ML20063G409
| ML20063G409 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/31/1993 |
| From: | Schwartz G COMMONWEALTH EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| BYRON-94-0041, BYRON-94-41, NUDOCS 9402160051 | |
| Download: ML20063G409 (28) | |
Text
{{#Wiki_filter:w, p7 p -- & pCY Commonwedith Edison-L 0 1 Byron Nuciter St!. tion . l C 4' 4450 North Grrman Church Rord . i 'L Byron, Illinois 61010 { i
' February 2, 1994 L!
LTR: BYRON 94-0041-FILE: 2.12.1522.(1.10.0101) ' g ,. ;
~!
Mr. J. B. Martin, Administrator Nuclear Regulatory Ceaunission Region III 5 801 Warrenville Road ; Lisle, Illinois 60532-4351 N
SUBJECT:
Semi-Annual Radiological Effluent Release Report .. Byron Station Units.1 and 2 1 Facility Operating License Nos. NPF 37 and 66. ' NRC Docket Nos. 50-454 and 50-45E
'?
Dear Mr. Martin:
i Enclosed is the Semi-Annual Radiological Effluent: Release Report for July. through December, 1993, 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 2! forwarded to the Document Control Desk and one copy to the Senior Resident. l Inspector.
'l Sincerely, l
W G.K. Schwartz ! Station Manager l Byron Nuclear Power Station l
.i GKS/DD/rp 'j -
l n Enclosure d. cct Distribution List l Attached l i
. (3 635z/013194 ) 5 l
140047 jM2tgggggggg2, g y g
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, 4 i.
. . p SEMI-ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT DISTRIBUTION LIST I Director of Nuclear Reactor Regulation - U.S. Nuclear
-i Regulatory Commission
- i Nuclear Regulatory Commission, Region III h f
f Illinois Department of Nuclear Safety, Office of Environmental Safety i A N.I. I l i U.S. Environmental Protection Agency Air and Radiation Branch - Region V Health Physicist
+
Murray and Trettel, Inc. l 1 Teledyne Isotopes Midwest Laboratory and General Manager ! C?temistry Services - Chemistry Services Director i l
-f Byron Station Central Files, File Number 2.12.1522 Health Physics Services Supervisor - Byron Nuclear Power Station i Radiological Effluent Monitoring Program Coordinator NRC Senior Resident Inspector - Byron Nuclear Power Station i B.P.I. Associates General Counsel
'i I
Health Physics Services Supervisor - Braidwood Nuclear Power Station. i , ? J
.]
.j i
i (3635z/012894) 1
. . BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JULY through DECEMBER 1993 Supplemental Information I
- 1. Regulatory Limits
- a. Fission and activation gases: ;
10CFR20 Whole Body = 500 mrem / year ; Skin = 3000 mrem / year - t 10CFR50 Gamma = 5 mrad / quarter; 10 mrad / year Beta = 10 mrad / quarter; 20 mrad / year i
- 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: '
10CFR50 Whole Body = 1.5 mrem / quarter; 3 mrem / year Organ - 5 mrem / quarter; 10 mrem / year
- 2. Maximum Permissible Concentration
- a. Fission and Activation Gases: 10CFR20 Appendix.B Table II
- b. Iodine: 10CFR20 Appendix B Table II ;
- c. Particulates: 10CFR20 Appendix B Table II
- d. Liquid Eftc aents: 10CFR20 Appendix 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 Approximations of Total Radioactivity i
- a. Fission and Activation Gases: Prior.to release, the isotopic content is determined. Released activity is calculated using volume of, release, $+.12 ic setermined by the change in tank or containment pressuze. Additional methods of calculation utilize historical data .i and a: sign an isotopic mix which is representative of normal vent ,
stack isotopics. l
- b. Particulate,' Tritium and Iodine sampling media for the plant vent i stacks are collected and isotopically analyzed daily for the' plant vent stacks.
?
(3635x /012894 ) i
. , , ~ ,y -
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1
. . ' BYRON NUCLEAR ~ POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JULY through DECEMBER 1993 Supplemental Infonnation i (continued)
- c. Liquido effluents: Batch releases are isotopically analyzed prior to' i release. Total release activity is calculated using volume of- i 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
(< LID) are reported in units of Ci/ml unless otherwis: noted. All LLD values are listed in Attachment A.
- 5. Batch Releases:
- a. Liquid:
- 1. Number of batch releases = 155 r
- 2. Total time period for batch releases = 15,281 minutes
- 3. Maximum time period for a batch release = 382 minutes q
- 4. Average time period for a batch release = 98.6 minutes
- 5. Minimum time period for a batch release = 6 minutes
- 6. Average stream-flow during periods of release of effluent into a ,
flowing stream = 8,322 cfs, based on information from the National Weather Service or1 Army Corps of Engineers for the Rock f River. ,
- b. Gaseous:
- 1. Number of batch releases = 154
- 2. Total time period for batch releases = 49,558 minutes
- 3. Maximum time period for a batch release = 14,185 minutes
- 4. Average time period for batch releases = 321.8 minutes
- 5. Minimum time period for a batch release = 13 minutes
- 6. Abnormal Releases:
- a. Liquid 'none
- b. Gaseous - none
- 7. Public dose calculations due to liquid and gaseous effluents are_ attached at the end of this' report.
i I (3635 z/013194) .i
],' . ~- ' CRP 6100'6T1 R3 vision 1
-
- BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT l' July 1993 THROUGH December
, 1993 i=1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES k UNITS IST CPrR 2ND QTR 3RD QTR 4TH QTR A. FISSION AND ACTIVATION GAS RELEASES
- 1. Total Releast Activity Ci
.,, 3.74E+0 4.52E+1-
- 2. Mav4== Release Rate for Quarter uCi/sec 4.85E+0 2.31E+0
- 3. % of 10CFR20 Limits
- i
- a. Whole Body (500 mrem /yr) % 0.00. 0.00
- b. Skin (3000 mrem /yr) %
0.00 'O.00 >
- 4. t 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 ** _ .. j
- 1. Total I-131/I-133 Activity Ci
< LLD < LLD .
C. PARTICULATE (>8 day half-life) RELEASES **
- 1. Gross Activity Ci --
3.75E-6 <LLD
- 2. Gross Alpha Activity for Quarter Ci (LLD <LLD !
i D. TRITIUM RELEASES ** 'I '
-1. Total Release Activity Ci '4.20E-1 8.56E-2. fi 1
% of 10CFR20 limits is based on the m=v4== release rate for the period considered. 1 Iodine, particulate, and tritium % of 10CFR20/10CFR50 limits -are tyressed as a. total limit. See step E.
1
- ~
Report Page 3 og 22 ' 1 JAN 011994 b (9916SS/WPF/110893) i
j, . ERP 6100-6T1 Revicion 1 BTRON NUCLEAR POWER STATION UNIT I DOCKET NDMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT July 1993 THROUGH l
, December , 1993 MEOUS EFFLUENTS - Smo4 TION OF' ALL RELEASES (CONT)
UNITS IST QTR 2ND CPTR 3RD QTR 4TH QTR , E. SUM OF IODINE, PARTICULATE (>8 day half-life), AND TRITIUM RELEASES
- 1. Total Activity C1 4.20E-1 8.56E-2
- 2. % of 10CFR20 Limit
- a. Any organ (1500 mrem /yr) % 0.00 0.00
- 3. % of 10CFR50 Limit l
- a. (>.arterly Any Organ (7.5 mram) % 0.01 0.00
- b. Annual Any Organ (15.0 mram) % 0.01 0.00
- GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE F. FISSION AND ACTIVATION GAS RELEASES Ar-41 ~
]-' Ci 7.57E-3 1.81E-2 Kr-85
_ Ci 2.42E-2 1.31E-2 Xe-133 Ci 2.01E-1 1.72E-1 Xe-133m Ci 7.24E-4 < LLD Xe-135-Ci 2.26E-3 1.95E-3
~
Ci < LLD 8.31E-4 Ci ' Ci i ci ; Ci > Ci Report.Page 4 of 22 , JAN 011994 g (9916SS/WPF/110893)
, BRP 6100-6T1 Revicion 1 BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN-50, 454 July ' RADIOACTIVE EFFLUENT 1993 THROogn RELEASE DecemberREPORT 1993 l' ,
GASEOUS EFFLUENTS - VENT STACK RELEASES - BATCH MODE (CONT) UNITS 1ST QTR 2ND QTR 3RD QTR 4TH.QTR , G. IODINE RELEASES o, I-131 ci * *- I-133 ci *
- T-135 Ci * * ,
- Value reported as Continuous Release Mode.
H. PARTICULATE (>8 day half-life) RELEASES Sr-89 et *
- Sr-90 ci *
- Ci Ci Ci
- Value reported as Continuous Release Mode.- i GASEOUS EFFLUENTS - VENT STACK DmM7S - Currrmuvus MODE ,
1 I. FISSION AND ACTIVATION GAS RELEASES . r- 8 Ci 3.50E+0 3.26E+0 Xe-131m Ci <LLD 3.27E+1 Xe-133 Ci <LLD 9.08E+0~ 4 .- i. C1 CL Ci
~
CL i Ci " j-l Report Page 5 of 22 APPROVED i l JAN 011994 ! l!
.-(9916SS/WPF/110893) 4
.1 '
'f.- ERP 6100-671 Revision 1
, , BYRON NUCLEAR POWER STATION UNIT 1~ DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT l July , 1993 THROUGH December 1993 MEOUS EFPLUENTS - VENT STACK PMn3ES - Cununuvus MODE (CONT) i UNITS IST QTR 2ND QTR 3RD QTR 4TH CTR J. IODINE RELEASES I-131'* Ci (LLD ~< LLD l-133
- Ci < LLD . < LLD l-135 Ci < LLD < LLD ,
K. PARTICULATE (>8 day half-life) RELEASES Co-58 Ci 5.75E-6 <LLD Sr-89 - Ci < LLD -
- Sr-90 c1 , < tty
- Ci ci
- Analysis done by off-site vendor. Results not available.
LIOUTD EFFLUENTS - SUMMATION OF ALL RU tn3ES L. FISSION AND A 6.0N GAS RELEASES
- 1. Total Activity Released Ci 3.18E-1 3.16E-2 ,
- 2. Average Concentration Released uCi/ml for Quarter 1.18E-7 1.37E-8 ,
~
- 3. % of 10CFR50 Limits
- a. Quarterly Whole Body *
(1.5 mrem) % 0.07
~
0.06
- b. Quarterly Any Organ ;
(5.0 mram) 0 0.10- 0.04
- c. Annual Whole Body (3.0 mram) % 0.04 0.02
- d. Annual Any Organ (10.0 mrem) % 0.05 0.02 Re,.rt ,a,e e e, 22 APPROVED' i i;
JAN 011994
- < (9916SS/WPF/110893)
CRP 6100-6T1- -3 Rsvision 1
* ' BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN 50- 454 RADIOAC17VE EFFLUENT RELEASE REPORT .
July 1993 -vug December 1993 1.TOUTD EFFLUENTS - SUMMATION OF ALL pr m_SES (CONT) UNITS- IST QTR 2ND QTR 3RD QTR -(TH QTR M. TRITIUM
- 1. Total Activity Released l'
C1 1.59E+2 1.05E+2
- 2. Average Concentration Released uCi/ml for Quarter 5.90E-5 4.55E-5
- 3. % of Limit (3.00E-3 uCi/ml) %
1.97- 1.52 N. DISSOLVED NOBLE GASES l
- 1. Total Activity Released Ci 7.59E-3 3.60E-3
- 2. Average Concentration Released uCi/ml for Quarter 2.82E-9 1.56E-9
- 3. t of Limit (2.00E-4 uCi/nl) % -
1.41E-3 7.82E-4 i O. GROSS ALPHA -
- 1. Total Activity Released Ci
< LLD <LLD
- 2. Average Concentration Released uCi/ml for Quarter 0.00 0.00 l
P. VOLOME OF WASTE RELEASED PER UNIT liters 4.91E+6 2.64E+6 Q. VOLUME OF DILUTION WATER PER UNIT liters 2.69E+9 2.30E+9 i LIOUID EFFLUENTS - COivrmuvus MODE R. LIQUID EFFLUEh'IS I Fe-55 gi i Sr-89 gg a Sr-90 ci , , i Sb-125 Ci 3.67E-2
< LLD C1 Ci
- Value reported as liquid effluents - Batch Mode.
Report Page 7 of 22
~
.s. JAN 011994 I)
(9916SS/WPF/110893) !
> f. ERP 6100-6T1 Ravicion 1 BYRON NUCLEAR POWER STATION 1
UKIT DOCKET NUMBER STN 50 454 RADIQACTIVE EFFLUENT RELEASE REPORT July , 1993 THROUGH December , 1993 LIOUTD EFFLUENT 9 'EATCH MDDE
.]
UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR S. LIQUID EFFLUENTS H-3 Ci 1.59E+2 1.05E+2 Cr-51 Ci 6.23E-3 3.94E-3 Mn-54 C1 1.52E-3 5.02E Fe-55 Ci 4.84E-2
- Co-57 Ci 3.67E-5 2.74E-5 Co-58 1.65E-2 ci 1.20E-2 Fe-59 Ci : 2.65E-3 1.07E-3 Co-60 Ci , 1.66E-2 4.22E 2n-65 Ci 6.94E-5 3.84E-5 Sr-89 Ci <LLD'
- Sr-90 Ci <LLD *-
Sr-92 - ~- Ci 2.78E-4 <LLD-Nb-95 ~ ci 8.29E-4 5.71E-4 Zr-95 Ci' , 3.55E-4 3.30E-4 Ru-105 ci 9.85E-6 <LLD Ag-110m Ci 8.51E-4 .7.04E-5 Sn-113
~
Ci 3.76E-5 < LLD Sn-117n .. C1 1.38E-4 1.98E-5 Sb-122 Ci '6'71E-5
. <LLD Sb-124 C1 2.68E-3 3.56E-4
_ . Sb-4 25 - ci. .9.86E-2 6.37E Sb-126 . Ci 1.40E-3 < LLD
- Analysis done by offsite vendor. Results not available.
Report Page 8 og 22
,. APPROVED I
JAN 011994
~ ~
l
~ (9916SS/WPF/110893) . -
j- CRP-610016T1 R vicion 1 BYRON NUCLEAR POWER STATION-UNIT I DOCKET NUMBER STN-50 454 RADIOACTIVE EFFLUENT RELEASE REPORT July , 1993 THRODGH December , 1993 troarn arrLustrrs - nATcn Moor UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR S. LIQUID EFFLUENTS Te-125m Ci _ 8.27E-2 '1.38E-3 Xe-133 Ci 7.49E '9.62E-4 Xe-133m Ci 2.70E-5 < LLD Xe-135 Ci 6.27E-5 5.52E-6 Cs-134 Ci 2.00E-4 2.33E-4 Cs-137 Ci
' ~ '
5.44E-4 4.79E-4 W-187 ci 8.72E-5 < LLD Kr-88 Ci <LLD 2.63E-3 Ci ci Ci Ci Ci-
.i Ci ,
Ci i ci l
~
C1 Ci ci Ci-
~
Ci ci Report Page 9 of 22 APPROVED JAN 011994
~
6-(9916SS/WPF/110893) , --
CRP .s100- 6T1 R vicion 1 I BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN-50 455 RADICACTIVE EFFLUENT RELEASE REPORT I July 1993 THROUGH December 1993
, l GASEOUS EFFLUElfrS - SUMMATION OF ALL RELRASES UNITS IST QTR 2ND QTR 3RD QTR 4TH yrR A. FISSION AND ACTIVATION GAS RELEASES
- 1. Total Release Activity Ci 6.93E+0 9.12E+0
- 2. Mar Release Rate for Quarter uCi/sec 4.85E+0- 1.48E+0
- 3. % of 10CFR20 Limits *
- a. Whole Body (500 mrem /yr) % 0.00 0.00
- b. Skin (3000 mrem /yr) %
0.00 0.00
- 4. % of 10CFRSO Limits
- a. Gamma Quarterly (5 mrad) t 0.00 0.00
- b. Beta Quarterly (10 mrad) t 0.00 0.00
- c. Gamma Annual (10 mrad) %
0.00 0.00 ,
- d. Beta Annual (20 mrad) t 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 **
t
- 1. Total Release Activity Ci '7.94E-2 1.18E-1
% of 10CFR20 limits is based on the ==v4== release rate for the period considered.
Iodine, particulate, and tritium % of 10CFR20/10CFRSO limits are expressed as a total limit. See step E.
~~~
Report Page 10 of 22 '
-1 JAN 011994 I (9916SS/WPF/110893)
. -[- ERP 6100-6T1 Revicion 1 6 BYRON NUCLEAR POWER STATION UNIT 2 pocKgT NUMBER STN 455 RADIQACTIVE EFFLUENT RRLEASE REPORT July , 1993 THROUGH December , 1993 'lL GASEOUS EFFLUENTS - SUMMATION OF ALL RETEASES (CONT)
' UNITS IST QTR 2ND CTTR 3RD CfrR 4TH QTR' E. SUM OF IODINE, PARTICULATE (>8 day half-life), AND TRITIUM RELEASES
- 1. Total Activity Ci 7.94E-2 1.18E-1 I
- 2. t of 10CFR20 51mit
- a. Any Organ (1500 mrem /yr) t l 0.00 0100
- 3. t of 10CFR50 Limit
- a. Quarterly Any Organ (7.5 mrem) %
0.00 0'.00
- b. Annual Any Organ (15.0 mram) %
0.00 0.00
.i GASEOUS EFFLUENTS - VENT STACK RELEASES - EATCH MODE F. FISSION AND ACTIVATION GAS RELEASES. '
Ar-41 ~' j Ci 1.38E-2 1.24E-2 Y-8 Ci. 2.42E-2 1.31E-2 Xe-133 Ci 1.33E-1 1.05E-2 Xe-133m Ci .7.24E-4 < LLD - Xe-135 Ci 2.73E-5' 2.34E-6 Ci i ci i
-- l 1
CL' l Ci-1 Ci Ci I i Report Page 11 of 2 i l i JAN 011994. ; (9916SS/WPF/110893)
-{
DRP 6100-6T1 R::vicion 1 BYRON NUCLEAR POWER STATION UNIT 1 DOCKET NUMBER STN-50 455 i RADIOACTIVE EFFLUENT RELEASE REPORT July , 1993.THROUGH December , 1993 l-) GASEOUS EFFLUENTS - VENT STACK _RRIJZASES - RATCH NODE (CONT) I UNITS IST QTR 2ND QTR 3RD QTR 4TH QTR ; l G. IODINE RELEASES I I-131 Ci *
- I-133 Ci *
- I-135 eg , ....
- Value reported as Continuous Release Mode.
H. PARTICULATE (>8 day half-life) RELEASES I Sr-89 Ci *
- Sr-90 Ci * *-
Ci Ci Ci
- Value reported as Continuous Release Mode.
GASEOUS EFFLUENTS - VENT STACK RELEASES - C0annuOus MODE I.- FISSION AND ACTIVATION GAS RELEASES l. Kr-88 , Ci 3.66E+0- <LLD Xe-133 Ci 3.10E+0 9.08E+0 , Ci i e CL Ci ci
~.
g3 Ci
- 1
, -h i Report Page 1 of 22 -
APPROVED l i JAN 011994 3 l.< (9916SS/WPF/110893)
l,. - ERP 6100-6T1 Ravision 1
- BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NUMBER STN 455 RADIOACTIVE EFFLUENT RELEASE REPORT l July , 1993 THROUGH December 1993 GASEOUS EFFLUENTS - VENT STACK RETM SES - CQwnnuvus MDDE (CONT)
UNITS 1ST QTR 2ND QTR 3RD QTR 4TH QTR J. IODINE RELEASES T-131 ' '
- Ci < LLD < LLD I-133 71 < LLD < LLD I-135 Ci < LLD < LLD K. PARTICULATE (>B day half-life) RELEASES l
Sr-89 Ci <ttp
- Sr-90 Ci <LLD
- Ci '
C1 Ci
- Analysis done by offsite vendor. Results not available.
LIOUID EFFLUENTS - SUMMATION OF ALL PrTRASES L. FISSION AND ACTIVATION GAS PJtLEASES q
't
- 1. Total Activity Released C1 3.18E-1 3.16E-2
- 2. Average Concentration Released uC1/ml for Quarter 1.18E-7 1.37E-8 6
- 3. t of 10CFR50 Limits
- a. Quarterly Whole Body (1.5 mrem) % 0.07 0.06 .l
- b. Quarterly Any Organ (5.0 mram) t 0.10 0.04
- c. Annual Whole Body ,
(3.0 mrem) t 0.04' O.02
- d. Annual Any Organ (10.0 mrem) %
0.05- 0.02
~
Re, ort ,a,e 13 ef .u APPROVED' l JAN 01'1994 I! '
^ (9916SS/WPF/110893)
i x . ERP 6100-6T1 Revicion 1
-BYRON NUCLEAR POWER STATION UNIT 2 DOCKET NDMBER STN 455
RADIOACTIVE EFFLUENT RELEASE REPORT July , 1993 m t December 1993 LIOUID EFFLUENTS - SUMMATION OF ' ALL pet.r2LSES (CONT) UNITS IST CTR 2ND QTR 3RD QTR 4TH QTR M. TRITIUM l
- 1. Total Activity Released Ci 1.59E+2 1.05E+2 i 2 Ave're'ge Concentration Released uCi/ml for Quarter 5.90E-5 4.55E 3. t of Limit (3.00E-3 uCi/ml) %
1-.97 1.52 N. DISSOLVED NOBLE GASES f
- 1. Total Activity Released Ci '
7.59E-3 3.60E-3
- 2. Average Concentration Released uCi/ml for Quarter 2.82E-9 1.56E-9
- 3. % of Limit (2.00E-4 uCi/ml) % -
1.41E-3)7.82E-4~ O. GROSS ALPHA -
- 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 liters 4.91E+6 2.64E+6~l Q. VOLUME OF DILUTION WATER PER UNIT liters 2.69E+9 2.30E+9 LTOUTD EFFLUENTS - Cwrmuvus MODE R. LIQUID EFFLUENTS Fe-55 .
Ci * *- Sr-89 ci
- 1 Sr-90 b Ci * *-
Sb-125 ' Ci 3.67E-2 <LLD i Ci Ci !
- Value reported as Liquid Effluents - Batch Report Page 14 of _21 I
- - ~
.s. JAN 011994 (9916SS/WPF/110893)
[ ERP 6100-6T1 R::vi= ion 1
- BYRON NUCLEAR POWER STATION '
UNIT 2 DOCKET m ER STN-50 455 RADICACTIVE EFFLUENT RELEASE REPORT Julv , 1993 THROUGH December , 1993 .
. LIOUID EFFLUENTS -~ BATCH MODE UNITS IST QTR '2ND QTR 3RD QTR 4TH QTR S. LIQUID EFFLUENTS H-3 Ci '
_. - 1.59E+2 1.05E+2 Cr-51 ci
- 6. 23E--3 3.94E-3 :
Mn-54 ci 1.52E-3 5.02E-a - Fe-55 ci 4.84E-2 * , Co-57 ci 3.67E-5 2.74E-5 Co-58 c1 1.65E-2 1.20E-2 Fe-59 Ci 2.65E-3 1.07E-3 Co-60 1.66E-2 Ci 4.22E-3 . Zn-65 ci 6.94E-5 3.84E Sr-89 Ci < LLD - *' Sr-90 ' ci < LLD
- Sr-92 -
Ci 2.7BE-4 < LLD ,
~
Nb-95 ci 8.29E-4 5.71E-4~ Zr-95 ci~ , 3.55E-4 3.30E-4 Ru-105 Ci 9.85E-6 < LLD Ag-110m Ci 8.51E-4 7.04E-5 Sn-113 ci 3.76E-5 < LLD - Sn-117m ci 1.38E-4 1.98E-5 Sb-122
'Ci 6.71E-5 - < LLD '
Sb-124 Ci 2.68E-3 3.56E-4 >
.Sb-125 ci 9.86E-2 6.37E-3 Sb-126 C1 1.40E-3 < LLD
- Analysis done by offsite vendor. Results not available.
Report Page 15 of 22 ' APPROVED JAN 011994 Ii (9916SS/WPF/110893) . --
~[ ERF 6100-6T1 Ravicion 1 BYRON 2r# M" POWER STATION UNIT 2 DOCKET NUMBER STN-50. 455 RADIOACTIVE EFFIDENT RELEASE REPORT !
July , 1993 WROUGH December , 1993 i LIOUID EFFLUENTS ' BATCH MODE 1 UNITS IST QTR ~2ND QTR 3RD QTR 4TH grR S. LIQUID EFFLUENTS ~k e'1 Te-125m Ci ' 8.27E-2I1.38E-3 Xe-133 Ci 7.49E-3 9.62E-4 Xe-133m C1 2.70E-5 < LLD
- Xe-135 Ci . 6 ~. 2 7 E-5 5.52E-6 Cs-134 Ci 2.00E-4 2.33E-4 Cs-137 Ci 5.44E-4 4.79E-4 W-187 Ci 8.72E-5 <LLD Kr-88 Ci < LLD 2.63E-3 ;
Ci , Ci ! CL Ci Ci Ci~ , Ci ci Ci C1 Ci ' Ci I gg Ci !
. i e
Report Page 2 of 1 f
- APPROVED ,
f i JAN 011994 > l '; (9916SS/WPF/110893) . --
- . rRP 6100-6T1 R3 vision 1 BYRON NUCLEAR POWER STATION UNIT 162 DOCKET NUMBER STN 454/455 ,
RADIGACTIVE EFFIDENT RELEASE REPORT
.Tulv , 1993 THROUGH _ December , 1993 SOLID RADIQACTIVE WASTE 3rd tm 1993 g DISPOSITION OF MATERIAL VOLUME (DESCRIPTION, CLASS, DODE PER CURIES TYPE, AND SOLIDIFYING OF SHIPMENT PER DATE AGENT). TRANSPORT DESTINATION CUBIC FT SHIPMENT ,
Dewatered bead resin, 07-19-93 Class C, HIC, None iclusive Use Barnwell,SC 132.4 3.32E+2 DAW, Glass A. Drums, 07-27-93 None sxclusive Use Barnwell,SC 622.5 1.02 l Dewatered bead resin. 08-09-93 Clasa E, HIC, None 2.xclusive Use Barnwell, SC 132.4 2.67E+1 Dewatered bead resin,and 09-10-93 DAW, Class A Unstable, Ixclusive Use Barnwell, SC 199.4 9,90 Cask, None newatereo neaa r_esant < 09-17-93 Class B, Cask, None Exclusive Use Barnwell.SC 202.1 1..'9E+1 L S P
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1288.8 387.52 QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 5 CUBIC FT CURIES k Report Page I7 of 22
, ,g , JAll 01 1994 ,
(9916SS/WPF/110893) >
'. CRP 6100-6T1 R3 vision 1 1 ,_ BYRON NUCLEAR POWER STATION UNIT 162 DOCFrr NUMBER STN-50 454/455 RADICACTIVE EFFLUENT RELEASE REPORT '
July , 1993 THROUGH December , 1993 SOLTD RADIQACTIVE WASTE 4th OUARTER 1993 YEAR t DISPOSITION OF MATERIAL VOLONE ' (DESCRIPTION, CLASS, ICDE PER CURIES TYPE, AND SOLIDIFYING OF EHIPMENT PER DATE AGENT) TRANSPORT DESTINATION CUBIC PT SHIPMENT Dewatered bead resin and 10-13-93 DAW, Class A, Unstable Exclusive Use Barnwell, SC 199.4 4.09 Cask, None F DAW Class A, Drums, 10-22-93 None Exclusive UseBarnwell, SC 622.5 1.07 Dewatered bead resin, 11-10-93 Class A Unstable. Cask Exclusive Use3arnwell. SC 199.4 1.00 None DAW, Class A, Drums and 12-10-93 LSA Boxes, None Exclusive UseBarnwell, SC 828 0.144 DAW Class A, Seavan, 12-17-93 None Exclusive Use3arnwell, SC 1280 0.285 Dewatered bead resin anc 12-20-93 DAW, Class A. Unstable. Exclusive Use Barnwell, SC 199.4 1.38 l Cask, None i 3328.7 7.97 ' QUARTERLY TOTALS - NUMBER OF SHIPMENTS: 6 CUBIC FT CDRIES. F l Report Page 18 of 22 OM l.
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(9916SS/WPF/Il0893) 3
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1 BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT JULY TO DECEMBER, 1993 'i ADDENDUM A. The following data is the estimated composition of Byron's solid waste.
- 1. Dry Active Waste (DAW) 2. Primary Resin 3. Radwaste Resin C2-51 12.82% Cr-51 <0.01%- Cr-51 0.10%
Mn-54 1.63% Mn-54 5.82% Mn-54 3.31% Co-57 <0.01% Co-57 0.62% Co-57 0.53%~ Co-58 20.29% Co-58 11.43% Co-58 29.39%- Fe-59 0.21% Fe-59 <0.01% Fe-59 0.03% Co 60 14.10% Co-60 15.38% Co-60 13.80% Zn-65 <0.01% Zn-65 <0.01% Zn-65 0.08% Sr-92 <0.01% Sr-92 <0.01% Sr-92 <0.01% Nb-95 11.05% Nb-95 <0.01% Nb-95. 0.08% Zr-95 3.26% Zr-95 <0.01% Zr-95 0.03% 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 0.09% Sb-125 1.17% -Sb-124 0.05% Cs-134 0.46% Cs-134 14.82% Sb-125 1.83% Cs-137 1.76% Cs-137 16.47% Cs-134 8.41%. H-3 2.96% H-3 <0.01% Cs-137 11.34% C-14 0.37% C-14 0.47% H-3 0.01% Fe-55 23.94% Fe-55 26.05% C-14 0.42% , Ni-63 7.04% Ni-63 7.69% Fe-55 23.66% Sr-90 <0.01% Sr-90 0.03% Ni-63 6.92% Tc-99 <0.01% Tc-99 <0.01% Sr-90 0.02% I-129 <0.01% I-129 <0.01% Tc-99 <0.01% l 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 0.03% 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% 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 servicec of Pacific Nuclear for ., dewatering and solidification services. l C. Error Analysis The following is an estimate of the errors associated with effluent. monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology. , (36352/013194) !
-r- __ '. 1. Gs330us Efflusnts Sampling error = 1 to 3.5%-
i Calibration error = 10% Counting Statistica error = 5% i Vent Stack Flowrates error = 1.5% Total error = 11 - 12%
- 2. Liquid Effluents ,
Sampling error = 1% i 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% _j Volume error = 5% Total error = 10% 4 '. DAW Counting Statistics error = 7% Calibration error = 10% Weight error = 2% , Total 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 releases. q H. The Offsite Dose Calculation Manual (DDCM) was revised effective January 1, 1994. This revision addressed changes to support the new
-10CFR20 implementation. These major changes ' include:
Whole body dose factors are now calculated using 1 cm depth as , opposed to 5 cm.' Restricted Area Boundaries have been revised and are included in-Appendix F of the ODCM. . The Land Use Census (e.g. nearest - resident, dairy and livestock was , used to update Appendix F tables in the ODCM. Joint Frequency Distribution Tables were added for reference to. , Appendix F in the ODCM. . Revised Curie limits for radioactivity in unprotected tanks. (3635z/013194) .
". i t ATTACHMENT A > BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT FOR JULY THROUGH DECEMBER, J 9 9 "i ; UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455) t LLD VALUES FOR GASEOUS RELEASES Isotones LLD(C1/ml) H-3 3.71E-17 , Ar-41 2.12E-13 t Mn-54 4.57E-19
'm-59 9.68E-19
'a 58 4.66E-19 !
Co-60 7.03E-19 i Kr-85 4.98E-11 Kr-85m 1.58E-12 Kr-87 3.23E-13 Kr-88 5.12E-13 Sr-89 3.45E-21 Sr-90 1.20E-21" I-131 3.28E-18 I-132 5.35E-19 I-133 5.20E-19 I-134 6.18E-18 I-135 2.09E-18 , Xe-131m 6.53E-12 Xe-133 3.69E-13 Xe-133m 1.35E-12 Xe-135 1.57E-13 Xe-135m 2.19E-13 Cs-134 4.58E-19 Cs-136 4.38E-19 , Cs-137 4.95E-19 Ba/La-140 2.9BE-18 9 (3635z/013194) ~, .
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ATTACHMENT A (cont.) ' BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL REPORT FOR JULY THROUGH DECEMBER, 1993 UNIT 1 AND 2 (DOCKET NUMBERS 50-454 AND 50-455) LLD VALUES FOR LIQUID RELEASES Isotones LLD (C1/ml) , H-3 2.57E-12 Cr-51 2.A1E-13 Mn-54 3.09E-14 Fe-55 7.27E-14 Fe-59 6.47E-14 l Co-57 1.96E-14 Co-58 3.11E-14 Co-60 4.60E-14 Zn-65 6.56E-14 Kr-88 7.46E-14 Sr-89 6.70E-15 Sr '0 4 B.57E-15 Sr-92 3.49E-14 Nb-95 2.84E-14 Zr-95 5.62E-14 Mo-99 2.64E ' Ru-105 8.28E-14 Ag-110m 4.86E-14 Sn-113 3.48E-14 , Sn-117m 2.0BE-14 Sb-122 4.99E-14 Sb-124 7.91E-14 Sb-125 7.36E-14 Sb-126 4.893-14 Te-125m 5.91E-12 Ze-133 5.35E-14 Xe-133m 1.96E-13 Xe-135 2.27E-14 Cs-134 3.20E-14 Cs-137 3.43E-14 Ba/La-140 2.95E-14 W-187 1.47E-13 1 i 7 (3635z/013194 ) 1
BYRON STATION UNIT ONE ; i ACTUAL 1993 + MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES i PERIOD OF RELEASE - 01/01/93 TO 12/31/93 . CALCULATED 01/07/94 : CHILD RECEPTOR [ 1ST 2ND 3RD 4TH TYPE- QUARTER QUARTER QUARTER QUARTER ANNUAL i JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.17E-04 1.14E-06 1.35E-06 3.58E-05 1.55E-04 (MRAD) (SSE ) (SSE ) (SSE ) (SSE') (SSE ) BETA AIR 4.89E-04 1.03E-05 4.12E-06 1.40E-04 6.43E-04 (MRAD) (SSE ) (SSE ) (SSE ) (SSE )- (SSE') TOT. BODY 6.16E-05 6.22E-07 7.89E-07 1.90E-05 8.20E 1 (MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) , SKIN 2.44E-04 6.51E-06 2.74E-06 6.92E-05 3.23E-04 (MREM) (SSE ) (SSE -) (SSE ) (SSE ) (SSE ) 5.64E-05 9.08E-04 ORGAN 7.39E-05 4.47E-05 7.43E-04 (MREM) (SSE ) (SE ) (SE ) (S ) (SSE ) _ ; THYROID LIVER GI LLI
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LIVER THYROID THYROID THYROID - KIDNEY KIDNEY , LUNG LUNG GI LLI GI~ LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I > CHILD RECEPTOR
% OF APP I. ------------
QTRLY 1ST QT3 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 (HREM) 7.5 0.00 0.00 0.01 0.00 15.0 0.01 THYROID LIVER GI-LLI LIVER THYROID' THYROID THYROID KIDNEY KIDNEY LUNG LUNG i GI_LLI GI_LLI RESULTS BASED UPON: ODCM ANNEX REVISION 0.K JANUARY 1993 : I ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 , i l
BYRON STATZON UNIT TWO + . ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 01/07/94 CHILD RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 6.16E-05 1.38E-06 1.50E-06 3.47E-05 9.92E-05 (MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) BETA AIR 2.64E-04 1.04E-05 3.31E-06 1.37E-04 4.15E-04 (MRAD) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) TOT. BODY 3.25E-05 7.86E-07 9.26E-07 1.84E-05 5.26E-05 (MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) SKIN 1.34E-04 6.81E-06 2.74E-06 6.73E-05 2.11E-04 (MREM) (SSE ) (SSE ) (SSE ) (SSE ) (SSE ) ORGAN 5.08E-05 5.52E-05 1.41E-04 6.15E-05 2.91E-04 (MREM) (S ) (SE ) (SE ) (S ) (SE ) THYROID LIVER LIVER LIVER THYROID THYROID THYROID THYROID KIDNEY KIDNEY KIDNEY LUNG LUNG LUNG GI LLI GI LLI GI -LLI THIS IS A REPORT FOR THE CALENDAR YEAR IV93 COMPLIANCE STATiiS - 10CFR 50 APP. I CHILD RECEPTOR
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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 0.00 0.00 0.00 15.0 0.00-THYROID LI/ER LIVER LIVER THYROID: THYROID THYROID THYROID KIDNEY KIDNEY KIDNEY LUNG LUNG LUNG GI_LLI GI_LLI GI_LLI RESULTS BASED UPON: ODCM ANNEX REVISION 0.E JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
BYRON STATION UNIT ONE-1 _ ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS r?ERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 01/07/94 ADULT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL , JAN-MAR APR-JUN JUL-SEP OCT-DEC ; TOTAL 7.31E-04 1.39E-03 1.05E-03 8.49E-04 4.02E-03 ' BODY ZNTERNAL 4.32E-03 5.71E-03 4.95E-03 2.13E-03 1.71E-02 , ORGAN GI_LLI GI_LLI GI_LLI GI_LLI GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 t COMPLIANCE STATUS - 10 CFR 50 APP. I
% 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 TOTAL BODY (MEEM) 1.5 0.05 0.09 0.07 0.06 3.0 0.13 CRIT. ORGAN (MREM) 5.0 0.09 0.11 0.10 0.04 10.0 0.17 GI_LLI GI_LLI GI_LLI GI_LLI GI_LLI , RESULTS BASED UPON: ODCM: ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
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BYRON STATION UNIT TWO ACTUAL 1993 MAXIMUM DCSES (MREM) RESULTING FROM AQUATIC. EFFLUENTS .i PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 01/07/94 s ADULT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER . ANNUAL , JAN-MAR APR-JUN JUL-SEP OCT-DEC , TOTAL 7.31E-04 1.39E-03 1.05E-03 8.49E-04 4.02E-03 BODY INTERNAL - 4.32E-03 5.71E-03 4.95E-03 2.13E-03 1.71E-02. ORGAN , GI_LLI GI_LLI GI_LLI GI_LLI GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i COMPLIANCE STATUS - 10 CFR 50 APP. I
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QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY %,OF-OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.05 0.09 0.07 0.06 3.0 0.13 CRIT. ORGAN (MREM) 5.0 0.09 0.11 0.10 0.04 10.0 0.17 ; GI_LLI GI_LLI GI_LLI GI_LLI GI_LLI RESULTS BASED UPON: ODCM ANNEX REVISION 0.K JANUARY 1993 f ODCM SOFTWARE VERSION 0.1 APRIL 1993 , ODCM DATABASE VERSION 0.1 APRIL 1993 i I 1 b}}