that the NPDES Permit be
reissued with limitations and monitoring requirements appropriate for this
industrial category and for the revised class of each outfall.
Note: The permit should not be drafted until the proposed revised facility
rating has been reviewed and classifications assigned.
Signature-bf reporti)reparer
Water Quality Regiona, upervisor

PA NY
'AI2TNIENT
IN)X :1:11)13), •1,22 sr>rrrr crruu4;rr tii'r+r:rrr
i ;lrn Ni,(YITI , \.(;., 21i
(70;) :i7:3-•).011
December 4, 1985
DEC 1985
PERMITS & ENGINEERING
Mr. R. Paul Wilms, Director
N. C. Division of Environmental. Management
P. O. Box 27687
Raleigh, NC 27611-7687
SUBJECT: McGuire Nuclear Station
NPDES Permit Application Modification
FILE: MC-704.15
Dear Sir:
The McGuire Nuclear Station NPDES permit (permit no.
NC0024392), Part II.A.1., specifies that notice is to
be provided to the Division of Environmental Management
of process modifications that affect discharge of
pollutants. This letter provides notice of such a
modification, specifically pertaining to the turbine
building sump discharge. Attached are the parts of the
permit application that are affected by the
modification, as well as an update on approved
modifications to the sewage treatment system.
Very truly yours,
H. B. Tucker, Vice President
Nuclear Production Department
WTG/wmc
Attachment
cc: South Piedmont Office
U. S. Nuclear Regulatory Commission, Region II

Reactor Coolant System (NC)
The Reactor Coolant. System transports heat from the
reactor to the steam generators where the heat is again
transferred to the Feedwater/Main Steam System.
Approximately 120 pounds of Lithium hydroxide
monohydrate are used in each unit per year for p11
control. The lithium is removed by demineralizers in
the NC system or by the Radioactive Liquid Waste
Recycle System. The resins and the cvap<car;at.or bottoms
are drummed for offsite disposal scar i_n either •case,
lithium is not normally discharged. Approximately
60,000 pounds of boric acid per year pose unit are used
for reactor shim. Boric acid wastes are concentrated
and the evaporator bottoms are drummed for offsite
disposal. Small quantities of boron are released from
the Radioactive Liquid Waste Recycle System as a result
of evaporator carryover and when radiation levels are
low enough so as not to require evaporation. The
discharge from the system will be diluted by large
quantities of condenser cooling water.
Liquid Radwaste System
The Liquid Radwaste System collects all radioactively
contaminated water from the equipment drains, spills,
or leaks within the auxiliary and reactor buildings.
The system is monitored and operated such that low
level radioactive waste may be released when its
activity is below prescribed limits or may be recycled
to the Reactor Coolant System. The system utilizes
filters, evaporators, and demineralizers for the
treatment process. All releases are regulated by the
Nuclear Regulatory Commission and are made to assure
compliance with 10 CFR 50 Appendix I. Maximum flow
from the system is 300 gpm.
NOTE: The turbine building sumps are normally routed
to the Conventional Wastewater Treatment System (WC).
However, when the sump has radioactive contamination,
its discharge may continue to be released to the WC
system, may be routed to the normal Liquid Radwaste
System discharge line for release to the condenser
circulating water or to the Liquid Radwaste Collection
tanks for processing prior to release. The release
method to be used depends on the level of
radioactivity, volume of wastes, other wastes to be
processed, NRC Technical Specifications processing
requirements, potential for an oil spill, and on the
need to process chemical wastes.
Outfall 002
Outfall 002 discharges treated water from the
Conventional Wastewater Treatment System to the Catawba
River below Cowans Ford Dam.

Co11Vc:
Conventional Wastewater
non -radioactive plant:
(WC)
t System acc pts
(excluding ry
sew ) treats it through a system of basins with
cherni.c 11 <a€3ditian and acrat1011 and discharges i.t 1Lo the
Catawba River. The turbine building sump, water
treatment system filter backwashes, condensate
demineralizer backwashes, and make up deminer.alizer
regeneration wastes will be routed through this system
aric:aa to discharge to the Catawba River.
Wastes are initially directed to a concrete lined
initial holdup pond where primary sedimentation occurs.
This 200,000 gallon capacity basin has a retention time
of from 12 hours to 24 hours and acts as a surge tank
to prevent overloading and subsequent degradation of
effluent quality throughout the remainder of the
system. This pond may be bypassed depending on
influent quality.
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 p11 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 flows 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 from the basin
is within specifications. The final effluent pH is
normally adjusted with an automatic CO2 addition system
before discharge.
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

3]_ additives may be used to process the waste
cases from the pond will comply with McGu ire
Speci fi..cations.
CB)
The Collection Basin receives treated sanitary
effluent, yard drainage and overflow from the Standby
Nuclear Service Water Pond. The overflow from the CB
mixes with the discharge from the WC system in a
concrete protected apron and is discharged to the
Catawba River downstream of Cowans Ford Dane.
Outfall 003
Outfall 003 discharges treated sanitary waste from the
Sanitary Waste Treatment System to the Collection
Basin.
Sanitary Waste Treatment System
The Sanitary Waste Treatment System consists of an
aerated -facultative lagoon system which is a
trapezoidal multicellular arrangement consisting of a
completely suspended cell followed by three partially
suspended cells in series. The lagoon provides an
approximate 5-day retention time and will allow for
variable flow discharge. The wastewater effluent from
the aerated lagoon flows through chlorinators, a
chlorine contact chamber and a Parshall Flume before
discharging to the Collection Basin. Expansion space
is provided should a sand filter be required in the
future.
The lagoon is lined with a flexible synthetic material
such as hypalon, it is divided into four 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. 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 Collection Basin.

The sewage lagoon
capability at 5,
different levels
provide a 5-day
flow rates of 40,000
respectively.
a multiple level discharge
and 8 feet. At each of these
tion, the lagoon is able to
time for influent wastewater
gpd, 52,000 gpd, and 64,000 gpd,

LAKE
NORMAN
NSW
INTAKE
FIRE
PROTECTION
LAKE
NOR AN
NTAKE
INTAKE
SCREEN
BACKWASH
4
NSW
SYSTEM
CCW
SYSTE M
LPSWNV.
©
SYSTEM
FILTERED
WATER
SYSTEM
2
271
6
250
DEMIN.
WATER
$YSTEM
ACKWASH REENERATIV
SANITARY
POTABLE
WATER
SEWAGE
TREATMENT
SYSTEM
OUTFALL
003
2
ASTE
SECONDARY
& AUX,
COOLANT
SYSTEMS
STEAM GEN.
BLOWDOWN
LEAKAGE &
DRAINAGE
METAL CLN.
WASTES
D/G SUMPS
REACTOR
COOLANT
SYSTEM
TURBINE
BUILDING
SUMPS
COND.
DEMIN.
BACKWASH
QUID
DWAST E
OCESSING
NOTE ALL FLOWS ARE IN GPM
FOR AVERAGED CONDITIONS.
ELECTION
BASIN
RAINFALL
SNSW POND
RUNOFF
E VAP. &
SEEPAGE
CONY.
WASTE
WATER
TREATMENT
OUTFALL
C2
2B2
©2
LAKE
NORVAN
OUTFALL
DO1
CATAWBA.
RIVER
(DUKE POWER COMPANY
MCGUIRE NUCLEAR STATION
WATER FLOW SCHEMATIC

April 14, 1986
SiONVOrt Ftk�..tl C N7A 1. MANAGLMENV
YORESYKAA
Mr Thurman Horne
Water Quality Section
South Piedmont Regional Office
N.C. Department of Natural Resources
and Community Development
Division of Environmental Management
919 North Main Street
Mooresville, NC 28115
SUBJECT: Turbine Building Sump Release
Radwaste Discharge Point
File: MC-704.15
Dear Mr. Horne:
During your inspection at McGuire Nuclear Station on
March 27, 1986, you requested information concerning
releasing the turbine building sump through the
radwaste release point. Attached, for your
information, is a copy of the station procedure,
Radioactive Liquid Waste Release. Section 4.4 is the
procedure for releasing the turbine building sump.
During the inspection, as you may recall, we stated
that we were limited by NRC on the release of specific
radioisotopes as well as total radiation. Section 3.3
of the attached procedure addresses this. Enclosure
5.3, Manual Calculations, is the method for calculating
the amount of activity that is released. As you can
see, for each isotope, the isotopic concentration
( uCi/ml) is divided by the maximum permissible
concentration (MPC,MCi/ml); all isotopic concentrations
are then totalled. The release rate is then calculated
to ensure sufficient dilution.
Should you have any additional questions, please
contact me at [phone].
Sincerely,
R.T. Simril, System Engineer
Nuclear Environmental Compliance
by: W.T. Grii 'n
Environmental Engineer
WTG/rhm
attachment

rVED
Form 34731 (R8-85)
1
PREPARATION
(2) STATION bra Nuclear Station
(3) PROCEDURE TITLE
Radioactive Liquid Waste Release (LWR)
10
Change(%)
—5 .__Incorpora
(4) PREPARED BY -, DATE . /1Je7 G
(5) REVIEWED BY 1J1 /h Ce Y, /�rG r1 DATE
Cross -Disciplinary Review By N/R laiFer3
(6) TEMPORARY APPROVAL. (If Necessary)
By (SRO) Date
By
(7) APPROVED BY
Atie,A404z,0*--
Data
DATE
(81 MISCELLANEOUS
Approved By
Date .ai ► —,""'
Reviewed/Approved By Date
(91 COMMENTS (For procedure reissue indicate whether additional lunges. other than previously approved charges, are inctuded.
Attach additional page, if necessary.) OAODITIONAL CHANGES INCLUDED.
COMPLETION
(10) COMPARED WITH CONTROL COPY DATE
(11) DATE(S) PERFORMED
(12) PROCEDURE COMPLETION VERIFICATION
© Yes © N/A Cited' Nees and/or Menem property initialed. signed. dated or filled in N/A or N/R. • appropriate?
© Yes 0 N/A LMatimaisolros astednd?
CI Yes 0 WA Om dross attached, cornpbt.d dated and tied?
© Yes 0 WA CaIIi, mks. tee. attached and properly dated. identified and monied?
© Yes 0 N/A Aawpsanaa arisen. nett
VERIFIED SY DATE
(131 PROCEDURE COMPLETION APPROVED DATE
1141 REMARKS (Attach additional pages, if necessary. 1

HP/0/B/1003/02
DUKE POWER COMPANY
McGUIRE NUCLEAR STATION
RADIOACTIVE LIQUID WASTE RELEASE (LWR)
1.0 Purpose
This procedure describes the proper method of aastpling, initiating and
documenting a radioactive liquid release from a Waste Monitor Tank (WMT)
or Recycle Monitor Tank (RMT), Containment Ventilation Unit Condensate
Drain Tank (CVUCDT), or Turbine Building Sump (TBS) to the RC System.
2.0 References
2 1 Duke Power Company, McGuire Nuclear Station, Liquid and Gaseous
Radwaste Computer Program User's Documentation.
2.2 McGuire Nuclear Station, Technical Specifications 3.11.1.1
2.3 Station Health Physics Manual, Section 13.5: Preparation of Sample
for Count Room Analysis.
2.4 Station Health Physics Manual, Section 13.6; Composite Sampling.
2.5 HP/0/B/1003/08, Determination of Radiation Monitor Setpoints (EMF's).
2.6 HP/0/B/1009/13, Health Physics Actions for Inoperable Liquid Effluent
Monitoring and Sampling Devices.
2.7 PT/0/B/4600/18, Radioactive Liquid Effluent Sampling and Analysis
Frequency.
2.8 0P/0/8/6200/35, Radwaste Procedure for Discharging a Waste Monitor
Tank to the Environment.
2.9 OP/0/B/6200/43, Radwaste Procedure for Discharging a Recycle Monitor
Tank to the Environment.
2.10 Code of Federal Regulations, Title 10, Part 20, Appendix B.
2.11 OP/0/1/62OO/56, Radwaste Chemistry Response to Indication of a
!Timmy to Secondary Leak.
2.12 0P/1/I/6400/OIA, Condenser Circulating Water and Low Level Intake;
Enclosure 4.11, Operation of Turbine Building Sump with High Activity
to RC Discharge.
2.13 OP/0/A/6500/O1A, Ventilation Unit Condensate Drain Tank Operation.
3.0 Limits and Precautions
3.1 Proper Health Physics methods shall be used when handling radioactive
or potentially radioactive liquids.

-2-
3.2 All liquid waste release (LWR) and dose calculations shall be made by
use of appropriate computer codes per Reference 2.1. The manual
methods presented shall be used if the computer is not available.
3.3 All releases shall be added to the total quarterly release using the
appropriate computer codes (Reference 2.1) to ensure that quarterly
and annual limits are not exceeded.
3.4 Corrections to the LWR Computer Program after the program has been
terminated shall be handled by the Radioactive Materials Control
Group personnel with assistance from the General Office Radwaste
Engineering staff as necessary.
3.5 If for any reason the EHF, composite sampler, or flow totalizer is
inoperable, refer to HP/O/B/1009/13 for required action.
3.6 Sample analysis results shall be valid for 4 hours for a CVUCDT and
TBS release and 24 hours for a WMT/RMT release from the time sample
was obtained.
3.7 Radwaste Chemistry shall be allowed 3 consecutive attempts at
releases via EMF49(L) with Hi-Rad Trips before a resample shall be
required.
3.8 If for any reason the release has to be terminated prior to
completion, the H.P. controlled valve (WH116 for WMT-A, WM43 for
WHT-B, WM222 for 1-CVUCDT, WM225 for 2-CVUCDT, WM47 for TBS) shall be
locked closed.
3.9 Boron analysis shall be performed when the effluent is expected to
contain 2 1000 ppm Boron.
3.10 TBS sampling and the release may be terminated when all of the
following are true:
1. No activity (except dissolved and entrained gases) above
background is identified in two consecutive samples.
2. •o additional sources of activity to the sumps are anticipated.
3. Tda total activity of dissolved and entrained gases is less than
2.0E-4 Mci/ml.
3.11 Manual adjustments of EMF trip setpoints shall be performed using
HP/0/B/1003/08 Enclosure 5.4.
3.12 Five LWR spares shall be entered on the VAX computer as soon as
possible on the first day of the month.

4.0 Procedure
4.1 For a WMT/RMT release go to Section 4.2. For CVUCDT release go to
Section 4.3. For a TBS release go to Section 4.4.
4.2 WMT/RHT Release
NOTE 1: Prior to WMT/RMT release read the Limits and Precautions
and Section 4.2 of this procedure.
NOTE 2: This procedure is performed in conjunction with Chemistry
release procedure Reference 2.8 or 2.9.
NOTE 3: If EMF49(L) is inoperable, refer to HP/0/B/1009/13 for
inoperable action.
4.2.1 Determine the Recommend Release Rate using Enclosure 5.1.
4.2.2 Record EMF49(L) as the EMF Utilized.
4.2.3 If EMF49(L) is inoperable, record EMF49(L) Inoperable and
N/A for the EMF Expected CPM, Background Reading, and Trip
1 and 2 Setpoints on the Discharge Document. Go to Step
4.2.5.
4.2.4 Determine the EMF49(L) Setpoints using HP/0/B/1003/18.
Record setpoints and sign the Discharge Document.
4.2.5 Independently verify the following and sign adjacent to
the performing Health Physics Technicians signature (see
Enclosure 5.2, page 1 of 3).
4.2.6
(a) Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
(b) Recommended Release Rate.
(c) EMF Trip 2 Value.
Take the Discharge Document and associated paperwork as
prescribed in the Chemistry release procedure to the
Control Room.
NOTE: The isotopic analysis printout can be replaced
with the computer program MGLIQRPT (Reference
2.1).

-4-
4.2.7 Adjust the EMF49(L) Setpoints, record in the EMI' Log Book
and deliver the document to the Operations Shift
Supervisor for appropriate signoffs. I.V. Trip
4.2.8 Take the discharge document and Chemistry release
procedure to Radwaste Chemistry personnel (716 Elevation).
NOTE: ,Ensure that all Health Physics signoffs in the
Chemistry release procedure are completed up to
this point.
4.2.9 As requested by Radwaste Chemistry, complete the Health
Physics portion of the Chemistry release procedure.
4.2.10 After the release is terminated, return EMF49(L) Setpoints
to the values in HP/0/B/1003/08 Enclosure 5.1 and record in
the ME Log Book. I.V. Trip
4.2.11 Review the LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.2.12 Record release information on PT/0/B/4600/18 Enclosure
13.1 and composite the appropriate volume as per reference
2.4.
4.3 CVUCDT Release
4.3.1 At the request of Operations, and after the CVUCDT has
been in recirc for thirty (30) minutes, obtain a Grab
Sample (cube container) from valve 1 or 2 WL403. Allow the
sample line to purge until no air is observed prior to
obtaining sample. Note the composite jug level.
4.3.2 Analyze 3500 ■1 sample for principal gamma emitters and
tritium per Reference 2.7.
NOTE 1: If the composite sampler is inoperable, label and
retain this sample for the weekly coapositing and
refer to HP/0/B/1009/13 and H.P. Manual Section
13.6 for inoperable, action.
NOTE 2: If EMF44(L) is inoperable, refer to
HP/0/B/1009/13 for inoperable action.

-5-
4.3.3 Determine the Recommended Release Rate using Enclosure 5.1.
4.3.4 Record 1 or 2 EMF44(L) as the EMF Utilized.
4.3.5 If EMF44(L) is inoperable, record 1 or 2 EMF44(L)
Inoperable and N/A for the EMF Expected CPM, Background
Reading, and Trip 1 and 2 Setpoints on the Discharge
Document. Go to Step 4.3.9.
4.3.6 Obtain the EMF44(L) reading from the Control Room and
record as the EMF Background Reading on the Discharge
Document.
4.3.7 Determine the Expected CPM of the EMF by multiplying the
EMF Correlation Concentration (Cs-137 Equivalent Activity
from HP/0/B/1003/18) times the EMF Correlation Factor from
HP/0/8/1003/08 Enclosure 5.3.
NOTE: If the EMF Correlation Concentration (Cs-137
Equivalent Activity from HP/O/B/1003/18) is
5.0E-4 NCi/ml, notify the H.P. Shift Supervisor
for approval of the release or send the tank
contents to the Floor Drain Tank.
4.3.7.1 Record the value from Step 4.3.6 or 4.3.7
(whichever is greater) as the Expected CPM of the
EMF.
4.3.8 Determine the EMF44(L) Setpoints as follows, record
setpoints and sign the Discharge Document.
4.3.8.1 Trip 2 Setpoint S 3.0E4 (#P)
where:
3.0E4 = derived from HP/0/B/1003/08 Enclosure
5.1 Note 12B for 1 RC pump running and
the release rate (f) is 120 gpm.
+1P = the number of RC pumps dedicated to
the release
NOTE 1: Trip 1 shall be greater than background
but less than Trip 2.

_b_
NOTE 2: If needed, the maximum Trip 2 setpoint
shall be calculated using
HP/0/B/1003/08 Section 4.2.
4.3.9 Independently verify the following and sign adjacent to
the performing Health Physics Technician's signature (see
Enclosure 5.2, page 1 of 3).
(a) Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
(b) Recommended Release Rate.
(c) EMF Trip 2 Value.
4.3.10 Take the Discharge Document to the Control Room, have
Operations adjust EMF44(L) Setpoints, record in the EMI' Log
Book, and deliver the document to the Operations Shift
Supervisor. I.V. Trip ;
4.3.11
NOTE: If the flow totalizer is inoperable, notify
Operations to manually calculate the volume
discharged.
I.V. WM222
4.3.12 Record the start date and tine, and the LWR # on the
CVUCDT chart recorder (0 WL 5900), initial it and inform
Operations of this action.
4.3.13 Coordinate with Operations to achieve the desired release
rate.
4.3.14 Once the release has started and daily if continuous
release,
4.3.14.1 Check the operation of the flow totalizer by
observing an appropriate change in the totalizer
count when compared to the actual release rate.
4.3.14.2 Check the operation of the composite sampler by
observing sample collection or a change in the
composite jug level.
At the request of Operations, rezero the CVUCDT flow
totalizer, and unlock and open WM222 (Unit 1) or WM225
(Unit 2). Report these actions completed and your name to
Operations.
or WM225

-7-
NOTE I: If the flow totalizer or composite
sampler is inoperable, refer to
HP/O/B/1009/13 and H.P. Manual Section
13.6 for action.
NOTE 2: pH adjust the composite sample per
reference 2.4 step 4.7.
4.3.14.3 Obtain a grab sample at least once per 24 hours
by having Operations put the tank in recirc and
obtaining a sample after recirc has been in
progress for thirty (30) minutes.
4.3.14.4 Analyze 3500 ml sample for principal gamma
emitters and tritium.
4.3.14.5 If the sample results indicate a new isotope, an
isotope disappears or the concentration of any
isotope changes by a factor of 10, generate a new
LWR per 4.3.3 through 4.3.10. Go to 4.3.14.7.
4.3.14.6 If the current LWR is to continue, read and
rezero the totalizer reporting the volume to
Operations. Continue step 4.3.14.
4.3.14.7 Close out the current LWR by obtaining the
volume released and rezeroing the flow totalizer.
4.3.14.8 Perform steps 4.3.12 and 4.3.13.
4.3.14.9 Perform steps 4.3.16 and 4.3.17.
4.3.14.10 Continue step 4.3.14.
4.3.15 When notified by Operations that the release is secured,
4.3.15.1 Close and lock WM222 (Unit 1) or WM225 (Unit 2).
4.3.15.2 Record the totalizer reading for discharge
volume.
4.3.15.3 Record the stop date and time on the CVUCDT
chart recorder and initial it.
4.3.15.4 Report to Operations the volume discharged, WM222
or W!l225 is locked closed, and the chart recorder
marked.
4.3.15.5 Ensure that Operations returns 1 or 2 EIIF44(L)
Setpoints to the values stated in HP/0/B/1003/08
Enclosure 5.1. Record in the EMF Log Book. I.V. Tri

-8-
4.3.15.6 Check the composite jug level to ensure an
adequate amount has been collected.
4.3.16 Review the LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.3.17 Record the required release information on PT/0/13/4600/18,
Enclosure 13.3 and composite as per reference 2.4.
4.4 Turbine Building Sump Release to RC System
NOTE: If EMF31 Trip 2 alarms while discharging to RC, perform
the following:
1. Obtain a sample.
2. Obtain the EMF reading.
3. Calculate the new EMF31 Trip 2 setpoint per 4.4.8.1
below. This setpoint must be above the ENF reading.
4. Evaluate this setpoint for multiple releases in
progress per Enclosure 5.1 step G or have Operations
secure any other release in progress.
5. Have Operations record the totalizer reading, rezero
the totalizer, and close out the current TBS LWR.
6. Have Operations reset E!!F Trip 2 setpoint and give
them permission to initiate a new release without LWR
paperwork to prevent overflowing of the sump.
Operations shall keep track of the volume from the
start of the release.
7. Generate a new LWR for the TBS as soon as possible and
reinitiate any secured releases from other sources,
ensuring multiple release calculations are performed
(Enclosure 5.1, Step G).
4.4.1 Obtain a representative sample of the TBS per
RP/00/1009/18 Enclosure 5.2, Sampling Instructions.
4.4.2 Analyze 3500 ml sample for principal gamma emitters and
tritium per Reference 2.7.
NOTE 1: Label and retain this sample for weekly
compositing.

4.4.3
-9-
NOTE 2: During a 1° to 2° leak Radwaste Chemistry may use
portable demineralizers to clean TBS effluent.
In this case samples for release rate
determination shall be obtained from the
demineralizer outlets.
NOTE 3: If EF31 is inoperable, refer to HP/0/B/1009/13
for inoperable action.
Determine the Recommended Release Rate using Enclosure
5.1.
NOTE: If Operations is unwatering the condenser of the
affected unit, ensure that 1RC21 (Unit 1) or
1RC22 (Unit 2) is closed.
4.4.4 Record 1 or 2 EMF31 as the EMF Utilized.
4.4.5 If EMF31 is inoperable, record 1 or 2 EMF31 Inoperable and
N/A for the EMF Expected CPM, Background Reading, and Trip
1 and 2 Setpoints on the Discharge Document. Go to Step
4.4.9.
4.4.6 Obtain the EMF31 reading from the Control Room and record
as the EMF Background Reading on the Discharge Document.
4.4.7 Determine the Expected CPM of the EMF by multiplying the
EMF Correlation Concentration (Cs•137 Equivalent Activity
from HP/0/B/1003/18) times the EMF Correlation Factor from
HP/0/8/1003/08 Enclosure 5.3.
4.4.7.1 Record the value from Step 4.4.6 or 4.4.7
(whichever is greater) as the Expected CPM of the
EMF.
4.4.$ Determine the EHF31 Setpoints as follows, record and sign
the Discharge Document.
4.4.8.1 Trip 2 Setpoint S 6..0E3(#P)
where:
6.0E3 = derived from HP/0/B/1003/08 Enclosure
5.1 Note 181 for 1 RC pump running and
the release rate (f) is 500 gp..
UP = the number of RC pumps dedicated to
the release.

4.4.9
4.4.10
4.4.11
4.4.12
4.4.11.2
4.4.11.3
Once the
4.4.12.1
4.4.12.2
-10-
NOTE 1: Trip 1 shall be greater than background
but less than Trip 2.
NOTE 2: If needed, the maximum Trip 2 setpoint
shall be calculated using
HP/0/B/1003/08 Section 4.4 for 1EMF31
or 2EMF31.
Independently verify the following and sign adjacent to
the performing Health Physics Technician's signature (see
Enclosure 5.2, page 1 of 3).
Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
Recommended Release Rate.
EMF Trip 2 Value.
Take the Discharge Document to the Control Room and notify
Operations to align the TBS for discharge to the RC system.
NOTE: If the TBS flow totalizer is inoperable, notify
Operations to manually calculate the volume
discharged.
Prior to release,
4.4.11.1 Nave Operations rezero the TBS
adjust the EMF31 Setpoints and
ENT Log Book.
Open the compo
Unlock i 147.
release has started and daily,
Check the operation of the flow totalizer by
observing an appropriate change in the totalizer
count when compared to the actual release rate.
Check the operation of the composite sampler by
observing sample collection or a change in the
composite jug level.
flow totalizer
record in the
e sampler isolation valve.
I.V.
Trip

-11-
NOTE 1: If the flow totalizer or composite
sampler is inoperable, refer to
HP/O/B/1009/13 and H.P. Manual Section
13.6.
NOTE 2: pH adjust the composite sample per
reference 2.4 step 4.7.
NOTE 3: If Operations is unwatering the
condenser of the contaminated unit,
sample the WU system at the following
frequency.
a. Once the TBS pumps are aligned to
RC and then once per 12 hours.
b. One hour after the initiation of
any WMT or CVUCDT release.
Obtain the sample for the affected WU
system, at Column 1H27 (valve 1WU18) or
Column 2H27 (valve 2WU18) located in
the Turbine Building Basement.
4.4.12.3 Obtain a grab sample at least once per 24 hours.
4.4.12.4 Analyze 3500 ■1 sample for principal gamma
emitters and tritium.
4.4.12.5 If the sample results indicate a new isotope, an
isotope disappears or the concentration of any
isotope changes by a factor of 10, generate a new
LWR per 4.4.3 through 4.4.10. Go to 4.4.12.7.
4.4.12.6 If the current LWR is to continue, continue step
4.4.12.
4.4.12.7 Closeout the current LWR by ensuring the volume
discharged is recorded and Operations rezeros the
flow totalizer.
4.4.12.8 Perform steps 4.4.14 and 4.4.15.
4.4.12.9 Continue step 4.4.12.

-12-
4.4.13 When the release is terminated,
4.4.13.1 Lock close WM47.
4.4.13.2 Close the composite sampler isolation valve.
4.4.13.3 Collect any water from the composite sampler.
4.4.13.4 Have Operations return EMF31 Setpoints to the
values in HP/0/B/1003/08 Enclosure 5.1. Record
in the EMF Log Book. I.V. Trip
4.4.14 Review tie LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.4.15 Record release information on PT/0/B/4600/18 Enclosure
13.9 and composite as per reference 2.4.
4.5 RMC Review and QA Check
4.5.1 Compare the computer isotopic input sheet or manual
calculation worksheet with the sample results used to
calculate the release rate.
4.5.2 After any errors have been corrected using Enclosure 5.4,
sign the LWR as Reviewed by RMC.
4.5.3 After the volume update of the LWR, a final QA check shall
be performed to ensure the correct volume, start/stop time
and date was entered. Use Enclosure 5.4 to correct any
errors.
5.0 Enclosures
5.1 Release Rate Deteruinatio
5.2 Release Rate Determination Fors
5.3 Manual Calculations
5.4 Liquid Error Correction Request.

RELEASE RATE DETERMINATION
Computer Method
HP/0/8/1003/02
Enclosure 5.1
Page 1 of 3
NOTE 1: An LWR number shall be assigned by the computer; verify in the
GWR/LWR Log Book that the correct LWR cumber has been assigned.
If this number is not correct, use the back-up procedure
(Section II fo this Enclosure) assigning the higher LWR# (from
VAX or GWR/LWR Log). Investigate discrepancy as soon as
possible.
A. Use Reference 2.1 and enter the isotopic analysis results, tritium,
boron, and current Teledyne analysis results. Independently verify
and sign the computer isotopic input sheet (see Enclosure 5.2, page
3 of 3).
NOTE: The computer does not calculate the release rate based on
boron.
B. Attach the computer input sheet to the isotopic analysis.
C. If required, record the Boron concentration on the Discharge Document
and if Boron a 1000 ppm, calculate the Instantaneous Release Rate
(fB) based on Boron Concentration as follows.
(#RC Pumps Running) (2.5E5 gpa/puap)(1
SB
#RC Pumps Running = obtained from Control Room (1-8 pumps)
LB = ppm Boron in Lake. This value (current to
within 6 weeks of release date, and less than 1
ppm) is obtained from Chemistry and monthly is
posted in the Shift Lab.
SB = ppm Boron in the sample
D. Release rate calculations based on Hydrazine are not required; eater
N/A.
E. Record the
System Release Rate or the calculated !lost
Restrictive Instantaneous Release Rate based on the number of RC
pumps required (whichever is less) as the Recommended Release Rate.

RP/0/B/1003/02
Enclosure 5.1
Page 2 of 3
xOTZ: Unless the tank discharge flowrate is manually restricted,
the Maximum System Release Rates are as follows:
WMT = 120 gpm
RMT : 120 gpm
TBS = 500 gpm
CVUCDT = 120 gpm
F. Record Tank Concentration, Dilution Flow Available, or Maximum System
Release Rate as Release Limited By.
G. When performing multiple releases (i.e., WMT/RMT, TBS, CVUCDT) a
calculation shall be performed to assure that MPC levels are not
exceeded.
1. Determine the number of RC Pumps required for each release
point. The total #RC pumps required for all releases shall not
exceed 8.
2. Perform calculations to assure that MPC levels are not exceeded
as follows. Record on the LWR.
or RMT
example: 120 + 500 + 500 + 120
500 1E4 1E5 8E3 '4E3
where:
120
.34
< 1
CVUCDT
a Recommended Release Rate
= Most Restrictive Instantaneous Release Rate based on
the number of RC pumps required for each release point.
The total #RC pumps required for all releases shall
not exceed 8.
NOTE: If sufficient dilution flow is not available to
discharje sources simultaneously, one or .ore of the
release rates (fREC) may be manually reduced or the
CVUCDT may be sent to the Floor Drain Tank. Dilution
flow shall first be allocated to the TBS, second to
the WMT or RMT and third to the CVUCDT.

HP/0/8/1003/02
Enclosure 5.1
Page 3 of 3
Also perform the following calculation and record on the LWR.
# P used for TBS Trip 2 sp t # P used for CVUCDT Trip 2 sp
# P available
example:
1-TBS
0
#P available
t 2 t 1.5
t
-TBS 81-CVUCDT 82-CVUCDT
#P used for WMT
#P available
where: # P available = # RC pumps running
The total # RC pumps used for all releases shall not exceed 8.
The information on the Release Rate Determination Form (Enclosure
5.2, page 2 of 2) labeled "To Be Completed Prior To Release" may be
entered and signed off by Health Physics, Chemistry or Operations
rather than the Shift Supervisor.
II. Back-up Procedure; G.O. VAX Computer Method
A. Use this procedure section if the Station VAX is inoperable. This
method does not enter the release on the McGuire Liquid Release
Program or assign an LWR number. When the Station VAX is operable
again, enter all releases done on the G.O. VAX on the Station VAX,
chronological order prior to entering any new releases.
B. Record the LWR number in the GWR/LWR Log Book.
C. Perform Enclosure 5.1 Section I. Steps A through H.
III. Manual Method
A. Use this procedure section if the Station VAX and G.O. VAX are
inoperable/unavailable.
B. Calculate the release rates using Enclosure 5.3, page 1,2,3 of 5.
Record results on Enclosure 5.3 page 4. Independently verify and sign the
Manual Calculation Worksheet (see Enclosure 5.3, page 2 of 5).
NOTE: Ensure Tritium and current Teledyne analysis results are
included.
C. Perform Enclosure 5.1 Section I. Steps C through H and attach the
Manual Calculation worksheet to the isotopic analysis.

Enclosure 5.2
Page 1 of 3
A.
[MR// Tank
Tank Level Before Release x,
Special Instruction(s) and/or Permiss
Date Time
Desired Tank Level After Release
n for this Release
RELEASE RATE DETERMINATION -
TANK CONC.
NCi/sl
Instantaneous Release Rate
1. Fission & Activation Products
2. Tritium Concentration
3. Dissolved & Entrained Gases
4. Gross Alpha Concentration
5. Boron Concentration (ppm)
NOTE: Release Rate Calculation
Required Yes No
If yes, List
6. Hydrazine Concentration
NOTE: Release Rate Calculation
Required Yes No
If yes, List
0.00E+00
0.00E+00
0.00E+00
0.00E+00
cGUIRE NUCLEAR STATION
TANK DISCHARGE RATE IN GPM
1 Pump 2 Pumps 3 Pumps 4 Pumps 5 Pumps 6 Pumps 7 Pumps 8 Pus
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.,50E+02 1.50E+02 1.50E
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E
Recommended Release Rate GPM with RC pumps
Release Limited By
EMF Utilized
EMF Correlation Concentration
(Fission and Activation Products)
Expected CPM of the EMF
EMF Background heading
EMF Trip 2 Setpoint
EMF Trip 1 Setpoint
Health Physics Technician
Date Time
NCi/m1
CPM
CPM
CPM
CPM
Reviewed by INC:
Date:
I.V.
Date
Time

Enclosure 5.2
Page 2 of 3
Shift Supervisor Authorizing Release
To Be Completed Prior To Release
(Signature
To Be Completed After Release
Initial, Initial
EMF Operable and Alarm (Trip 1) Set at CPM Recorder Stamped - LWR# Stop
EMF Trip 2 Set at CPM Time/Date Release Secured
No. of RC pumps operating Tank Level After Release
Recorder Stamped - LWR# at Start Commence Flush per Procedure OP/Q/B/62
Time/Date Release Started Procedure OP/©/B/6400/43
Flush Secured
Volume Release
Completion of Release Acknowledged
By Shift Supervisor
Date:
Time:
Gallons
Shift H.P. Review
Date:
Time:
(Signature)
(Signature)

HP/0/B/1003/02
Enclosure 5.2
Page 3 of 3
EXAMPLE: COMPUTER ISOTOPIC INPUT SHEET
System Rev-1.0 VAX/VMS Rev 4.1
Username: RWD7320
Password:
Welcome to VAX/VMS - Duke Power Company
Enter Name of Program: MGLIQUID
THIS RELEASE NUMBER IS 0081
IS THIS THE CORRECT LWR#? (Y/N)
Y
PLEASE ENTER THE TYPE OF RELEASE
EXAMPLE: RMT-A, RMT-B, WMT-A, WMT-B, 1-CVUCDT, 2-CCDT
WC, SPARE, 1-TBS, 2-TBS
1-CVUCDT
ENTER RADIONUCLIDE NAME
XE-133
ENTER CONCENTRATION
4.01E-5
ENTER RADIONUCLIDE NAME
CO-60
ENTER CONCENTRATION
3.51E-6
ENTER RADIOSOCLIIX RAM
STOP
CO-60 3.511-6
XE-133 4.01E-5
ARE THESE VALUES CORRECT? (Y/N)
Y
BETA -GAMMA TOTAL = 3.51E-6
ENTER NAME OF PERSON RUNNING REPORT
H. SLOAN I.V.

MANUAL CALCULATIONS
Fissiomr-aad Activation Products
a. Total all isotopic concentration (NCi/ml)
NOTE 1:
NOTE 2:
b. Calculate
HP/0/B/1003/02
Enclosure 5.3
Page 1 of 5
Tritium, dissolved and entrained gases, and gross alpha
concentrations are to be included as valid isotopes in
addition'to their separate concentration calculations.
Tritium is not to be included in the sum for EMT'
correlation concentration.
release rate in GPM for conditions when 1 - 8 RC pumps ° are
in service for dilution using the following formula:
(P) (2.5E+5)
Where:
2.5E+5 = gpm per RC pump
P = number of pumps operating
v = recirculation factor at equilibrium = 2.4
C. = the concentration of radionuclide, i, in undiluted
effluent as determined by laboratory analysis in
pCi/ml.
MPC1 the concentration of radionuclide, i, from 10CFR20,
appendix B. Table II, column 2 or Enclosure 5.3 page
3 of 5.
Tritium Concentration
a. Use same basic formula as in fission and activation products, except:
C fa the concentration of tritium, i, in diluted effluent as
determined by laboratory analysis, in NCi/al
for tritium, value It 3.0E-3
Dissolved and entrained gases
a. Use same basic formula as
activation products, except:
MPCi = 2.0E-4 NCi/al for all dissolved and entrained noble gases.
4. Gross alpha concentrations
a. Use same basic formula as in fission and activation products, except:
MPC1 = 3.0E-8 NCi/ml for gross alpha concentrations.
fission and

MANUAL CALCULATIONS WORKSHEET
Flagon and Activation Products
Isotope
C. MPC.
(P)(2.5E+5)
(2.4) +c Ci
MPC.
i
2. Tritium: C.
MPC. — 3.0E-3
(P)(2.5E+5)
(2.4) f Ci
Total
HP/O/B/1003/02
Enclosure 5.3
Page 2 of 5
Dissolved and Entrained Gases: C
Isotope
f
ci
= (P)(2.5
(2.4) B C
i=1
4. Gross Alpha: Ci
MPC. 3.0E-
(P)(2.5E+5)
(2.4)! ci
MPC
MPCi
2.0E-4
2.0E-4
2.0E-4
2.0E-4
2.0E-4
Total.
Performed by
i=1
ci
Ci
I.V.

HP/0/B/1003/02
Enclosure 5.3
Page 3 of 5
MPC. VALUES FROM 10CFR20
TRITIUM 3.00E-03 NB-95 1.00E-04 CS-138 3,00E-06
ALPHA ACT 3.00E-08 NB-95M 3.00E-06 BA-133 3.00E-06
BE-7 2.00E-03 NB-97 9.00E-04 BA-139 3,00E-06
F-18 5.00E-04 NB-97M 3.00E-06 BA-140 2,00E-05
NA-24 3.00E-05 MO-99 4.00E-05 BA-141 3,00E-06
CL-38 4.00E-04 TC-99M 3.00E-03 BA-142 3,00E-06
K-40 1.00E+130 TC-101 3.00E-06 LA-140 2.00E-05
CR-51 2.00E-03 RU-103 8.00E-05 LA-142 3.00E-06
MN-54 1.00E-04 RU-105 1.00E-04 CE-141 9.00E-05
MN-56 1.00E-04 RU-106 1.00E-05 CE-143 4,00E-05
FE-55 8.00E-04 AG-108M 3.00E-06 CE-144 1,00E-05
FE-59 5.00E-05 AG-110M 3.00E-05 PR-143 5,00E-05
CO-57 4.00E-04 CD-115 3.00E-05 PR-144 3,00E-06
CO-58 9.00E-05 CD-115M 3.00E-05 ND-147 6,00E-05
CO-60 3.00E-05 IN-113H 1.00E-03 W-187 6.00E-05
NI-63 3.00E-05 IN-115M 4.00E-04 BI-212 4.00E-04
NI-65 1.00E-04 I-130 3.00E-06 BI-214 3,00E-06
CU-64 2.00E-04 I-131 3.00E-07 PB-212 2,00E-05
ZN-65 1.00E-04 I-132 8.00E-06 PB-214 3,00E-06
ZN-69 2.00E-03 I-133 1.00E-06 TL-208 7.00E-06
ZN-69M 6.00E-05 I-134 2.00E-05 AC-228 9,00E-05
SE-75 3.00E-04 I-135 4.00E-06 TH-228 7.00E-06
BR-82 4.00E-05 SB-122 3.00E-05 NP-239 1.00E-04
BR-83 3.00E-06 SB-124 2.00E-05 AR-41 2.00E-04
BR-84 3.00E-06 SB-125 1.00E-04 KR-83M 2.00E-04
BR-85 3.00E-06 SN-113 8.00E-05 KR-85 2.00E-04
RB-86 2.00E-05 SN-123 3.00E-06 KR-85M 2.00E-04
RB-88 3.00E-06 SN-126 3.00E-06 KR-87 2.00E-04
RB-89 3.00E-06 TE-125M 1.00E-04 KR-88 2.00E-04
SR-89 3.00E-06 TE-127 2.00E-04 KR-89 2.00E-04
SR-90 3.00E-07 TE-127M 5.00E-05 KR-90 2.00E-04
SR-91 5.0M-05 TE-129 8.00E-04 XE-131M 2.00E-04
SR-92 CASK-05 TE-129M 2.00E-05 XE-133 2.00E-04
Y-90 E41111-05 TE-131 3.00E-06 X8-133H 2.00E-04
Y-91 3.0111-03 TE-131M 4.00E-)5 a 135 2.00E-0
4
Y-91M 3.01W03 TE-132 2.00E-05 XE•135M 2.00E-04
Y-92 6.00E-05 TE-134 3.00E-06 XE•137 2.00E-04
Y-93 3.00E-05 CS-134 9.00E-06 XE•138 2,00E-04
ZR-95 6.00E-,5 CS-136 6.00E-05
ZR-97 2.00E-05 CS-137 2.00E-05

11{ / V/ L IvvJ/ VL
Enclosure 5.3
Page 4 of 5
A. Instantaneous Release Rate
1. Fission & Activation Products
2. Tritium Concentration
3. Dissolved & Entrained Gases
4. Gross Alpha Concentration
5. Boron Concentration (ppm)
NOTE: Release Rate Calculation
Required Yes No
If yes, List
6. Hydrazine Concentration
NOTE: Release Rate Calculation
Required Yes No
If yes, List
Recommended Release Rate
Release Limited By
EMF Utilized
EMF Correlation Concentration
(Fission and Activation Products)
Expected CPH of the EMF
EMF Background Reading
EMF Trip 2 Setpoint
EMF Trip 1 Setpoint
Health Physics Technician
Date Time
GWR# Tank
Tank Level Before Release % Desired Tank Level After Release %
Special Instructions) and/or Permission for this Release
Date Time
MANUAL RELEASE RATE DETERMINATION - McGUIRE NUCLEAR STATION
TANK CONC.
NCi/ml
TANK DISCHARGE RATE IN GPM
2 Pumps 3 Pumps 4 Pumps 5 Pumps 6 Pi ps 7 Pumps 8 Pt
GPM with RC pumps
NCi/m1
CPM
CPM
CPM
CPM
Reviewed by WIC:
I.V.
Date
Date:
Time

Enclosure 5.3
Page 5 of 5
Shift Supervisor Authorizing Release
To Re Completed Prior To Release
Initial
(Signature)
ENF Operable and Alarm (Trip 1) Set at CPH
EHF Trip 2 Set at CPH
No. of CCW pumps operating
Recorder Stamped - LWR# at Start
Time/Date Release Started
To Be Completed After Release
Initial
Recorder Stamped - LWR# Stop
Time/Date Release Secured
Tank/Level After Release
Commence Flush per Procedure OP/O/B/62©0/35 or
Procedure OP/O/B/6400/43
Flush Secured
Volume Release Gallons
Completion of Release Acknowledged
By Shift Supervisor
Date:
Time:
Shift H.P. Review
Date:
Time:
(Signature)
(Signature)

Form 34629 (R11-84)
Liquid Re!
Type of Release
Release Rate
LIQUID ERROR CORRECTION REQUEST
STATION
(Actual(
ERRORS:
Name
Effective 1.1.85
RP/©/B/1003/Cs:
Enclosure 5.4
Date/Time
(Making Error)
(Of Release)
Entered as
Should be Should be
Entered as Entered as
Should be Should be
Corrected Bets -Gamma Total (if applicable) µCi/ml (See Back For Additional
Corrected Noble Gas Total (if applicable) Information)
µCi/ml
Notified
Entered as
(Name)
at
(Time) (Date)
of error request.
Error correction request mailed to the Radioactive Waste Management Group at the General Office by
for correction.
(Name) (Date)
...........................FORGENERALOFFICE USE ONLY ••• ••••.•••••••••••••••..
Above errors corrected and request returned to originator by
on
(Date)
(Name
COMMENTS:
• s ♦ * • • ♦ • • • • s • • • • • • • • • • • * • • • •.♦ ♦ s • ♦ • • * • s • * * • • • • • • • ♦ • • * . * * • • • ♦ • • • • • • • • • • • • • • * • .. .. * . . . .
COPY DISTRIBUTION:
Original • To Radioactive Waste Management Group then to applicable release file when corrected.
Canary Copy • Retained at General Office
Pink Copy • To be filed in outstanding error log book
Goldenrod Copy • To be filed temporarily with applicable release file

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PUKE POWER COMPANY
NUCLEAR PRODUCTION DEPARTMENT
ay. opx 33189, 422 SOUTH CHURCH STREET
CHARLOTTE, N.G. 28242
[phone]
February 28, 1986
Mr. D. Rex Gleason, P.E.
Water Quality Regional Engineer
North Carolina Department of Natural
Resources and Community Development
Division of Environmental Management
919 North Main Street
Mooresville, NC 28115
SUBJECT: McGuire Nuclear Station
Use of Biocide
Containment Spray Heat Exchanger
File: MN-208.38, 702.12, 730.65
Dear Sir:
On November 27, 1985, we requested permission to use a
biocide, Calgon H-106 in the containment spray (NS)
heat exchangers at McGuire Nuclear Station to assist in
cleaning the exchangers and to restore their efficiency
and ensure their operability. Should the efficiency
deteriorate excessively, the unit(s) would have to be
shut down.
In providing approval to use the biocide, you requested
a report on the chemical(s) used, the amount of the
chemical(s) used, and the discharge concentration.
Attached is a listing of the heat exchangers cleaned,
the chemicals used, the amount of the chemical, and the
maximum discharge concentration as well as flow rates.
Also attached is a short description of each chemical.
As can be seen, the biocide was used in only two (2) of
the heat exchangers. We found that equal or better
cleaning was obtained by using surfactants, penetrants,
and disperants for this particular fouling. Biocides
may be more effective on other types of fouling.
Only three of the four heat exchangers were cleaned at
this time. It may be necessary in the future to clean
the fourth heat exchanger and/or to reclean one that
was cleaned at this time. If a biocide is needed in a
future cleaning, we will contact you for approval.

Mr. D. Rex Gleason, P.E.
February 28, 1986
Page Two
Should you have any questions or desire additional
information, please contact me at [phone].
Sincerely,
R. T. Simril, System Engineer
Nuclear Environmental Compliance
WTG : h j p
Attachments
cc: W.A. Haller
R.W. Eaker
P.W. Downing
W.M. Suslick
MN-2002.02
MN-2002.03-04

HEAT EXCHANGER CLEANINGS
HX. # Chem. Flush Time Length CCW Flow Max. Dischg.
Date Time H.X. Vol., Chemical Used. Rate, gpm of ➢isch. min. Rate, gpm Conc. ppm
gal.
12/12/85 1330 "lA" NS 4,000 H-106 4.3 5,000
12/12/85 2000 "lA" NS 4,000 PCL-2000 5.2 5,000
12/31/85
12/31/85
1430 "lA" NS 4,000 H-106
1430 "lA" NS 4,000 CL-361
4.3 2,250
4.5 2,250
1/6/86 2300 "lA" NS 4,000 CL-361 4.5 5,000
1/6/86 2300 "lA" NS 4,000 PCL-2000 10.4 5,000
0.8 2,032,000 0.32
0.8 2,032,000 0.38
1.8 2,032,000 0.14
1.8 2,032,000 0.15
0.8 2,032,000 0.33
0.8 2,032,000 0.77
1/14/86 1000 "lA" NS 4,000 TSP 150 33 120 1,883,000 0.079
1/14/86 1000 "lA" NS 4,000 Triton X-100 7.1 33 120 1,883,000 0.0037
1/14/86 1000 "lA" NS 4,000 PCL-2000 5.2 33 120 1,883,000 0.0027
1/27/86 0830 "213" NS 4,000 TSP 150 200 20 2,032,000 0.44
1/27/86 0830 "213" NS 4,000 Triton X-100 4.7 200 20 2,032,000 0.014
1/27/86 0830 "213" NS 4,000 PCL-2000 5.2 200 20 2,032,000 0.015
2/5/86 0900 "2B" NS 4,000 TSP 150 33 120 2,032,000 0.073
2/5/86 0900 "213" NS 4,000 Triton X-100 7.1 33 120 2,032,000 0.0035
2/5/86 0900 "2B" NS 4,000 PCL-2000 5.2 33 120 2,032,000 0.0025
2/12/86 0900 "2A" NS 4,000 TSP 150 33 120 1,948,000 0.076
2/12/86 0900 "2A" NS 4,000 Triton X-100 7.1 33 120 1,948,000 0.0036
2/12/86 0900 "2A" NS 4,000 PCL-2000 5.2 33 120 1,948,000 0.0026

Definition of Chemicals
H-106 - Calgon H-106 Microbiocide (a quaternary ammonium
biocide)
PCL-2000 - Calgon Powergaurd 2000 (an anionic, polyacyrlic
acid dispersant/scale inhibitor)
CL-361 - Calgon CL-361 Deposit Inhibitor (a blend of
penetrants, surfactants, and dispersants)
Triton X-100 - Rohm & Haas Triton X-100 (a non-ionic, poly -
ether alcohol surfactant/detergent)
TSP - Trisodium Phosphate

April 14, 1986
ater Quality Section
South Piedmont Regional Office
N.C. Department of Natural Resources
and Community Development
Division of Environmental Management
919 North Main Street
Mooresville, NC 28115
SUBJECT: Turbine Building Sump Release
Radwaste Discharge Point
File: MC-704.15
Dear Mr. Horne:
During your inspection at McGuire Nuclear Station on
March 27, 1986, you requested information concerning
releasing the turbine building sump through the
radwaste release point. Attached, for your
information, is a copy of the station procedure,
Radioactive Liquid Waste Release. Section 4.4 is the
procedure for releasing the turbine building sump.
During the inspection, as you may recall, we stated
that we were limited by NRC on the release of specific
radioisotopes as well as total radiation. Section 3.3
of the attached procedure addresses this. Enclosure
5.3, Manual Calculations, is the method for calculating
the amount of activity that is released. As you can
see, for each isotope, the isotopic concentration
( PCi/ml) is divided by the maximum permissible
concentration (MPC,pCi/ml); all isotopic concentrations
are then totalled. The release rate is then calculated
to ensure sufficient dilution.
Should you have any additional questions, please
contact me at [phone].
Sincerely,
R.T. Simril, System Engineer
Nuclear Environmental Compliance
oil Li
by: W.T. Griffin
Environmental Engineer
WTG/rhm
attachment

V . C©,y
RECEIVED
(7) APPROVED BY
Form 34731 (R8.85)
PREPARATION
(2) STATION
Masora Nuclear Station
(3) PROCEDURE TITLE
7 1986
b.
Radioactive Liquid Waste Release (LWR)
ID NoHP/0/B/1003/0,
Change(%) 0 to
's Incorporated
(4) PREPARED BY
(5) REVIEWED BY
Cross -Disciplinary Review By
(6) TEMPORARY APPROVAL (If Necessary)
By (SRO) Date
By Date
DATE
DATE /! Z7
DATE
A.44„..iefr
N/R LUFre
(8) MISCELLANEOUS
Approved By!" �*rrr� Date
Reviewed/Approved By Date
(9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, are included.
Attach additional pages, if necessary.) ©ADDITIONAL CHANGES INCLUDED.
COMPLETION
(10) COMPARED WITH CONTROL COPY DATE
(11) DATE(S) PERFORMED
(12) PROCEDURE COMPLETION VERIFICATION
C Vas 0 N/A Check um and/er blanks properly initialed, signed. dated or filled in N/A or N/R, as appropriate?
C Yes 0 N/A Lieu f'aia Anal attached?
C Yes © N/A 0111111 dims shacked, completed, dated and signed?
C Yes © N/A a'ilk SNOW eta. attached and properly dated, identified and marked?
© Yas ©N/A Astai Lance criteria reset?
VERIFIED BY DATE
(13) PROCEDURE COMPLETION APPROVED DATE
(14) REMARKS (Attach additional pages, if necessary.)

HP/0/B/1003/02
DUKE POWER COMPANY
McGUIRE NUCLEAR STATION
RADIOACTIVE LIQUID WASTE RELEASE (LWR)
1.0 Purpose
This procedure describes the proper method of sampling, initiating and
documenting a radioactive liquid release from a Waste Monitor Tank (WMT)
or Recycle Monitor Tank (RMT), Containment Ventilation Unit Condensate
Drain Tank (CVUCDT), or Turbine Building Sump (TBS) to the RC System.
2.0 References
2.1 Duke Power Company, McGuire Nuclear Station, Liquid and Gaseous
Radwaste Computer Program User's Documentation.
2.2 McGuire Nuclear Station, Technical Specifications 3.11.1.1
2.3 Station Health Physics Manual, Section 13.5: Preparation of Sample
for Count Room Analysis.
2.4 Station Health Physics Manual, Section 13.6; Composite Sampling.
2.5 HP/0/B/1003/08, Determination of Radiation Monitor Setpoints (EMF's).
2.6 HP/0/B/1009/13, Health Physics Actions for Inoperable Liquid Effluent
Monitoring and Sampling Devices.
2.7 PT/0/B/4600/18, Radioactive Liquid
Frequency.
2.8 OP/0/B/6200/35, Radwaste Procedure
Tank to the Environment.
2.9 OP/0/B/6200/43, Radwaste Procedure
Tank to the Environment.
2.10 Code of Federal Regulations, Title
Effluent Sampling and Analysis
for Dischar
a Waste Monitor
for Discharging a Recycle Monitor
10, Part 20, Appendix B.
2.11 O /0/1/6200/S6, Radwaste Chemistry Response to Indication of a
Prfrry to Secondary Leak.
2.12 010/1/1/6400/01A, Condenser Circulating Water and Low Level Intake;
Enclosure 4.11, Operation of Turbine Building Sump with High Activity
to RC Discharge.
2.13 OP/0/A/6500/01A, Ventilation Unit Condensate Drain Tank Operation.
3.0 Limits and Precautions
3.1 Proper Health Physics methods shall be used when handling radioactive
or potentially radioactive liquids.

-2-
3.2 All liquid waste release (LWR) and dose calculations shall be made by
use of appropriate computer codes per Reference 2.1. The manual
methods presented shall be used if the computer is not available.
3.3 All releases shall be added to the total quarterly release using the
appropriate computer codes (Reference 2.1) to ensure that quarterly
and annual limits are not exceeded.
3.4 Corrections to the LWR Computer Program after the program has been
terminated shall be handled by the Radioactive Materials Control
Group personnel with assistance from the General Office Radwaste
Engineering staff as necessary.
3.5 If for any reason the EMF, composite sampler, or flow totalizer is
inoperable, refer to HP/0/B/1009/13 for required action.
3.6 Sample analysis results shall be valid for 4 hours for a CVUCDT and
TBS release and 24 hours for a WMT/RMT release from the time sample
was obtained.
3.7 Radwaste Chemistry shall be allowed 3consecutive attempts at
releases via EMF49(L) with Hi-Rad Trips before a resample shall be
required.
3.8 If for any reason the release has to be terminated prior to
completion, the H.P. controlled valve (WM116 for WMT-A, WM43 for
WMT-B, WM222 for 1-CVUCDT, WM225 for 2-CVUCDT, WM47 for TBS) shall be
locked closed.
3.9 Boron analysis shall be performed when the effluent is expected to
contain = 1000 ppm Boron.
3.10 TBS sampling and the release may be terminated when all of the
following are true:
1. No activity (except dissolved and entrained gases) above
background is identified in two consecutive samples.
2. 10 additional sources of activity to the sumps are anticipated.
3. The total activity of dissolved and entrained gases is less than
2.O11-4 Nci/ml.
3.11 Manual adjustments of EMT trip setpoints shall be performed using
HP/0/B/1003/08 Enclosure 5.4.
3.12 Five LWR spares shall be entered on the VAX computer as soon as
possible on the first day of the month.

4.0 Procedure
4.1 For a WMT/RMT' release go to Section 4.2. For CVUCDT release go to
Section 4.3. For a TBS release go to Section 4.4.
4.2 WMT/RMT Release
NOTE 1: Prior to WMT/RMT release read the Limits and Precautions
and Section 4.2 of this procedure.
NOTE 2: This procedure is performed in conjunction with Chemistry
release procedure Reference 2.8 or 2.9.
NOTE 3: If EMF49(L) is inoperable, refer to HP/0/B/1009/13 for
inoperable action.
4.2.1 Determine the Recommend Release Rate using Enclosure 5.1.
4.2.2 Record EMF49(L) as the EMF Utilized.
4.2.3 If EMF49(L) is inoperable, record EMF49(L) Inoperable and
N/A for the EMF Expected CPM, Background Reading, and Trip
1 and 2 Setpoints on the Discharge Document. Go to Step
4.2.5.
4.2.4 Determine the EMF49(L) Setpoints using HP/0/B/1003/18.
Record setpoints and sign the Discharge Document.
4.2.5 Independently verify the following and sign adjacent to
the performing Health Physics Technician's signature (see
Enclosure 5.2, page 1 of 3).
4.2.6
(a) Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
(b) Recommended Release Rate.
(c) EMF Trip 2 Value.
Take the Discharge Document and associated paperwork as
prescribed in the Chemistry release procedure to the
Control Room.
NOTE: The isotopic analysis printout can be replaced
with the computer program MGLIQRPT (Reference
2.1).

-4-
4.2.7 Adjust the EMF49(L) Setpoints, record in the EMF Log Book
and deliver the document to the Operations Shift
Supervisor for appropriate signoffs. I.V. Trip 2
4.2.8 Take the discharge document and Chemistry release
procedure to Radwaste Chemistry personnel (716 Elevation).
NOTE: Ensure that all Health Physics signoffs in the
Chemistry release procedure are completed up to
this point.
4.2.9 As requested by Radwaste Chemistry, complete the Health
Physics portion of the Chemistry release procedure.
4.2.10 After the release is terminated, return EMF49(L) Setpoints
to the values in HP/0/B/1003/08 Enclosure 5.1 and record in
the EMF Log Book. I.V. Trip 2
4.2.11 Review the LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.2.12 Record release information on PT/0/B/4600/18 Enclosure
13.1 and composite the appropriate volume as per reference
2.4.
4.3 CVUCDT Release
4.3.1
At the request of Operations, and after the CVUCDT has
been in recirc for thirty (30) minutes, obtain a Grab
Sample (cube container) from valve 1 or 2 WL403. Allow the
sample line to purge until no air is observed prior to
obtaining sample. Note the composite jug level.
4.3.2 Analyze 3500 ml sample for principal gamma emitters and
tritium per Reference 2.7.
If the composite sampler is inoperable, label and
retain this sample for the weekly compositing and
refer to HP/0/B/1009/13 and H.P. Manual Section
13.6 for inoperable action.
NOTE 2: If EMF44(L) is inoperable, refer to
HP/0/B/1009/13 for inoperable action.

-5-
4.3.3 Determine the Recommended Release Rate using Enclosure 5.1.
4.3.4 Record 1 or 2 EMF44(L) as the EMF Utilized.
4.3.5 If EMF44(L) is inoperable, record 1 or 2 EMF44(L)
Inoperable and N/A for the EMF Expected CPM, Background
Reading, and Trip 1 and 2 Setpoints on the Discharge
Document. Go to Step 4.3.9.
4.3.6 Obtain the EMF44(L) reading from the Control Room and
record as the EMF Background Reading on the Discharge
Document.
4.3.7 Determine the Expected CPM of the OF by multiplying the
EMF Correlation Concentration (Cs-137 Equivalent Activity
from HP/0/B/1003/18) times the EMF Correlation Factor from
HP/O/B/1003/08 Enclosure 5.3.
NOTE: If the EMF Correlation Concentration (Cs-137
Equivalent Activity from HP/O/B/1003/18) is
5.0E-4 pCi/ml, notify the H.P. Shift Supervisor
for approval of the release or send the tank
contents to the Floor Drain Tank.
4.3.7.1 Record the value from Step 4.3.6 or 4.3.7
(whichever is greater) as the Expected CPM of the
EMF.
4.3.8 Determine the EMF44(L) Setpoints as follows, record
setpoints and sign the Discharge Document.
4.3.8.1 Trip 2 Setpoint S 3.0E4 (#P)
where:
3.0E4 = derived from HP/0/B/1003/08 Enclosure
5.1 Note 12B for 1 RC pump running and
the release rate (f) is 120 gpm.
IMP = the number of RC pumps dedicated to
the release
NOTE 1: Trip 1 shall be greater than background
but less than Trip 2.

-6-
NOTE 2: If needed, the maximum Trip 2 setpoint
shall be calculated using
HP/O/B/1003/08 Section 4.2.
4.3.9 Independently verify the following and sign adjacent to
the performing Health Physics Technician's signature (see
Enclosure 5.2, page 1 of 3).
(a) Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
(b) Recommended Release Rate.
(c) EMF Trip 2 Value.
4.3.10 Take the Discharge Document to the Control Room, have
Operations adjust EMF44(L) Setpoints, record in the EMF Log
Book, and deliver the document to the Operations Shift
Supervisor.
NOTE: If the flow totalizer is inoperable, notify
Operations to manually calculate the volume
discharged.
I.V. Trip 2
4.3.11 At the request of Operations, rezero the CVUCDT flow
totalizer, and unlock and open WM222 (Unit 1) or WM225
(Unit 2). Report these actions completed and your name to
Operations.
I.V. WM222 or
2
4.3.12 Record the start date and time, and the LWR # on the
CVUCDT chart recorder (0 WL 5900), initial it and inform
Operations of this action.
4.3.13 Coordinate with Operations to achieve the desired release
rate.
4.3.14 Once the release has started and daily if continuous
release,
4.3.14.1 Check the operation of the flow totalizer by
observing an appropriate change in the totalizer
count when compared to the actual release rate.
4.3.14.2 Check the operation of the composite sampler by
observing sample collection or a change in the
composite jug level.

-7-
NOTE 1: If the flow totalizer or composite
sampler is inoperable, refer to
HP/O/B/1009/13 and H.P. Manual Section
13.6 for action.
NOTE 2: pH adjust the composite sample per
reference 2.4 step 4.7.
4.3.14.3 Obtain a grab sample at least once per 24 hours
by having Operations put the tank in recirc and
obtaining a sample after recirc has been in
progress for thirty (30) minutes.
4.3.14.4 Analyze 3500 ml sample for principal gamma
emitters and tritium.
4.3.14.5 If the sample results indicate a new isotope, an
isotope disappears or the concentration of any
isotope changes by a factor of 10, generate a new
LWR per 4.3.3 through 4.3.10. Go to 4.3.14.7.
4.3.14.6 If the current LWR is to continue, read and
rezero the totalizer reporting the volume to
Operations. Continue step 4.3.14.
4.3.14.7 Close out the current LWR by obtaining the
volume released and rezeroing the flow totalizer.
4.3.14.8 Perform steps 4.3.12 and 4.3.13.
4.3.14.9 Perform steps 4.3.16 and 4.3.17.
4.3.14.10 Continue step 4.3.14.
4.3.15 When notified by Operations that the release is secured,
4.3.15.1 Close and lock WM222 (Unit 1) or WM225 (Unit 2). I.V.
4.3.15.2 Record the totalizer reading for discharge
volume.
4.3.15.3 Record the stop date and time on the CVUCDT
chart recorder and initial it.
4.3.15.4 Report to Operations the volume discharged, WM222
or WM225 is locked closed, and the chart recorder
marked.
4.3.15.5 Ensure that Operations returns 1 or 2 EMF44(L)
Setpoints to the values stated in HP/0/B/1003/08
Enclosure 5.1. Record in the EMF Log Book. I.V. Trip

4.3.15.6 Check the composite jug level to ensure an
adequate amount has been collected.
4.3.16 Review the LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.3.17 Record the required release information on PT/0/B/4600/18,
Enclosure 13.3 and composite as per reference 2.4.
4.4 Turbine Building Sump Release to RC System
NOTE: If EMF31 Trip 2 alarms while discharging to RC, perform
the following:
1. Obtain a sample.
2. Obtain the EMF reading.
3. Calculate the new EMF31 Trip 2 setpoint per 4.4.8.1
below. This setpoint must be above the EMF reading.
4. Evaluate this setpoint for multiple releases in
progress per Enclosure 5.1 step G or have Operations
secure any other release in progress.
5. Have Operations record the totalizer reading, rezero
the totalizer, and close out the current TBS LWR.
6. Have Operations reset EMF Trip 2 setpoint and give
them permission to initiate a new release without LWR
paperwork to prevent overflowing of the sump.
Operations shall keep track of the volume from the
start of the release.
7. Generate a new LWR for the TBS as soon as possible and
reinitiate any secured releases from other sources,
ensuring multiple release calculations are performed
(Enclosure 5.1, Step G).
4.4.1 Obtain a representative sample of the TBS per
HP/0/B/1009/18 Enclosure 5.2, Sampling Instructions.
4.4.2 Analyze 3500 ■1 sample for principal gamma emitters and
tritium per Reference 2.7.
NOTE l: Label and retain this sample for weekly
compositing.

_9_
NOTE 2: During a 1° to 2° leak Radwaste Chemistry may use
portable demineralizers to clean TBS effluent.
In this case samples for release rate
determination shall be obtained from the
demineralizer outlets.
NOTE 3: If EMF31 is inoperable, refer to HP/O/B/1009/13
for inoperable action.
4.4.3 Determine the Recommended Release Rate using Enclosure
5.1.
NOTE: If Operations is unwatering the condenser of the
affected unit, ensure that 1RC21 (Unit 1) or
1RC22 (Unit 2) is closed.
4.4.4 Record 1 or 2 EMF31 as the EMF Utilized.
4.4.5 If EMF31 is inoperable, record 1 or 2 EMF31 Inoperable and
N/A for the EMF Expected CPM, Background Reading, and Trip
1 and 2 Setpoints on the Discharge Document. Go to Step
4.4.9.
4.4.6 Obtain the EMF31 reading from the Control Room and record
as the EMF Background Reading on the Discharge Document.
4.4.7 Determine the Expected CPM of the EMF by multiplying the
EMF Correlation Concentration (Cs-137 Equivalent Activity
from HP/0/8/1003/18) times the EMF Correlation Factor from
HP/O/B/10O3/08 Enclosure 5.3.
4.4.7.1 Record the value from Step 4.4.6 or 4.4.7
(Whichever is greater) as the Expected CPM of the
EMF.
4.4.$ Determine the EMF31 Setpoints as follows, record and sign
the Discharge Document.
4.4.8.1 Trip 2 Setpoint 5 6.0E3(#P)
where:
6.0E3 = derived from HP/O/8/1003/08 Enclosure
5.1 Note 1B1 for 1 RC pump running and
the release rate (f) is 500 gpm.
IMP = the number of RC pumps dedicated to
the release.

4.4.9
-1©-
NOTE 1: Trip 1 shall be greater than background
but less than Trip 2.
NOTE 2: If needed, the maximum Trip 2 setpoint
shall be calculated using
HP/0/B/1003/08 Section 4.4 for 1EMF31
or 2EMF31.
Independently verify the following and sign adjacent to
the performing Health Physics Technician's signature (see
Enclosure 5.2, page 1 of 3).
(a) Any manual calculations such as Boron Release Rate
and Multiple Release Calculations.
(b) Recommended Release Rate.
(c) EMF Trip 2 Value.
4.4.10 Take the Discharge Document to the Control Room and notify
Operations to align the TBS for discharge to the RC system.
NOTE: If the TBS flow totalizer is inoperable, notify
Operations to manually calculate the volume
discharged.
4.4.11 Prior to release,
4.4.11.1 Have Operations rezero the TBS flow totalizer,
adjust the EMF31 Setpoints and record in the
EMF Log Book. I.V. Trip 2
4.4.11.2 Open the composite sastpler isolation valve.
4.4.11.3 Unlock WM47.
4.4.12 Once the release has started and daily,
4.4.12.1 Check the operation of the flow totalizer by
observing an appropriate change in the totalizer
count when compared to the actual release rate.
4.4.12.2 Check the operation of the composite sampler by
observing sample collection or a change in the
composite jug level.

-11-
NOTE 1: If the flow totalizer or composite
sampler is inoperable, refer to
HP/0/B/1009/13 and H.P. Manual Section
13.6.
NOTE 2: pH adjust the composite sample per
reference 2.4 step 4.7.
NOTE 3: If Operations is unwatering the
condenser of the contaminated unit,
sample the WU system at the following
frequency.
a Once the TBS pumps are aligned to
RC and then once per 12 hours.
b. One hour after the initiation of
any WMT or CVUCDT release.
Obtain the sample for the affected WU
system at Column 1H27 (valve 1WU18) or
Column 2H27 (valve 2WU18) located in
the Turbine Building Basement.
4.4.12.3 Obtain a grab sample at least once per 24 hours.
4.4.12.4 Analyze 3500 ml sample for principal gamma
emitters and tritium.
4.4.12.5 If the sample results indicate a new isotope, an
isotope disappears or the concentration of any
isotope changes by a factor of 10, generate a new
LWR per 4.4.3 through 4.4.10. Go to 4.4.12.7.
4.4.12.6 If the current LWR is to continue, continue step
4.4.12.
4.4.12.7 Closeout the current LWR by ensuring the volume
discharged is recorded and Operations rezeros the
flow totalizer.
4.4.12.8 Perform steps 4.4.14 and 4.4.15.
4.4.12.9 Continue step 4.4.12.

-12-
4.4.13 When the release is terminated,
4.4.13.1 Lock close WM47.
4.4.13.2 Close the composite sampler isolation valve.
4.4.13.3 Collect any water from the composite sampler.
4.4.13.4 Have Operations return EMF31 Setpoints to the
values in HP/0/B/1003/08 Enclosure 5.1. Record
in the EMF Log Book. I.V. Trip 2
4.4.14 Review the LWR for complete documentation and sign below
the Shift Supervisor's signature for completion of release.
4.4.15 Record release information on PT/0/B/4600/18 Enclosure
13.9 and composite as per reference 2.4.
4.5 RMC Review and QA Check
4.5.1 Compare the computer isotopic input sheet or manual
calculation worksheet with the sample results used to
calculate the release rate.
4.5.2 After any errors have been corrected using Enclosure 5.4,
sign the LWR as Reviewed by RMC.
4.5.3 After the volume update of the LWR, a final QA check shall
be performed to ensure the correct volume, start/stop time
and date was entered. Use Enclosure 5.4 to correct any
errors.
5.0 Enclosures
5.1 Release Rate Determination
5.2 Release Rate Determination Form
5.3 Manual Calculations
5.4 Liquid Error Correction Request.

RELEASE RATE DETERMINATION
Computer Method
HP/0/8/1003/02
Enclosure 5.1
Page 1 of 3
NOTE 1: An LWR number shall be assigned by the computer; verify in the
GWR/LWR Log Book that the correct LWR number has been assigned.
If this number is not correct, use the back-up procedure
(Section II fo this Enclosure) assigning the higher LWR# (from
VAX or GWR/LWR Log). Investigate discrepancy as soon as
possible.
A. Use Reference 2.1 and enter the isotopic analysis results, tritium,
boron, and current Teledyne analysis results. Independently verify
and sign the computer isotopic input sheet (see Enclosure 5.2, page
3 of 3).
NOTE: The computer does
boron.
0
calculate the release rate based on
B. Attach the computer input sheet to the isotopic analysis.
C. If required, record the Boron concentration on the Discharge Document
and if Boron 1000 ppm, calculate the Instantaneous Release Rate
(f ) based on Boron Concentration as follows.
(#RC Pups R
) (2.5E5 gpm/pump)(1
#RC Pump
SB
= obtained from Control Room (1-8 pumps)
= ppm Boron in Lake. This value (current to
within 6 weeks of release date, and less than 1
ppm) is obtained from Chemistry and monthly is
posted in the Shift Lab.
= ppm Boron in the sample
D. Release rate calculations based on Hydrazine are not required; enter
N/A.
E. Record the Maximum System Release Rate or the calculated Most
Restrictive Instantaneous Release Rate based on the number of RC
pumps required (whichever is less) as the Recommended Release Rate.

HP/0/B/1003/02
Enclosure 5.1
Page 2 of 3
NOT!: Unless the tank discharge flowrate is manually restricted,
the Maximum System Release Rates are as follows:
WMT = 120 gpm
RMT = 120 gpm
TBS = 500 gpm
CVUCDT = 120 gpm
F Record Tank Concentration, Dilution Flow
Release Rate as Release Limited By.
G. When performing multiple releases (i.e.,
calculation shall be performed to assure
exceeded.
Available, or Maximum System
WMT/RMT, TBS, CVUCDT) a
that MPC levels are not
1. Determine the number of RC Pumps required for each release
point. The total #RC pumps required for all releases shall not
exceed 8.
2. Perform calculations to assure that MPC levels are not exceeded
as follows. Record on the LWR.
or RMT
example: 120
500
where:
-T
-TB
500 + 500 + 120 + 120
1E4 1E5 8E3 4E3
Recommended Release Rate
.34
Most Restrictive Instantaneous Release Rate based on
the number of RC pumps required for each release point.
The total #RC pumps required for all releases shall
not exceed 8.
NOTE: If sufficient dilution flow is not available to
discharge sources simultaneously, one or more of the
release rates (fREC) may be manually reduced or the
CVUCDT may be sent to the Floor Drain Tank. Dilution
flow shall first be allocated to the TBS, second to
the WMT or RMT and third to the CVUCDT.

HP/0/B/1003/02
Enclosure 5.1
Page 3 of 3
Also perform the following calculation and record on the LWR.
# P used for TBS Trip 2 sp + # P used for CVUCDT Trip 2 sp
# P available
example:
#P available
+ 0.5
1-TBS 82-TBS 81-CVUCDT 82-CVUCDT+
#P used for WMT
#P available
where: # P available # RC pumps running
The total # RC pumps used for all releases shall not exceed 8.
The information on the Release Rate Determination Form (Enclosure
5.2, page 2 of 2) labeled "To Be Completed Prior To Release" may be
entered and signed off by Health Physics, Chemistry or Operations
rather than the Shift Supervisor.
II. Back-up Procedure; G.O. VAX Computer Method
A. Use this procedure section if the Station VAX is inoperable. This
method does not enter the release on the McGuire Liquid Release
Program or assign an LWR number. When the Station VAX is operable
again, enter all releases done on the G.O. VAX on the Station VAX,
chronological order prior to entering any new releases.
B. Record the LWR number in the GWR/LWR Log Book.
C. Perform Enclosure 5.1 Section I. Steps A through H.
III. Manual Method
A. Use this procedure section if the Station VAX and G.O. VAX are
imparable/unavailable.
B. Calculate the release rates using Enclosure 5.3, page 1,2,3 of 5.
Record results on Enclosure 5.3 page 4. Independently verify and sign the
Manual Calculation Worksheet (see Enclosure 5.3, page 2 of 5).
NOTE: Ensure Tritium and current Teledyne analysis results are
included.
C. Perform Enclosure 5.1 Section I. Steps C through H and attach the
Manual Calculation worksheet to the isotopic analysis.

Ht'/ u/ n/ i vu.10/L
Enclosure 5.2
Page 1 of 3
Expected CPM of the EMF
EMF Background Reading
EMF Trip 2 Setpoint
EMF Trip 1 Setpoint
IMR# Tank
Tank Level Before Release %
Date Time
Desired Tank Level After Release
Special Instruction(s) and/or Permission for this Release
RELEASE RATE DETERMINATION - McGUIRE NUCLEAR STATION
TANK CONC.
NCi/m1
A Instantaneous Release Rate
1. Fission & Activation Products
2. Tritium Concentration
3. Dissolved & Entrained Gases
4. Gross Alpha Concentration
5. Boron Concentration (ppm)
NOTE: Release Rate Calculation
Required Yes No
If yes, List
6. Hydrazine Concentration
NOTE: Release Rate Calculation
Required Yes No
If yes, List
Recommended Release Rate
Release Limited By
EMF Utilized
0.00E+00
0.00E+00
0.00E+00
0.00E+00
TANK DISCHARGE )LATE IN GPM
1 Pump 2 Pumps 3 Pumps 4 Pumps 5 Pumps 6 Pumps 7 Pumps 8 Pump
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+1
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+1
1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+02 1.50E+1
GPM with RC pumps
EMF Correlation Concentration NCi/m1
(Fission and Activation Products)
CPM
CPM
CPM
CPM
Health Physics Technician
Date Time
Reviewed by MC:
Dote:
I.V.
Date
Time

HP/0/R/1003/02
Enclosure 5.2
Page 2 of 3
Shift Supervisor Authorizing Release
To Be Completed Prior To Release
(Signatu
To Be Completed After Release
Initial Initial
EMF Operable and Alarm (Trip 1) Set at CPM Recorder Stamped - LWR# Stop
EMF Trip 2 Set at CPM Time/Date Release Secured
No. of RC pumps operating Tank Level After Release
Recorder Stamped - LW at Start Commence Flush per Procedure OP/O/B/6200/35 or
Time/Date Release Started
Procedure OP/O/B/6400/43
Flush Secured
Volume Release Gallons
Completion of Release Acknowledged
By Shift Supervisor
Date:
Time:
Shift H.P. Review
Date:
Time:
(Signature)
(Signature)

Username:
Password:
HP/0/B/1003/02
Enclosure 5.2
Page 3 of 3
EXAMPLE: COMPUTER ISOTOPIC INPUT SHEET
RWD7320
System Rev-1.0 VAX/VMS Rev 4.1
Welcome to VAX/VMS - Duke Power Company
Enter Name of Program: MGLIQUID
THIS RELEASE NUMBER IS 0081
IS THIS THE CORRECT LWR#? (Y/N)
Y
PLEASE ENTER THE TYPE OF RELEASE
EXAMPLE: RMT-A, RMT-B, WMT-A, WMT-B, 1-CVUCDT, 2-CVUCDT
WC, SPARE, 1-TBS, 2-TBS
1-CVUCDT
ENTER RADIONUCLIDE NAME
XE-133
ENTER CONCENTRATION
4.01E-5
ENTER RADIONUCLIDE NAME
CO-60
ENTER CONCENTRATION
3.51E-6
ENTER RADIO11t1CLIDI MAMR
STOP
CO-60 3.51E-6
XE-133 4.01E-5
ARE THESE VALUES CORRECT?' (Y/N)
Y
BETA -GAMMA TOTAL = 3.51E-6
ENTER NAME OF PERSON RUNNING REPORT
H. SLOAN I.V.

HP/0/B/1003/02
Enclosure 5.3
Page 1 of 5
MANUAL CALCULATIONS
Fissiouraad Activation Products
a. Total all isotopic concentration (NCi/ml)
NOTE 1: Tritium, dissolved and entrained gases, and gross alpha
concentrations are to be included as valid isotopes in
addition to their separate concentration calculations.
NOTE 2: Tritium is not to be included in the sum for EMF
correlation concentration.
b. Calculate release rate in GPM for conditions when 1 - 8 RC pumps are
in service for dilution using the following formula:
(P) (2.5E+5)
Where:
2.5E+5 = gpm per RC pump
P = number of pumps operating
a = recirculation factor at equilibrium = 2.4
C. = the concentration of radionuclide, i, in undiluted
effluent as determined by laboratory analysis in
NCi/ml.
MPC. = the concentration of radionuclide, i, from 10CFR2O,
appendix B. Table II, column 2 or Enclosure 5.3 page
3 of 5.
2. Tritium Concentration
a. Use same basic formula as in fission and activation products, except:
C at the concentration of tritium, i, in diluted effluent as
determined by laboratory analysis, in NCi/ml
i s for tritium value = 3.0E-3
3. Dissolved and entrained gases
a. Use same basic formula as in fission and activation products, except:
MPC. = 2.0E-4 NCi/ml for all dissolved and entrained noble gases.
4. Gross alpha concentrations
a. Use same basic formula as in fission and activation products, except:
MPC. = 3.0E-8 NCi/al for gross alpha concentrations.

HP/0/B/1003/02
Enclosure 5.3
Page 2 of 5
MANUAL CALCULATIONS WORKSHEET
Fisson and Activation Products
Isotope Ci MPC. C.
(P)(2.5E+5)
(2.4)r Ci
i=1 MPCi
2. Tritium: Ci
MPC.
(P)(2.5E+5)
(2.4) / Ci
3.0E-3
Dissolved and Entrained Gases:
Ci .
Isotope
.001.1111111.011011111101111.
4. Gross Alpha: Ci
MPC.
i
Total
MPCi
2.0E-4
2.0E-4
2.0E-4
2.0E-4
2.0E-4
3.0E-8
Total
Performed by
I.V.
C.
i
MPC.
i

HP/0/B/1003/02
Enclosure 5.3
Page 3 of 5
MPC. VALUES FROM 10CFR20
TRITIUM 3.00E-03 NB-95 1.00E-04 CS-138 3.00E-06
ALPHA ACT 3.00E-08 NB-95M 3.00E-06 BA-133 3.00E-06
BE-7 2.00E-03 NB-97 9.00E-04 BA-139 3.00E-06
F-18 5.00E-04 NB-97M 3.00E-06 BA-140 2.00E-05
NA-24 3.00E -05 MO-99 4.00E-05 BA-141 3.00E-06
CL-38 4.00E-04 TC-99M 3.00E-03 BA-142 3.00E-06
K-40 1.00E+00 TC-101 3.00E-06 LA-140 2.00E-05
CR-51 2.00E-03 RU-103 8.00E-05 LA-142 3.00E-06
MN-54 1.00E-04 RU-105 1.00E-04 CE-141 9.00E-05
MN-56 1.00E-04 RU-106 1.00E-05 CE-143 4.00E-05
FE-55 8.00E-04 AG-108M 3.00E-06 CE-144 1.00E-05
FE-59 5.00E-05 AG-110M 3.00E-05 PR-143 5.00E-05
CO-57 4.00E-04 CD-115 3.00E-05 PR-144 3.00E-06
CO-58 9.00E-05 CD-115M 3.00E-05 ND-147 6.00E-05
CO-60 3.00E-05 IN-113M 1.00E-03 W-187 6.00E-05
NI-63 3.00E-05 IN-115M 4.00E-04 BI-212 4.00.E-04
NI-65 1.00E-04 1-130 3.00E-06 BI-214 3.00E-06
CU-64 2.00E-04 1-131 3.00E-07 PB-212 2.00E-05
ZN-65 1.00E-04 1-132 8.00E-06 PB-214 3.00E-06
ZN-69 2.00E-03 1-133 1.00E-06 TL-208 7.00E-06
ZN-69M 6.00E-05 1-134 2.00E-05 AC-228 9.00E-05
SE-75 3.00E-04 I-135 4.00E-06 TH-228 7,00E-06
BR-82 4.00E-05 SB-122 3.00E-05 NP-239 1.00E-04
BR-83 3.00E-06 SB-124 2.00E-05 AR-41 2.00E-04
BR-84 3.00E-06 SB-125 1.00E-04 KR-83M 2.00E-04
BR-85 3.00E-06 SN-113 8.00E-05 KR-85 2.00E-04
RB-86 2.00E-05 SN-123 3.00E-06 KR-85M 2.00E-04
RB-88 3.00E-06 SN-126 3.00E-06 KR-87 2,00E-04
RB-89 3.00E-06 TE-125M 1.00E-04 KR-88 2.00E-04
SR-89 3.00E-06 TE-127 2.00E-04 KR-89 2.00E-04
SR-90 3.001-07 TE-127M 5.00E-05 KR-90 2.00E-04
SR-91 5.0C1-05 TE-129 8.00E-04 XE-131M 2.00E-04
SR-92 6.016-05 TE-129M 2.00E-05 XE-133 2.00E-04
Y-90 3•S-05 TE-131 3.00E-06 XE-133M 2.00E-04
Y-91 3.05 TE-131M 4.00E-05 XE-135 2.00E-04
Y-91M 3.088-03 TE-132 2.00E-05 XE-135M 2.00E-04
Y-92 6.00E-05 TE-134 3.00E-06 XE-137 2.00E-04
Y-93 3.00E-05 CS-134 9.00E-06 XE-138 2.00E-04
ZR-95 6.00E-05 CS-136 6.00E-05
2R-97 2.00E-05 CS-137 2.00E-05

HP/O/B/ Iuu.i/uL
Enclosure 5.3
Page 4 of 5
A. Instantaneous Release Rate
1. Fission & Activation Products
2. Tritium Concentration
3. Dissolved & Entrained Gases
4. Gross Alpha Concentration
5. Boron Concentration (ppm)
NOTE: Release Rate Calculation
Required Yes No
If yes, List
6. Hydrazine Concentration
NOTE: Release Rate Calculation
Required Yes No
If yes, List
LWRI/ Tank Date Time
Tank Level Before Release X Desired Tank Level After Release
Special Instruction(s) and/or Permission for this Release
MANUAL RELEASE RATE DETERMINATION - McGUIRE NUCLEAR STATION
TANK CONC. TANK DISCHARGE RATE IN GPM
NCi/ml 1 Pump 2 Pumps 3 Pumps 4 Pumps 5 Pumps 6 Pumps 7 Pumps 8 Pu m
Recommended Release Rate GPM with RC pumps
Release Limited By
EMF Utilized
EMF Correlation Concentration NCi/ml
(Fission and Activation Products)
Expected CPM of the EMF CPM
EMF Background Reading CPM
EMF Trip 2 Setpoint CPM
EMF Trip 1 Setpoint CPM
Health Physics Technician
Date Time
Reviewed by RMC:
I.V.
Date
Date:
Time

nr/ u/ n/ i vv„ t,,..
Enclosure 5.3
Page 5 of 5
Supervisor Authorizing Release
To Be Co
Prior To Release
(Signature
To Be Completed After Release
Initial Initial
EMF Operable and Alarm (Trip 1) Set at CPN
EMF Trip 2 Set at CPM
No. of CCW pumps operating
Recorder Stamped - LWR# at Start
Time/Date Release Started
Recorder Stamped - LWR# Stop
Time/Date Release Secured
Tank/Level After Release
Commence Flush per Procedure OP/0/0/6200/35 or
Procedure OP/0/B/6400/43
Flush Secured
Volume Release Gallons
Completion of Release Acknowledged
By Shift Supervisor
Date:
Time:
Shift N.P. Review
Date:
Time:
(Signature
(Signature)

Form 34629 (R11-84)
LIQUID ERROR CORRECTION REQUEST
STATION
Liquid Release
Type of Rel
Release Rate
(Actual)
ERRORS:
Entered as
Should be
Entered as
Should be
Name
Effective 1.1.85
HP/0/B/1003/02
Enclosure 5.4
DatefTime
(Making Error)
(Of Release)
Entered es
Should be
Entered as
Should be
Corrected Bets -Gamma Total (if applicable) µCi/ml (See Back For Additional
Information)
Corrected Noble Gas Total (If applicable) µCi/ml
Notified at on of error
request.
(Name) (Time) (©ate) *
Error correction request mailed to the Radictitre Waste Management Group at the General Office by
(Name)
(Date)
for correction.
.FOR GENERAL OFFICE USE ONLY .......................... .
Above errors corrected and request returned to originator by
on
(Date)
(Name)
COMMENTS:
COPY DISTRIBUTION:
Original • To Radioactive Waste Management Group then to applicable release file when corrected.
Canary Copy • Retained at General Office
Pink Copy • To be filed in outstanding error log book
Goldenrod Copy . To be filed temporarily with applicable release file

ALLOCATION APPROVAL FORM
Requeu« No.
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Ag2RL mr 9ER1-1.I1'
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922D m« en2 e<RPI9r q:1LST2S < miPs
E?nT»C
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STAFF REPORT AND RECOMMENDATIONS
Part I - INSPECTION OF PR©POSED/EXISTING WASTEWATER TREATMENT Pi.ANT SITE
1. a. Place visited: Duke Power Company
McGuire Nuclear Station
b. Mailing Address: General Offices
422 South. Church Street
Charlotte, North Carolina 28242
Mecklenburg County
2. Date of Investigation: 8/16/82
3. By: J. Thurman Horne, P. E.
4. a. Persons contacted: Mr.°Rarker. Downing, P. E.
b. Phone No.: 704/373-8779
Date of Report: 9/27/82
0?6
5. Directions to site: From the intersection of Highway 16 and Highway
73, travel east on Highway 73 approximately 3.2 miles. The facility
is on the north (left) side of Highway 73 on the southern shore of
Lake Norman.
6. a. The coordinates to the existing points of effluent discharge
are: Latitude: (Outfall 001) 35°26'10" (Outfall 002 & 003) 35°25'40
Longitude: 80°56'30" 80°57'20
b. USGS Quad No.: F15NW (see attached map)
7. Size (land available for expansion and upgrading): Adequate area is
available for the proposed wastewater treatment plant modifications.
8. Topography: Mildly rolling, 3-10% slopes.
9. Location of nearest dwelling: None within 1000 feet.
10. Receiving Stream: (Outfall 001) - Lake Norman - Class A -II & B
(Outfall 002 & 003) - Catawba River - Class A -II
River Basin and Sub -Basin No.: 03-08-32
Part II - DESCRIPTION OF PROPOSED/EXISTING TREATMENT FACILITIES
1. Existing Facilities: Outfall 001 - Cooling water discharge -
This discharge is a combination of condenser cooling water (1,727,100
gpm - avg.), conventional low pressure service water (6,500 gpd - avg.)
nuclear service water (20,000 gpd - avg.) and low level liquid radwaste
(8 gpd - avg.). The cooling water discharge flows to Lake Norman via
a discharge canal approximately 2,500 feet long and 200 feet wide.

Page Two
©utfall 002 - Conventional Wastewater Treatment System Discharge - This
system treats a non -radioactive waste from the plant with the exception
of domestic wastewater. Wastewater generated by steam generator
blowdown, condensate demineralizer backwashes, water treatment system
backwashes, demineralizer backwashes, building drains, and metal
cleaning wastes are treated in this system.
The facilities consist of a 200,000 gallon initial holding pond, two
settling ponds, installed in parallel, each with 2.5 million gallon
capacity, a 1 million gallon aerated (diffused air) final holding
pond, and final effluent pH adjustment consisting of an automated
CO addition.
The initial holding pond acts as a flow equalization basin. This
pond may be bypassed, depending on the nature of the wastewater.
The two settling ponds are operated such that one pond remains in
standby. Treatment can be enhanced by the addition of coagulant
aids and pH adjustment in these ponds.
The effluent from the settling ponds may be discharged directly to
the receiving stream via outfall 002 or it may be routed to the final
holding pond. Effluent from the final holding pond may be discharged
through outfall 002 or recirculated to the settling ponds, depending
upon effluent quality.
autfall 003 - Wastewater Collection Basin Discharge - The-13.4 acre
wastewater collection basin receives wastewater from the domestic
wastewater treatment system, the overflow from the standby (emergency)
nuclear service water pond, and area surface runoff.
The existing domestic wastewater treatment system consists of an
extended aeration type facility followed by a 200,000 gallon aeration
basin for tertiary treatment.
Note: ©utfall 002 and 003 join at a common point before flowing into
the Catawba River.
2. Proposed Modifications: The existing domestic wastewater treatment
system is to be replaced by a proposed new facility. This facility
will be a 64,000 gpd aerated lagoon (mechanical aerators), divided
into four (4) cells with flexible curtains. The lagoon will be
followed by a chlorine contact chamber, Parshall flume and existing
polishing pond, before discharging into the existing wastewater
collection basin.
Note: Plans, specifications and application for Authorization to
Construct this facility have been submitted and are available
for review in the Permits & Engineering Section.

Page Three
Part III EVALUATION AND RECOMMENDATIONS
1. Performance Evaluation: The facility has a history of non-compliance
with the pH limitations for the discharge from the wastewater collection
basin during the warmer months of the year. This non-compliance
appears to be a result of increased photosynthesis in the basin during
these warmer months. Duke has requested a waiver of the existing pH
limitation.
2. 0 & M Evaluation: The facilities appear to be very well operated and
maintained.
Recommendations and/or Special Conditions: It is recommended that the
Permit be renewed as requested. Although Duke has requested that
their Permit be issued such that only two discharge points are
identified in the Permit, it is our understanding that the Federal
guidelines for this industrial category will not allow this.
As for Dukes request for a waiver of the pH limitation for the
discharge from the wastewater collection basin, the Mooresville
Regional Office recommends that the pH limitations recommended by
Technical Services be included in the Permit. However, considering
that this discharge is essentially domestic wastewater, and
considering the large dilution thAt the discharge will be subject
to (the Catawba River), it is recommended that Technical Services
be requested to re-evaluate the effluent pH limitations for this
discharge. It is our understanding that in cases of sufficient
dilution of domestic dischargers, pH limitations are not necessary.