ML20072G521

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Effluent & Waste Disposal Rept Jan-June 1994
ML20072G521
Person / Time
Site: Byron  Constellation icon.png
Issue date: 06/30/1994
From: Schwartz G
COMMONWEALTH EDISON CO.
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
BYRON-94-0300, BYRON-94-300, NUDOCS 9408250003
Download: ML20072G521 (17)
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,1 C Byron Nuclear Station 4450 North German Church Road

' Byron,'lilinois 61010 August 15, 1994 LTR: BYRON 94-0300 FILE: 2.12.1522 (1.10.0101)

Mr. J. B. Martin, Administrator Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, Illinois 60532-4351

SUBJECT:

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

Dear Mr. Martin:

Enclosed is the Semi-Annual Radiological Effluent Release Report for January through June, 1994, for Byron Nuclear Power Station. This report is required by Technical 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.

Sincerely,

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G.K. Schwartz [

Station Manager Byron Nuclear Power Station GKS/DD/rp Enclosure 1

I cc: Distribution List Attached i

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(36 35::Z / 081094 )

I 9408250003 940630 PDR ADOCK 05000424 R PDR

i SEMI-ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT DISTRIBUTION LIST l l

i I

Director of Nuclear Reactor Regulation - U.S. Nuclear Regulatory Commission <

l Nuclear Regulatory Commission, Region III Illinois Department of Nuclear Safety, Office of Environmental Safety A.N.I.

U.S. Environmental Protection Agency Air and Radiation Branch - Region V Health Physicist Murray and Trettel, Inc.

Teledyne Isotopes Midwest Laboratory and General Manager Chemistry Services - Chemistry Services Director By"on Station Central Files, File Number 2.12.1522 Health Physics Services Supervisor - Byron Nuclear Power Station Radiological Effluent Monitoring Program Coordinator NRC Cenior Resident Inspector - Byron Nuclear Power Station B.P.l. Associates General Counsel Health Physics Services Supervisor - Braidwood Nuclear Power Station f

(3635ZZ/081094)

I f

a .

, . +

+

BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JANUARY through JUNE 1994 Supplemental Information ,

1. Regulatory Limits ,
a. Fission and activation gases:

10CFR20 Whole Body = 500 mrem / year Skin = 3000 mrem / 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 mrem / year 10CFR 50 Organ = 7.5 mrem / quarter; 15 mrem / year d, Liquid effluents:

10CFRSC Whole Body = 1.5 mrem / quarter; 3 mrem / year i

Organ = 5 mrem / quarter; 10 mrem / year

e. Total Effective Dose Equivalent 10CFR20 TEDE = 100 mrem / year
2. Maximum Permissible Concentration
a. Fission and Activation Gases: 10CFR20 Appendix B Table 2
b. Iodine: 10CFR20 Appendix B Table 2
c. Particulates: 10CFR20 Appendix B Table 2
d. Liquid Effluents: 10CFR20 Appendix B Table 2
3. Average Energy: This item is not applicable. Release rates are j calculated using an isotopic mix rather than average energy.
4. Measurements and Approximations of Total Radioactivity j i

. . I

a. Fission and Activation' Gases: Prior to release, the isotopic content 1 is' determined. . Released activity'is calculated using volume of

. release, which is determined _by the' change in tank or containment pressure. Additional methods of calculation utilize historical data: 1 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 analyzed daily for the plant vent stacks, i

(3635ZZ/081094) 1 I

BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JANUARY through JUNE 1994 Supplemental Information (continued)

c. Liquids 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 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:
a. Liquid:
1. Number of batch releases = 99
2. Total time period for batch releases = 8,648 minutes
3. Maximum time period for a batch release = 233 minutes
4. Average time period for a batch release = 97.4 minutes
5. Minimum time period for a batch release = 8 minutes
6. Average stream flow during periods of release of effluent into a flowing stream = 8,448 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 = 174
2. Total time petiod for batch releases = 14,361 minutes
3. Maximum time period for a batch release = 386 minutes
4. Average time period for batch releases = e2.5 minutes S. Minimum time period for a batch release =.2 minutes l
6. Abnormal Releases: j
a. . Liquid - none
b. Gaseous - none (3635ZZ/081094) 2 i

mr a____ _ _ _ _ _ _ _ _ _ . _. _ __ _. _ , , __. ,

BRP 6100-6T1 R3 vision 2 BYRON NUCLEAR POWER STATION UNIT I DOCKET NUMBER STN 50 454 RADIOACTIVE EFFLUEITT RELEASE REPORT Januarv , 1994 THROUGH .T un e , 1994 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNITS IST CfrR 2ND QTR 3RD QTR 4TH (7tE A. FISSION AND ACTIVATION GAS RELEASES

1. Total Release Activity C1 2.72E-1 3.51E-1
2. Maximum Release Rate for Quarter uCi/sec 2.85E+0 1.97E+0
3.  % of 20CFR20 Limits *
a. Whole Body (500 mrem /yr)  % 0.00 0.00
b. Skin (3000 mrem /yr)  % 0.00 0.00
4.  % of 10CFR50 Limits
a. Gamma Quarterly (5 mrad)  % 0.00 0.00
b. Beta Quarterly (10 mrad)  % 0.00 0.00
c. Gamma Annual (10 mrad)  % 0.00 0.00
d. Beta Annual (20 mrad)  % 0.00 0.00 B. IODINE RELEASES **
1. Total I-131/I-133 Activity Ci <LLD <LLD C. PARTICULATE (>8 day half-life) RELEASES **
1. Gross Activity Ci <LLD <LLD
2. Gross Alpha Activity for Quarter Ci <LLD <LLD D. TRITIUM RELEASES **
1. Total Release Activity Ci 1.37E-1 7.20E-1
  • % of 10CFR20 limits is based on the mav4 mum release rate for the period considered.
    • Iodine, particulate, and tritium % of 10CFR20/10CFR50 limits are expressed as a total limit. See step E.

Report Page 3 of ,3

. APPROVED APR 181994 2

(9916SS/WPF/041194)

BRP 6100-6T1

, Ravicion 2 BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN 454 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1994 THROUGH June , 1994 QASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (COITT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR E. SUM OF IODINE, PARTICULATE (>B day half-life), A!O TRITIUM RELEASES

1. Total Activity C1 1.37E-1 7.20E-1
2.  % of 10CFR20 Limit
a. Any Organ (1500 mrem /yr)  % 0.00 0.00
3.  % of 10CFR50 Limit
a. Quarterly Any Organ (7.5 mrem)  % 0.00 0.00 1
b. Annual Any Organ (15.0 mrem)  % 0.00 0.00 l l

GASEOUS EFFLUENTS - VETTP STACK RELEASES - BATCH MODE j l

l F. FISSION AND ACTIVATION GAS RELEASES Xe-133 Ci 1.46E-1 5.86E-2 l Ar-41 C1 1.80E-2 3.85E-2 Kr-85 Ci 8.57E-3 5.93E-3 Kr-88 Ci 3.64E-3 <LLD Xe-135 Ci 9.15E-4 <tL9 C1 -

C1 Ci C1 Ci C1 Ci Report Page 4 of 23 APPROVED APR 18 894 2-(9916SS/WPF/041194)

BRP 6100-6T1 Ravision 2 I l

BYRON NUCLEAR POWER STATION UNIT I DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT I

.Tanuarv , 1994 THROUGH June ,

1994 j GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE (CONT) l UNITS IST QTR 2ND QTR 3RD QTR 4TH GrrR l

G. IODINE RELEASES T-131 Ci *

  • I-133 Ci *
  • T-135 Ci *
  • l l

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

Sr-90 Ci *

  • Ci Ci i Ci
  • - Value reported as CONTINUOUS RELEASE MODE.

GASEOUS EFFLUENTS - VENT STACK RELEASES - COiffinuOuS MODE I. FISSION AND ACTIVATION GAS RELEASES Xe-133 Ci 9.45E-2 2.48E-1

~

Ci Ci

- Ci ~

Ci Ci Ci CL Report Page 5 of 23 APPROVED APR 181994 (9916SS/WPF/041194)

BRP G100-6T1 }

Rsvision 2 BYRON NUCLEAR POWER STATION UNIT l DOCKET NUMBER STN-50 !A A RADIOACTIVE EFFLUENT RELEASE REPORT Januarv 1994 THROUGH Jime , 1004 GASEOUS EFFLUENTS - VENT STACK RELEASES - CONTINUOUS Mor3 (CONT)

UNITS 1ST QTR 2ND grR 3RD (TTR 4TH QTR J. IODINE RELEASES T-131 Ci <LLD <LLD I-133 Ci <LLD <LLD )

I-135 Ci <LLD <LLD l

K. PARTICULATE (>8 day half-life) RELEASES j Sr-89 Ci <LLD

  • Ci CL Ci
  • Analysis done by offsite vendor: Results not available.

LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES L. FISSION AND ACTIVATION GAS RELEASES l

1. Total Activity Released Ci 9.23E-3 5.10E-2
2. Average Concentration Released uCi/ml 3.61E-9 1.92E-8 for Quarter
3. 4 of 10CFR50 Limits -

5

a. Quarterly Whole Body (1.5 mrem) t 0.03 0.05
b. Quarterly Any Organ (5.0 mrem) t 0.01- 0.02
c. Annual Whole Body (3.0 mrem)  % 0.01 0.03
d. Annual Any Organ (10.0 mrem)  % 0.01 0.01 APPROVED Report Page 6 of..,3<

APR 181994 (9916SS /WPF/041194)

BRP 6100-6T1 )

Revision 2 l

BYRON NUCLEAR POWER STATION l I

UNIT DOCKET NUMBER STN-50 454 RADICACTIVE EFFLUENT RELEASE REPORT January , 1994 THROUGH Junn , 1944 l LIOUID EFFLUEfES - SUfetATION OF ALL RELEASES (CONT) )

UNITS 1ST QPTR 2ND QTR 3RD QTR 4TH QTR j 1

M. TRITIUM

1. Total Activity Released Ci l 1.95E+2 3.22E+2 I

, 1

2. Average Concentration Released uC1/ml 7.64E-5 1.21E-4 for Quarter
3. t of Limit (1.00E-3 uCi/ml)  %

7.64 12.12 1

l l

l N. DISSOLVED NOBLE GASES

1. Total Activity Released Ci 7.38E-4 4.49E-3
2. Average Concentration Released uCi/ml for Quarter 2.89E-10 1.69E-9
3.  % of Limit (2.00E-4 uCi/ml)  %

1.44E-4 8.47E-4 O. GROSS ALPHA

1. Total Activity Released Ci

<LLD <LLD

2. Average Concentration Released uCi/ml 0.00 0.00 for Quarter P. VOLUME OF WASTE RELEASED PER UNIT liters 2.10E+6 2.68E+6 Q. VOLUME OF DILUTION WATER PER UNIT liters 2.56E+9 2.65E+9 LIOUID EFFLUENTS - COfCINdOUS MODE R. LIQUID EFFLUENTS vn-s9 Ci *
  • Sr-89 Ci *
  • C1 Ci ci
  • Value reported as LIQUID EFFLUENTS - BATCH MODE. ggg Report Page 7 of 23 APR 181994 5-(9916SS/WPF/041194) 1

BRP 6100-6T1 Ravicion 2

, BYRON NUCLEAR POWER STATION UNIT I DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUE!rr RELEASE REPORT Januarv , 1994 THROUGH June , 1994 LIOUID EFFLUEffrS - BATCH MODE UNITS IST QTR 2ND QTR 3RD QTR 4TH QTF S. LIQUID EFFLUENTS H-3 Ci 1.95E+2 3.22E+2 Ci Mn-54 C1 1.61E-4 1.70E-3 co-57 Ci 1.24E-5 1.56E-4 co-58 C1 1.12E-3 3.13E-3 Fe-59 Ci 1.27E-5 <LLD Co-60 Ci 4.82E-3 3.07E-2 Zn-65 Ci 8.88E-6 2.74E-4 Kr-88 Ci 3.90E-5 <LLD {

Nb-95 Ci 1.95E-5 1.66E-4 Zr-95 Ci 5.33E-6 <LLD I Ag-110m Ci 2.28E-5 8.31E-4 1

Sn-113 Ci ( r, T,n 4.29E-5 Sb-122 Ci <LLD 2.55E-4 Sb-124 Ci <LLD 5.61E-4 Sb-125 Ci 2.74E-3 6.30E-3 Te-125m Ci <T.i n 6.29E-3 I-131 Ci ~ l 2.96E-6 <LLD I Xe-133 Ci 6.96E-4 4.39E-3 Xc-133m Ci 777 g 3,797_5 Xe-135 Ci 3.72E-6 5.89E-5 co-134 Ci 9.23E-5 1.07E-4 Report Page 8 of 23 APPROVED APR 18 894 6-(9916SS /WPF/041194 )

BRP 6100-6T1 Ravision 2 1

BYRON NUCLEAR POWER STATION l l

UNIT I DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT IGLEASE REPORT I Januarv , 1994 THROUGH June ,

1994 '

LIOUID EFFLUENTS - BATCH MODE (CONT.) )

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

S. LIQUID EFFLUENTS (CO!Tr.)

Cs-13h Ci 2.19E-4 3.49E-4 Sr-92 Ci <LLD 2.01E-4 Fe-55 Ci 5.49E-3

  • Sr-89 Ci 4.09E-6

1.65E-6

  • i l

Ci Ci l

Ci '

Ci I Ci ,

1

. Ci l 1

Ci l l

Ci l Ci ci ci ci CL -

  • Analysis performed by Off-site vendor. Results not available.

T. 10CFR20 PUBLIC TEDE COMPLIANCE

1.  % OF 10CFR TEDE LIMIT t 0.00 0.00 (100 mrem /yr) l l

Report Page 9 of 23 I

l APPROVED APR 18 894 (9916SS/WPF/041194)

BRP 6100-6T1

, asvision 2 )

BYRON NUCLEAR POWER STATION  ;

UNIT 2 DOCKET NUMBER STN 50 455 RADIOACTIVE EFFLUEIC RELEASE REPORT January , 1994 THROUGH June ,

1994 QASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ,

UNITS IST QTR 2ND QTR 3RD (TTR 4TH QTR A. FISSION AND ACTIVATION GAS RELEASES

1. Total Release Activity Ci 1.59E-1 3.44E-1
2. mv4 mum Release Rate for Quarter uCi/see 1.91E+0 1.38E+0
3.  % of 10CFR20 Limits
  • I i

1

a. Whole Body (500 mrem /yr)  % 0.00 0.00 j
b. Skin (3000 mrem /yr)  % 0.00 0.00 l l
4. 4 of 10CFR50 Limits 4
a. Gamma Quarterly (5 mrac'.)  % 0.00 0.00
b. Beta Quarterly (10 mrad)  % 0.00 0.00  ;
c. Gamma Annual (10 mrad)  % 0.00 0.00 I
d. Beta Annual (20 mrad)  % 0.00 0.00 '

B. IODINE RELEASES **

1. Total I-131/I-133 Activity Ci <LLD <LLD C. PARTICULATE (>8 day half-life) RELEASES **
1. Gross Activity Ci (LLD <LLD
2. Gross Alpha Activity for Quarter Ci < f,LD <LLD l

1 1

D. TRITIUM RELEASES ** '

1. Total Release Activity C1 2.75E-1 4.75E-1

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

    • Iodine, particulate, and tritium t of 10CFR20/10CFR50 limits are expressed as a total limit. See step E.

Report Page 10 of 23 APPROVED APR 181994 (9916SS/WPF/041194)

BRP 6100-6T1 Ravision 2 l BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50 455 RAD 10 ACTIVE EFFLUENT RELEASE REPORT January ,

1994 THROUGH June ,

1994 GASEOUS EFPLUENTS - SUMMATION OF ALL RELEASES (CONT)

UNITS IST QTR 2ND CfrR 3RD QTR 4TH QTR E. SUM OF IODINE, PARTICULATE (>8 day half-life), AND TRITIUM RELEASES 1

1. Total Activity C1 2.75E-1 4.75E-1
2.  % of 10CFR20 Limit
a. Any Organ (1500 mrem /yr)  % 0.00 0.00
3.  % of 10CFRSO Limit
a. Quarterly Any organ (7.5 mrem)  % 0.00 0.00
b. Annual Any organ (15.0 mrem)  % 0.00 0.00 GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE F. FISSION AND ACTIVATION GAS RELEASES Ar-41 Ci 7.73E-3 7.35E-3 Kr-85 Ci 8.47E-3 5.93E-3 Xe-133 C1 4.74E-2 8.21E-2 Xe-135 Ci 6.19E-4 <LLD Ci ci -

Ci C1 Ci ci ci ci Report Page 1I of 23 APPROVED APR 181994 (9916SS/WPF/041194)

BRP 6100-6T1 R2 vision 2

, BYRON NUCLEAR POWER STATION UNIT _.2__, DOCKET NUMBER STN 50 455 l RADIOACTIVE EFFLUENT RELEASE REPORT January , 1994 THROUGH June ,

1994 GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE (CONT)

UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR G. IODINE RELEASES 1-131 Ci *

  • I-133 Ci *
  • T-135 Ci *
  • H. PARTICULATE (>8 day half-life) RELEASES Sr-89 Ci *
  • Ci Ci Ci
  • Value reported as CONTINUOUS RELEASE MODE.

GASEOUS EFFLUENTS - VENT STACK RELEASES - COrrrinuOu8 MODE l I. FISSION AND ACTIVATION GAS RELEASES l

l Xe-133 Ci 9 . 4 ',E- 2 2.48E-1 Ci

- Ci Ci ~

Ci Ci l Ci ci Report Page 12 of 23 APPROVED APR 181994 3

(9916SS/WPF/041194 )

BRP 6100-6T1 Rsvicion 2 BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50 455 RADIOACTIVE EFFLUENT RELEASE REPORT

.f anua ry , 1994 THROUGH Ti m o , lood GASEOUS EFFLUENTS - VENT STACK RELEASES - COtTTINUOUS MODE (CONT)

UNITS IST GrrR 2ND QTR 3RD QTR 4T:i QTR J. IODINE RELEASES I-l31 Ci n T.n < t T.n 1-133 Ci (LLo (LLo I-135 Ci <LLD <LLD K. PARTICULATE (>8 day half-life) RELEASES Ci

  • Sr-89 <LLD Sr-90 Ci enno Ci Ci Ci
  • Analysis done by Offsite vendor. Results not available.

LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES L. FISSION AND ACTIVATION GAS RELEASES

1. Total Activity Released Ci 9.23E-3 5.10E-2
2. Average Concentration Released uCi/ml for Quarter 3.61E-9 1.92E-8
3. t of 10CFR50 Limits -

5

a. Quarterly Whole Body (1.5 mrem) t 0.03 0.05
b. Quarterly Any Organ (5.0 mrem) t 0.01 0.02
c. Annual Whole Body (3.0 mrem) t ).01 0.03
d. Annual Any Organ .

(10.0 mrem) t I 0.01 0.01 Report Page 13._ of 71 APR 181994  !

(9916SS/WPF/041194)

BRP 6100-6T1 i

' Ravicion 2 l

BYRON NUCLEAR POWER STATION {

UNIT 2 DOCKET NUMBER STN 455 l RADIOACTIVE EFFLUENT RELEASE REPORT l

January , 1994 .THROUGH June ,

1994 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES (CONT) i UNITS IST QTR 2ND GPTR 3RD QTR 4TH QTR '

M. TRITIUM

1. Total Activity Released Ci 1.95E+2 3.22E+2 j
2. Aver $ge Concentration Released uCi/ml for Quarter 7.64E-5 1.21E-4
3.  % of Limit (1.00E-3 uC1/ml)  %

7.64 12.12 ,

l, N. DISSOLVED NOBLE GASES

1. Total Activity Released Ci

. 7.38E-4 4.49E-3 i

2. Average Concentration Released uCi/ml for Quarter 2.89E-10 1.69E-9
3. t of Limit (2.00E-4 uCi/ml)  %

1.44E-4 8.47E-4

)

i O. OROSS AI.PHA

1. Total Activity Released Ci

<LLD <LLD

2. Average Concentration Released uCi/ml for Quarter 0.00 0.00 P. VOLUME OF WASTE RELEASED PER UNIT liter 8 2.10E+6 2.68E+6 Q. VOLUME OF DILUTION WATER PER UNIT liters 2.56E+9 3.65E+9 LIOUID EFFLUENTS - CONTINdOUS MODE R. LIQUID EFFLUENTS ,

Fe-55 Ci *

  • Sr-89 Ci *
  • I l

Ci j Ci I Ci 1

  • Value reported as LIQUID EFFLUENTS - BATCH MODE. PPROWD Report Page 1 of' 'l APR 181994 )

l (9916SS/WPF/041194) l

BRP 6100-6T1 Rsvision 2 BYRON 2CCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN 455 RADICACTIVE EFFLUENT RELEASE REPORT

.innuarv , 1994 THROUGH . lune ,

1994 LIOUID EFFLUE?TrS - BATCH MODE UNITS IST QTR 2ND QTR 3RD QTR 4TH GPrF S. LIQUID EFFLUENTS H-3 C1 1.95E+2 3.22E+2 Mn-54 Ci 1.61E-4 1.70E-3 Co-57 Ci 1.24E-5 1.56E-4 Co-58 Ci 1.12E-3 3.13E-3 Fe-59 C1 1.27E-5 <LLD Co-60 Ci 4.82E-3 3.07E-2 Zn-65 Ci 8.88E-6 2. 74E- 4 Kr-88 C1 <LLD 3.90E-5 Nb-95 Ci 1.66E-4 1.95E-5 7r-95 Ci 5.33E-6 <LLD Ag-110m Ci 2.28E-5 8.31E-4 Sn-113 Ci <LLD 4.29E-5 SS-122 Ci <LLD 2.55E-4 Sb-124 Ci (LLD 5.61E-4 Sb-125 Ci 2.74E-3 6.30E-3 Te-125m Ci <LLD 6.29E-3 I-131 C1 <LLD 2.96E-6 Xe-133 Ci 6'.96E-4 4.39E-3 Xe-133m Ci (LLD 3.70E-5 Xe-135 Ci 3.72E-6 5.89E-5 Cs-134 Ci 9.23E-5 1.07E-4 Cs-137 Ci 2.19E-4 3.49E-4 Report Page 15 of 23 APPROVED APR 181994 6-(9916SS/WPF/041194)

i BRP 6100-6T1 Ravision 2 BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50 455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1994 THROUGH June ,

1994 LIOUID EFFLUENTS - BATCH MODE (CONT.)

UNITS IST GTR 2ND QTR 3RD 77R 4TH QTR S. LIQUID EFFLUENTS (CONT. )

Sr-92 Ci <LLD 2.01E-4 Fe-55 Ci 5.49E-3

  • Sr-89 Ci 4.09E-6
  • Ci ci Ci C1 C1 C1 CL C1 Ci Ci Ci Ci C1 C1 -
  • Analysis performed by Offsite vender. Results not available.

T. 10CFR20 PUBLIC TEDE COMPLIANCE

1.  % OF 10CFR TEDE LIMIT t (100 mrem /yr) 0.00 0.00 Report Page 16 og 23 APPROVED APR 18 694 (9916SS/WPF/041194)

BRP 6100-6T1 Rsvision 2 BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv ,

1994 THROUGH _ June ,

1994 SOLID RADIOACTIVE WASTE 1st ogARTER 1994 g DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES TYPE, AND SOLIDIPTING OF SHIPMENT PER DATE ,

AGENT) TRANSPORT DESTINATION CUBIC FT SHIPMENT 02-11-94 Dewatered bead resin,' Class A Exclusive Barnwell, 199.4 3.21 Unstable, Liner, None Use S.C.

02-18-94 Filters, Class A Stable, HIC, Exclusive Barnwell, 132.4 14.6 None Use S.C.

l l

l i.. l

'I 331.8 17.81 2

QUARTERLY 'ICTALS - NUMBER OF SHIPMENTS: -_ CUBIC PT CURIES 17 '

Report Page of '3 g

,7 3 13 APR 18 $34 (9916SS /WPF/041194 )

BRP 6100-6T1 )

Ravision 2 BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT Januarv , 1994 THROUGH June , 1994 SOLID RADIOACTIVE WASTE 2nd OUARTER 1994 YEAR DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES SHIPMENT PER  !

TYPE, AND SOLIDIFYING OF DATE AGENT) TRANSPORT DESTINATION CUBIC FT SHIPMENT l

04-05-94 Dewatered Bead Resin, Class B Exclusive Barnwell, 132.4 68 l Stable, HIC, None Use S.C. l 04-18-94 DAW, Class A Unstable, Drums, Exclusive Barnwell, 105 3.08 l None Use S.C. I i

05-03-94 Dewatered Bead Resin, Class A Exclusive Barnwell, 199.4 3.59  !

Unstable, Cask, None Use S.C.

05-10-94 Filters, Class B Stable. HIC, Exclusive Barnwell, 132.4 69 i None Use S.C.

05-17-94 Dewatered Bead Resin, Class A Exclusive Barnwell, 199.4 9 I

Unstable, Cask, None Use S.C.

05-24-94 Dewatered Bead Resin, Class A Exclusive Barnwell, 199.4 12 i Unstable, Cask, None Use S.C.

06-07-94 DAW, Class A Unstable, Drums, Exclusive Barnwell, 399.6 0.479 ,

None Use S.C.

06-10-94 Dewatered 3ead Resin, Class A Exclusive Barnwell, 199.4 0.26 )

Unstable, Cask, None Use S.C.

(Continued on Page 19 of 23) 1939.3 167.72 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 10 CUBIC FT CURIES I

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Report Page 18 of _2_3, 3 APR 18iS34 l (Final) '

l (9916SS /WPF/041194) i

BRP 6100-6T1 l Ravision 2 i

BYROM NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454/455 RADIDACTIV6 EFFLUENT RELEASE REPORT Januarv , 1994 THROUGH June , 1094 SOLID RADIOACTIVE WASTE ?nd OUARTER 1004 YEAR DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, MODE PER CURIES TYPE, AND SOLIDIFYING OF SHIPMENT PER DATE AGENT) TRANSPORT DESTINATION CUBIC PT SHIPMENT 06-17-94 Dewatered Bead Resin, Class A Exclusive Barnwell, 170.2 0.535 l Unstable, Cask, None Use S.C. l 1

1 06-27-94 Dewatered Bead Resin & Filters, Exclusive Barnwell, 202.1 1.78 Class A Stable, HIC, None Use S.C. I l

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(Totals an Page) 18 o f 23 QUARTERLY TOTALS - IIUMBER OF SHIPMENTS: (See Pace 18 of 2M CUBIC FT CURIES i

Report Page 19 of 23 APPROVED

,, 3 13 APR 181994 (9916SS/WPF/041194 )

F1CN NUCLEAR POWER STATICN EFFLUENT AND WASTE DISPOSAL REPORT JANUARY 'IO JUNE,1994 ADDEt0UM A. The following data is the estimated composition of Byron's solid waste.

1. Dry Active Waste (DAW) 2. Primary Resin 3. Radwaste Resin Cr-51 5.36% Cr-51 <0.01% Cr-51 <0.01%

Mn-54 1.89% Mn-54 5.31% Mn-54 1.16%

Co-57 <0.01% Co-57 0.44% Co-57 0.13%

Co-58 22.40% Co-58 7.28% Co-Sa 2.45%

Fe-59 <0.01% Fe-59 <0.01% Fe-59 <0.01%

Co-60 18.12% Co-60 17.32% Co-60 23.08%

Zn-65 <0.01% Zn-65 0.36% Zn-65 <0.01%

Sr-92 c.0.01% Sr-92 <0.01% Sr-92 <0.01%

Nb-95 2.11% Mb-95 <0.01% Nb-95 <0.01%

Zr-95 1.19% Zr-95 <0.01% Zr-95 <0.01%

Sb-124 <0.01% Ag-110m <0.01% Ag-110m <0.01%

Sb-125 <0.01% Sb-124 <0.01% Sn-113 <0.01%

Sn-113 <0.01% Sb-125 1.60% Sb-124 <0.01%

Cs-134 0.70% Cc-134 10.41% Sb-125 0.81%

Cs-137 2.21% Cs-137 16 00% Cs-134 6.24%

H-3 3.80% H-3 <0 Sit Cs-137 12.32%

C-14 1.09% C-14 1.04% H-3 <0.01%

Fe-55 32.58% Fe-55 31.12% C-14 1.38%

Ni-63 8.51% Ni-63 8.12% Fe-55 41.51%  ;

Sr-90 0.04% Sr-90 0.04% Ni-63 10.86%

Tc-99 <0.01% Tc-99 <0.01% Sr-90 0.05%

I-129 <0.01% I-129 <0.01% Tc-99 <0.01%

Pu-239 <0.01% Pu-239 <0.01% I-129 <0.01%

Pu-238 <0.01% Pu-238 <0.01% Pu-239 <0.01%

Pu-241 <0.01% Pu-241 <0.01% Pu-238 <0.01%

Am-241 <0.01% Am-241 <0.01% Pu-241 0.02%

Cm-242 <0.01% Cm-242 <0.01% Am-241 <0.01%

Cm-244 <0.01% Cm-244 <0.01% Cm-242 <0.01%

Sb-122 .95% 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 Station continues to utilize the services of Pacific Nuclear for dewatering and solidification services.

1 C. Error Analysis The following is an estimate of the errors associated with effluent

- monitoring and analysis. The estimate it calculated using the square root of ;

the sum of the squares methodology.

{36350Z/081094) i

4

1. Caseous Effluents Sampling error = 1 to 3.5%

Calibration error = 10%

Counting Statistics error = 5%

Vent Stack Flowrates error = 1.5%

Total error = 11 - 12%

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 Statistica error = 7%

Weight error = 1%

Volume error = 5%

Total error = 10%

4. DAU Counting Statistico error =.7%

Calibration error = 10%

Weight error = 2%

Total 1 error = 12.4%

D. Meteorological and environmental impact information is. reported in the Station Annual Radiological Environmental 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 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 releanes.

H, There were no revisions to the-Offsite Dose Calculation Manual for this.

period.

(3635ZZ/081094)

ATTACHMENT A BYRCN NUCLEAR POWER STATION EFFLUENT AND NASTE DISPOSAL REPORT FOR JANUARY THROUGH JUNE, 1994 UNIT 1 AND 2 (DOCKET NUMBERS 5 0- 4 54 AND 5 0-4 5 5 )

LLD VALUES FOR GASEOUS RELEASES Icotores T in (ci /ml)

H-3 3.75E-17 Ar-41 2.35E-13 Mn-54 4.64E-19 Fe-59 9.37E-19 Co-58 4.84E-19 Co-60 6.05E-19 Kr-85 5.12E-11 Kr-88 5.51E-13 Sr-89 2.17E-22 Sr-90 6.60E-23 I-131 3.15E-18 I-133 5.61E-19 I-135 2.27E-18 Xe-133 4.19E-13 Xe-135 1.63E-13 Ca-134 4.61E-19 Cs-136 4.53E-19 Cs-137 5.10E-19 l

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a .

4 ATTACHMENT A (cont.)

BYRON NUCLEAR POWER STATION EFFLUDTI AND WASTE DISPOSAL REPORT FOR JANUARY THROUGH JUNE, 1994 LRIIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455)

LLD VALUES FOR LIQUID RELEASES Lgotcpes TTnfci/ml)

H-3 2.73E-12 Mn-54 3.01E-14 Fe-55 1.79E-14 Fe-59 5 99E-14 Co-57 2.13E-14 Co-58 3.15E-14 Co-60 3.89E-14 Zn-65 6.66E-14 Kr-88 7.79E-14 Sr-89 1.58E-15 Sr-90 1.32E-15 Sr-92 3.28E-14 Nb-95 3.06E-14 Zr-95 5.41E-14 Ag-110m 4.41E-14 Sn-113 3.54E-14 Sb-122 4.99E-14 Sb-124 7.91E-14 Sb-125 7.72E-14 Te-125m 6.32E-12 Xe-133 5.19E-14 Xe-133m 2.00E-13 Xe-135 2.28E-14 Cs 134 3.03E-14 Cs-137 3.32E-14 I-131 1.71E-13 (3635ZZ/081094)

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