ML20136B627

From kanterella
Revision as of 11:27, 19 June 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Bnps Effluent & Waste Disposal Rept Jan-Dec 1996
ML20136B627
Person / Time
Site: Byron  Constellation icon.png
Issue date: 12/31/1996
From: Kofron K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-97-0017, BYRON-97-17, NUDOCS 9703110063
Download: ML20136B627 (40)
v • d • e


Text

Commonwealth I'dhon Company

$ T llyron Generating Station 1450 North German Church Itoad

  • Byron,. IL 6101n99 4

'Ilcl N1423 4-51 i1 March 5, 1997 LTR: BYRON 97-0017 FILE: 2.12.1522 Mr. A. Bill Beach Regional Administrator, Region III i U.S. Nuclear Regulatory Commission j 801 Warrenville Road I Lisle, Illinois 60532-4351

SUBJECT:

Annual Radiological Effluent Release Report Byron Station Unita 1 and 2 Facility Operating License Nos. NPF 37 and 66 NRC Docket Nos. 50-454 and 50-455 i l

Dear Mr. Beach:

Enclosed is the Annual Radiological Effluent Release Report for January l through December, 1996, for Byron Nuclear Power Station. Attached are the 10CFR20 and 10CFR50 Dose Calculations for 1996 Aquatic and Airborne Effluents for Units 1 and 2. This report is required by Technical l Specification 6.9.1.7.

Two copies of the report are provided for your use. Two copies will be forwarded to the Document Control Desk and one copy to the Senior Resident Inspector. 1 Sincerely,

). O K.L. Kof o ) k' Station MaI1ager d Byron Nuclear Power Station / l I KLK/DT/ba Attachment cc: Distribution List Attached 9703110063 961231 PDR ADOCK 05000454 R PDR t.

@$[$5E%kE%%%E A Unicom Company j

. _ . - _ _ . . - . _ _ . . _ _ _ . _ . ~ . . . _ _ _ _ . . . _ _ _ _ _ . _ . _ - _ ...__.__ __ ___._ - .__ _ _ . - . _ _ -

)

i 4

{ , ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT i

DISTRIBUTION LIST 4

4 i

Director of Nuclear Reactor Regulation - U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Region III a

{ Illinois Department of Nuclear Safety, Office of Nuclear Facility Safety j A.N.I.

i

! U.S. Environmental Protection Agency Air and Radiation Division - Region V

) Health Physicist Murray and Trettel, Inc.

Teledyne Brown Engineering Environmental Services Midwest Laboratory Environmental Law and Policy Center Byron Station Central Files, File Number 2.12.1522 Health Physics Services Supervisor - Byron Nuclear Power Station Radiological Environmental Monitoring Program Coordinator U.S. NRC Senior Resident Inspector - Byron Nuclear Power Station Health Physics Services Supervisor - Braidwood Nuclear Power Station Mr. Louis DelGeorge Nuclear Licensing Operations ODCM Coordinator, HPSD Health Physics Support Department Director (p:\97byltrs\970017.wpf)

4 J

. t i i --

l , BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JANUARY through DECEMBER 1996 j Supplemental Information 1

1. Regulatory Limits  !

1 1

i a. Fission'and activation gases: l i l

! Tech Spec Whole Body = 500 mrem / year j l Skin = 3000 mrem / year l 10CFR50 Gamma = 5 mrad / quarter; 10 mrad / year j- Beta = 10 mrad / quarter; 20 mrad / year i i

i b. Iodine: (summed with particulate, see below) i' c. Particulates with half-lives > 8 days: l

! l Tech Spec Organ = 1500 mrem / year

10CFR50 Organ = 7.5 mrem / quarter; 15 mrem / year l l I j d. Liquid effluents

! 10CFR50 Whole Body = 1.5 mrem / quarter; 3 mrem / year Organ = 5 mrem / quarter; 10 mrem / year i e. Total Effective Dose Equivalent l

1 j 10CFR20 TEDE = 100 mrem / year i l i

l 2. Maximum Permissible Concentration

! a. Fission and Activation Gases: 10CFR20 Appendix B Table 2 1 l b. Iodine: 10CFR20 Appendix B Table 2 l l c. Particulates: 10CFR20 Appendix B Table 2 l

d. Liquid Effluents: 10CFR20 Appendix B Table 2 j 3. Average Energy: This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.

4 l

j 4. Measurements and Approximations of Total Radioactivity i a. Fission and Activation Gases: Prior to release, the isotopic

content is determined. Released activity is calculated using l l

volume of release, which is determined by the change in tank or q containment pressure. Additional methods of calculation utilize i historical data and assign an isotopic mix which is representative I of normal vent stack isotopics. l i

Report Page 1 of 28

(p
97byhrs\970017.wpf) i

. t s '

, BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JANUARY through DECEMBER 1996 Supplemental Information (continued)

b. Particulate, Tritium and Iodine sampling media for the plant vent stacks are collected and isotopically analyzed weekly for the plant vent stacks.
c. Liquids effluents: Batch releases are isotopically analyzed prior to release. Tetal release activity is calculated using volume of release.

Total tritirm activity released is calculated from the highest of a monthly circ ulating water blowdown composite 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 Attachment A.
5. Batch Releases:

l a. Liquid:

1. Number of batch releases = 228
2. Total time period for batch releases = 19,153 minutes
3. Maximum time period for a batch release = 266 minutes
4. Average time period for a batch release = 84 minutes
5. Minimum time period for a batch release = 3 minute
6. Average stream flow during periods of release of effluent I into a flowing stream = 7,690 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 = 340
2. Total time period for batch releases = 161,289 minutes
3. Maximuu. time period for a batch release = 18,115 minutes
4. Average time period for batch releases = 474.4 minutes

( 5. Minimum time period for a batch release - 9 minutes l

6. Abnormal Releases:
a. Liquid - None
b. Gaseous - None l

l (p:97byttrs\970017 wpf)

I

~

BRP 6100-6T1

, , Revision 3 EYRON NUCLEAR POWER STATION l UNIT L DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT January , 1996 THROUGH December , 1996 l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1

i UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR A. FISSION AND ACTIVATION GAS RELEASES i 1. Total Release Activity Ci 6.20E+0 1.46E+1 7.63E-1 5.77E-1 j e

i 2. Maximum Release Rate for Quarter uCi/sec 6.79E+1 1.40E+2 1.01+0 1.72E+0 l

. 3.  % of Tech Spec Limits

  • l a. Whole Body '.5 JO mrem /yr)  % 0.00 0.00 0.00 0.00 i
b. Skin (3000 mrem /yr)  % 0.00 0.00 0 00 0.00 l
4.  % of 10CFR50 Limits

\

l

a. Gamma Quarterly (5 mrad)  % 0.00 0,00 0,00 o,00
b. Beta Quarterly (10 mrad)  % 0.00 0.00 0.00 0.00 l c. Gamma Annual (10 mrad)  % 0.00 0.00 0.00 0.00 4
d. Beta Annual (20 mrad)  % 0.00 0.00 0.00 0.00 i

j B. IODINE RELEASES **

i

1. Total I-131/I-133 Activity Ci <LLD 2.36E 4 <LLD <LLD l

C. PARTICULATE (>8 day half-life) RELEASES **

1. Gross Activity Ci <LLD <LLD 7.63E 5 1.49E-5
2. Gross Alpha Activity for Quarter Ci <LLD <LLD 3.04E 6 <LLD D. TRITIUM RELEASES **
1. Total Release Activity Ci 1.35E+1 1.65E+1 1.97E+0 3.36E-1
  • % of Tech Spec limita is based on the maximum release rate for the period considered.
    • Iodine, particulate, and tritium are expressed as a total limit. See step E.

l Report Page 3 of 28 (p:97byttn4970017.wp0

4 BRP 6100-6T1

, Revision 3

. EYRON NUCLEAR POWER STATION

$ UNIT ,_.l__. DOCKET NUMBER STN-50-454 i RADIOACTIVE EFFLUENT RELEASE REPORT

. Januarv , 1996 THROUGH December , 1996 1

1 Q&jEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (CONT) '

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR l

E. TOTAL OF IODINE, PARTICULATE (>8 day half-life), AND TRITIUM RELEASES i

I

1. Total Activity Ci 1.35E+1 1.65E+1 1.97E+0 3.36E-1 1
2.  % of Tech Spec Limit a
a. Any Organ (1500 mrem /yr)  % 0.00 0.00 0.00 0.00
3.  % of 10CFR50 Limit 4 a. Quarterly Any Organ (7.5 mrem)  % 0.05 0.10 0.03 0.00

{ b. Annual Any Organ (15.0 mrem)  % 0.03 0.05 0.02 0.00

1 1

i^ i GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE 1

l F. FISSION AND ACTIVATION GAS RELEASES '

l ,

j Ar-41 C1 1.06E-3 2.22E-3 2.31E-3 5.01E-4 Kr-85m Ci 2.42E-4 8.85E-5 <LLD <LLD

Kr-85 Ci 4.23E-2 7.14E-2 3.58E-3 <LLD i

Kr-88 Ci 2.42E-4 <LLD <LLD <LLD

} Xe-131m Ci 1.86E-2 3.08E-2 <LLD <LLD Xe-133m Ci 5.12E-3 9.11E-3 9.84E-4 1.22E-3 l,

Xe-133 Ci 6.05E+0 1.35E+1 1.33E-1 2.14E-1 Xe-135m Ci 4.01E-5 <LLD <LLD <LLD Xe-135 Ci 8.30E-3 5.00E-3 2.77E-4 2.30E-3

] Ci Ci i

1 Ci i-i i Report Page 4 of 28 i (p:97byttrs\970017.wpf) a

BRP 6100-6T1

, , Ravision 3

, XYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN 50-454 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , ,1995 THROUGH December , 1996 GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH NODE (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR G. IODINE RELEASES I-131 Ci * * *

  • I-133 Ci * * *
  • I-135 Ci * * *
  • I H. PARTICULATE (>8 day half-life) RELEASES Sr-89 Ci * * *
  • l I

ci Ci Ci

  • Value reported as CONTINUOUS MODE l

l GASEOUS EFFLUENTS - VENT STACK RELEASES - CONTINUOUS MODE i I. FISSION AND ACTIVATION GAS RELEASES l Xe-133 Ci 7.02E-2 9.83E-1 6.23E-1 3.63E-1 Ci l Ci l Ci Ci l Ci Ci Ci l Report Page 5 of 28 (p:97byhrs\970017.wpf)

BRP 6100-6T1

, , Ravision 3 BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN-50-454 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 GASEOUS EFFLUENTS - VENT STACK RELEASES - CONTINUOUS MODE (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR J. IODINE RELEASES I-131 Ci <LLD 2.31E-4 <LLD <LLD I-133 Ci <LLD 4.54E-6 <LLD <LLD I-132 Ci <LLD 1.74E-4 <LLD <LLD K. PARTICULATE (>8 day half-life) RELEASES Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD 6.47E-5 1.80E-6 Co-60 Ci <LLD <LLD 1.07E-5 1.21E-5 Te-123m Ci <LLD <LLD 9.70E-7 <LLD S r. - 113 Ci <LLD <LLD <LLD 1.04E-6 Zn-69m Ci <LLD <LLD <LLD 5.48E-7 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES l

L. FISSION AND ACTIVATION PRODUCT RELEASES

1. Total Activity Released Ci 8.72E-2 1.42E+0 5.26E-1 3.83E-2
2. Average Concentration Released uCi/ml 3.32E-8 7.21E-7 2.43E-7 1.50E-8
3.  % of 10CFR50 Limits l
a. Quarterly whole Body 0.11 0.15 0.95 0.05
b. Quarterly Any Organ 0.04 0.22 0.36 0.03
c. Annual Whole Body 0.06 0.08 0.48 0.03
d. Annual Any Organ 0.02 0.11 0.18 0.02 Report Page 6 of 28 (p:97byltrs\970017.wpf)

1 BRP 6100 6T1

. , Ravlsion 3 a .

EYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN 50-454 RADIOACTIVE EFFLUENT RELEASE REPORT

Januarv , 1996 THROUGH December , 1996 a

i LIQUID EFFLUENTS - SUMMATION OF ALL REI nSES (COI;T) ,

l i

UNITS IST QTR 2ND QTR 3RD QPR 4TH QM M. TRITIUM i 1. Total Activity Released Ci 1.49E+2 1.38E+2 6.862+1 3.49E+2 l

2. Average Concentration Released uCi/ml 5.70E-5 7.00E-5 3.18E-5 1.37E-4
3.  % of 10CFR20 Limit  % 5.70 7.00 3.18 13.67 i

t N. DISSOLVED NOBLE GASES

1. Total Activity Released Ci 5.98E-2 7.95E-1 4.61E-2 1.16E-2 j 2. Average Concentration Released uCi/ml 2.28E-8 4.04E-7 2.14E 8 4.56E-9

? 3.  % of Admin Tech Regt. Limit  % 1.14E-2 2.02E-1 1.07E-2 2.28E-3 O. GROSS ALPHA J 1. Total Activity Released Ci <LLD <LLD <LLD <LLD 4

2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD P. VOLUME OF WASTE RELEASED PER UNIT liters 1.59E+6 3.56E+6 3.95E+6 1.77E+6 Q. VOLUME OF DILUTION WATER PER UNIT liters 2.62E+9 1.97E+9 2.16E+9 2.55E+9 LIOUID EFFLUENTS - CONTINUOUS MODE R. LIQUID EFFLUENTS Fe-55 Ci * * *
  • Sr-89 Ci * * *
  • Ci Ci Ci l
  • Value reported as BATCH MODE Report Page 7 of 28 (p:97byttrs\970017.wp0

BRP 6100-6T1

, , Rsvision 3 BYRON NUCLEAR POWER STATION UNIT 1 DOCT.ET NUMBER STN 50-4ji4 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 LIQUID EFFLUENTS - BATCH MODE UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR o

S. LIQUID EFFLUENTS Fe-55 Ci 4.78E-3 1.05E+0 1.22E-2 5.43E-3 Sr-89 Ci 3.02E-4 5.66E-4 <LLD <LLD Sr-90 Ci 1.32E-4 <LLD <LLD <LLD H-3 Ci 1.49E+2 1.38E+2 6.86E+1 3.49E+2 Ar-41 Ci 1.62E-4 7.56E-4 1.83E-3 1.98E-5 Cr-51 Ci 1.08E-3 2.73E-2 9.29E-3 2.35E-4 Mn-54 Ci 7.96E-4 1.49E-2 3.16E-3 4.55E-4 Fe-59 Ci 2.45E-4 5.35E-4 3.13E-3 1.76E-5 Co-57 Ci 2.39E-5 1.24E-3 3.46E-4 1.14E-4 Co-58 Ci 3.30E-3 3.64E-2 3.66E-2 8.27E-2 Co-60 l Ci 1.66E-2 1.58E-1 3.19E-2 7.02E-3 l l

Zn-65 Ci 6.22E-5 3.23E-3 3.82E-4 6.53E-4 Kr-85 Ci 3.93E-3 3.46E 2 4.08E-2 1.13E-2 Kr 88 Ci 1.75E-3 <LLD 2.72E-4 <LLD Sr-92 Ci 4.197-5 5.96E-4 <LLD 2.20E-6 Nb-95 Ci 1.20E-4 4.55E-3 1.32E-3 1.78E-4 l Zr-95 Ci 1.99E-6 2.28E-3 5.10E-4 1.11E-4 Aa-110m Ci 6.17E-4 1.75E 3 3.70E-4 1.95E-5 Sn-113 Ci <LLD 3.91E-4 1.75E-5 <LLD Report Page 8 of 28 (p:97byltrs\970017.wpf)

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

BRP 6100-(T1

]

, , Revision 3 EYRON NUCLEAR POWER STATION l , ,

UNIT _1 .. DOCKET NUMBER STN-50-454

> a RADIOACTIVE EFFLUENT RELEASE REPORT i Januarv , 1996 THROUGH December , 1996 5

LIQUID EFFLUENTS BATCH MODE (CONT.)

UNITS IST Q'.'R 2ND QTR 3RD QTR 4TH QTR J

S. LIQUID EFFLUENTS (CONT.)

l Te-123m Ci 9.15E-3 2.64E-2 6.97E-3 4.77E-4 Te-125m Ci 1.38E-3 1.50E-2 3.25E-2 1.00E 2

Sb-122 Ci <LLD 1.18E-4 8.19E-4 <LLD

! Sb-124 Ci 1.60E-2 2.17E-2 8.33E-2 5.33E-4 Sb-125 Ci 2.99E-2 2.89E-2 4.59E-2 3.65E-3 Sb-126 Ci <LLD 6.35E-6 2.22E-1 <LLD I-131 Ci <LLD 6.30E-4 <LLD <LLD

! I-132 Ci <LLD 4.47E-4 6.84E-5 <LLD

]

I-133 Ci <LLD 1.89E-5 <LLD <LLD l Xe-131m ___ Ci 2.68E-4 1.12E-2 <LLD <LLD

Xe-133 Ci 5.33E-2 7.43E-1 3.26E-3 2.71E-4

)

Xo-133m Ci 3.72E-4 5.35E-3 <LLD <LLD

)'

Xe-135 Ci 2.22E-5 3.91E-4 1.67E-5 5.13E-6 Cs-134 Ci 1.35E-3 1.44E-3 1.42E-2 1.54E-4 Cs-137 Ci 4.24E-4 6.63E 4 2.60E-3 3.37E-5 Ce-144 Ci <LLD <LLD 8.35E-5 <LLD Cu-64 Ci 8.12E-4 <LLD <LLD <LLD Te-132 Ci <LLD <LLD 1.40E-5 <LLD Pr-144 Ci <LLD <LLD 8.06E-2 <LLD I-134 Ci <LLD <LLD 4.34E-4 <LLD Hf-181 Ci <LLD <LLD 1.25E-5 <LLD T. 10CFR20 PUBLIC TEDE COMPLIANCE

1.  % OF 10CFR20 TEDE LIMIT  % 4.42E-3 1.01E-2 1.10E-2 8.67E-4 Report Page 9 of 28 (p:97byltrs\970017.wp0

BRP 6100-6T1

. Rsvision 3 BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50-455 RADIOACTIVE EFFLUENT RELEASE REPORT January , 1996 THROUGH December , 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR A. FISSION AND ACTIVATION GAS RELEASES

1. Total Release Activity C1 1.39E+0 2.51E+0 7.29E-1 4.66E-1
2. Maximum Release Rate for uCi/sec 6.79E+1 1.40E+2 2.22E+0 1.72E+0
3.  % of Tech Spec Limits *
a. Whole Body (500 mrem /yr)  % 0.00 0.00 0.00 0.00
b. Skin (3000 mrem /yr)  % 0.00 0.00 0.00 0.00
4.  % of 10CFR50 Limits
a. Gamma Quarterly (5 mrad)  % 0.00 0.00 0.00 0.00
b. Beta Quarterly (10 mrad)  % 0.00 0.00 0.00 0.00
c. Gamma Annual (10 mrad)  % 0.00 0.00 0.00 0.00
d. Beta Annual (20 mrad)  % 0.00 0.00 0.00 0.00 B. IODINE RELEASES **
1. Total I-131/I-133 Activity Ci <LLD 2.30E-4 <LLD <LLD C. PARTICULATE (>8 day half-life) RELEASES **
1. Gross Activity Ci <LLD <LLD 6.73E-6 '7.67E-6
2. Gross Alpha Activity for Ci <LLD <LLD <LLD <LLD Quarter D. TRITIUM RELEASES **
1. Total Release Activity Ci 2.97E-1 1.62E-1 4.43E+0 1.13E-1

% of Tech Spec limits is based on the maximum release rate for the period considered.

I

    • Iodine, particulate, and tritium are expressed as a total limit. See step E.

l Report Page 10 of 28 ,

(p:97byhrs\970017.wpt) I j

BRP 6100-6T1

. Ravision 3

  • ~

BYRON NUCLEAR POWER STATION

, , UNIT 2 _ DOCKET NUMBER STN-50-455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASE _3 (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR E. TOTAL OF IODINE, PARTICULATE (>8 day half-life), AND TRITIUM RELEASES

1. Total Activity Ci 2.97E-1 1.62E-1 4.43E+0 1.13E-1
2.  % of Tech Spec Limit
a. Any Organ (1500 mrem /yr)  % 0.00 0.00 0.00 0.00
3.  % of 10CFR50 Limit
a. Quarterly Any Organ (7.5 mrem)  % 0.00 0.01 0.06 0.00
b. Annual Any Organ (15.0 mrem)  % 0.00 0.00 0.03 0.00 GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE l

l F. FISSION AND ACTIVATION GAS RELEASES Ar-41 Ci 1.45E 2 1.04E-2 3.53E-3 5.01E-4 Kr-85m Ci 2.42E-4 8.85E-5 (LLD 9.90E 4 Kr-85 Ci 4.23E-2 7.14E-2 3.58E-3 <LLD Kr-88 Ci 2.42E-4 <LLD <LLD 1.76E-3 Xe-131m Ci 1.86E-2 3.08E 2 <LLD <LLD Xe-133m Ci 5.12E-3 9.11E-3 9.84E-4 1.22E-3 Xe-133 Ci 1.24E+0 1.40E+0 9.77E-2 1.03E-1 Xe-135m Ci 4.01E-5 <LLD <LLD <LLD Xe-135 Ci 5.75E-3 5.00E-3 2.77E-4 2.30E-3 Ci Ci Ci Report Page 11 of 28 (p:97byttrs\970)t7.wp0

BRP 6100-6T1

,, Ravision 3

' BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50-455 RADIOACTIVE AFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR G. IODINE RELEASES I-131 Ci * * *

  • I-133 Ci * * *
  • I-135 Ci * * *
  • H. PARTICULATE (>8 day half-life) RELEASES 1

1 Sr-89 Ci * * *

  • 1 Ci

,1 j

j Ci l Ci

)

4 1

  • Value reported as CONTINUOUS MODE GASEOUS SFFLUENTS - VENT STACK RELEASES - CONTINUOUS MODE I. FISSION AND ACTIVATION GAS RELEASES j

Xe-133 Ci 7.02E-2 9.83E-1 6.23E-1 3~.63E 1 Ci ci ci Ci Ci Ci Ci Report Page 12 of 28 (p:97byttrs\970017.wp0

BRP 6100-6T1

,, Ravicion 3 l EYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50-455 I '

RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 a GASEOUS EFFLUENTS - VENT STACK RELEASES - CONTINUOUS MODE (CONT) 1 i UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR i

i J. IODINE RELEASES I

j I-131 Ci <LLD 2.28E 4 <LLD <LLD a

I-133 Ci <LLD 1.788-6 <LLD <LLD t l I-132 Ci <LLD 1.21E-5 7.76E-7 <LLD 1

K. PARTICULATE (>8 day half-life) RELEASES i

i Sr-89 Ci <LLD <LLD <LLD <LLD

]

Sr-90 Ci <LLD <LLD <LLD <LLD i

Co-58 Ci <LLD <LLD 4.19E-6 1.56E-6 Co 60 Ci <LLD <LLD 2.54E-6 6.11E-6 j Ci j LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES L. FISSION AND ACTIVATION PRODUCT RELEASES

1. Total Activity Released Ci 8.723-2 1.42E+0 5.26E-1 3.83E-2
2. Average Concentration Released uCi/ml 3.32E-8 7.21E-7 2.43E-7 1.50E 8
3.  % of 10CFR50 Limits  ;

l

a. Quarterly Whole Body 0.11 0.15 0.95 0.05  ;

l

b. Quarterly Any Organ 0.04 0.23 0.36 0.03 1
c. Annual Whole Body 0.06 0.08 0.48 0.03 1
d. Annual Any Organ 0.02 0.12 0.18 0.02  ;

i l

Report Page 13 of 28 (p:97byttrs\970017.wr0 l i

l BRP 6100-6T1

,, Ravision 3

, BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN 50-455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 LIQUID EFFLUENTS - SUNNATION OF ALL RELEASES (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR M. TRITIUM

1. Total Activity Released Ci 1.49E+2 1.38E+2 6.86E+1 3.49E+2
2. Average Concentration Released uCi/ml 5.70E- 7.00E-5 3.18E-5 1.37E 4 9-
3.  % of 10CFR20 Limit  % 5.70 j 00 3.18 13.67 N. DISSOLVED NOBLE GASES
1. Total Activity Released Ci 5.98E-2 7.95E-1 4.61E 2 1.16E-2
2. Average Concentration Released uCi/ml 2.28E-8 4.04E-7 2.14E-8 4.56E-9
3.  % of Admin Tech Regt. Limit  % 1.14E-2 2.02E-1 1.07E-2 2.28E-3 i l

O. GROSS ALPHA

1. Total Activity Released Ci <LLD <LLD <LLD <LLD
2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD P. VOLUME OF WASTE RELEASED PER UNIT liters 1.59E+6 3.56E+6 3.95E+6 1.77E+6 Q. VOLUME OF DILUTION WATER PER UNIT liters 2.62E+9 1.97E+9 2.16E+9 2.55E+9 LIOUID EFFLUENTS - CONTINUOUS MODE R. LIQUID EFFLUENTS Fe 55 Ci * * *
  • Sr 89 Ci * * *
  • Sr 90 Ci * * *
  • Ci Ci Ci
  • Value reported as BATCH b10DE Report Page 14 of 28 (p:97byttrs\070017.wpf)

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

BRP 6100-6T1

., Revision 3

. BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN 50 455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , _1996 THROUGH December , 1996 4

i LIQUID EFFLUENTS - BATCH NODE

.i a

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR

S. LIQUID EFFLUENTS 1

Fe-55 _ Ci 4.78E 3 1.05E+0 1.22E 2 5.43E-3 Sr-89 Ci 3.02E-4 5.66E-4 <LLD <LLD Sr-90 Ci 1.32E 4 <LLD <LLD <LLD 1

H-3 Ci 1.49E+2 1.38E+2 6.86E+1 3.49E+2 Ar-41 Ci 1.62E-4 7.56E-4 1.83E-3 1.98E-5 Cr-51 Ci 1.08E-3 2.73E-2 9.29E-3 2.35E-4 Mn-54 Ci 7.96E-4 1.49E-2 3.16E-3 4.55E-4 j Fe-59 Ci 2.45E-4 5.35E-4 3.13E-3 1.76E-5 Co-57 Ci 2.39E-5 1.24E-3 3.46E-4 1.14E-4

_ Co-58 Ci 3.30E-3 3.64E-2 3.66E-2 8.27E-2 f Co 60 Ci 1.66E-2 1.58E-1 3.19E-2 7.02E-3 Zn-65 Ci 6.22E-5 3.23E-3 3.82E-4 6.53E-4 l

Kr-85 Ci 3.93E-3 3.46E-2 4.08E-2 1.13E-2 1

Kr-88 Ci 1.75E-3 <LLD 2.72E-4 <LLD 1

Sr-92 Ci 4.19E-5 5.96E-4 <LLD 2.20E-6 l Nb-95 Ci 1.20E-4 4.55E-3 1.32E-3 1.78E 4 1

Zr-95 C1 1.99E-6 2.28E-3 5.10E-4 1.11E-4 Aa-110m Ci 6.17E-4 1.75E-3 3.70E-4 1.95E-5 1

Sn-113 Ci <LLD 3.91E-4 1.75E-5 <LLD

'I i

e i

4 Report Page 15 of 28 (p:97byltrs\970017 wp0

BRP 6100-6T1

., Rsvision 3 l BYRON NUCLEAR POWER STATION l UNIT 2 DOCKET NUMBER STN-50-455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 l LIQUID EFFLUENTS - BATCH MODE (CONT . )

l l

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR l

S. LIQUID EFFLUENTS (CONT.) I Te-123m Ci 9.15E-3 2.64E-2 6.97E-3 4.77E-4 l Te-125m Ci 1.38E-3 1.50E-2 3.25E-2 1.00E-2 Sb-122 Ci <LLD 1.18E-4 8.19E-4 <LLD l l

Sb-124 Ci 1.60E-2 2.17E-2 8.33E-2 5.33E-4 l Sb-125 Ci 2.99E-2 2.89E-2 2.22E-1 3.65E-3 Sb-126 Ci <LLD 6.35E-6 3.77E-4 <LLD I-131 Ci <LLD 6.30E-4 <LLD <LLD l

I-132 Ci <LLD 4.47E-4 6.84E-5 <LLD l

I-135 Ci <LLD 1.89E-5 <LLD <LLD Xe-131m Ci 2.68E-4 1.12E-2 <LLD <LLD Xe-133 Ci 5.33E-2 7.43E-1 3.26E-3 2.71E-4 l l

Xe-133m Ci 3.72E-4 5.35E-3 <LLD <LLD l l

Xe-135 Ci 2.22E-5 3.91E-4 1.67E-5 5.13E-6 Cs-134 C1 1.35E-3 1.44E-3 1.42E 2 1.54E 4 Cs-137 Ci 4.24E-4 6.63E-4 2.60E-3 3.37E-5 Ce-144 Ci <LLD <LLD 8.35E-5 <LLD Qv-64 Ci 8.12E-4 <LLD <LLD <LLD Te-132 Ci <LLD <LLD 1.40E-5 <LLD Pr-144 Ci <LLD <LLD 8.06E-2 <LLD I-134 Ci <LLD <LLD 4.34E-4 <LLD Hf-181 Ci <LLD <LLD 1.25E-5 <LLD T. 10CFR20 PUBLIC TEDE COMPLIANCE i 1.  % OF 10CFR20 TEDE LIMIT  % 1.26E-3 4.01E-3 1.29E-2 7.14E-4 Report Page 15 of 28 (p:97byttrs\970017.wpf)

BRP 6100-6T1

., Ravision 3 BYRON NUCLEAR POWER STATION

, UNIT 1/2 DOCKET NUMBER STN 50-454/455 RADICACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 SOLID RADIOACTIVE WASTE 1st QUARTER 1996 YEAR DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES TYPE, AND SOLIDIFYING OF SHIPMENT PER DATE AGENT) TRANSPORT DESTINATION CUBIC FT SHIPMENT Steam Generator Secondary Exclusive Oak Ridge 788 0.010 01/15/96 Sludge, Low Specific Activity, Use TN NOS 7 UN2912 srong-tight container, none l

01/22/96 Steam Generator Secondary Exclusive Oak Ridge 591 0.008 Sludge, Low Specific Activity, Use TN NOS 7 UN2912 srong-tight j container, none l 1

03/25/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 4.17 l Stable, HIC, none Use SC l 1581.1 4.19 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 3 CUBIC FT CURIES (P:97byttrs\970017.wp0

BRP 6100-6T1

,, Rsvision 3 BYRON NUCLEAR POWER STATION

, , UNIT 1/2 DOCKET NUMBER STN-50-454/455

( RADIOACTIVE EFFLUENT RELEASE REPORT l Januarv , 1996 THROUGH December , 1996 1

l l SOLID RADIOACTIVE WASTE 2nd QUARTER 1996 XEAR l

l DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES TYPE, AND SOLIDIFYING OF SHIPMENT PER DATE AGENT) TRANSPORT DESTINATION CUBIC FT SHIPMENT RTD Piping, Low Specific Exclusive Barnwell 2382 1.87 04/23/96 Activity NOS 7 UN2912, Use SC strong-tight container, None 04/22/96 RTD Piping, Low Specific Exclusive Barnwell 2382 1.99 Activity NOS 7 UN2912, Use SC  ;

strong-tight container, None 05/01/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 51.9 Stable, HIC, none Use SC l

05/09/96 RTD Piping, Low Specific Exclusive Barnwell 2382 .004 Activity NOS 7 UN2912, Use SC  ;

strong-tight container, None l

05/22/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 19.0 l Stable, HIC, none Use SC 06/03/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 141 Stable, HIC, none Use SC l

l l

l l

7752.3 215.8 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 6 CUBIC FT CURIES Report Page 18 of 28 (p:97byttrs\970017,wp0

BRP 6100-6T1

.. Revision 3

. BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN 50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT  ;

Januarv , 1996 THROUGH December , 1996 SOLID RADIOACTIVE WASTE 3rd QUARTER 1996 YEAR DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES TYPE, AND SOLIDIFYING OF SHIPMENT PER DATE AGENT) TRANSPORT DESTINATION CUBIC FT Sl;IPMENT Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 11.2 07/31/96 Stable, HIC, none Use SC

]

08/29/96 RTD Piping, Low Specific Exclusive Barnwell 2560 12.60 Activity NOS 7 UN2912, Use SC i strong-tight container, None  !

08/29/96 RTD Piping, Low Specific Exclusive Barnwell 2560 12.90 l Activity NOS 7 UN2912, Use SC )

strong-tight container, None 08/28/96 Dewatered Bead Rosin, Class A Exclusive Barnwell 202.1 6.70 Stable, HIC, none Use SC l

09/11/96 RTD Piping, Low Specific Exclusive Barnwell 2720 .002 l Activity NOS 7 UN2912, Use SC strong-tight container, None 8,244.2 43.6 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 5 CUBIC FT CURIES Report Page 19 of 28 (p;97byttrs\970017.wp0

BRP 6100-6T1

., Revision 3

, BYRON NUCLEAR POWER STATION l

' ' UNIT 1/2 DOCKET NUMBER STN 50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1996 THROUGH December , 1996 SOLID RADIOACTIVE WASTE 4th QUARTER 1996 YEAR J

1 DISPOSITION OF MATERIAL VOLUME

(DESCRIPTION, CLASS, MODE PER CURIES j TYPE, AND SOLIDIFYING OF SHIPMENT PER i DATE AGENT) TRANSPORT DESTINATION CUBIC FT SHIPMENT l 10/04/96 Steam Generator Secondary Exclusive Oak Ridge 2560 2.19  ;

j Sludge Low Specific Activity Use TN l i NOS 7 UN2912 strong-tight container, none

, 10/11/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 9.90 Stable, HIC, none Use SC 4

j 10/28/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 24.4 Stable, HIC, none Use SC 10/29/96 Dewatered Bead Resin, Class A Exclusive Barnwell 202.1 0.50

! Stable, HIC, none Use SC 4

1 i

j 1

1 7

i 1

3,166.3 37.0 QUARTERLY TOTALS - NUMBER OF SHIPMENTS. 4 CUBIC FT CURIES Report Page 2Q of 28 (p:97byltrs\970017.wpf)

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

i 1  !

I

Revision 3 i

ADDENDUM  ;

j A. There wero no major changes or modifications to the PCP, or to any

, liquid ga seous or solid radwaste treatment systems for this period. In l l November of 1996 Byron Station retained the services of Chem-Nuclear to j replace Vacific Nuclear for dewatering and solidification services, '

however, no major changes to these processes were instituted. '

1 l B. Error Analysis l l

The following is an estimate of the errors associated with effluent  !

i monitoring and analysis. The estimate is calculated using the square '

i root of the sum of the squares methodology, i

l 1. Gaseous Effluents I, (

4 Sampling error = 1 to 3.5%

)

l Calibration error = 10%  !

j Counting Statistics error = 5%

l Vent Stack Flowrates error = 1.5% l 1

Total error = 11 - 12% 1

2. Liquid Effluents Sampling error = 1%

Calibration error = 10%

Sample volume error = 1%

Discharged volume error = 2%

Total error = 10%

3. Waste Resin Sampling error = 5%

Counting Statistics error = 7%

Weight error = 1%

Volume error = 5%

Total error = 10%

4. DAW Counting Statistics error = 7%

Calibration error = 10%

Weight error 2%

Total error = 12.4%

Report Page 21 of 28 (p:97byhrs\970017.wp0

  • BRP 6100-6T1  !

, Revision 3

. c. Meteorological and environmental impact information is reported in the l Station Annual Radiological Environmental Operating Report as required i by Technical Specifications 6.9.1.6.

)

D. 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 Specifications 3.11.2.6.

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

F. There were no elevated releases. All releases are considered vent or ground level releases.

G. The Offsite Dose Calculation Manual was revised in February 1996. The Revision implements a uniform radiological monitoring program (REMP) consistent among all six (6) Commonwealth Edison sites. In general, it reduces the number of environmental water, fish, sediment, and airborne particulate and iodine samples and increases the number of environmental milk, food product, and broad leaf vegetation samples. The change does not affect the level of safety of the plant or affect the dose to the public or environment.

H. Attached are the Offsite Dose Calculations for January through December of 1996.

l Report Page 22 of 28 (p:97byttrs\970017.wp0

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

' BRP 6100-6T1

, Ravision 3

, 2. The following data is the estimated composition of Byron's solid waste.

1. Dry Active Waste (DAW) 2. Primary Resin H3 <0.01% H-3 <0.01%

C-14 0.08% C 14 2.88%

Mn 54 0.64% Mn-54 1.31%

Fe-55 15.88% Fe-55 3.06%

Co 57 0.01% Co-57 0.23%

Co-58 10.46% Co-58 73.99%

Co-60 60.59% Co 60 3.25%

Ni-63 2.53% Ni-63 8.55%

l Sr-90 0.01% Sr-89 0.01%

Zr-95 3.15% Sr-90 <0.01%

Nb 95 5.92% Nb-95 <0.01%

Tc 99 <0.01% Tc-99 <0.01%

Ag-110m 0.01% Te-123m <0.01%

Sn-113 0.33% Sb 124 1.56%

Te-123m <0.01% Sb-125 1.14%

Sb-124 <0.01% Te-125m <0. 01% -

Sb 125 <0.29% I 129 <0.01%

Te-125m <0.01% Cs-134 1.92%

I-129 <0.01% Cs-137 2.12%

Cs-134 <0.01% Pu 238 <0.01% l Cs-137 <0.01% Pu-239 <0.01%

Pu 238 <0.01% Pu-241 <0.01%

Pu 239 <0.01% Am 241 <0.01%

Pu-241 0.10% Cm 242 <0.01%

Am 241 <0.01% Cm 244 <0.01%

i Cm 242 <0.01%

Cm-244 <0.01%

i Report Page ?) of 28 (p:97byttr \970017.wp0 l

i

(

, BRP 6100-6T1

, R3 vision 3 l

I. (Continued)

3. Radwaste Resin H-3 0.15%

C-14 0.21%

l Mn-54 2.60%

1 Fe 55 25.71%

Co 57 0.38%

Co-58 37.25%

l Co-60 10.38%

Ni-63 19.43%

Zn-65 <0.01%

Sr-90 <0.01%

Tc-99 <0.01%

Ag-110m <0.01%

Te-123m 0.02%

Sb-124 <0.01%

Sb-125 0.35%

Te-125m <0.01%

I-129 <0.01%

Cs-134 1.16%

Cs-137 2.34%

Pu 238 <0.01%

Pu-239 <0.01%

Pu-241 0.01%

Am-241 <0.01%

Cm-242 <0.01%

Om 244 <0.01%

i l

l l

Report Page 24 of 28 (p:97byltrs\970017.wpf)

  • BRP 6100-6T1 Revision 3 J. The following process radiation monitors were out of service longer than allowed by the Administrative Technical Requirements:
1. ORE-PR001 exceeding the 14 day LCO.

On 5/29/96, ORE-PR001 Liquid Radwaste Effluent Radiation Monitor was taken out of service (OOS) to decontaminate the sample chamber. The monitor was valved in for a release as a Post Maintenance Test. After the release, the monitor had to be decontaminated again. After the second decontamination the monitor was taken OOS for a modification to its seal-in logic. The LCO was exited on 6/20/96, which exceeded the 14 day limit.

2. ORE-PR041 exceeding the 30 day LCO.

On 7/22/96, ORE-PR041 was declared inoperable due to a flow transmitter not working. A replacement transmitter was ordered without the electronic boards, because the electronics were proven to be functional and the flow sensor was found to be defective.

The replacement transmitter arrived but was found to be incompatible with the original version. A complete flow transmitter was subsequently ordered and received. The new transmitter was installed and tested on 9/23/96, and the monitor was returned to service.

J l

Report Page 25 of _L (p;97byltrs\970017.wp0

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

a

' Revision 3

. ATTACHNENT A BYRON NUCLEAR POWER STAT'.ON EFFLUENT AND WASTE DISPOSAL REPORT FOR JANUARY THROUGH DECEMBER, 1996 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50 455)

LLD VALUES FOR GASEOUS RELEASES Isotopes LLD (Ci/ml)

H-3 4.04E-17 l

Ar-41 2.29E-13 j Co-58 5.51E-19 l

Co-60 3.89E-18 1 Zn-69m 2.67E-18 P

Kr-85 4.88E-11 Kr-85m 1.73E 12 Kr-88 5.78E-13 Sr-89 3.58E-21 Sr-90 1.22E-21 Sn-113 5.41E-20 Te-123m 3.23E-19 I-131 5.70E-19 I 132 6.16E-19 I-133 5.99E-19 I-135 2.47E 19 Xe 131m 7.55E-12 Xe-133 4.88E-13 Xe-133m 1.60E-12 Xe-135 1.80E-13 Xe-135m 2.19E-13 Report Page 26 of 28 (p:97byltt \970017,wpf)

e ,

' Ravision 3

(

ATTACHNENT A (cont.)

BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT FOR JANUARY THROUGH DECEMBER, 1996 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455)

LLD VALUES FOR LIQUID RELEASES Isotopes LLD(Ci/ml)

H-3 1.63E-12 Ar-41 2.31E-13 Cr 51 2.21E 13 Mn-54 3.23E-14 Fe-55 5.40E-14 Fe-59 8.02E-14 Co-57 2.08E-14 Co 58 3.74E-14 Co-60 5.40E 14 l Cu-64 3.04E 14  ;

Zn-65 7.55E-14 Kr-85 4.07E-11 Kr-88 7.60E 14 Sr-89 2.13E-14 l Sr-90 9.30E 15 Sr-92 2.82E l Nb 95 3.13E-14 Zr-95 5.68E 14 l l

Ag 110m 1.97E-13  !

I Sn 113 2.37E-13 l Sb-122 2.52E-13 Sb-124 2.95E 14 Sb-125 7.44E-14 Report Page 27 of 28  !

(p:97byttr \970017.wp0

' Rovision 3 ATTACEMENT A (cont.)

BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT FOR JANUARY THROUGH DECEMBER, 1996 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455)

LLD VALUES FOR LIQUID RELEASES Isotopes LLD (Ci/ml) 1 Sb-126 2.03E-13

__ Te-121m 8.82E-14

_,,_ Te-123m 2.28E-14 l Te-125m 5.91E-12 Te-132 1.60E-13 Xe-125m 5.91E-12 l l

Xe-131m 9.95E-13 l Xe-133 2.44E-13 j 1

Xe-133m 2.11E-13 Xe-135 2.37E-14 Cs-134 2.89E-14 Cs-137 3.72E-14 I-131 3.37E-13 I-132 2.94E-14 I-133 3.04E-14 I-134 3.62E-14 Ce-144 1.69E-13 Pr-144 1.40E-11 Hf-181 2.30E 13 (Final)

Report Page 28 of 28 (p:97byttrs\970017.wp0

. BYRON STATION UNIT ONE 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/96 TO 12/31/96 CALCULATED 02/19/97 l

1 l

1. 10 CFR 20.1301 (a) (1) Compliance l

l Total Effective Dose Egivalent, mrem /yJ 2.64E-02 l

10 CFR 20.1301 (a) (1) limit mrem /yr 100.0 l

l  % of limit 0.03 Compliance Summary - 10CFR20 let 2nd 3rd 4th  % of Qtr Qtr Qtr Qtr Limit l TEDE 4.42E-03 1.01E-02 1.10E-02 8.67E-04 0.03 RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 l

l I

I l

I l

-. . _ . . _ .._-.-...._...._.__.-....___-_....-_.._m._.._. _ . _ - . _ _ _ . _ .

I

,, i

..< 1 O

BYRON STATION UNIT ONE 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/96 TO 12/31/96 l l

? CALCULATED'02/19/97 l

1

2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance j j

Dose Limit  % of (mreI .) (mrem) Limit Whole Body Plume 5.81E-05 (DDE) Skyshine 0.00E+00 Ground 6.66E-05 Total 1.25E-04 25.0 0.00 Organ Dose Thyroid 1.28E-02 75.0 0.03 (CDE) Gonads 2.65E-02 25.0' O.11 Breast 2.27E-02 25.0 0.09 Lung 2.27E-02 25.0 0.09 Marrow 2.45E-02 25.0 0.10 ,

Bone 2.90E-02 25.0 0.12 Remainder 3.00E-02 25.0 - 0.32 CEDE 2.63E-02 i.

TEDE 2.64E-02 100.0 0.03 RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWk/S VERSION 1.1 January 1995 ODCM DATABASL ~'E}'SION 1.1 2 'nuary 1995 l

J l

l

e e

BYRON STATION UNIT ONE

, , ACTUAL 1996 i MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES i

' PERIOD OF RELEASE - 01/01/96 TO 12/31/96 CALCULATED 02/25/97 ADULT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUNRTER QUARTER QUARTER ANNUAL

, JAN-MAR APR-JUN JUL-SEP OCT-DEC I I

l j GAMMA AIR 2.31E-05 5.43E-05 2.99E-06 2.28E-06 8.27E-05 J

(MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) l j BETA AIR 9.35E-05 2.20E-04 1.16E-05 8.96E-06 3.34E-04 l (MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) I TOT. BODY 1.62E-05 3.82E-05 2.11E-06 1.61E-06 5.81E-05 )

(MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE )

! SKIN 4.59E-05 1.07E-04 5.80E-06 4.44E-06 1.64E-04 l

. - (MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) *

, ORGAN 3.71E-03 7.40E-03 2.02E-03 2.33E-04 1.33E-02

! (MREM) (S ) (S ) (SE ) (S ) (S )

4

!. L1VER THYROID GI_LLI GI_LLI THYROID

! THYROID 1- KIDNEY

LUNG GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1996 I

COMPLIANCE STATUS - 10CFR 50 APP. I ADULT RECEPTOR

 % OF APP I. ------------

QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0:00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.05 0.10 0.03 0.00 15.0 0.09 LIVER THYROID GI_LLI GI_LLI THYROID THYROID KIDNEY LUNG GI_LLI RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

}

~

BYRON STATION UNIT ONE

., ACTUAL 1996 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/96 TO 12/31/96 CALCULATED 02/20/97 i ADULT RECEPTOR l

1ST 2ND 3RD 4TH DOSE-TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR 'APR-JUN JUL-SEP OCT-DEC TOTAL 1.64E-03 2.29E-03 1.42E-02 7.93E-04 1.90E-02 BODY INTERNAL 2.00E-03 1.12E-02 1.78E-02 1.27E-03 2.42E-02 ORGAN LIVER GI_LLI LIVER GI_LLI LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1996 l

)

l l

COMPLIANCE STATUS - 10 CFR 50 APP. I

 % OF APP I. ------------

l l

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF l OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I i TOTAL BODY (MREM) 1.5 0.11 0.15 0.95 0.05 3.0 0.63 CRIT. ORGAN (MREM) 5.0 0.04 0.22 0.36 0.03 10.0 0.24 .l LIVER GI_LLI LIVER GI_LLI LIVER RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

  • BYRON STATION UNIT ONE

. , 1996 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/96 TO 12/31/96 CALCULATED 02/20/97 ADULT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.00E-04 9.88E-05 7.57E-05 4.49E-04 7.24E-04 BODY INTERNAL 1.02E-04 1.42E-04 7.86E-05 4.65E-04 7.85E-04 ORGAN GI_LLI GI_LLI LIVER GI_LLI GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1996 COMPLIANCESTATUS-40CI$1141 TYPE ANNUAL LIMIT  % OF LIMIT TOTAL 4.O MREM 0.018 BODY INTERNAL 4.O MREM 0.020 ORGAN GI_LLI
  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 i

l l

?

I

] .. BYRON STATION UNIT TWO 10 CFR 20 COMPLIANCE ASSESSMENT ,

PERIOD OF ASSESSMENT 01/01/96 TO 12/31/96 CALCULATED 02/19/97

1. 10 CFR 20.1301 (a) (1) Compliance Total Effective Dose Egivalent, mrem /yr 1.89E-02 10 CFR 20.1301 (a) (1) limit mrem /yr 100.0

% of limit 0.02 Compliance Summary - 10CFR20 1st 2nd 3rd 4th  % of Qtr Qtr Qtr Qtr Limit TEDE 1.26E-03 4.01E-03 1.29E-02 7.14E-04 0.02 l RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 1

l I

m

BYRON STATION UNIT TWO 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/96 TO 12/31/96 CALCULATED 02/19/97

2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance Dose Limit  % of (mrem) (mrem) Limit Whole Body Plume 1.48E-05 (DDE) Skyshine 0.00E+00 Ground 2.47E-05 Total 3.94E-05 25.0 0.00 Organ Dose Thyroid 1.60E-02 75.0 0.02 (CDE) Gonads 1.91E-02 25.0 0.08 Breast 1.53E-02 25.0 0.06 l Lung 1.53E-02 25.0 0.06 l

Marrow 1.71E-02 25.0 0.07 Bone 2.16E-02 25.0 0.09 Remainder 2.26E-02 25.0 0.09 CEDE 1.89E-02 TEDE 1.89E-02 100.0 0.02 RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

l J '" BYRON STATION UNIT TWO

, , ACTUAL 1996 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE -- 01/01/96 TO 12/31/96 CALCULATED 02/25/97 ADULT RECEPTOR 1ST 2ND 3RD 4TH *

)

TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL i JAN-MAR APR-JUN JUL-SEP OCT-DEC l l

GAMMA AIR 6.11E-06 9.79E-06 2.95E-06 1.98E-06 2.08E-05 l (MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) l BETA AIR 2.20E-05 3.89E-05 1.11E-05 7.00E-06 7.90E-05 (MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE )

TOT. BODY 4.35E-06 6.92E-06 2.08E-06 1.41E-06 1.48E-05 (MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE )

SKIN 1.22E-05 2.02E-05 5.65E-06 3.69E-06 4.17E-05  :

(MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) I ORGAN 7.95E-05 6.95E-04 4.46E-03 5.73E-05 5.22E-03 '

(MREM) (S ) (SSE ) (SE ) (S ) (SE )

LIVER THYROID GI_LLI GI_LLI THYRGID THYROID KIDNEY LUNG GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1996 COMPLIANCE STATUS - 10CFR 50 APP. I ADULT RECEPTOR

 % OF APP I. ------------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00  ;

ORGAN (MREM) 7.5 0.00 0.01 0.06 0.00 15.0 0.03 l LIVER THYROID GI LLI GI LLI

~

THYROID l THYROID l KIDNEY LUNG GI_LLI RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ,

ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 i

e ,'" BYRON STATION UNIT TWO 9

ACTUAL 1996 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/96 TO 12/31/96 CALCULATED 02/20/97 ADULT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.64E-03 2.32E-03 1.42E-02 7.93E-04 1.90E-02 BODY INTERNAL 2.00E-03 1.13E-02 1.78E-02 1.27E-03 2.43E-02 ORGAN LIVER GI_LLI LIVER GI_LLI LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1996 COMPLIANCE STATUS - 10 CFR 50 APP. I

 % OF APP I. ------------

l QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF l OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.11 0.15 0.95 0.05 3.0 0.63 CRIT. ORGAN (MREM) 5.0 0.04 0.23 0.36 0.03 10.0 0.24 LIVER GI_LLI LIVER GI_LLI LIVER RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 i

l t

/ BYRON STATION UNIT TWO

, . 1996 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/96 TO 12/31/96- CALCULATED 02/20/97
ADULT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL 4

JAN-MAR APR-JUN JUL-SEP OCT-DEC l

TOTAL 1.00E-04 1.32E-04 7.57E-05 4.49E-04 7.57E-04 y BODY INTERNAL 1.02E-04 1.77E-04 7.86E-05 4.65E-04 8.20E-04 ORGAN l i GI_LLI GI_LLI LIVER GI_LLI GI_LLI l THIS IS A REPORT FOR THE CALENDAR YEAR 1996 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT  % OF LIMIT TOTAL 4.0 MREM 0.019 BODY INTERNAL 4.0 MREM 0.020 ORGAN I l

GI LLI ,

l

  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES D1FFER FROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 1.3 MARCH 1996 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 l

4

Retrieved from "https://kanterella.com/w/index.php?title=ML20136B627&oldid=2838790"