ML20006E942

Semiannual Effluent Rept for Jul to Dec 1989. W/900214 Ltr

ML20006E942
Person / Time
Site:	Braidwood
Issue date:	12/31/1989
From:	Querio R COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
BW-90-0161, BW-90-161, NUDOCS 9002260572
Download: ML20006E942 (28)

Text

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b m  :* . Commonwoolth Edison  !

-._..., Br;ldwood Nuclear Power Station Houte #1, Bok 84 .

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s. precevlee, Illinois 60.407 j Telephone 815/459-2001 e i

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February 14, 1990 l Bw/90-0161 l Director-of Nuclear Reactor Regulation -

U.S. Nuclear Regulatory Commission Mail Station P1-137

- Washington, D.C. 20555

Subject:

Braidwood Station Operating Report, NRC Dockets STN 50-456 and STN 50-457

' To Whom It May Concern:

Enclosed is the Radioactive Effluent Report for July through December 1989, for Braidwood Nuclear Station. Copies of this report will also be furnished to.the entities listed on the enclosed distribution list.

' Sincerely, t&N R.E. Querio Station Manager Braidwood Nuclear Station REQ /RK/sgr

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c Braidwood Semiannual Radioactive Effluent Release Report- .

Distribution List ,

i in Nuclear Regulatory Commission, Region III u 799 Roosevelt Road

['u Glen Ellyn,'IL 60137 t

L Illinois Department of Nuclear Safety F Office of Nuclear Facility Safety i 1035 Outer Park- Drive Springfield, IL 62704 -

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f l Librarian I - Technical irocessing. u The Exchange,-Suite 245 270 Farmington Ave..

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American Electric Power Service Corp. ,

. Nuclear; Operations Division. 3

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!. Columbus, Ohio 43216 U.S.-Environmental Protection Agency -l Air and Radiation Branch, Region V '

Health Physicist

• 230 S.:Dearborn St.

Chicago, IL'60606,

' Illinois Environmental Protection Agency 'I i- Region III _ DWPC/F05 a

5415 North University  ;

Peoria, IL 61614 '

Illinois, Environmental Protection Agency [

!' Division of Water Pollution Control i Enviromental Protection Specialist  :

2200 Churchill.Rd. i p Springfield, IL 62706  :

' Murray & Trettel, Inc.

Environmental Meteorologist  ;

414 West Frontage Rd.

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.BRAIDWOOD NUCLEAR PIM R STATI0st: 7

SDupaamunas ?TFLUENT REPORT FOR JULY...T0 M7.1989 -

GASEGUS EFFLUENTS - VDIT STACK RELEASES UNIT 1 (Docket Mus6er 56-456)' i h SUf9tATION OF ALL RELEASES  ?

I tseITS ~l JULY I AUG l SEPT I 3rd GUARTERI OCT I NOV I DEC I4th OUARTERl'.

C.

~

Particulate (> 8 day half-life) Releases ,

1. Gross Activity (LLD = *) " Ci < LLD I < LLD < LLD < LLD 1.15E-5 1 1.66E-7 1.15E-6 1.iK-5 l 2. Gross Alpha Activity (LLD=3.70E-18 Ci/el) Ci < LLD ! < LLD < LLD < LLD 4.75E-6 4.82E 1.76E-5 2.12E-5

3.  % of 10CFK20/10CFR50 Limits +

D. Tritium Releases -

1. Total Release ActivitvfLLD=5.21E-12Ci/el)I Ci l 1.66E-1 1 2.24E-1 1 1.11Ed I 1.50Ed I 3.9tE-3 1 1.42E-2 1 2.00E-2 1 3.82E-2 1'

2.  % of 10CFR20/10CFR50 Limits + .

E. Sum of Iodine Particulate (> 8 day half-life), and Tritium Releases

1. Total Activity (LLD = *) I Ci i 1.66E-1 1 2.24E-1 I 1.11Ed I 1.50Ed I 4.26E-3 1 1.42E-2 1 2.00E-2 I 3.85E-2 l'

2.  % of 10CFR20 Limit -

a. Any Oraan (1500 aree/vear) l'  % 1 0.00 1 0.00 1 0.00 1 0.00 1 0.00 I 0.00 l 0.00 1 0.00 l

3.  % of 10CFR50 Limit

a. Guarterl y Any Oraan (7.5 areal  % 0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00

b. Annual Any Oraan (15.0 ares)  % 0.00 0,00 0.00 0.00 0.00 '0.00 0.00 0.00

+ Iodine, particulate, and tritium limits are expressed as a total limit. See Step E.

LLD reflects LLDs for individual isotopes included in calculation.

Results do not include quantity of Sr-89/90 free October through December 1989 - awaiting results from outside vendor.

Updated values will be presented in an errata to the Semi-Annual Report.

2 2985m(020990)

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,. ORAIOWDOD NUCLEAR POE R STATINI .

SOf!AISIUAL EFFLUENT REPORT FOR JULY TO DEEDGER 1989 GASEOUS EFFLUDITS"- VENT STACK RELEASES -

UNIT 1 (Docket Nu d er 50-456)

BATCH MODE I ISIITS I JULY l AUG l SEPT "I 3rd GUARTERI OCT I NOV I DEC I4th GMRTERl-A. Particulate (> 8 day half-life) Releases Mn-54 (LLD = 3.81E-19 Ci/el) Ci ~ 0.00 - .0.00 0.00 0.00 d.00 'O.00 0.00 0.00 Fe-59 (LLD = 1.07E-18 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Co-58 (LLD = 3.33E-19 C1/ ell Ci 0.00 0.00 ~0.00 0.00 0.00 0.00 0.00 5.-00 Co-60 (LLD = 4.80E-19 Ci/ ell Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

$r-89 (LLD =

• 1 Ci ~ 0.00 ~ 0.00 0.00 0.00 0.00 0.00 0.00 'O.00 Sr-90 (LLD = * ) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Y-88 (LLD = 1.60E-18 Ci/ ell Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ~0.00 Ru-103 (LLD = 3.83E-19 C1/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ao-110m (LLD = 3.72E-19 Ci/el) Ci 'O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Cs-134 (LLD = 4.64E-19 Ci/el) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Cs-136 (LLD = 3.48E-19 C1/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Cs-137 (LLD = 3.95E-19 Ci/el) C1 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '

Ba/La-140 (LLD = 1.06E-18 Ci/ ell Cl 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ce-144 (LLD = 2.31E-18 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ~

Others (Specify) .i B. Tritium Releases i

1. Total Release Activity i j (LLD = 5.21E-12 Ci/ ell Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

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• idaiting for results from off-site vendor - data will be presented in an errata to the Seel-Annual Report.

Note: Braidwood monitors for particulates, iodines and tritive via continuous monitoring.

b 3 '

2985e(020990)

BRAIDW0lm telCLEAR POWER STATION .

. SEMIAf0R14L EFFLUENT REPORT FOR .luLY TO DECDEER 1989 '

GASEGUS EFFLUENTS - VENT STACK RELEASES , .

tMIT.1 (Docket Number 56-456) E._,

BATCH MODE I 1811TS 1 JULY l AUG l SEPT I 3rd M1ARTERI OCT I NOV I DEC ~ 14th MIARTER C. Fission and Activation Gas Releases Xe-131e (LLD = 1.2SE-11 Ci/al) C1 3.14E-2 < LLD 7.66E-1 7.97E-1 1.67E-2' < LLD 2.47E-2 4.14E-2 Xe-133e (LLD = 2.64E-12 Ci/el) C1 1.04E-2 < LLD 4.68E-1 4.7K-1 1.12E-2 < LLD 1.46E-2 2.58E-2 Xe-135m (LLD = 3.17E-11 C1/el) Ci < LLD '< LLD < LLD < LLD < LLD < LLD < LLD' < l.LD Xe-133 (LLD = 8.22E-13 Ci/el) C1 2.85E+0 1.32E-1 3.95E+1 4.25E+1 7.89E-1 < L1D- 2.34E+0 3.13E40.

Xe-135. (LLD = 2.82E-13 Ci/el) Ci 7.83E-3 1.17E-3 2.71E-2 1.17E-2 1.50E+0 < LLD 3.25E-3 1.30E+0 '

Kc-85e (LLD = 4.63E-13 C1/ ell Ci 2.17E-4 < LLD < LLD 2.17E-4 < LLD < LLD < LLD < LLD Kr4 (LLD = 8.09E-11 C1/el) Ci 1.82E-2 < LLD~ < LLD 1.82E 2- 1.99E-4 < LLD < LLD 1.99E-4 Kr-87 (LLD = 1.31E-12 C1/el) Ci < LLD < LLD < LLD ' < LLD < LLD < LLD < LLD < LLD Kr-88 (LLD = 1.45E-12 Ci/ ell Ci < LLD < LLD < LLD < LL3 < LLD < LLD < LLD < LLD Ar-41 (LLD = 9.39E-13 Ci/el) C1 6.07E-2 I.56E-2 5.17E-4 7.6E-2 < LLD < LLD 8.32E-3 8.23E-3 Xe-138 fLLD = 1.76E-11 Ci/ ell C1 < LLD- < LLD < LLD < LLD < LLD < LLD < LLD < LLD Others (Specify)

D. Iodine Releases I-131 (LLD = 5.70E-19 Ci/el) Cl 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I-132 (LLD = 3.60E-18 Ci/el)~ Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I-133 (LLD = 5.36E-19 Ci/el) Ci 0.00 'O.00 0.00 0.00 0.00 0.00 0.00 0.00 I-134 (LLD = 1.45E-16 Ci/ ell Cl 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 I-135 (LLD = 4.32E-18 Ci/el1 Cl 0.00 'O 00 0.00 0.00 0.00 0.00 0.00 0.00 Others (Specify)

!I Note: Braidwood monitors for particulates, iodines and tritive via continuous monitoring.

4 2985e(020990)

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BRAIDWOOO NUCLEAR POWER'STATIGI _ _ [..,

- SDf!AleRIAL EFFLUENT REPORT FOR 2iLY TO DECDGER 1.3R1 GASEOUS EFFLUENTS - VENT STAOC RELEASES , ,

UNIT 1 (Docket Neder 50-456) 1 CONTINUOUS MODE-I tseITS I .lulY I AUG' 'I SEPT I 3rd GUARTERl GCT I NDY I DEC I4th OUARTERl-A. Particulate (> 8 day half-life) Releases .

(LLD = 3.81E-19 Ci/el)

Mn-54 Ci < LLD ~ < L8E < LLD < LLD < LLD < LLD < LLD '< LLD Fe-59 (LLD = 1.07E-18 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD < L1D < LLD < LLD Co-58 (LLD = 3.33E-19 C1/ ell' Ci < LLD < LLD < LLD < LLD 1.15E-5 < LLD " 1.11E- 6 1.26E-5 Co-60 (LLD = 4.80E-19 Ci/ ell Ci < LLD < LLD < LLD- < LLD < LLD ~1.66E-7 4.02E-8 2.96E-7 Sr-89 '(LLD =

• 1 C1 - - - - - - - -

Sr-90 (LLD =

• 1 Ci - - - - - - - -

Y-89 (LLD = 1.60E-18 Ci/el) Ci < LLD < LLD < LLD < LLD < LID < LLD < LLD < LLD Ru-103 (LLD = 3.83E-19 C1/ ell Cl < LLD < LLD < LLD < LLD < LLD < LLD < LLD <*LLD Ao-110e (LLD = 3.72E-19 C1/ ell Ci < LLD < LLD < LLD < LLD < LLD' < LLD < LLD < LLD Cs-134 (LLD = 4.64E-19 C1/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD- < LLD Cs-136 (LLD = 3.48E-19 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD ' < LLD -

Cs-137 (LLD = 3.95E-19 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Ba/La-140 (LLD = 1.06E-18 C1/ ell Ci - < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Co-144 (LLD = 2.31E-18 C1/ ell Ci < LLD < LLD < LLD' < LLD < LLD < LLD < L1D < LLD Others (Specify)

8. Tritius Releases

1. Total Release Activity (LLD = 5.21E-12 Ci/ ell Ci 1.66E-1 2.24E-1 1.11E4e 1.50E46 3.98E-3 1.42E-2 2.00E-2 3.82E-2 Waiting for analysis results from outside vendor - Data will be presented in an errata to the Semi-Annual . Report.

5 2985e(020990)

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BRAIDWOtB IEELEAR POtEE STATISI- -

~ SOf!AleIUAL EFFLUDIT REPORT FOR JULY TO DECEMER 1989 GASEOUS EFFLUDITS - VDIT STAOC RELEASES ,_z UIIIT 1 (Docket flumber 50-456)

C0llTIIEUGUS 980DE-I talITS 1 JULY l" AUG 'I SEPT I 3rd M1ARTERI OCT I st(N I- DEC 14thm_"'TERh' >

C. Fission and Activation Gas Releases -

Xe-131e (LLD = 1.2SE-11 Ci/ ell C1' < LLD < LLD < 1.LD < LLD < LLD < LLD' < LLD < LLD' Xe-133e (LLD = 2.64E-12 Ci/el) C1 < LLD < LLD < LLD < LLD < LLD < LLD < L1D < LLD Xe-135m (LLD = 3.17E-11 C1/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < 1,LD '

Xe-133 (LLD = 8.22E-13 C1/el) Ci ~1.25E+1' 8.55E+4 < LLD 2.11E+1 1.85E+1 2.40E+1 2 TF+1 -6. M +1 Xe-135 (LLD = 2.82E-13 Ci/el) Ci < LLD 5.78E+2 4.2 O 2 1.00E+3 2.85E-1' 3.33h8 7.53Ee8 ' 1.'11E+1 Kr-85m (LLD = 4.63E-13 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD '3.33E-2 3.33E-2 Kr-85 iLLD = 8.09E-11 Ci/el) Ci < LLD < LID < LLD < LLD < LLD < L1D < LLD < LLD Kr-87 (LLD = 1.31E-12 Cl/el) Ci < LLD R LLD < LLD < LLD < LLD < LLD < LLD

< LLD' Kr-88 (LLD = 1.45E-12 Ci/ ell

~

Ci < LLD < L1D < LLD < LLD < LLD < LLD < LLD- < LLD Ar-41 (LLD = 9.39E-13 Ci/el) C1 < LLD < LLD < LLD < LLD < LLD < LLD < LLD -( LLD Xe-138 (LLD = 9.28E-11 Ci/el) Ci < LLD < LLD < LtB < LLD < LLD < LLD < LLD < LLD

. Others (Specify)

D. Iodine Releases I I-131 (LLD = 5.70E-19 Ci/ ell Ci 3.37E-6 ~1.81E-5 ~4.13E-5 6.28E-5 4.89E4 1.05E-7 1.57E-6 6.57E-6 I-132 (LLD = 3.6CE-18 Ci/el) Ci < LLD < LLD < LLD < LLD 2.64E-4 < LLD < LLD 2.64E-4 I-133 (LLD = 5.36E-19 Ci/al) Ci < LLD 2.55E-5 4.84E-6 3.03E-5 < LLD < LLD 5.24E-6 5.24E-6 I-134 (LLD = 1.45E-16 Ci/ ell Ci < LLD < LLD < LLD < L1D < LLD ( LLD < LLD < L1D I-135 (LLD = 4.32E-18 Ci/el) 'Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Others (Specify) 6 2985m(020990)

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.,BRAIDWOOD NUCLEAR POWER STATIch

-r SENIAfedUAL EFFLUENT REPORT FOR JULY TO DECDEER .1989 GASEOUS EFFLUENTS *AP9mTION OF ALL RELEASES

. tmIT 2 (Docket Musber 50--457) -

SUNuTION OF ALL RELEASES

'l _tMITS I JULY l AUG l SEPT l 3rd anADTERI OCT 'l NOV I DEC 14th OUARTER .'

A. Fission and Activation Gas Releases.

l Cl 7.31E+1' ~1.38E+1 8.41Ee0 9.53E+1 6.07E+1 4.0SE+1 2.02E+2 3.03E+2

1. Total Release Activity ( LLD = ")

uCi/sec 2.10E+2 1.51E+2 1.21E+2 2AGEe2 2.13E+2 9.31E+1 7.73E+1 2.13E+2

2. Maximum Release Rate

3.  % of 10d x20 Limits"-

dveari  % 0.00 0.00 0.00 0.00 0.01 ~0.00 0.00- 0.01

a. Whole Bodv (S00

% 0.00 0.a0 0.00 0.00 0.01 0.00 0.00 6.01 i b. Skin (3000 M vear)

4.  % of'10CFR50 Limits c.a=== Ouarterlv (5 erad)  % 0.01 0.00 0.00 -0.01 0.01 0.02 0.04 0.07 a.

b. Beta Guarterly (10'erad)

% 0.03 ~0.01 0.00 0.04 0.02 0.04 0.08 0.14' r--- Annual (10 mrad)  % 0.00 0.00 0.00 0.ui 0.00 0.01 0.02 0.03 l-c.

% 0.02 0.00 0.00 0.02 0.01 0.02 0.04 0.07

! d. Beta Annual (20 mrad) l-B. Iodine Releases l ...

1. Total I-131 Activity (LLD=S.70E-19 Ci/ml)1 Ci I 8.10E-6 l 1.33E-S I 1.81E-6 1 2.32E-S I 5.09E-6 1 3.03E-6 l 1.80E-5 1 2.61E-5

2.  % of 10CFR20/10CFRSO Limits +

i

% of 10CFR20 limits is based on the maximum release rate for the period considered.

o Iodine, particulate, and tritium limits are expressed as a total limit. See Step E. .

• o LLD reflects, LLDs for individual isotopes included in calculation.

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WIAIDW0lB NUCLEAR POWER STFTION J ~O SENDWNRIAL EFFLilENT REP (RT FOR 2lLY TO DECDeG 1989

' GASEOUS EFFLUENTS - VENT STACK RELEASES 1. . .

LMIT 2 (Docket Musber 50-457) --

StM ETION OF ALL RELEASES l tasITS ' I '.1ULY l AUG 1 SEPT ~ l 3rd 00ARTERI OCT I NOW l DEC' leth GuARTERI:

C. Particulate (> 8 day half-life) #eleases

1. Gross Activity (LLD = *) Ci < LLD < LLD < LLD' < LLD 1.03E-5 1.2SE-5 3.59E-5 5.ME-5

' 2. Gross Aloha Activity (LLD=3.70E-18 C1/ ell Ci < LLD ' < LLD- ( LLD~ < LLD 1.11E-5 1.02E-5 7.53E-6 2. BIE-5 ~

3.  % of 10CFR20/10CFR50 Lisits+ "--

D. Iritive Releases .

1. Total Release ActivitvfLLD=5.21E-12Ci/m111 Ci I 7.93E-1 I 9.49E-1 1 2.52E-1 1 1.99E4a 1 6.42E-3 l' 9.23E-2 I 1.14E-1 I' 2.13E-1 1

2.  % of 10CFR20/10CFR50 Limits + ,

E. Sua of Iodine, Particulate (> 8 day half-life), and Tritive Releases

1. Total Activity (LLD = *) I Ci l 7.93E-1 l 9.49E-1 1 2.52E-1 1 1.99E+a I 6.4E-3 l 9.23E-2 I 1.14E-1 1 2.13E-1 'l:

2.  % of 10CFR20 Limit

a. Anv 0 roan (1500 aree/vearl l  % I 0.00 1 0.00 1 0.00 1 0.00 1 0.00 l' G.00 1 0.00 1 0.00 'j

3.  % of 10CFR50 Limit

a. Quarterl y Anv Oraan (7.5 areal  % 0.00 0.01 0.00 0.01 0.00 0.00 0.00 0.00

b. Annual Anv Oraan (15.0 oreal  % 0.00 0.01 0.00 0.01 0.00 0.00 0.00 0.00

+ Iodine, particulate, and tritium limits are expressed as a total lleit. See Step E.

• LLD reflects LLDs for individual isotopes included in calculation.

Results do not include quantity of Sr.89/90 from October through December.' 1989 - awaiting results from outside vendor. Updated values will be presented in an errata to the Semi-Annual Report.

j 8

2985m(021390)

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~~ #^-

BRAIDWOW) NUCLEAR POIER STATIST _ . _

SDi1AfgelAL EFFLUENT REPORT FOR 3LY TO DECDGER 1989 x

^ '

GASEGUS EFFLUENTS - VENT STACK RELEASES , ,

iseIT 2 (Docket Number 50-457) .

BATCH NODE ,

1 t08ITS I .1ULY I AUG I SEPT I 3rd GUARTERI OCT -I Notf i DEC ~14th M1ARTERl-A. Particulate (> 8 day half-life) Releases Mn-54 (LLD = 3.81E-19 Ci/el) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 Fe-59 (LLD = 1.07E-18 Ci/el) Ci 'O.00 0.00 a 00 0.00 0.00 0.00 0.00 0.00 Co-58 (LLD = 3.33E-19 Ci/ml) Ci 0.00 0.00 0.00 0.00' O.00 0.00 0.00 0:00

• Co-40 (LLD =.4.80E-19 Ci/ml) Ci 0.00 0.00 0.00 ~ 0.00 0.0C ~0.00 0.00 0.00 Sr-89 (LLD = * ) C4 0.00 0.00 0.00 0.00 -' O.00 0.00 9.00 0.00 Sr-90 (LLD =

• 1 Ci 0.00 - 0.00 0.00' O.00 0.06 0.00 0.00' O.00

• Y-88 (ILD = 1.60E-18 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ru-103 (LLD = 3.83E-19 Ci/el) Ci 'O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Aa-110m (LLD = 3.72E-19 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Cs-134 (LLD = 4.64E-19 Ci/ ell Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00-Cs-136 (LLD = 3.48E-19 C1/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 -

Cs-137_ (LLD = 3.95E-19 Ci/m11 Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ba/La-140 (LLD = 1.06E-18 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ce-144 (LLD = 2.31E-18 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Others (Specify)

B. Tritium Releases

1. Total Release Activity 0.00 0.00 0.00 0.aa l

(LLD = 5.21E-12 C1/ ell C1 0.00 0.00 0.00 0.00 .

i

• Waiting for results from off-site vendor - data will be presented in an errata to the Semi-Annual Report.

Note: Braidwood monitors for particulates, iodines and tritium via continuous monitoring.'

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BRAIDWOOD NUCLFAt POWER STATISS .

SDi1JueWAL EFFLUElff REPORT FOR RLDLHECDEER 1989

_ GASEGUS EFFLUENTS - VENT STACK RELEASES- <

~

UNIT;2 (Docket Nueer 50-457)

~

CONTINUGUS NODE

'l tmITs l .lulY I AUG I SEPT I 3rd m_MTERl GCT I NOW l DEC leth0MARTERl A. Particulate (> 8 day half-life) Releases l Mn-54 (LLD = 3.81E-19 Ci/el) Ci ~< LLD < LLb < LLD < LLD < LLD '< LLD 1.60E-6 1.60E-6~l Fe-59 (LLD = 1.07E-18 C1/ ell Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Co-58 fLLD = 3.33E-19 C1/ ell Ci < LLD < LLD < LLD < LLD 1.03E-5 4.27E-6 2.7K-5 '4.24E-5

Co-60 (LLD = 4.80E-19 Ci/ ell -- Ci < LLD < LLD < LLD < LLD < LLD 8.4K-4 5.67E-6 '1.42E-5' l Sr-89 (LLD =

• 1 Ci * * * * * * * ' '

• Sr-90 (LLD =

• 1 Ci * * * * * * *

• Y-88 (LLD = 1.60E-18 Ci/all Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD (LLD = 3.83E-19 C1/el)

Ru-103 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD' < LLD +

Ao-110m fLLD = 3.72E-19 Ci/el) Ci < LLD- < LLD < LLD < LLD < LLD < LLD < LLD < LLD

. Cs-134 (LLD = 4.64E-19 Ci/ ell C1 < LLD < LLD < LLD < LLD < LLD ' < LLD < LLD < LLD Cs-136 '(LLD = 3.48E-19 Ci/ml) C1 < LLD < LLD < LLD' < LLD - < LLD < LLD < LLD < LLD-Cs-137 (LLD = 3.95E-19 Ci/ml) Ci '< LLD < LLD < LLD < LLD < LLD' < LLD 9.14E-7 9.14E-7 Ba/La-140 (LtD = 1.06E-18 C1/ ell Ci < LLD < LLD < LLD < LLD < LLD < LLD

< LLD < LLD Co-144 (LL3 = 2.31E-18 Ci/ml) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Others (Specify)

~

B. Tritium Releases ~2

1. Total Release Activity

, (LLD = 5.21E-12 Ci/el) Ci 7.93E-1 9.49E-1 2.52E-1 1.99E+0 6.42E-3 9.23E-2 1.14E-1 -2.13E-1 i

i i

a o

Waiting for analysis results - Data will be presented in an errata to the Semi-Annual Report.

I i

l 11 2985m(021390)-

~ V --

2 -

.c

'a BRAIDWOOD NUCLEAR P0lER STATION " * "

SEMIAIEEUAL. EFFLUENT atEPORT FOR JULY TO DECDGER 1989 ..

GASEOUS EFFLUENTS - VDIT STACK RELEASES - --

UNIT 2 (Docket Number 50-457)

~

'CONTINUCUS M(BE~

'I UIIITS 1 JULY 'l AUG' I SEPT I 3rd '* 2TERI OCT' 'l IIOV I DEC I4th 'm*TERC.

C. Fission and Activation Gas Releases-Xe-131m (LLD = 1.25E-11 Ci/ ell Ci < LLD 4 LLD- < LLD < LLD < LLD' < LLD~ <.LLD ~< LLD

, Xe-133m (LLD = 2.64E-12 Ci/ml) Ci < LLD < LLD < LLD < LLD ' < LLD < LLD < LLD

< LLD Xe-135m (LLD = 3.17E-11 Ci/el) Cl- < LLD- < LLD < LLD < LLD' < LLD < LLD < LLD < LlD '

'Xe-133 (LLD = 8.22E-13 Ci/ml) Ci 6.63E+1 9.52Ee4 5.21E+d 8.10C+1 5.69E+1 1.49E+G 1.75E+2 2.1T+2 Xe-135 (LLD = 2.82E-13 Ci/el) C1 < LLD < LLD < LLD < LLD 1.25E+0 3.68E+1 1.4 6 1 5.201. ,

Kr-85e (LLD = 4.63E-13 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD 1.68E-1 < LLD 1.68E-1 Kr-85 iLLD = 8.09E-11 Ci/ ell Ci < LLD < LLD' < LLD. < LLD < LLD < LLD < LLD ' <.LLD Kr-87 iLLD = 1.31E-12 C1/el) C1 < LLD < LLD < LLD < L1D < LLD < LLD < LLD -< LLD Kr-88 fLLD = 1.45E-12 Ci/el) C1 < LLD < LLD < LLD < LLD < LLD < LLD ' < LLD < LLD Ar-41 (LLD .: 9.39E-13 Ci/ ell Ci < LLD < LLD ~ < LLD < LLD < LLD 8.01E-2 < LLD~ 8.91E-2~

Xe-138 (LLD = 9.28E-11 Ci/ml) Ci < LtD < LLD < LLD < LLD < LLD < LLD < LLD < LLD

'Others (Specify)

I D. Iodine Releases I-131 (LLD = 5.70E-19 Ci/ ell Ci 8.10E-6 1.33E-5 1.81E4 2.32E-5 5.09E4 3.03E-6 1.80E-5 2.61E-5 I-132 (LLD = 3.60E-18 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD < LID' < t LD < L".D I-133 (LLD = 5.36E-19 Ci/ml) C1 1.03E4 1.53E-5 4.57E-7 1.68E-5 < LLD 7.24E4 4.88E-5 5.60E-5 I-134 (LLD = 1.45E-16 Ci/ml) Ci 2.81E4 < LLD < LLD 2.81E-6 < LLD < LLD~ ' < LLD < LLD I-135 iLLD = 4.32E-18 Ci/ ell C1 - < LLD 1.83E-3 < LLD 1.83E-3 < L1D < LLD 9.19E-4 9.14E-4 ,

Others (Specify)  !

-12 2985m(020990) .-,

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^

.BRAIDWOOD NUCLEAR POWER STATION 7 SEMIANNUAL EFFLUENT REPORT FOR JULY TO DECEPBER'1989 l LIQUID EFFLUENTS - SUP9tATION OF ALL RELEASES -

f UNIT 'l (Docket Number 50-456) ~[

!- SUP9tATION OF ALL RELEASES i

I UNITS'l ' JULY ! 'I 'AUG l SEPT I 3rd OUARTERI OCT l NOV I DEC 'I4thOUARTER]5 A. Fission and Activation Products

1. Total Activity Released Ci 5.62E-3'" 1.60E-2 6.45E-2 8.61E-2 1.61E-2 2.38E-1 8.01E-1 1.05E+0

2. Averace Concentration Released uCi/ml 2.02E-9 7.64E-9 2.56E-8 1.16E-8 8.08E-9 1.09E-7 2.91E-7 4.08E-7 l 3.  % of 10CFR20 Limits _ -

I a. Guarateriv Whole Bodv i1.5 mres)  % 0.03- 0.01 1 0.C3 'O.07- 0.19 0.17 8.74 9.10 I

0.00 ~ l 0.01

~

b. Guarteriv Any Oroan (5.0 mres)  % 0.01 -0.02 0.08 0.45 3.14 3.67'

c. ' Annual Whole Body (3.0 mrea)  % 0.65 0.04 0.02 0.71 0.80 0.09 4.37 5.26 -

d. Annual Any Oroan (10.0 mres)  % 0.26 0.02 0.00 0.28~ 0.32 0.18 1.62 2.12-B. Tri tium

1. lotal Activity Released

• Ci 4.36E+1 2.63E+1 3.62E+1 1.%E4 2.27E+1 2.07E+1 1.74E+1 6.08E+1

2. Averace Concentration Released ** uCi/mi 1.56E-5 1.26E-5 1.43E-5 1.43E-5 1.14E-5 9.57E-6 6.33E-6 8.81E-6

3.  % of Limit (3E-3 uCi/ml)  % 5.20E-1 l 4.20E-1 4.77E-1 4.77E-1 3.8SE-1 3.19E-1 2.11E-1 2.94E-T

' C. Dissolved Noble Gases

1. Total Activity Released *** Ci 8.07E-2 7.65E-3 1.68E-2 i.05E-1 2.02E-2 2.39E-2 1.72E-2 6.13E-2

2. Averace Concentration Released "" uCi/el 2.89E-8 3.65E-9 6.66E-9 1.42E-8 1.01E-8 1.10E-8 6.25E-9 8.88E-9

3.  % cf Limit (2E-4 uCi/ml)  % 1.45E-2 1.83E-3 3.33E-3 7.10E-3 5.05E-3 5.50E-3 '3.13E-3 4.44E-3 D. Gross Alpha

1. Total Activity Released "*** Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD

2. Aver 30e Concentration Released **"" uCi/mi < LLD < LLD < LLD ~ < LLD < LLD < LLD < LLD < LLD E. Volume of Liouid Waste to Discharoe I liters 1-6.48E+6 l 5.08E+6 l'4.23E+6 1 1.58E+7 1 3.57E+6 1 4.11E d l 5.23E+6 l 1.29E+7 l F. Volume of Dilution Water I liters' l 2.78E+9 1 2.09E+9 I 2.52E+9 I 7.39E+9 l 1.99E+9 I 2.16E+9 l 2.74E+9- 1 S.89E+9 l (LLD = 2.67E-12 ci/ml)

(LLD = 2.67E-12 ci/ml)

(LLD = 4.15E-13 ci/ml)

(LLD = 4.15E-13 ci/ml)

(LLD = 9.32E-14 ci/ml)

• • • • • • ( LLD = 9.32E-14 ci /ml ) .

'13

-2985m(021490)

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~

g n -y ~

p- -

SRAIDWOOD NUCLEAR P0lE:R STATION .

' SOf!AleRIAL EFFLUDIT REPORT FOR JULY TO DECDGER 1989 LIQUID EFFLUDITS , [

[ UNIT 1 (Docket Mus6er 50-456) ~ -

h BATCH MODE I tmITS I JULY l AUG l' SEPT I 3rd OUARTERl GCT I' NOV I DEC !4th GUARTER A. Liquid Effluents Fe-55 " Ci - - - * - -

Sr-89 ** Ci - - - * - - -

Sr-90 ** Ci - - - * - - .-

Co-58 (LLD = 5.07E-14 Ci/ ell C1 4.61E-3 8.47E-3 3.34E-2 4.65E-2 1.03E-2 1.43E-1 4.07E-1 5.607-1

• Co-60 (LLD = 5.02E-14 Ci/ ell Ci 8.13E-4 4.15E-3 5.60E-3 1."4E-2 1.18E-3 3.1E-2 7.20E-2 1.05E-1 Cs-134 (LLD = 4.58E-14 Ci/mii C1 1.70E4 4.04E-4 7.19E-5 4.78E-4 8.47E-4 7.20E.-4 5.50E-2' 5.66E-2 Cs-136 (LLD = 4.03E-14 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD '< LLD < LLD < LLD

• Cs-137 (LLD = 4.53E-14 Ci/al) Cl 6.57E-5 7.28E-4 1.03E-4 8.91E-4 1.86E-3 1.33E-3 6.07E-2 6.39E-2

! I-131 iLLD = 6.33E-13 Ci./el) Ci 3.21E-5 1.41E-5 1.72E-4 2.18E-4 2.65E-5 < LLD 1.98E-5 ' 4.63E-5 I-133 (LLD = 6.19E-14 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD l Ba/La-140 (LLD = 4.88E-14 Ci/el) Ci 5.70E4 < LLD 5.65E-5 6.22E-5 < LLD < LLD < LLD < LLD l Xe-133 (LLD = 1.42E-13 Ci/ ell Ci 7.99E-2 7.54E-3 1.67E-2 1.04E-1 1.99E-2 2J5E-2 1.50E-2 5.84E-2 __

Xe-135 (LLD = 4.12E-14 Ci/ ell Ci 7.38E-4 1.12E-4 6.50E-5 9.15E-4 2.05E-4 2.24E-4 2.21E-3 2.64E-3 Others (Specify)

Mn-54 (LLD = 4.18E-14 Ci/ ell Ci 8.83E-5 1.40E-3 2.55E-3 4.04E-3 3.18E-4 1.0K-2 3.08E-2 4.19E-2 Sb-124 (LLD = 3.93E-14 Ci/el) C1 1.91E-6 < LLD 1.26E-3 1.26E-3 2.09E-4 5.2K-4 3.13E-3 3.87E-3 I-132 (LLD = 6.15E-14 C1/el) C1 2.37E4 < LLD < LLD 2.37E4 1.22E-4 4.37E-4 2.72E-2 2.78E-2 Xe-133m (LLD = 4.15E-13 Ci/ ell Cl 8.87E-E < LLD < LLD 8.87E-5 1.18E-4 2.03E-4 < LLD 3.21E-4 Kr-88 fLLD = 1.70E-13 C1/ ell C1 1.48E-5 < LLD < LLD 1.48E-5 < LLD < LLD ' < LLD < LLD 2r-95 (LLD = 1.05E-13 C1/el) Ci < LLD 2.83E-4 7.43E-5 3.57E-4 < LLD 3. N -3 7.90E-3 1.12E-2 Nb-95 (LLD = 4.43E-14 Cl/ ell Cl '< LLD 5.46E-4 3.43E-4 8.89E-4 4.46E-4 6.12E-3 1.52E-2 2.18E-2 Fe-59 (LLD = 8.59E-14 Ci/el) Ci < LLD 6.08E-5 4.11E-4 4.72E-4 3.34E-5 1.36E-2 8.88E-3 2.2SE-2 Sn-113 "

Ci < LLD 5.90E-5 < LLD 5.90E-5 < LLD 7.73-4 1.39E-3 2.16E-3 Cr-51 (LLD = 3.37E-13 Ci/el) Ci < LLD 2.24E-4 2.25E-3 2.47E-3 < LLD 1.78E-2 3.83E-2 5.61E-2 Co-57 (LLD = 4.63E-14 Ci/ ell Ci < LLD 2.37E-5 4.32E-4 4.56E-4 < LLD 5.26E-4 1.99E-3 2.52E-3 Ru-105 (LLD = 1.31E-13Ci/el) Ci < LLD 7.00E.-6 < LLD 7.00E-6 < LLD < LLD < LLD < LLD

_ Na-24 (LLD = 5.94E-14 Ci/ ell Ci < LLD < LLD 5.60E4 5.60E4 < LLD < LLD 1.05E-3 1.05E-3 Sb-125 (LLD = 1.32E-13 Ci/el) Ci < LLD < LLD 2.50E-3 2.50E-3 7.52E-4 2.44E-3 2.68E-2 2.99E-2 3 Sb-122 iLLD = 7.88E-14 Ci/ ell C1 < LLD < LLD 4.08E-6 4.08E4 < LLD < LLD < LLD < LLD Zr-97 (LLD = 5.26E-14 Ci/el) Ci < LLD < LLD 1.52E-2 1.52E-2 < LLD 1.5K-3 < LLD 1.58E Zn-65 (LLD = 6.79E-14 Ci/ ell Ci < LLD < LLD 2.94E-5 2.94E-5 < LLD 9.94E-4 1.50E-3 2.49E-3 Waiting for analysis results - Data will be presented in an errata to the Semi-Annual Report.

LLD for this isotope is being developed and will be presented in an errata to the Semi-Annual Report.

14 2985m(020990)

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[s;

^

.l BRAIDM IRICLEAR POWER STATIWI -

. SEMIAf810AL EFFLUDIT REPORT FOR JULY TO DECDBER 1989

.LI0UID EFFLUENTS ~..

2-UNIT 1 (Dt.chet leader 50-456) -

, B,'TCH MWlE I latITS I .1ULY l AUG l SEPT- l 3rd OHARTERI GCT I NOV l DEC leth 9_"TERl A. Liquid Effluents (Continued)

Ni-65 Ci < LLD < LLD < LLD < LLD < LLD '2.60E-4 2.25E-3' 2 E-3 Ru-103 "

- Ci < LLD < LLD < LLD < LLD < LLD 1.05E-4 < LLD 1.95E-4 Aa-110m Ci. < LLD < LLD < LLD < LLD < LLD '1.95E-3 1.63E-5 1.9)E-3' Br-82 fLLD = 4.78E-14 C1/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.?N-2 1.22E-2 I-134 Ci < LLD < LLD < LLD < LLD < LLD -< LLD 2.72E-2 ~ 2.72E-2 Sr-92 Ci < LLD < LLD < LLD < LLD < LLD < LLD 5.75E-6: 5.75E-6 Sc-46 **

C1 -< LLD < LLD ~ < LLD < LLD '< LLD < LLD 2.41E-5 2.41E-5 Mo-99 (LLD = 6.62E-13 C1/all Ci < LLD < LLD < LLD < LLD < LLD < LLD 4.95E-4 4.95E-4 Ce-144 fLLD = 3.56E-13 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD < LLD 3.44E-4 3.44E-4 B. Averaae Duration of Release ' si n 63.8 65.7 91.5 73.7 105.7 85.0 115.8 101.9-LLD for this isotope is being developed and will be presented in an -

arrata to the Semi-Annual Report.

'15 2985e(020990)

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g BRAIDWOOD NUCLEAR. POWER STATION-SENIANNUAL EFFLUENT REPORT FOR JULY TO DECDBER 1989.

LIQUID EFFLUENTS - SIM % TION OF ALL RELEASES UNIT' 2 { Docket Number 50-457)

~7 SUMPtATION OF ALL RELEASES i SEPT l 3rd DUARTERI OCT l NOV I DEC I4thOUARTERl

! l UNIT % 1 JULY l AUG-A. Fission and Activation Products 1.60E-2 6.45E-2 8.61E-2 1.61L-2 2.38E-1 8.01E-1 1.05E40

1. Total Activity Released Ci 5.62E-3 7.64E-9 2.56E-8 1.16E-8 8.08E-9 1.09E-7 2.91E-7 4.08E-7

2. Averaae Concentration Released uCi/mi 2.02E-9

3.  % of 10CFR20 Limits 9.10

% 0.03 0.01- 0.03 0.07- 0.19 0.17 8.74

a. Guaraterlv Whole Bodv i1.5 mres) 3.14 3,67 0.01 0.00 0.01 0.02 0.08 0.45

b. Quarterl y Anv Oroan (5.0 mreal  %

4.37 5.26 '

0.65 0.04 0.02 0.71 0.80 0.09

c. Annual Whole Body (3.0 orea)  %

0.02 0.00 0.28 0.32 0.18 1.62 2.12

d. Annual Any Oraan (10.0 ores)  % 0.26 .

B. Tritium 3.62E+1 1.06E+2 2.27E+1 2.07E+1 1.74E+1 6.08E+1

1. Total Activity Released " Ci 4.36E+1 2.63E+1 1.26E-5 1.43E-5 1.43E-5 1.14E-5 9.57E-6 6.33E-6 8.81E-6

2. Averaoe Concentration Released ** uCi/el 1.56E-5 4.20E-1 4.77E-1 4.77E-1 3.80E-1 3.19E-1 2.11E-1 2.94E-1

3.  % of Limit (3E-3 uCi/ml)  % 5.20E-1 C. Dissolved Noble Gases 7.65E-3 1.68E-2 1.050-1 2.02E-2 2.39E-2 1.72E-2 6.13E-2 3

1. Total Activity Released *** Ci 8.07E-2 3.65E-9 6.66E-9 1.42E-8 1.01E-8 1.10E-8. 6.25E-9 8.88E-9

2. Averaoe Concentration Released **" uCi/e1 2.89E-8 3.33E-3 7.10E-3 5.SSE-3 5.50E-3 3.13E-3 4.44E-3 ~

3.  % of Limit (2E-4 uCi/ mil  % 1.45E-2 1.83E-3 D. Gross Alpha

< LLD < LLD < LLO < LLD < LLD < LLD Total Activity Released "*** Ci < LLD < LLD

1. ' < LLD < LLD

< LLD < LLD < LLD < LLD < LLD < LLD

2. Averaae Concentration Released *"*" vCi/e1 l liters- l 6.48E46 1 5.08E+6 I 4.23E+6 1 1.58E+7 1 3.57Ed I 4.11E46 I 5.23E+6 1 1.29E+7 l j E. Volume of Liouid Waste to Discharoe l liters l 2.78E+9 l 2.09E+9 l 2.52E+9 1 7.39E+9 l 1.99E+9 .I 2.16E+9 I 2.74E+9 I 6.89E+9 l F. Volume of Dilution Water

• (LLD = 2.67E-12 ci/ml)

• • (LLD = 2.67E-12 ci/ml)

• • • (LLD = 4.15E-13 ci/ml)

(LLD = 4.15E-13 ci/ml)

• • • • • (LLD = 9.32E-14 ci/ml)

• • • • • • (LLD = 9.32E-14 ci/ml) 18 2985m(021490)

p BRAIDW0lB MUCLEAR P0tER STATIGIL

~ SEMIAf50UAL EFFLUDIT REPORT FOR 2 FLY TO DECDSER 1989

LIQUID EFFLUENTS'-

UNIT 2 (Docket IIumber 50-457) -

BATCH MIBE ,

I 1511T5 I .1ULY l AUG 1 SEPT I 3rd GUARTERI OCT I IIDW I DEC '14th OUARTERl A. Liquid Effluents Fe-55 ** C1 - - -

• - - - M Sr-89 " Ci - - - - - -

~

• ~- *'

Sr-90 ** Ci - - - -

Co-58 (LLD = 5.07E-14 Ci/el)

C1 4.61E-3 8.47E-3 3.34E-2 4.65E-2 1.03E-2 1.43E-1 4.07E 5.6 K -l' Co40 (LLD = 5.02E-14 C1/el) Ci 8.13E 4 4.15E-3 E.60E-3 1.06E-2 1.1K-3 3.1K-2 7.2DE-2 '1.95E-1 Cs-134 (LLD = 4.58E-14 Ci/el) C1 1.70E4 4.04E-4 7.19E-5 4.7K-4 8.47E-4 7.2DE-4 5.50E-2 5.'66E-2 Cs-136 (LLD = 4.03E-14 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Cs-137 (LLD = 4.53E-14 Ci/el) Ci 6.57E-5 7.2K-4 1.03E-4 8.97E-4 1.86E-3 1.33E-3 6.07E-2 6.39E-2 I-131 (LLD = .6.33E-13 Ci/el) Ci 3.21E-5 1.41E-5 1.72E-4 2.18E-4 2.65E-5 < LLD 1.98E-5 _4.63E-5 I-133 (LLD = 6.19E-14 Ci/ ell Ci < LLD < LLD < LLD < LLD < LLD < LLD '< LLD < LLD Ba/La-140 (LLD - 4.88E-14 Ci/ ell C1 5.70E4 < LLD'. 5.65E-5 6.22E-5 < LLD < LLD < LLD < LLD Xe-133 (LLD = 1.42E-13 Ci/el) Ci 7.99E-2 7.54E-3 1.67E-2 1.04E-1 1.99E-2 2.35E-2 1.50E-2 5.84E-2 Xe-135 (LLD = 4.12E-14 C1/el) C1 7.38E-4 1.12E-4 6.50E-5 '9.15E-4 2.05E-4 2.24E-4 2.21E-3 2.64E-3 Others (Specify) .

Mn-54 (LLD = 4.18E-14 Ci/ ell Ci 8.83E-5 1.40E-3 2.55E-3 4.04E-3 3.18E-4 1.08E-2 3.08E-2 4.19E-2 Sb-124 (LLD = 3.93E-14 Ci/ ell ~ Ci 1.91E4 < LLD 1.26E-3 1.26E-3 2.09E-4 5.2ar-4 3.13E-3 3.87E-3 I-132 (LLD = 6.15E-14 Ci/ ell Ci 2.37E4 < LLD < LLD 2.37E4 1.22E-4 4.37E-4 2.72E-2 '2.780-2' Xe-133m (LLD = 4.15E-13 Ci/el) Ci 8.87E-5 < LLD < LLD 8.87E-5 1.1K-4 2.03E-4 < LLD 3.21E-4 Kr-88 (LLD = 1.70E-13 Ci/el) C1 1.4 K-5 '< LLD < LLD 1.48E-5 < LLD < LLD < LLD < LLD ,

Tr-95 (LLD = 1.05E-13 Ci/el) Ci < LLD 2.83E-4 7.43E-5 3.57E-4 < LLD 3.26E-3 7.90E-3 1.12E-2 Mb-95 (LLD = 4.43E-14 Ci/el) _Ji < LLD 5.46E-4 3.43E-4 8.89E-4 4.46E-4 6.12E-3 1.52E-2 2.18E-2  ;

Fe-59 (LLD = 2.59E-14 Ci/el) ?Ci < LLD 6.08E-5 4.11E-4 4.72E-4 3.34E-5 1.36E-2 8.8K -3' 2.2SE-2 Sn-113 " Ci < LLD 5.90E-5 < LLD 5.90E-5 < L1D 7.73-4 1.39E-3 2.16E-3 Cr-51 (LLD = 3.37E-13 Ci/el) Ci < LLD 2.24E-4 2.2SE-3 2.47E-3 < LLD 1.7K-2 3.83E-2 5.61E-2 Co-57 (LLD = 4.63E-14 Ci/ ell Ci < LLD 2.37E-5 4.32E-4 4.56E-4 < LLD 5.26E-4 1.99E-3 2.52E-3 Ru-105 (LLD = 1.31E-13Ci/ ell Ci < LLD 7.00E4 < LLD 7.00E4 < LLD . _. < LLD < LLD < LLD Na-24 (LLD = 5.94E-14 Ci/el) Ci < LLD < LLD 5.60E4 5.60E4 < LLD < LLD 1.05E-3 1.05E-3 Sb-125 (LLD = 1.32E-13 Ci/el) Ci < LLD < LLD 2.50E-3 2.50E-3 7.52E-4 2.44E-3 2.68E-2 2.99E-2 Sb-122 (LLD = 7.88E-14 Ci/el) Ci < LLD < LLD 4.08E-6 4.08E4 < LLD < LLD < LLD < LLD Zr-97 (LLD = 5.26E-14 Ci/ ell Ci < LLD < LLD 1.52E-2 1.52E-2 < L1D 1.58E-3 < LLD 1.5 K-3' Zn-65 (LLD = 6.79E-14 Ci/el) C1 < LLD '< LLD 2.94E-5 2.94E-5 < L1D 9.94E-4 1.50E-3 2.49E-3 <

• Waiting for analysis results - Data will be presented in an errata to the Semi-Annual Report.

• • LLD for this isotope is being developed and will be presented in an errata to the Semi-Annual Report.

19 2985e(020990)

.~ - _ - - - - , - . - -

BRAIDWOOD NUCLEAft POWElt ST2. TION -

L SD?IAf8 RIAL EFFLUENT REPORT FOR JULY TO DECDBER 1989 LIQUID EFFLUENTS , . . .

UNIT 2 (Docket Number 50-457) _ --

BATCH MIME I talITS -I .lutY ' l AUG I SEPT l 3rd a - TERI OCT I NDV I DEC 14thGUARTERl.

A. Liquid Effluents (Continued) -

Mi45 " Ci < LLD < LLD

< LLD < LLD < LLD 2.60E-4 2.15E-3 2.51E-3 Ru-103 "

Ci < LLD < LLD' < LLD < LLD < LLD 1.05E-4 < LLD 1.05E-4 Ao-110e ** Ci < LLD < LLD ~ < LLD < LLD '< LLD 1.95E-3 1.63E-5 1.915 Br-82 (LLD = 4.78E-14 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD < LLD 1 N -2 1.22E-2 I-134 "

Ci < LLD < LLD < LLD < LLD < LLD < LLD '2.72E-2 2.72E-2 Sr-92 "

Ci < LLD < LLD '< LLD < LLD < LLD < LLD 5.75E4 5.75E4 '

Sc-46 "

Ci < LLD < LLD < LLD < LLD < LL3 < LLD 2.41E-5 2.41E-5 Mo-99 (LLD m 6.62E-13 Ci/el) Ci < LLD < LLD < LLD < LLD < LLD ~ < LLD 4.95E-4 4.9BE-4 Ce-144 (LLD = 3.56E-13 Ci/el) Ci < LLD < LE9 ' < LLD < LLD < LLD < LLD 3.44E-4 ~3.44E-4 B. Averaoe Duration of Release ein '63.8 65.7 91.5 73.7 105.7 85.0 115.0 101.9 Ai LLD for this isotope. is being developed and will be presented in an errata to the Semi-Annual Report.

20 2985e(021390)

___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ = _ _ - _ = _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ .

_ .= _ -_-__-__ _ _ _ = - _ _ _ . _ __. .____.=

~

.U ,

BRAIOWOOD NUCLEAR P0hER STATION . - -[

. SENIAf0 RIAL EFFLUENT REPORT FOR 21LY TO DECDBER 1989 -

4 LIQUID EFFLUENTS LSIIT 2 (Docket Number 50-457) - -:

CONTINUOUS MODE ,

i.

I taeITS I .lULY l AUG I SEPT l 3,d GUARTERl OCT l NDY I 'DEC I4th '"*TER[ _

A. Liquid Effluents Fe-55 " 0.00 0.00 Ci 0.00 0.00 0.00 0.00- 'O.00 0.00 Sr-89 Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sr-90 " Ci 0.00_ -0.00 0.00 0.00 0.00 -0.00 0.00 0.00 Co-58 iLLD = 5.07E-14 Ci/ml) Ci 0 de 0.00 0.00 0.00 0.00 0.00 0.00 0._00 '

Co-60 iLLD = 5.02E-14 Ci/ ell Ci 0.00 0.00' O.00 0.00 0.00 0.00' O.00 0.00 Cs-134 (LLD = 4.58E-14 Ci/ml) Ci 0.00 0.00' O.00 0.00 0.00 0.00 0.00 0.00-Cs-136 (LLD = 4.03E-14 C1/el) Ci 0.00 0.00 0.00 0.00 0.00 3 0.00 0.00 0.00 Cs-137 (LLD = 4.53E-14 Ci/ ell C1 0.G0 0.00 0.00 0.00 ~ 0.00 0.00 "

0.00 0.00 I-131 iLLD = 6.33E-13 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 -

I-133 (LLD = 6.19E-14 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 j . . . Ba/La-140 (LLD = 4.88E-14 Ci/el) Ci 0.00 0.00 0.00 0.G0 0.00 0.00 0.00 0.00

, Xe-133 (LLD = 1.42E-13 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Xe-135 (LLD = 4.12E-14 Ci/ml) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ,

l Others (Specify)

Mn-54 iLLD = 4.18E-14 Ci/ ell Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sb-124 (LLD = 3.93E-14 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00-I-132 iLLD = 6.15E-14 Ci/ ell Ci 0.00 0.00 0.00 0.00 -0.00 0.00 0.00 0.00 ..

Xe-133m (LLD = 4.15E-13 C1/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.G0 - 0.00 Kr-88 (LLD = 1.70E-13 Ci/ml) Ci 0.00 0.00' O.00 0.00 0.00 0.00 0.00 0.00 Zr-95 iLLD = 1.05E-13 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 'O.00 0.00 0.00 Nb-95 (LLD = 4.43E-14 Ci/ml) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Fe-59 (LLD = 8.59E-14 Ci/ml) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sn-113 **

C1 0.00 0.00 -0.00 0.00 0.00 0.00 0.00 0.00 Cr-51 (LLD = 3.37E-13 Ci/el) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Co-57 (LLD = 4.63E-14 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ru-105 (LLD = 1.31E-13 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Na (LLD = 5.94E-14 Ci/el) C1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sb-125 (LLD = 1.32E-13 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 "

Sb-122 (LLD = 7.88E-14 Ci/ml)' Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 -

Zr-97 (LLD = 5.26E-14 Ci/ml) Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Zn-65 (LLD = 6.79E-14 Ci/ml) Ci 0.00 ' O.00 0.00 0.00 0.00 0.00 0.00 0.00 -;

Ni-65 Ci 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Nota: Braidwood Station does not release in the continuous mode.

• • LLD for this isotope is being developed and will be presented in an errata to the Semi-Annual Report.

2985m(020990) 21

. _ . - _ . . , _- ,~_ - - _ _ .

~

' i-OSAIDWO0e ItsCLEAR P0tER STATION -~ '

$ENraanmana ' EFFLtENT REPIRT FOR ~2a.Y TO m 1989 LIQUID EFFLUDITS - M teIIT 2 (Docket pluster 56-457)

• CONTIIIUGUS MODE I ~ tesITS l .1HLY I AMG l SEPT I 3rd (WeRTERl  : eCT ~l IIDW ~l tre 14th maeRTERI A. Liquid Effluents (Ccatinued) ,

Ras-le3 C1 0 se e.ee ~S.se e.ee 0.00 8.ee ' e.es - e.as An-110m - ** C1 0.00 e.ee e.ee e.te 8.ee 8.00 e.00 tie sr-a2 ftLD = 4.70E-14 C1/m11 C1 0.00 'O.00 e.00 e.00 e ee e.00 e.ee e.at I-134 **

Ci a cs e.4e' O.ee e.00 G.ee e.ee e.Se e.as '

= e.ee sr-92 CI - e se d.Ge e.ee e.se e.ee e.ee a;ee Sc-46 = -1 C1 e.00 0.00 0.0a 0.00 e.ee G.ee e.ee e.se

• Ms-99 (LLD = 6.62E-13 Ci/ ell C1 c.00 0.00 0.00 e.ee emos e.ee e.00 0.0e '

Co-144 (LLD = 3.56E-13 C1/el) Ci 0.00 0.00 0.00 e.00 0.00 eJe 0 e0 e.0e ' d

8. Averaae Duration of Re1==== min. a.se 0.00 e.00 e.ee 0.00 e.00 e.at 0.00 .. !

i I

l l

i i

Nota: Bralesood Station does not release in the continoons mode. I l

! " LLD for this isotope is being developed and will be presented in an I errata to the Semi-Annual Report.

22-2985=(020990)

y . ' '

9  % '

BRAIDNOOD NUCLEAR POWER' STATION 4 l gjEf ^ . ; -t SEMI-ANNUAL EFFLUENT REPORT FOR~ JULY TO D'ECEMBER 1989 l

.. ja lb, SOLID. RADIOACTIVE WASTE =

. UNIT ,1 yD '2 COMBINED: (Dock 3t Numb 2r : 50-456 cad 50-457)

-J A."

?

'..SdLID' WASTE' SHIPPED OFFSITE FOR' BURIAL ~OR~ DISPOSAL- a 3

i

. DESCRIPTION' . VOLUME (m3) CURIES  : MAJOR NUCLIDES/ CURIES

R t'

Process Waste- 3.95E+1 3.61E+2 Co-58 1.89E42 1 2.61E+0%. -(

Error =1.47E+00% Co-60 5.79E+1 ' i 2.39E+0%'

' Fe-55 3.58E+1 i ' 2'21E+0%

Mn-54 3.38E+1- 1 -2.47E+0%

j, . Ni 2.94E+1 ' ' i '2.36E+0%~ .

t y Cs-137 4.11E+0 1 1.83E t0%' L{

Nb 2.35E+0 1- 2.34E+0%

Sb-125 1.98E+0 1 2.80E+0%

Cs-134 1.S6E+0 1 2.70E+0%' -j

1. Zr-95 1.16E+0 1- 2.36E+0% '

Co-57 9.24E-1 2' -1.92E+0%'

{ Be ' 8.11E-1 2.83E+0%

1 t lf Zn-65 7.79E 1- 2.68E+0%' [

Ze-59 5.71E-1 1 2.08E+0%i .

" Sn-113 3.24E-1 A 2.58E+0%.

Dry Active Waste 2.17E+2 4.48E-0 Co-58 1.77E+0 1 3.14E+0% ,

E ,

' Error 1.72E-0% Fe-55 1.53E+0 -1 3.14E+0%

i Mn-54 6.82E 1 3.14E-0%.

Ni-63 1.91E-1 i. '3.14E+0%'

Co-60 '1.85E -i '3.14E-0%: g l

Nb-95. 4.31E-2 1 -3.14E+0%

! Fe-59 3.34E-2 'A 3.14E+0%-

Cs-137 2.21E-2 1- '3.14E+0%.

[

Cs-134 1.12E-2' i 3.14E+0%

hi s Pu-241- .7.14E-3 A 3.14E-0% '[

' Co-57 3.94E-3 1 '3.14E+0% l C-14 '8.41E-4 1 -3.14E+0%

Sr-90 6.04E-4 -'i 3.14E+0%;  ;

Pu-239 2.41E-4 1- 3~.14E+0% ,

p. Pu-238- 2.02E-4 1 3.14E+0%

4 drradiatedComponents 0.00E+0 0.00E+0 r ,- .

2 iOther:

-y o ~

. . , , .. n n

- .: g. , 33; J) ' IKumber of Shipments: 11 s

'i Mode of Transportation: Exclusive Use Vehicle Deetination U.S.' Ecology, Richland, WA (5)

SEG,_ Oak Ridge, TN (3)

- Chem-Nuclear, Barnwell, S.C. (3)

B.- IRRADIATED FUEL SHIPMENTS l

No irradiated fuel shipments for July to December, 1989 23-l' _.

E' ;2986a(020990);

AL _ = _ _ L . w __ _ _ --. _ _ - _ _ _ . . _ _ . _

y.

k

, 4, / _l

. : . e , ,. 4 l) j Q .' .

+ . . -,,.9- -BRAIDWOOD NUCLEAR POWER STATION ,

Sh !. ANNUAL EFFLUENT REPORT FOR JULY TO DECEMBER.1989 SOLID RADIOACTIVE WASTE-

l.  : UNIT,1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457) '

(Continued)

. Shipment Number Maste Class. Type of_ Container _ Solidification' Agent _-

or Absorbent.

l0 -

RWS-9007' A LSA Safe-N-Dri.

RWS-9008' B HIC. None -

.RNS-9009- A LS A' Safe-N-Dri

RNS-9010- A LSA Safe-N-Dri ERNS-9011.' A LSA- Safe-N-Dri l

' RWS-9012 .A .LSA Safe-N-Dri :l RNS-9013:- A LSA Safe-N-Dri

. a .;

RWS-9014 A HIC None

RNS-9015 'A LSA Safe-N-Dri i

-4 A LSA Safe-N-Dri l

~RNS-9016- i RNS-9017- B HIC None j I

'. i

-t

i

a.

-1

, . ( I:

24

-l L2986m(020990)

~

1

---S_

.c s g-ni;

+

, - v.9 .

4 Braidwood Station Operating Repoht NRC Dockets STN 50-456 and'STN 50-457 4

1. TheBraidwbodStationProcessControlProgram(PCP)wasrevisedto' -

' incorporate. polymer solidification formulas and a list of implementing procedures previously located in attachments to the PCP. Additionally,

' administrative requirements concerning solidification, deleted from '

.the Technical Specifications per NRC Notice 89-01, were incorporated into the PCP as an appendix.

This procedure revision'was reviewed and approved in accordance with

Braidwood Station on-site review practices. The review process included a 10 CFR 50.59 safety-evaluation.. The changes do not reduce the-overall conformance ofEthe solidified waste product to existing. criteria for c ' solid waste..

- The changes to the'Braidwood Station Process Control Program were-found

acceptable by the on-site review committee and approved and implemented on November:1, 1989.

J 2. -There were-no liquid ^ holdup tanks or gas decay tanks which-exceeded the-

. limits addressed-in the Technical Specifications.

3. There were no major changes to the liquid, gaseous, or solid Radwaste Treatment Systems.

4. None-of the Station's effluent process monitors exceeded the

, LC0AR time frame specified in Technical Specifications.

1 (Final)