ML20076F116

Semi-Annual Radiological Effluent Release Rept for Jan-June 1993

ML20076F116
Person / Time
Site:	Byron
Issue date:	06/30/1993
From:	Schwartz G COMMONWEALTH EDISON CO.
To:	Martin J NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-93-0347, BYRON-93-347, NUDOCS 9410120196
Download: ML20076F116 (24)

Text

• -* C:mmonwealth Edison < p..

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Byron Nuciter St: tion 4450 N:rth G1rmin Church Rord w

Byron, Illinois 61010

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August 6, 1993 LTR: BYRON 93-0374 FILE: 2.12.1522 (1.10.0101) ,

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Mr. J. B. Martin, Administrator Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

SUBJECT:

Semi-Annual Radiological Effluent Release Report Byron Station Units 1 and 2 Facilit:y Operating License Nos. NPF 37 and 66 NRC Docket Nos. 50-454 and 50 455

Dear Mr. Martin:

i; Enclosed is the Semi-Annual Radiological Effluent Release Report for January through June, 1993, for Byron Nuclear Power Station. This report is L required per Technical Specification 6.9.1.7.

Two copies of the report are provided for your use. Two copies will be forwarded to the Docinnant Control Desk and one copy to the Resident Inspector.

Sincerely, l

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G.K. Schwartz Station Manager Byron Nuclear Power Station l

GKS/DD/rp Enclosure cc: Distribution List Attached (3635s/072793) ,

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SEMI-ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT DISTRIBUTION LIST

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Director of Nuclear Reactor Regulation - U.S. Nuclear i Regulatory Cernmiasion Nuclear Regulatory Commission, Region III Illinois G?partment of Nuclear Safety, Office of Nuclear Facili*.y Safety ,

A.H.I.

U.C. Environmental Protection Agency Air and Radiation Branch - Region V Health Physicist Illinois Environmental Protection Agency Division of Water Pollution Control Environmental Protection Specialist Murray and Trettel, Inc.

Teledyne Isotopes Midwest Laboratory and General unnager Chemistry Services - Chemistry Services Director Byron Station Central Filas, File Number 1.12.1522 Health Physics Services Supervisor - Byron Nuclear Power Station Radiclogi.:al Effluent Monitoring Program Coordinator NRC Senior Resident Inspector - Byron Nuclear Power Station ,

B.P.I. Associates General Counsel Illini State Park Site Superintendent Nuclear Oversight Manager (2635s/072793) i

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- , - , ,- 1 BYRON NUCLEAR POEER STATION f EFFLUENT AND WAS*II DISPOSAL REPORT 1 JANUARY through JUNE 1993  !

Supplemental Information

(

1. Regulatory Limits

a. Fission and activation gases:

10CFR20 Whole Body - 500 mrea/ year Skin = 3000 mres/ year 10CFR50 Gamma = 5 mrad / quarter;~10 mrad / year Beta = 10 mrad / quarter; 20 mrad / year

b. Iodine: (summed with particulate, see below)

c. Particulates with half-lives > 8 days:

10CFR 20 Organ = 1500 mram/ year 10CFR 50 Organ = 7.5 mrem / quarter; 15 mrom/ year

d. Liquid effluents:

10CFR50 Whole Body = 1.5 mram/ quarter; 3 mres/ year organ = 5 mrom/ quarter; 10 mrom/ year

2. Maximum Permissible Concentration

s. Fission and Activation Gases: 10CFR20 Appendiw 3 Table II

b. Iodine: 10CFR20 Appendix L Table II

c. Particulates: 10CFR20 AppenA4w B Table II

d. Liquid Effluents: 10CFR20 N y div B Table II

3. Average Energy: This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.

4. Measurements and Apprnvimations of Total Radioactivity

a. Fission and Activation Gases: Prior to release, the isotopic content is determined. Released activity is calculated using volume of release, which is determined by the change in tank or containment pressure. Additional sethods of calculation utilize historical data and assign an isotopic mix which is representative of normal vent stack isotopics.

b. Particulate, Tritium and Iodine sampling media for the plant vent stacks are collected and isotopically analysed daily for the plant vent stacks.

1 1

(3635s/072793)

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BYRON NUCLEAR POWER STATICE EFFLUENT AND MASTE DISPOSAL REPORT JANUARY through JUNE 1993 Supplemental Informatics (continued)

c. Liquida effluents: Batch releases are isotopically analyzed prior to release. Total release activity is calculated using volume of release. Total tritium activity released is calculated from the ,

highest of a monthly circulating water bloudown camposite activity or )

a sum of the input composite activities.

d. Analysis results which are less than the lower limit of detection

(<LLD) are reported in units of Ci/ml unless otherwise noted. All LLD values are listed in Attar +===nt A. -

5. Batch Releases:

a. Liquid:

1. Number of batch releases = 185

2. Total time period for batch releases = 17,755 minutes.

3. Mav4== time period for a batch release = 231 minutes.

4. Average time period for a batch release = 96 minutes

5. Minimum time period for a batch release = 60 minutes

6. Average stream flow during periods of release of effluent into a flowing stream = 10,978 cfs, based on information from the National Weather Service or Army Corps of Engineers for the Rock River.

b. Gaseous:

1. Number of batch releases = 173

2. Total time period for batch releases - 86,226 minutes

3. M=v4== time period for a batch release = 32,301 minutes.

4. Average time period for batch releases = 498 minutes.

5. Minimum time period for a batch release = 30 minutes.

6. Abnormal Releases:

a. Liquid - = =

b. Gaseous - none i

(3635s/072793)

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UNIT 1 DOCEET EtBSER IIs m 454.".;., ..

EFFLUENT AND MASTE DIErtEhL REPORT T January 1993 TEROUGg June , 1993 ,

GASEOUS EFFIDElrTE - EtBEIRTIM M ALL EEEEEEE ,

I UNITE 15E GER 2ED QTR 3RD gIR 4Tg gig i

A. FI5SION AND ACTIVATICRI gag err.nmES

1. Total Release Activity C1 3.18E+1 4.86E-1 l

2. Maximum Release Rate uC1/see 1.695+3 '1.31E+1 for Quarter

- \

3.  % of 10CTR20 Limits

• i

a. Whole Rody (500 mrom/yr)  %

0.03 0.00

b. Skin (3000 mres/yr)  %

0.02' O.00 l

}

4. .% of 10CFR50 Limits

a. Gasuna Quarterly (5 mrad)  %

0.00 0.00 1

b. Beta Quarterly (10 mrad)  %

0.00 0.00

c. Gassna Annual (10 stad)  %

. 0.00 0.00

d. Beta Annual (20 mead)  % 0.00 0.00 f R. IODINE RELEASES **

1. Total I-131/I-133 Activity C1 3.13 y < LLD C. PARTICULATE (>8 day half-life) RELEASEE **

1. Gross Activity C1 < LLD < LLD 1

2. Gross Alpha Activity C1 < LLD < LLD .

for Quarter D. TRITIUM RELEASES **

1. Total Release Activity C1 5.46E-2 3.39E-2

• % of 10CTR20 limits is based on the maximum releman rate for the period considered.

• • Iodine, particulate, and tritium % of 10CTR20/10CTR50 limits are expressed as a total limit. See step E.

APPROVED Report Page 3 of 22

_i_ APR 261993

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. 1993

$ d %.;&'?@.k'~ .

r*1nzuus 1.11 unuus E"'""TTtEr tr wr verwsere (CINI)

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WITE 1ar gt1 2ND QTR 3RD QTR 4TH QTR

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r 4 E. SUM OF IODINE, PARTICULATE (>8 day half-life), m 33ITIUM ggLgAggs

1. Total Activity Ci 5.49E-2 3.39E-2

2.  % of 10CTR20 Limit -

a. Any Organ (1500 mrem /yr)  %

• 0.00 0.00 I

r 3.  % of 10CT250 Limit

a. Quarterly Any Organ  %

' 0.00 0.00 (7.5 mrem) .

Annual Any Organ  %

b. 0.00 0.00 (15.0 mres) i ris e = m arrr-m - vusrr arrar r ======= _ unvent wer l

h r. FISSION AND ACTIVATION GAS RELEASES

i. 4 Xe-131m 2.56E-1 6.03E-3 Xe-133m 1.84E-1 1.66E-3 Xe-135m < 12.D < LLD Xe-133 3.04E+1 1.44E-1 1

lL 8.43E-3 Xe-135 7.79E-2 1.91E-4 1.83E-4 Kr-85m 6.87E-1 2.23E-1 Kr-85 I

Kr-87 < LLD < LLD 1

I Kr-88 <LLD < LLD

{l C1 4.57E-3 8.14E-5 Ar-41 CL

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Ci Report Page 4 of II

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GASEOUS EFFIDENTE - TElrf EThM EELEBREE - 512M IEDE (CWT)

UNIS IST GER 2ND QTR 3RD UIR 4TH QTR G. IODINE RELEASE 5 I-131 _.

I-133 I-135

8. PARTICULATE ()8 day half-life) RELEASES Sr-89 *

• Sr-90 Ci CL CL

• Value reported as continuous release mode.

GREEDUE EFFIREEEE - TEET ETACI EELESERE - CMTIEntEm mtyr F. FISSION AND ACTIVATICBf GAS RELEASE 5 Xe-131m < LLD < LLD Xe-135m < LLD < LLD Xe-133 4.02E0 1.02E-1 Xe-135 <LLD < LLD Kr-85m < LLD < LLD C < LLD < LLD Kr-85 O < LLD < LLD Kr-88 C1 < LLD < LLD Ar-41 4 APPROVED 5 og 22

/ Report Page APR 261993

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, , UNIT 1 DOCEET EB8BER 83-515 454 l

EFFLUENT AND WASTE DISPOSAF. REPORT Januar'f , 1993 Tint 0UGg June ,

1993 cAsEctis ErrrrrrrTs - vent STAcr wr.nmen ,, _m,,uuun wmr (Cart)

UNITS IST QII 2ND QIR 3RD QTR 4TH QTR J. IODINE RELEASES I-131 2.7BE-4 < LLD I-133 3.51E-5 < LLD I-135 < LLD < LLD K. PARTICULATE (>8 day half-life) RELEASES sr-89 < LLD

• C1 St-90 . T.Tm

• Ci C1' C1 l l

• Analysis done by offsite vendor. Resulta not available.

l LTIMTD YPFTEENTM - HMAELTIIW OF ALL lEEfJt1A"R$

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F. FISSION AND ACTIVATION GAS RELEASES

1. Total Activity Released C1 1.95E-1 5.40E-2

2. Average Concentration uC1/ml 7.86E-8 2.08E-8i Released for Quarter

3.  % of 10CTR50 Limits

a. Quarterly Whole Body  %

0.04 0.10 (1.5 mrem)

b. Quarterly Any Organ  %

0.09 0.11 (5.0 mrem)

c. Annual Whole Body  %

0.02 0.06 (3.0 mram)

d. Annual Any Organ  % 0.04 0.06 (10.0 mrem)

APPROV.8D Report Page _6,,, og 22 APR ?.61993 7 _---

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ErrLUEwT AND unsTE nIsPosar. REPonT l 47 January , 1993 2530DGE -June . 1993 gg GAEEDUS EFFLUENTE - 502251TI3 W AEL RELE1EES (C3E)

UNITS IST GER 2ND 021 3RD QTR 4TH QTR N. TRITIUM

1. Total Activity Released C1 1.93B+2 5.70E+2

2. Average Concentration aci/a1 7.78E-5 2.19E-4 Released for Quarter

3.  % of Limit  %

2.5980 7.30E0 (3.00E-3 uC1/al)

N. DISSOLVED NORLE GASES

1. Total Activity Released C1 9.51E-2 7.36E-3

2. Average concentration uC1/mi 3.83E-8 2.83E-9 -

Released for Quarter -Q 4 3.  % of Limit  % 1.92E-2 1.42E-3 .

(2.00E-4 uC1/ml)

O. GROSS ALPHA

1. Total Activity Released Ci g <g

.i

2. Average Concentration aci/a1 0.00 0.00 i Released for Quarter

~i P. VOLUME OF WASTE RELEASED liters 4.29E+6 4.71E+6 Q. VOLUME OF DILUTION MATER liters 2.48E+9 2.60E+9 LItIIID EFFI22ERTE_.- (IEEIERIIE MIII R. LIQUID ETTLUENTS I

ci e e Sr-89 C1 e e Sr-90 Xe-133 ,

Ci e

• Fe-55 C1 Ci Report Page 7 of 1

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BYRON NUCLEhE PGIRE mwrffw .

UNIT __1. DOCIET NOBEREE E25-5EW454 ErrLUENT AND MASTE DIBftEnr. IEPORT Januarv , __lff)TEROUGE 4'Jene ' t ' . 1993 ,

.Q % p.S t ,

LIGITID EFFIREETE - Barrt2 EIR .

UNITS 2ET SIR 2ND QIR 3RD QTB 4TH OTR

.. 4 S. LIQUID ErrLUENTS t,,. ,

ci H-3 1.93E+2 5.70E+2 Cr-51 't.52E-2 3.45E-3 Mn-54 4.848-4 3.60E-4' Fe-55 < 122

• Co-57 2.66E-5 1.48E-5 Co-58 3.10E-2 2.09E12 Fe-59 1.79E-3 6.80E-4 -

Co-60 6.53E-3 4.48E-3 Zn-65 ,

1.32E-4 2.76E-6

~

Br-82 1.04E-5 (LLD Kr-85 0 < IID 2.14E-3 C1 1.34E-3 Nb-95 1.13E-3 C1 7.26E-4 8.12E-4 Zr-95 C1 3.89E-5 <LLD Mo-99 C1 1.07E-5 < LLD Ru-103 C1 1.04E-4 9.97E-5 Ru-105 Ag-110m C1 2.98E-5 1.76E-4 Su-113 Ci 8.20E-5 6.69E-5 Su-117m C1 4.26E-5 2.25E-6 Sb-122 C1 1.79E-4 < LLD

! Sb-124 ,

ci 5.%E-3 9.11E-4 i Sb-125 C1 3.95E-2 1.2SE-2

• Analysis done by offsite vendor. Results not available Report Page j_ of 12.

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UNIT 1 DOCERT EDISER SM 454 '

ETTLUENT AND MmSTE DISPWE. REPORT  !

January 1993 TEBOUGE J""" 1993

, - , j LIQUID EFFIREMIE - BREX MEME l 1

tErITs 1st gra 2ND QTa 3RD QTR 4TE QTR E. LIQUID ETTLUENTS Sb-126 8.80E-3 < LLD Te-125m 1.11E-2 1.43E-2' l C1 l I-131 9.60E-4 < LLD ' l Xe-131m

" 1.25E-3 < LLD i

4 CL Xe-133 9.29E-2 5.19E-3 i i

Xe-133m 8.98E-4 < LLD Xe-135 7.26E-5 3.53E-5

• - CA Cs-134 5.25E-5 7.78E-5 Cs-136 d < LIA < LLD Cs-137 d 3.19E-4 1.16E-4 Sr-89 U 7.26E-2

• Sr-90 C1 < Lgp a Ba/I4-140 C1 < LLD < LLD Ci C1 C1 C1 CL C1 h

C1

. C1 CL

~

• Analysis done by offsite vendor. Results not available Report Page 9 of 1 Gyhy

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ggacus Errr.terrs everer or arr. wrrnm tarITS 1sT DIR 2ND QTR 3RD QTR 4TH QTR A. TISSION AND ACTIVATION GAS RELEASES

1. Total Release Activity C1 1.70E+1 4.92E-1

2. Maximum Release Rate uC1/sec 1.69E+3 1.31E+1 for Quarter

3.  % of 10CTR20 Limits *

a. Whole Body (500 arem/yr)  %

0.03 0.00

b. Skin (3000 mrem /yr)  %

0.02 0.00

4.  % of 10CTR50 Limits

a. Gama Quarterly (5 mrad)  % 0.00 0.00

b. Beta Quarterly (10 mrad)  % 0.00 0.00

c. Gamma Annual (10 mead)  % 0,00 0,00

d. Beta Annual (20 stad)  % 0.00 0.00 l

B. IODINE RELEASES **

1. Total I-131/I-133 Activity C1 1.54E-4 <LLD I C. PARTICULATE (>8 day half-life) RELEASES **

1. Gross Activity Ci <g < tty

2. Gross Alpha Activity C1

< LLD < LLD for Quarter D. TRITIUM RELEASES **

1. Total Release Activity Ci 9.47E-1 4.61E-2 a  % of 10CTR20 limits is based on the maximum release rate for the period considered.

• • Iodine, particulate, and tritium % of 10CTR20/10CT150 limits are expressed as a total limit. See step E.

APPROVED Report Page 10 og 22 A N __

":  : BRP 1100-T7 i s , ,. - Revisisa 1 ,

ETEGI NUCLEAR POWER EIEEIM

. Ulf!T 2 DOCEET WEREBER 333 33. 4 .

\%S EFFLUENT AND NASTE DISPOEAL REPORT January 1993_ TEROUGg Jana v 1993 pQ,b ,

CAEEnmt EFFLDEltTE - EMAlh2IM W BEL MEr.EXEEE (CET)

UNIT 5 IST GIR 2ND QIR 3RD 7II 4XE QTR E. SUM OF IODINE, PARTICULATE D8 day half-life), M TRITIUM wr.nsu

1. Total Activity CA 9.4 3-2 4.61E-2_

2.  % of 10CFR20 Limit ,

a. Any organ (1500 mres/yr)  %

0.00 0.00

3.  % of 10CFR50 Limit I

a. Quarterly Any organ  %

0.00 0.00 (7.5 mrom)

b. Annual Any Organ  %

0.00 0.00' (15.0 mres)

-#...., , , , , , , . -p, ,, . .. . - - ... . . ,

F. FISSION AND ACTIVATIN GAS RELEASES Xe-131m 2.23E-1 6.03E-3 C1 Xe-133m 7.47E-2 1.66E-3 C1 Xe-135m < Li2 < LLD C1 Xe-133 1.60E+1 2.40E-1 Xe-135 C1 1.10E-2 8.71E-3 Kr-85m C1 1.91E-4 1.83E-4 kr-85 d 6.87E-1 2.23E-1 Kr-87 C1 <D <LLD Kr-88 C1 (LLD '<LLD Ar-41 C1 1.75E-2 1.91E-2 C1 C1 Report Page 11 of 22 l

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CASE 005 EFrGERTS - YERT 52hCK EELEnEEE - B&TCH REE3R (CWT)

UNITE 1ET QIR 2ND Q2E 3RD QTR 4TE QTE G. IODINE m xanES I-131 l Ci *

• I-133 l I-135 E. PARTICULATE (>8 day half-life) RELEASES C1 1 Sr-89 Sr-90 *

• C1 l

~ ~

1 ct t

Ci j .

• Value reported as continuous Release Mode.

aAsurms ErrrRElrEE - TEET BERCE RELEREEE - GETIERIOmf kEmq

r. FISSION AND ACTIVATIGt GAS m 21RES Xe-131m < LLD < LLD Xe-135m < LLD < LLD Xe-133 4.02E0 1.02E-1 Ie-135 < LLD < LLD Kr-85m < LLD < LLD C1 Kr-85 < LLD < LLD I

Kr-88 < LLD < LLD C1 Ar-41 < LLD < LLD APPROVED Report Page 1 of 1 APR 261993

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1 3

, sap 1100-T7 Revicies 1 BTEON NUCLEAR POIER STRIICE

, gyry 2 DOCEET NthmEE 525-50 455 EFFLUENT AND WA5TE DISPOSAL REPORT January , 1993 vaarnna June ,

1993 , ,

cAstatrs ErrrEEIrrs - TEIIT STkCK EELEhEEE - HErrrimatf5 MIFE (CEErf)

UNITS IST QTR 2ND 011t 3RD QII 4TE QTR J. IODINE RELEASES I-131 1.54E-4 (LLD I-133 <LLD <LLD I-135 <LLD <LLD E. PARTICULATE (>8 day half-life) RELEASES Sr-89 <LLD

• i Sr-90 (LLD

• CL Ci CL  :

4

• Analysis done by offsite vendor. Rasults not available.

I t

i tratrIQ EFFfEMETE - EERIh2mf CT ALL RELERREE F. FISSION AND ACTIVATION GAS RELEASES

1. Total Activity Released C1 1.95E-1 5.40E-2

2. Average Concentration ucl/ml 7.86E-8 2.08E-8 Released for Quarter

3.  % of 10CFR50 Limits

a. Quarterly Whole Body  %

0.04 0.10 (1.5 arem) i

b. Quarterly Any Organ  %

0.09 0.11 j

(5.0 mres)

c. Annual Whole Body  %

0.02 0.06 (3.0 mres) )

d. Annual Any Organ  %

(10.0 mrea) 0.04 0.06 )

i APPROVED i

Report Page 13 of 22 APP, 261993 l

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'..'. ; , , e e , , . , 'C ' Revisica 1 NEEN NUCLEAR MBER 3333 N 4,..

UNIT 2,,DOCEET MBSER'33 X EEMENT AND WESM DIERMht EEMET

'[ January , 1993TamREg June .E g@

g caszms amarrrs - smenTrca er um nELuasus (corr)

UNITS 252 GER 2ND QIR 3RD QTE 4TE QIR N. TRITIUM

1. Total Activity Released C1 1.9342 5.70E+2

2. Average concentration #C1/81 7.785-5 2.19E-4 Released for Quarter

3.  % of Limit 2.59m 7.30E0 1 (3.00E-3 oci/al) l j

j N. DISSOLVED NOBLE GASES .

i l ty.  ;

1. Total Activity seleased M 9.51E-2 7.36E-3 J' i l

2. Average Concentration uci/mi 3.835-8 2.83E-9 Released for Quarter l

3.  % of Limit '

1.92E-2 1.42E-3  !

(2.00E-4 uC1/ml)

O. GROSS ALPHA

1. Total Activity Released Ci g

2. Average Concentration uci/mi 0.00 0.00 Released for Quarter P. VOLUME OF WASTg err. m ED liters 4.29E+6 4.71E+6 Q. VOLUME OF DILUTION WATER liters 2.48E+9 2.60E+9 LItxrID EFFEREETE - 6 M R. LIQUID EFTLUENTS C1 e

• Sr-89 C1 . .

Sr-90

~

Xe-133 C1 .

• Fe-55 C1 Ci Report Page 14 of 2.2. .

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al BRP 1100-T7 Revici.r.2 1 i BYIGt NUCLEAR PONER mTmerrar i a UNIT 2 DOCIET NEIMBER 535-5g.,455 ETTLUENT AND NASTE DISPOB&L REPORT January , 1993 TEROUGg June , __1993 LICITID EFFIREETE - BRIER EDE l

1 l

UNITS IsT OIR 2ND QTR 3an gra 4TH QTR 1

5. LIQUID ETTLUENTS '

H-3 1.93E+2 5.70E+2 Cr 1.62E-2 3.45E-3 l U

Mn-54 4.84E-4 3.60E-4 Fe-55 < LLD

• l l C1 Co-57 2.66E-5 1.4BE-5 l Co-58 Ci I 3.10E-2 2.09E-2 Fe-59 Ci l 1.79E-3 6.80E-4 l Co-60 E1' 6.53E-3 4.48E-3 Zn-65 1.32E-4 2.76E-6 i

• Br-82 U 1.04E-5 < LLD Kr-85 0 < LLD 2.14E-3 Nb-95 UI 1.13E-3 1.34E-3 Zr-95 Ci 7.26E-4 8.12E-4 Mo-99 01 3.89E-5 < LLD Ru-103 C1 1.07E-5 <LLD Ru-105 C1 1.04E-4 9.97E-5 Ag-110m 2.98E-5 1.76E-4 l l

C1 Sn-113 8.20E-5 6.69E-5 l l

Sn-117m 4.26E-5 2.25E-6 Sb-122 1.79E-4 <LLD ,

Sb-124 .

U 5.96E-3 9.11E-4 Sb-125 0 3.95E-2 1.28E-2 I i

• Analysisdonebyoffsitevendor.Regitsn available Report Page of MPROVED  !

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..  : BIP 1100-T7 a

• s .< : Revision 1 BTEst NUCLI&E M aguerrus

. UNIT 2 nnr-rut M E35. 80 455

• EFFLUENT AND M&SEE DI N REPORT January , 1993 2Eacum Juma

, 1993 ,

LIDUID EFFMIEEE - MGM IERIE UNITE 152 GEE IND 7IR 3RD QTR 4TE QTR 1

l

5. LIQUID EFFLUENTS Sb-126 8.M3 <LLD Te-125m 1.11E-2 1.43E-2 ,

ci . I I-131 9 . 61 5 - 4 < LLD  ;

Xe-131m a 1.25E-3

<LLD l

l Xe-133 9.29E-2 5.19E-3 Xe-133m 8.98E-4 <LLd Xe-135 7.26E-5 3.53E-5 Cs-134 a 5.25E-5 7.78E-5 El I Cs-136 <t1D < LLD C1 Cs-137 3.19E-4 1.16E-4 f

Sr-89 O 7.62E-2

• l Sr-90 Ci < LLD

• 1 i Ba/La-140 C1 <ID < LLD t

C1 Ci Ci i

C1 rj U l

Ci

I -

C1 C1

• Analysis.done by offsite vendor. Results not available Report Page 16 og 22 P OVED

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. BTECEI NUCLEAR NNIER 52322CN

. DNIT 1/2 DOCIET EEEEEE S2N-50 454 /455 EFFI.UEllT AND NhETE DISPOSAL IIPORT l

January ,

1993 guarnrm: ' June , 1993 . l EOLID RADItRCTIVE M1ETE ist GIREEIR 1993 g DISPOSITICH OF MATERIAL VOLUME (DESCRIPTICM, CLAS8, IEEE PER CURIES TIPE, AND SOLIDIFYING OF EBIPMENT PER DATE ACEttr) TRAMENET NTTCN CUBIC FT SHIPMENT Devatered Resin and DAW, 05 ch s A Unstable, Cask.

~

Exclusive Use Barnwell, SC 199.4 2.25 25 March DAW, Class A, 1993 Drums, None Exclusive Use Barnwell, SC '622.5 0.95 I

f 3

821.9 3.20 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 2 CUBIC FT CURIES Report Page 17 of 22 PROV@

(Final)

_ _ . _ , . . - . . - _ _ .- _ ..e _- . - __ . _ _ . - _____ ___ _ __

24'T Y.AfTN i gap 1100-T7

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l ETRGI NUCLEAR 343RR ST1223

" UNIT 1/2 DOCIET aummuta 325-50 454/455 EFFLUENT AMD M&EEE DISPOSAL REPORT January , 1993 TEumag Juna 1993 i

BOLID R&D70&cTIVE M&BTg 2nd WhETER 1993 g I i

DISPOSITIGt OF MATERIAL VOLUME (DESCRIPTICEt, CLASS, M3DE PER CURIES TTPE, AND SOLIDIFYING OF EEIPMENT PER DATE AGENT) TRANIPM E DESTIMATI M CUBIC FT SEIPMENT 14 May Dewatered Resin and DAW '

1993 gaAUnstable. Cask. Exclusive Use Barnwell. S.C. 199.4 7.00 16 June Dewatered Resin and DAW .

1993 Class A Unstable, Cask, .

None Exclusive Use Barnwell, S.C. 199.4 3.60 l

l 398.8 10.60 j QUARTERLT TOTALS - NUMBER OF SHIPMENTS: CUBIC FT CUEIES Report P m 18 of 22 PROV W (Final)

C.__. . _ . _ _ _ _ _

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'. BTRON NUCLEAR PONER STATION IFFLUENT AMD M&STI DISPOSAL REPORT JANUARY TO JUNE, 1993 j ADDEMDUM A. The following data is the estimated composition of Byron's solid waste.

1. Dry Active Waste (DAW) 2. Primary Resin 3. Radwaste Rosin I

H-3 0.48% H-3 0.18% H-3 0.35%

C-14 0.14% C-14 1.83% C-14 0.74%

Cr-51 32.31% th-54 8.12% Cr-51 1.41%

Mn-54 0.82% Fe-S5 38.07% Mn-54 2.63%

Fe-55 3.85% Co-57 0.56% Fe-55 19.65%

Fe-59 0.77% Co-58 9.64% Co-57 0.25%

Co-58 13.99% Co-60 25.38% Co-58 53.46%

Co-60 2.27% Ni-63 14.72% Fe-59 0.10%

Ni-63 1.13% Sr-90 0.07% .Co-60 11.79%

Sr-90 <0.01% Tc-99 <0.01% Ni-63 5.97%

Nb-95 34.72% Sn-117m <0.01% Zn-65 0.13%

1 Zr-95 8.68% Sb-124 <0.01% Sr-90 0.03%

Tc-99 <0.01% Sb-125 0.86% Mb 95 0.15%

Sn-133 0.31% .Te-125m <0.01% Zr-95 0.05%

I-129 <0.01% I-129 <0.01% Mo-99 <0.01%

Cs-134 0.11% Cs-134 0.19% T,c-99 <0.01%

Cs-137 0.41% Cs-137 0.32% Sn-113 <0.01%

Pu-238 <0.01% Pu-238 <0.01% Sb-124 <0.01%

Pu-239 <0.01% Pu-239 <0.01% Sb 125 0.30%

Pu-241 <0.01% Pu-241 0.06% I-129 <0.01%

Am-241 <0.01% Am 241 <0.01% I-131 0.05%

Cm 242 <0.01% Cm-242 <0.01% Cs-134 0.95%

Cm 244 <0.01% Cm-244 <0.01% Cs-136 0.01%

Cs-137 1.91%

La 140 <0.01%

Co-144 0.02%

Rf-181 <0.01%

Pu-238 <0.01%

Pu-239 <0.01%

Pu-241 0.02%

Am-241 <0.01%

Cm-242 <0.01%

Cm-244 <0.01%

B. There were no major changes or modifications to the PCP or to any liquid gaseous or solid radwaste treatment systems for this period. Byron l Station continues to utilise the services of Pacific Nuclear for dewatering and solidification services.

C. Error Analysis i

The following is an estimate of the errors associated with effluent monitoring and analysis. The est imate is calculated using the square root of the sum of the squares methodology.

(3635s/072791)

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

1. Gaseous Effluent 3  !

l l

Sampling error = 1 to 3.5% l Calibration error m.10% l Counting Statistics error = 5%

Vent Stack Flowrates error = 1.5%

Total error = 11 - 12%

2. Liquid Effluents i

Sampling error = 1%

Calibration error = 10%

Sample volume error = 1%

Discharged voltsee error = 2%

Total error = 10%

l

3. Waste Rosin +

1 l

Sampling error = 5%  !

Counting Statistics error = 7%

, Weight error = 1%

volume error = 5%

Total error = 10%

, 4. DAW l

Counting Statistica error = 7%  !

l Calibration error = 10% )

Weight error = 2%

l- Total error = 12.4%

D. Meteorological and envimntal impact information is reported in the Station Annual Radiological Envirnnanntal Operating Report as required by Technical Specifications 6.9.1.6.

E. No limits were exceeded in liquid hold up tanks as stated in Technical Specifications 3.11.1.4 or in waste gas decay tanks as stated in Technical l Specifications 3.11.2.6. ,

F. There were no irradiated fuel shipments during this period.

G. There were no elevated releases. All releases are considered ground level releases.

5 H. The Offsite Calculation Manual (ODCM) was revised in january 1993. This revision addressed cessments and rera==andations provided by the Nuclear

i Regulatory en==4seien in their Safety Evaluation Report (SER) and Idaho National Engineering Laboratory,in their Technical Evaluation Report (TER) . Two' primary modifications were made based on the SER/TER. First, in the past Commcowealth Edison calculated doses to adults, children and infants. Cn==anwealth Edison will now calculate does for the teenager, also. Inhalation and ingestion values were oben4nad frcus Regulatory Guide 1.109. Secondly, the Radiological Effluents and Monitoring Chapter of the ODCM (Chapter 10) was rewritten to specifically reflect how effluent

values and setpoints are determined. In additian, the daenhame of  ;

meteorological values utilized in CDCM calculations was expanded from I about three, years to ten years. 'this anamnet, based on site meteorology, provides a more representative basis.

(3635s/072793) ,

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ATTACEMENT A BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT FOR JANUARY THEOUGH JUNE, 1993 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455)

LLD VALUES IOR GASEOUS permaqEs t

Isotonea un fci/ml)

~

H-3 3.28E-17 Ar-41 1.72E-13 Mn-54 4.57E-19 Fe-59 9.70E-19 Co-58 4.66E-19 Co-60 7.03E-19 Kr-85 3.72E-11 Kr-85m 1.19E-12 Kr-87 3.40E-13 Kr-88 5.07E-13 Y-88 2.225-18 Sr-89 2.69E-17 Sr-90 9.23E-18 ,

Ru-103 3.84E-19 Ag-110m 7.04E-19 I-131 3.28E-18 I-132 5.35E-19

.I-133 5.20E-19 I-134 6.18E 19 I-135 2.09E-19 Xe-131m 5.12E-13 Ze-133 3.00E-13 Ze-133m 1.34E-13 Ze-135 7.91E-13 Ze-135m 1.70E-13 Cs-134 4.58E-19

.cs-136 4.38E-19 Cs-137 4.95E-19 Ba/La-140 2.98E-18 Co-144 2.03E-18 (3635s/072793)

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ATTACEMENT A. (' cont.)

BYRON NUCLEAR POWER STkTION EFFLUENT AND MASTE DISPOSAL REPORT FOR JANURRY TEROUGE JUNI, 1993 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455)

LLD VALUES FOR LIQUID RELERSES Isotones Ttn (cl /ml H-3 2.64E-12 Cr-51 2.21E-13 Mn-54 4.57E-19 I Fe-55 2.10E-14 l Fe-59 5.76E-14 1 Co-57 1.96E-14 Co 58 3.11E-14 Co-60 4.60E-14 Zn-65 6.56E-14 Br-82 3.44E-14 Kr-85 5.59E-12

'Br-39 2.55E-14 Sr-90 6.605-15 Nb-95 2.84E-14 Zr-95 5.62E-14 Mo-99 2.21E-13 Ru-103 2.99E-14 Ru-105 5.55E-14 Ag-110m 4.86E-14

, Sn-113 3.48E-14 l 'Sn-117m 2.08E-14 Sb-122 3.63E-14 Sb-124 2.77E-14 Sb-125 7.36E-14 Sb-126 2.65E-14 Te-125m 5.60E-12

• I-131 1.86E-13 Xe-13La 9.50E-13 Xe-133 5.35E-14 Ze-133m 1.96E-13 Ze-135 2.27E-14 Cs-134 3.20E-14 Cs-136 2.93E-14 Cs-137 3.43E-14 Ba/La-140 2.95E-14 Co-144 2.03E-18

- ~

(3635s/072793)

,