ML20012A119
| ML20012A119 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1989 |
| From: | Mccormick M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20012A116 | List: |
| References | |
| NUDOCS 9003080309 | |
| Download: ML20012A119 (52) | |
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PHILADELPHIA ~ ELECTRIC COMPANY-LIMERICK GENERATING STATION '
UNIT NO. I and UNIT NO. 2 DOCKET NO. 50-352 (Unit 1)
DOCKET NO. 50-353 (Unit 2)'
1
-SEMI-ANNUAL' EFFLUENT RELEASE REPORT NO. 11
. JULY 1, 1989 THROUGH DECEMBER 31, 1989 r
Submitted to The. United States Nuclear Regulatory Commission Pursuant.to Facility Operating Licenses NPF-39 (Unit 1) and NPF-85 (Unit 2)
, , Preparation Directed by:
G. .M. Leitch, Vice President Limerick Generating Station
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M. J. WCormick , Jr.
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Pl~ ant Manager
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L, 9: TABLE OP CONTENTS I
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l - I .t - Introduction .
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!II. Tables A. Summary of' Radioactive Gaseous. Effluents B.: Summary of Radioactive Liquid Effluents l- C. Solid-Waste Disposition Report D. Offsite' Radiation Dose Assessment E. Radiation Doses to Memberslof the Public due to their Activities Inside Site' Boundary i
1
!III. Attachments L
A. Supplemental Information - Assumptions Used in Report
' Generation.
B.- -Residual: Heat Removal (RHR) Service Water Radiation Monitor-and Service Water Radiation Monitor Removal' -t
'from/ Restoration to Service C '. - Process-Control Program,. Revision 8 (Submitted Under SeparateiCover)
D. -Change in Environmental Monitoring-Locations-i e
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ns I .. INTRODUCTION-This submittal complies with the format d'escribed in Regulatory Guide 1.21', " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants", Revision 1, June, 1974.
The following information is included as Tables to'this report:
A summary of the gaseous and liquid effluent releases for the report period. Where "0.00E+00" is used, it denotes the less than' detectable level for the given isotope.
Composite particulate air samples counted for beta emitters (eg. Sr-89, Sr-90) are submitted to an offsite vendor laboratory for analysis. Since data for the t fourth quarter particulate air samples had not yet become available at the time this report was prepared, it will.be necessary to submit an addendum in the future if fourth quarter particulate air samples-results are reported >LLD.
Since Limerick Technical Specification limits for liquid and gaseous effluent releases are prescribed in terms of quarterly and annual offsite doses, " percent technical specification limit" is entered as 0.00E+00 below effluent release rates and quantity totals.
A summary of solid waste dispositioned during the report period, to include: total activity shipped by waste type and an estimate of the error in the reported totals; the estimated composition of each type.of waste by isotope,_the number of shipments, mode of transportation, destination, type of container, total container volume, and solidification agent.
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I;( INTRODUCTION (continued) l The following-information is included as Attachments to this report: I An explanation concerning Residual Heat Removal Service Water Radiation Monitors removal from/ return to service pursuant to Technical-Specification 3.3.7.11, and Service Water Radiation Monitor removal from/ return to service during the period.
A copy of documentation describing the relocation of a site environmental TLD station. Station 36S1 was moved '
to a nearby location within the same sector to accommodate a construction contingency, late in 1989. '
The ODCM had-not been revised to reflect this relocation prior to the end of 1989, but the change .
will be reflected-in. Revision 8 of the ODCM, to be submitted with subsequent SAERR no. 12 for January 1 -
June 30, 1990. The incorporation of Radiological Effluent' Technical Specification (RETS) into the ODCM NRC generic letter 89-01, will also be effected in '
Revision 8. ,
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- II.- TABLES'. -
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SUMMARY
OF RADIOACTIVE GASEOUS EFFLUENTS'
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July 1, 1989 to December 31, 1989 !
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-SITE: LIMERICK - 1 UNIT:-U1 l USER: CONB * '
1 DATE: #02/22/90 08:39 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS:--' SUMMATION OF ALL RELIASES. 1
- UNITS : QUARTER : QUARTER :EST. TOTAL: )
? : : 3 .: 4 : ERROR,- % :- '
A.s FISSION-AND ACTIVATION-GASES
- 1. - TOTAL RELEASE . -CI : 0.721E+01 : 0.151E+02 : 0.453E+02 : }
I'.2. AVERAGE RELEASE UCI/SEC: 0.907E+00 : 0.190E+01 :
3 RATE FOR PERIOD : : : :
i: 8. 3. PERCENT OF TECHNICAL: 4 : 0.000E+00 : 0.000E+00 :
SPECIFICATION LIMIT : : : :
B. IODINES
~ 1.^ TOTAL IODINE-131 : CI : 0.000E+00 : 0.000E+00 : '0.453E+02 : >
's 2.. AVERAGE. RELEASE :UCI/SEC: O.000E+00 : O.000E+00 : 1
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RATE FOR PERIOD : : : : [
3 3. PERCENT OF. TECHNICAL: %- : 0.000E+00 : 0.000E+00 :
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SPECIFICATION LIMIT : : : :
C.: PARTICULATES
- 3 1. PARTICULATES WITH : CI : 0.581E-04 : 0.189E-03 : 0.453E+02.:
HALF-LIVES >8 DAYS : : : :. :
3 : 2. AVERAGE RELEASE :UCI/SEC: 0.730E-05 : 0.283E-04 :
3 RATE FOR PERIOD. : : : : .
t 3.LPERCENT OF TECHNICAL: 4 : 0.000E+00 : 0.000E+00 :
3 ' SPECIFICATION LIMIT : : : :
t 4. GROSS ALPHA : CI : 0.000E+00 : 0.000E+00 : ,
a RADIOACTIVITY : : : :
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.D. TRITIUM........_____'___._
8}1. TOTAL RELEASE
- CI :J0.000E+00 : O.000E+00 : .O.453E+02 :
it-2.-AVERAGE RELEASE :UCI/SEC::0.000E+00 : 0.000E+00 : , ,
8 RATE FOR-PERIOD. :. :, :. : t. ;
8 - 3. PERCENT OF. TECHNICAL: % -- : 0.000E+00 : 10.000E+00 :
. $- SPECIFICATION LIMIT : : : :
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s 1 PAGE 1 OF 12 l SITE: LIMERICK l
~ UNIT: U1- '
l USER: CONB DATE: 02/22/90 08:39 EFFLUENT AND WASTE DISPOSAL REPORT 1
GASEOUS EFFLUENTS FOR RELEASE POINT: 1 North Stack '
l i
CONTINUOUS MODE BATCH MODE I NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
3 3E12ASED : : 3 : 4 : 3- : 4 :
- 1.: FISSION GASES
-t AR41 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : .
t KR83M : CI : 0.000E+00 : 'O.000E+00 : 0.000E+00 : 0.000E+00 :
3- KR85M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
-t KR85 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+0'0 :
t- KR87 : HCI - .: 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t- KR88 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
g t~ KR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t KR90 : CI : 0.000E+00 : 0.000E+00 : - 0.000E+00 : 0.000E+00 :
- . XE131M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t XE133M : CI : 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
L 8- XE133 : CI- : 0.000E+00 : 0.000E+00 : :-0.000E+00 :
( ............___..._________.__..________._______0.000E+00 ______________...______
3 : CI : : 0.000E+00 : 0.000E+00 : 0.000E+00 :
________..._________0.000E+00
___'XE135M ____-___________... _____________________...___
3 XE135 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : .i t XE137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :-0.000E+00 :
t XE138 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t- TOTAL FOR : : : : : :
. PERIOD : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
8 (ABOVE) : : : : : :
_ + -_ _ _ _ . _ - _ _ _ _
_ . _ _ _ _ _ _ _ - _ _ ._ ____.________,___.a
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, PAGE 2 OF 12 SITE: LIMERICK UNIT: U1 '
t USER: CONB . .
DATE:.02/22/90 08:39 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 1 North Stack CONTINUOUS MODE BATCH MODE 3 NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER QUARTER : .
3 RELEASED : : 3 : 4 : 3 3 4 : .i
- 2. IODINES
- I131 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : >
I133 : CI : .0.000E+00 : 0.390E-04 0.000E+00 : 0.000E+00 :
t TOTAL FOR : : : : :
PERIOD : CI : 0.000E+00 : 0.390E-04 : 0.000E+00 : 0.000E+00 :
(ABOVE) : : : : : :
- 3. PARTICULATES
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t C14 : CI. : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
3 CR51 : CI : 0.000E+00 :.0.000E+00 : 0.000E+00 : 0.000E+00 :
MN54 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :-0.000E+00 : ,
s FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
8 COS8- : :-0.000E+00 : 0.000E+00-: 0.000E+00 : 0.000E+00 :
l __________......'CI ...___.....____. ______..._________...___ ............ -
L 8 CO60 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
1 ...__...___...___.....____..........____.........__... ___ ....... ... .
& : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00':
___ZN65 3 SR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
1 _....._. ___. ..._..__......_....__.....__.............. ..... ..___._
1 s SR90 : CI : 0.180E-06 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
s ZR95 : CI : 0.000E+00 : 0.000E+00 2 0.000E+00 0.000E+00 :
L c SB124: : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : r s CS134 : CI- : 0.000E+00 : 0.000E+00 ! 0.000E+00 : 0.000E+00 :
L E CS136 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
'_s_____________________________________...____ ...... _.. __........___
CS137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
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t PAGE 3 OF 12 SITE: LIMERICK .
UNIT: ' U1
- USER:-CONB- , .
DATE: 02/22/90 08:39 '
' EFFLUENT AND WASTE DISPOSAL REPORT CASEOUS EFFLUENTS FOR RELEASE POINT: 1 North Stack CONTINUOUS MODE BATCH MODE I
- NUCLIDES : UNITS : QUARTER. : QUARTER : QUARTER : QUARTER : >
RELEASED : : 3 : 4 : 3 : 4 :
- 3. PARTICULATES (CONTD) _. ___ . __ .__ . ___.... . ... . ..______ ...
- BA140 : CI : 0.000E+00 : 0.000E+00. . . ...
- 0.000E+00 :-0.000E+00-:
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
'.:. . C E .1__4 1
- - CE144 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- t. TOTAL FOR : : : : : :
i
' PERIOD' : CI : 0.180E-06 : '0.000E+00 : O.000E+00 :_0.000E+00 :
- (ABOVE)- : : : : : :
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PAGE 4 OF 12
- SITES LIMERICK
' UNIT: U1 '
USER:~CONB '
DATE: 02/22/90 08:39 '
EFFLUENT AND WASTE DISPOSAL REPORT CASEOUS ~ EFFLUENTS FOR RELEASE POINT: 2 Unit 1 - South Stack CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER- :
3 RELEASED : : 3 : 4 : 3 : 4 :
' 1'. FISSION GASES
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : 4 MR 441 __.-----.....__-_-__.._________..____.-________--
KR83M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
I
- KR85M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :-
L * -KR85 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
[ . __.._-______...___-..__....-________...__....__.._________-______.__.
t KR87 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
l KR88 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
(
KR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
I KR90 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
. XE131M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :.0.000E+00 :
XE133M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- XE133 : CI : 0.000E+00 : 0.950E-01 : 0.000E+00 : 0.000E+00 :
i XE135M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
XE135 : CI : 0.721E+01 : 0.135E+02 : 0.000E+00 : 0.000E+00 :
- XE137' : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- . XE138 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- TOTAL FOR : : : : : :
- PERIOD : CI : 0.721E+01 : 0.135E+02 : 0.000E+00 : 0.000E+00 :
- (ABOVE) : : : : : :
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USER: CONB -
DATE: 02/22/90 08:39 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 2 Unit l'- South Stack b
CONTINUOUS MODE BATCH MODE t NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER : i t RELEASED 3 : 4 : 3 : 4 :
2.' IODINES t I131 : CI : 0.000E+06 2 0.000E+00 : 0.000E+00 : 0.000E+00 :
-t I133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t TOTAL FOR : : : : : :
l' PERIOD : CI : 0.000E+00 : 0.000E+00 0.000E+00 0.000E+00 :
1 (ABOVE) : : ? : : :
- 3. PARTICULATES
- C : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
____.14 .._____.___......___________...._____________________.___________
- CRS1 : CI : 0.000E+00 :- 0.189E-03 : 0.000E+00 : 0.000E+00 :-
- MN54 : CI : 0.393E-05 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- . FE59- : CI ::0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- - C058 : CI : : 0.000E+00 : 0.000E+00 : 0.000E+00 :
_______________________-0.000E+00 ______...___.______._______...__.____________._
- -CO60 :- CI : 0.270E-04-: 0.000E+00 : 0.000E+00 : 0.000E+00 :
- ZN65 : CI : 0.270E-04 : 0.000E+00 0.000E+00 : 0.000E+00 :
-: SR89 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- SR90 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :-0.000E+00 :
- . ZR95 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- SB124 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CS134 : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
__________.__:__CI_______. _____________ ______'_________________________
- CS136 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- . CS137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : '
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PAGE 6 OF 12
. SITE:-LINERICK UNIT: U1 ,
USER: CONB
' DATE: 02/22/90 08:39 EFFIDENT AND WASTE DISPOSAL REPORT
. GASEOUS EFFLUENTS FOR RELEASE POINT: 2 Unit 1 - South Stack-CONTINUOUS MODE BATCH MODE t- NUCLIDES- UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
RELEASED : : 3 : 4 : 3 : 4 :
- 3. PARTICUIATES (CONTD)
I BA140 :- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CE141 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CE144 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
3.-TOTAL FOR : : : : : :
- PERIOD : CI : 0.579E-04 : 0.189E-03 : 0.000E+00 : 0.000E+00 :
(ABOVE) : : : : : :
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f PAGE 7 OF 12 SITE: LIMERICK UNIT: U1' '
USER: CONB DATE: 02/22/90 08:40 i
! EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 3 Unit 2 - South Stack CONTINUOUS MODE BATCH MODE L* NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
RELEASED : : 3 : 4 : 3 : 4 :
- 1. FISSION GASES AR41 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
KR83M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00
.: : CI . : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+C0 : ?
___'KR85M 3- KR85 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : O.000E+00 :
- KR87 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t KR88 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
KR89 :. CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 t
- -KR90
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
l3- ' _t__________.. _.___.__.. .._________......_____________________... _._
L ! XE131M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t XE133M : CI
._________......_..____'0,000E+00 : : 0.000E+00 : 0.000E+00 : 0.000E+00 :
__................_______m.._..______ _.......
3 .: CI : 0.000E+00 i 0.000E+00 : 0.000E+00 : 0.000E+00 :
. _XE133 s' .XE135M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
L .XE135 : CI : 0.000E+00 : 0.154E+01 0.000E+00 : 0.000E+00 :
XE137 : 0.000E+00 : 0.000E+00 : 0.000E+00 : G.000E+00 :
________..____:_.CI __________ ____________________________________...___
XE138 : CI .: 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
l l
- TOTAL FOR : : : : : :
l- 3 PERIOD : CI . 0.000E+00 : 0.154E+01 : 0.000E+00 : 0.000E+00 :
3- (ABOVE) : : : : : :
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- SITE: ' LINERICK-
' UNIT: U1 .
P USER: CONB .
DATE: 02/22/90 08:40 EFFLUENT AND WASTE DISPOSAL REPORT
- GASEOUS EFFLUENTS FOR RELEASE POINT
- 3 Unit 2 - South Stack CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
0 .: RELEASED : : 3 : 4 : 3 : 4 :
- 2. IODINES
- I131 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : ,
- . I133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 ::
- . TOTAL,FOR : : : : : :
.: PERIOD : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00':
3- (ABOVE) : : : : : : .
3'. PARTICULATES
.: C14 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :.
- CR51 .: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- MN54 : CI' : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- :FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : :
._. .........._______...________--______.......__....._____-0.000E+00 ___________
- : CI : 0.000E4 00 : - 0.030E+00 : 0.000E+00 : 0.000E+00 :
.__C058-
- -CO60 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00-:
- ZN65 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :' O.000E+00 :
- ' SRB 9 :- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E400 :
- SR90 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- - ZR95 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- - SB124 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- :- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- .__CS134
- CS136 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CS137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
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PAGE 9 OF 12 H SITE: LIMERICK -
JVNIT:.U1 '
l DSER: CONB DATE: 02/22/90 08:40 EFFLUENT.AND WASTE DISPOSAL REPORT-GASEOUS EFFLUENTS FOR RELEASE POINT: 3 Unit 2 - South Stack CONTINUOUS MODE BATCH MODE
- - NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
8 RELEASED : : 3 : 4 : 3 : 4 : '
- 3. PARTICULATES (CONTD)
-: BA140- -: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CE141 : CI . 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CE144 : CI- : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- :' TOTAL FOR : : : : : :
- PERIOD : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- (ABOVE) : : : : : :
9
- ,m - - - , , . - - - . - . - - - - . - - , , . _ - - - - - - , -
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.w J PAGE 10 OF 12
. SITE: LIMERICK
' UNIT: U1- '
USER:1CONB-DATE:'02/22/90 08:40 EFFLUENT AND WASTE DISPOSAL REPORT i
__-----------------......-__. l GASEOUS' EFFLUENTS FOR RELEASE POINT: 4 Hot Maintenance Shop j CONTINUOUS MODE BATCH MODE 8 NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER : l 3 RELEASED : : 3 : 4 : 3 : 4 :
1
- 1. FISSION GASES
. AR41 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t KR83M- : CI : 0.000E+00 : 0.000E+00 : 0.000E+00-: 0.000E+00 t'
- ' -KRB5M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
, t- KR85 -: CI : 0.000E+00 :~0.000E+00 : 0.000E+00 : 0.000E+00 :
- KR87 -: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- :KR88 : CI : 0.000E+00 : 0.000E+00 :.0.000E+00 : 0.000E+00 :
s KR89: : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00':
- ' KR90 : CI- : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
.: XE131M- .: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- . XE133M. : CI : 0.000E+00 : 0.000E+00.: 0.000E+00': 0.000E+00-':
- .XE133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- -XE135M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- XE135 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- XE137 : CI : 0.000E+00': 0.000E+00 : 0.000E+00 : 0.000E+00 :
- ~XE138- : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- -TOTAL'FOR : : : : : :
. :- PERIOD -: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- ' (ABOVE) : : : : : :
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<=
60 t ek:_
t PAGE 11 OF 12 SITE: LIMERICK
- ' UNIT: U1' USER: CONB DATE: 02/22/90'08:40
. EFFLUENT AND WASTE DISPOSAL REPORT GASDUS EFFLUENTS FOR RELEASE POINT: 4 Hot Maintenance Shop CONTINUOUS MODE BATCH MODE 3 NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
RELEASED : : 3 : 4 : 3 : 4 :
2.~ IODINES t- 1131 : CI. : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- I133 : CI : 0.000E+00 0.000E+00 : 0.000E+00 : 0.000E+00 :
- TOTAL FOR': : : : : :
- PERIOD. CI : 0.000E+00 : 0.000E+00 : O'.000E+00 : 0.000E+00':-
- (ABOVE) : : : : : :
-3. PARTICULATES
.: Cid : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CRS1 ~: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- MN54 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- FE59. ~: CI : 0.000E+00~: 0.000E+00 : 0.000E+00 : 0.000E+00 :
- C058 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : f
- CO60 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- ZN65 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 'O.000E+00 :
--_-SR89
- SR90 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- '_ZR95
- SB124 : CI : 0.000E+00 : 0.000E+00 :.0.000E+00 : 0.000E+00 :
- CS134 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- CS136 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- -CS137 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
n ., -
- AL i
PAGE'12 OF 12
.-SITE: LIMERICK UNIT: U1 ,
USER: CONB DATE:;02/22/90 05:40 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 4 Hot Maintenance Shop CONTINUOUS MODE BATCH MODE t NUCLIDES- : UNITS": QUARTER : QUARTER : QUARTER : QUARTER :
- L RELEASED : : 3 : 4 : 3 : 4 : ;
A ._____.__..__________._____ __...____ _____._______...________________
-3. PARTICULATES (CONTD) t BA140 ~: CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t CE141 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
t- CE144 : CI : 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
__...___ ____..___..._________._________________...______._____________ t 8- TOTAL FOR : : : : : :
- PERIOD : CI : 0.000E+00 : 0.000E+00' 0.000E+00 : 0.000E+00 : 6
.t ___(__..__--_____.________-_________--__________-____.-----._____----.
ABOVE)
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- I I . .-- . TABLES-
-s
- B.
SUMMARY
OF RADIOACTIVE-LIQUID EFFLUENTS ,
i July,1,'1989 to December 31, 1989
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. SITE: LLIMERICK-p : UNIT "U1' '
USER: CONB' L DATE: 02/22/90 08:40 ,
1 EFFLUENT-
.___ AND WASTE
. . . . '. DISPOSAL
. . REPORT-
- LIQUID EFFLUENTS -- SUMMATION _ . . .
OF..ALL' RELEASES . .. __
)
- UNITS : QUARTER : QUARTER :EST. TOTAL:.
l
- : 3 _: 4 : ERROR, .,% :
I
- A. FISSION AND ACTIVATION PRODUCTS I l'. TOTAL RELEASE (EXCL.: CI : 0.123E-01 : 0.400E-01 : 0.630E+01-:
. TRIT., GASES, ALPHA) : : : :
t 2. AVERAGE DILUTED. :UCI/ML : 0.583E-07 : 0.217E-06 :.
t ' CONC. DURING PERIOD : : : :
- 3 3 '. PERCENT OF : % : 0.000E+00 : 0.000E+00 :
3- APPLICABLE LIMIT : : : :
B. TRITIUM .
t 1. TOTAL RELEASE : CI : 0.557E+01 : 0.777E+01 : 0.630E+01 :
8 2. AVERAGE DILUTED :UCI/ML : 0.264E-04 : 0.422E-04 :- ;
I 1
- CONC. DURING PERIOD : : : :
l- t-3.= PERCENT OF : 4 : 0.000E+00 : 0,000E+00 :-
-t APPLICABLE LIMIT- : : : :
L . .__. .. _ ...
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE : CI : 0'116E-01
. : 0.396E-02 : 0.630E+01 :
- 2. AVERAGE DILUTED- :UCI/ML : 0.557E-07 : 0.190E-07 :-
- CONC. DURING PERIOD : :. :
- 3. PERCENT OF : % : 0.000E+00 : 0.000E+00 :
- APPLICABLE LIMIT : : : :
D.. GROSS ALPHA RADIOACTIVITY ___- __ . _ __ .
J: 1. TOTAL RELEASE : CI : 0.000E+00 : 0.000E+00 : 0.630E+01-: S
__ . u_ __ _ ._ . .. _ .. ..
E. VOLUME WASTE RELEASED : LITERS : O.675E+07 : 0.605E+07.: O.000E+00 :
1
~s (PRIOR. TO DILUTION) _ . . . . ___ . . . __. . t
~~ ~~ ~~ ~~ ~
~
EVb"Lbkk D5[bh5bh"hA55k IL5T5E5 I bI255E+b5 I bI5845+b9: I bIbb05+bb :I USED DURING PERIOD : : :
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PAGE 1 OF 5
~ SITES. LIMERICK- l
' UNIT: U1 '
USER: CONB=
DATES 02/22/90 08:40 t
' EFFLUENT AND WASTE DISPOSAL REPORT '
} LIQUID EFFLUENTS FOR RELEASE POINT: 1 Liquid Rad Waste Discharge to Sch. ,
3 River 1, CONTINUOUS MODE BATCH MODE !
- 3. NUCLIDES- : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- . RELEASED : : 3 : 4 : 3 : 4 :
L .
H3 ': CI. : 0.000E+00 ; 0.000E+00 : 0.557E+01 : 0;777E+01 : 3 s
- HH 3- C14
- CI : 20.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
1 . ...._____ --_-____.______-____.-____------..__.._...__-----...--._--- ,
3 NA24 . : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
3- P32 : CI : 0.000E+00 : 'O.000E+00 : 0.000E+00 : 0.000E+00 :.
.s s CRS1 : CI : 0.000E+00 : 0.000E+00 :'O.759E-03 : 0.805E-02 :
2 MN54 : CI : 0.000E+00 : 0.000E+00 : 0.202E-03 : 0.323E-03 :-
L 3 MN56 :' CI : 0.000E+00 :'O.000E+00 : 0.000E+00 : 0.000E+00 :
.3- FESS : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 0.205E-01 : ,
'FE59 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : .
' .s ..._____..____...__.._______..._____________ ..______.--.__....____.-
- . C058= CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.107E-04 : i CO60' .:- CI : 0.000Et00 : 0.000E+00 ::0.827E-03 : 0.131E-02 :
l I
'_s___.... ______ __ ...... ___._____...___..._______..... __...________
3 NI63 : CI : 0.000E+00 : 0.000E+C0 : 0.000E+00 : 0.000E+00 :
.NI65 : CI : 'O.000E+00 : 0.000E+00.: 0.000E+00 : 0.000E+00 :
3 CU64 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
3 .ZN65 -: CI :s 0.000E+00 : 0.000E+00 : 0.681E-02 : 0.957E-02 : ,
L ________--___________ _______.________________...____...... --_---. _.
- ZN69 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- BR : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
l _-__-.83.___---____---_ -__ --__--_....___ _------___-.-___-.____---___.
- BR84 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
L : BR85 : CI : 0.000E+00 0.000E+00 : 0.000E+00 : 0.000E+00 :
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PAGE 2 OF 5 SITE:-LINERICK LUNIT: U1. !
USER: CONB '
i DATE: 02/22/90 08:40 l EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 1 Liquid Rad Waste Discharge to Sche l
' River l v ......______.__..............._____
"c CONTINUOUS MODE BATCH MODE
- . NUCLIDES : UNITS : QUARTER- : QUARTER : QUARTER : QUARTER :
- RELEASED : : 3 : 4 : 3 : 4 :
LIQUID EFFLUENTS (CONTD) t RB86 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 1 0.000E+00 : -
y _'___.. ...._____..___.. ______....._.____...____.____.___.__.......___ r
- RB88 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- RB89_ : CI : 0.000E+00 : 0.000E+00': 0.000E+00 : 0.000E+00 : ;
- SR89 : CI :: 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
I i : SR90 : : 0.000E+00 :-0.000E+00 :,0.000E+00 : 0.000E+00 :
1
........._______'CI ...._______.........______________________..........__
- SR91 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : *
! :- SR92 :- CI : 0.000E+00-: 0.000E+00 : 0.000E+00 : 0.000E+00 : ;
j ____.....________.______...____.-______. ........._______._______.__ .
- CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
___Y90 _. __.__________..._____..____ ____...____'__..._______________..___
l
- . Y91M_ : CI : 0.000E+00 : : 0.000E+00 : 0.000E+00 :
......__.__...........______ ___.__'O.000E+00 ___......______________.__...._____
- Y91 : CI : 0.000E+00 : 0.000E+00-:-0.000E+00 : 0.000E+00 : -
k
- Y92 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- Y93 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 :-0.000E+00 :
- . ZR95 : CI :-0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00-:
, : CI : 0.000E+00 : 0.000E+00 :-0.000E+00 : 0.000E+00 :
'.:._ZR97________......__________.....___________________...__.....__________ ,
- NB95 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- .:, MO99 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
- TC99M : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : !
~; TC101 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
[.i
y __. _.__ _ _ _ _ . _ _ _ _ _ _ _ __ . _ _ _ _ _ __ _
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a PAGE 3 0F 5 SITE: LIMERICK UNIT U1 I USER: CONB '
DATEt 02/22/90 08:40 EFFLUENT AND WASTE DISPOSAL REPORT
- LIQUID ZFFLUENTS FOR RELEASE POINT: 1 Liquid Rad Waste Discharge to Sch. i River ,
I CONTINUOUS MODE BATCH MODE I NUCLIDES UNITS : QUARTER QUARTER QUARTER QUARTER : ,
t RELEASED t 3 4 3 3 4 : i LIQUID EFFLUENTS (CONTD)
- RU103 : CI : 0.000E+00 : 0.000E+00 t 0.000E+00 2 0.000E+00 l
- RU105 : CI : 0.000E+00 t 0.000E+00 0.000E+00 t 0.000E+00 : !
- RU106 : CI : 0.000E+00 t 0.000E+00 1 0.000E+00 t 0.000E+00 t V AG110M : CI : 0.000E+00 1 0.000E+00 1 0.000E+00 1 0.000E+00 : :
- TE125M : CI : 0.000E+00 3 0.000E+00 t 0.000E+00 3 0.000E+00 t TE127M : CI : 0.000E+00 0.000E+00 0.000E+00 3 0.000E+00 a a 8 TE127 : CI 0.000E+00 1 0.000E+00 1 0.000E+00 0.000E+00 t .
8 TE129M : CI : 0.000E+00 t 0.000E+00 t 0.000E+00 0.000E+00 t t
t TE129 : CI t.0.000E+00 t 0.000E+00 3 0.000E+00 1 0.000E+00 ,
- TE131M : CI t 0.000E+00 0.000E+00 t 0.000E+00 0.000E+00
- TE131 : CI : 0.000E+00 : 0.000E+00 t 0.000E+00 : 0.000E+00 :
TE132 : CI : 0.000E+00 0.000E+00 t 0.000E+00 0.000E+00 t 1130- : CI : 0.000E+00 : 0.000E+00 2 0.000E+00 0.000E+00 t
...................................................................... 4
- I131 : CI : 0.000E+00 0.000E+00 1 0.000E+00 3 0.000E+00 t 1132 : CI : 0.000E+00 : 0.000E+00 0.000E+00 3 0.000E+00 t
. 1133 : CI : 0.000E+00 : 0.000E+00 : 0.000E+00 2 0.000E+00 ,t I134 : CI : 0.000E+00 t 0.000E+00 t 0.000E+00 0.000E+00 :
I135 : CI : 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
- - + , . .--
l t )
,t.
l PAGE 4 OF 5 ;
SITE: LINERICK !
UNIT U1 )
USER: CONB ,
.DATE: 02/22/90 08:40 EFFLUENT AND WASTE DISPOSAL REPORT }
LIQUID EFFLUENTS FOR RELEASE POINT! 1 Liquid Rad Waste Discharge to Sch.
River I t
E CONTINUOUS MODF BATCH MODE i t NUCLIDES : UNITS : QUARTER : QUARTER t QUARTER QUARTER l t RELEASED t : 3 3 4 3 4 : !
.......... ........................................................... i LIQUID EFFLUENTS (CONTD)
- CS134 : CI : 0.000E+00 3 0.000E+00 t 0.148E-02 0.833E-04 :
CS136 : CI 0.000E+00 2 0.000E+00 0.000E+00 t 0.000E+00 ,
3 CS137 : CI : 0.000E+00 0.000E+00 : 0.223E-02 0.157E-03 :
CS138 : CI : 0.000E+00 2 0.000E+00 t 0.000E+00 : 0.000E+00 t l
...........................................................__......... t
- BA139 : CI : 0.000E+00 t 0.000E+00 0.000E+00 2 0.000E+00 : i l 8 BA140 : CI 0.000E+00 t 0.000E+00 0.000E+00 0.000E+00 : ,
i 2 BA141 : CI 0.000E+00 t 0.000E+00 : 0.000E+00 0.000E+00 t 3 BA142 : CI : 0.000E+00 3 0.000E+00 0.000E+00 0.000E+00 t i
........... ___..................................................._... t l
3 LA140 t CI :-0.000E+00 1 0.000E+00 0.000E+00 1 0.000E+00 :
t LA142 : CI : 0.000E+00 3 0.000E+00 0.000E+00 3 0.000E+00 CE141 : CI : 0.000E+00 1 0.000E+00 : 0.000E+00 0.000E+00 t CE143 : CI 0.000E+00 8 0.000E+00 : 0.000E+00 t 0.000E+00 : -
CE144 : CI : 0.000E+00 t 0.000E+00 : 0.000E+00 : 0.000E+00 t l
t PR143 : CI 0.000E+00 3 0.000E4 00 : 0.000E+00 0.000E+00 :
- PR144 : CI : 0.000E+00 0.000E+00 0.000E+00 2 0.000E+00
. ND147 : CI : 0.000E+00 t 0.000E+00 0.000E+00 : 0.000E+00 :
AS76 : CI : 0.000E+00 0.000E+00 0.000E+00 1 0.000E+00 t 2 W187 : CI 0.000E+00 t 0.000E+00 : 0.000E+00 1 0.000E+00 :
- - m..a_
i T
O PAGE 5 0F 5 SITEt LIMERICK' UNIT U1 USER: CONB ,
DATEt 02/22/90 08:40 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 1 Licplid Rad Waste Discharge to Sch.
River CONTINUOUS MODE BATCH MODE
- NUCLTDES UNITS : QUARTER t QUARTER QUARTER QUARTER :
- RELEASED : 3 4 3 8 4 LIQUID EFFLUENTS (CONTD) t NONE : CI : 0.000E+00 t 0.000E+00 t 0.000E+00 t 0.000E+00 t
- TOTAL FOR t t t t t t
- PERIOD CI t 0.000E+00 t 0.000E+00 t 0.558E+01 0.781E+01 :
- (ABOVE) t t t I
t XE-133 : CI : 0.000E+00 t 0.000E+00 t 0.661E-02 3 0.199E 02 XE-135 : CI : 0.000E+00 t 0.000E+00 3 0.501E-02 1 0.197E-02 3 l
l i
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-,4:
i:;~.' -'
E' ,
i-l-
II. TABLES C. SOLID WASTE DISPOSITION REPORT July 1, 1989-to December 31, 1989 l
l*
4 l
4 SOLID WASTE AND IRRADIATED FUEL GHIPMENTS PERIOD 07/01/89 TO 12/31/89 A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated Fuel)
- 1. Type of Waste Unit Period Error, %
- a. Spent resins, filter sludges, m3 2.57E+02 evaporator bottoms, etc. Ci 8.29E+02 25%
- b. Dry compressible waste, m3 6.42E+01*
contaminated equipment, etc. Ci 5.58E+00 25%
- c. Irradiated components, m3 6.37E-01 control rods, etc. Ci 3.14E+04 25%
- d. Other (describe) m3 None Ci None
- Processed by offsite vendors (Quadrex, SEG)
Activity is estimated. ,
O t -
e + m 's b v '9-**v e - = m ---ef em-em- w m- -- ew---e--g++> --ye 5: w=-
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ST-0-RRR-991-0, ROV. 1 1
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I
. ATTACHMENT A (Page 2 of 2)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS !
i B.- Irradiated Fuel Shipments (Disposition) 1 Number of Shipments Mode of Transportation Destination t !
N/A sa vw
. COMMENTS:
1 0 SUpmenic ADL mak l rom %erick f6 .
.4udra (w processing l'
3 SUpmeMSS wcro mEde $pno lJhericb fo sc6 kr proceshy GblIYllbU"' "0" flb Completed By M d.f[uAff c9 /3 / 9g Date V f Reviewed By '
0 o [d d/d/d Date 4
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- II. TABLES ,
l-D. OFFSITE RADIATION DOSE ASSESSMENT l January 1, 1989 to December 31, 1989 .
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SITE: LIMERICK UNIT: U1 USER: CONB i DATE: 02/22/90 08:43 ,
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES -
TOTAL ACCUMULATION FOR PERIODS:
LIQUID: FROM 01/01/89 0:00 TO 12/31/89 23:00 i GASEOUS: FROM 01/01/89 0:00 TO 12/31/89 23:00. ^
AIR: FROM 01/01/88 0:00 TO 12/31/88 23:00 APPLICABLE -ESTIMATED AGE IDCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MR)
(MREM) (M) (TOWARD) LIMIT LIQUID TOTAL BODY 1.01E-01 ADULT RECEPTOR 1 1.7E+00 6.0 LIQUID LIVER 1.72E-01 TEEN RECEPTOR 1 8.6E-01 20.0 R. NOBLE GAS AIR DOSE 5.70E-03 793. ENE 2.9E-02 20.0 (GAMMA-MRAD) '
l NOBLE GAS AIR DOSE 8.99E-03 1006. SSE 2.2E-02 40.0 i
i (BETA-MRAD)
NOBLE GAS T. BODY l (GAMMA) 8.94E-03 ALL 965. SW 4.5E-02 20.0 NOBLE GAS SKIN (BETA) 2.03E-02 ALL 965. SW 5.1E-02 40.0 IODINE + SKIN 7.07E-02 ADULT 965. ESE 2.4E-01 30.0 PARTICULATES l
SUMMARY
OF POPULATION DOSES I
TOTAL ACCUMULATION FOR PERIODS:
LIQUID: FROM 01/01/89 0:00 TO 12/31/89 23:00 GASEOUS: FROM 01/01/89 0:00 TO 12/31/89 23:00 l
l EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)
. LIQUID TOTAL BODY 1.8E+00 LIQUID THYROID 1.4E+00 GASEOUS TOTAL BODY. 5.4E-01 l
GASEOUS THYROID 6.0E-01 l
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II. TABLES E. RADIATION DOSES TO MEMBERS OF THE PUBLIC i l DUE TO THEIR ACTIVITIES INSIDE SITE BOUNDARY ll January 1, 1989 to' December 31, 1989 c.
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Page 1 of 2 ,
Ao RADIATIONbOSESTOMEMBERSOFTHEPUBLICDUETOTHEIRACTIVITIES INSIDE SITE BOUNDARY ,
Per Technical Specification 6.9.1.8, the Semi-Annual Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to Members of the Public due to their activities inside the Site Boundary during the report period. Technical Specifications state that Members of the Public i shall include all persons not occupationally associated with the plant. This category does not include employees of the utility its contractors, or vendors. Also excluded from this category are ,
persons who enter the site to service equipment or to make i deliveries. This category does include persons who use portions of the site for recreational, occupational educational, or other ,
purposes not associated with the plant. In previous Semi-Annual Effluent Release Reports, radiation doses to Members of the Public ,
for one location within the Site Boundary were included. This location was the railroad tracks which run along the east shore of the Schuylkill River within the Site Boundary. Based on discussion with the Commission, this report now includes radiation doses for two ,
additional locations: the Limerick Information Center on Longview '
Road near the rear exit of the plant, and Frick's Lock Environmental Laboratory on the west shore of the river. The radiation doses to Members of the Public have been estimated using methodology stated in the ODCM, including determination of annual X/Q, depleted X/Q and deposition X/Q for these locations. The maximum gaseous dose to Members of the Public at these locations is based on the following assumptions:
- 1. Real time meteorology and acutal effluent releases.
- 2. Beta air dose attributed to noble gas releases.
- 3. Highest exposed sector.of the railroad tracks (W), and the sectors enclosing Prick's Lock and the Information Center -
available for occupancy.
- 4. The maximum expected occupancy factor is a working year (or 25%)
in any of the locations.
- 5. Distance to the railroad tracks, which pass through the Site '
-Boundary in the W sector, is approximately 225 meters.
- 6. Distance to the Limerick Information Center is approximately 884
-meters in the ESE sector.
- 7. Distance to Frick's Lock Environmental Laboratory is approximately 450 meters in the WSW sector.
A summary of gaseous radiation doses to Members of the Public at these locations is included in this Attachment.
- 4. ,
q, s - .n TABLE II. C Page 2 of 2-RADIATION DOSE TO MEMBERS OF PUBLIC WITHIN LIMERICK GENERATING STATION SITE BOUNDARY FOR AFFECTED SECTORS AND DISTANCES ,
APPROXIMATE GAMMA AIR BETA AIR IODINE / PARTICULATE H-3/ BETA-EMITTER
- LOCATION SECTOR DISTANCE DOSE, MRAD DOSE, MRAD ORGAN DOSE, MREM INGESTION DOSE, (METERS) MREM FRICK'S LOCK WSW 450 1.80E-8 3.27E-8 3.5IE-2 I.72E-3 INFO. CENTER ESE 884 5.36E-8 9.46E-8 I.20E-I 4.86E-3 R.R TRACKS W 225 8.20E-8 1.41E-7 1.15E-1 7.28E-3 m
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, i III. ATTACRMENTS !
A. SUPPLEMENTAL INFORMATION l Facility: Limerick Generating Station - Unit 1 and Unit 2 !
Licenses NPF-39 (Unit 1) and NPT-85 (Unit 2)
- 1. Regulatory Limits (Technical Specification Limits) [
A. Noble Gases 1 5 500 mRems/Yr - total body " instantaneous" limits per i 5 3000 mRems/yr - skin Tech Spec 3.11.2.1 #
- 2. $ 10 mRads - air gamma - quarterly air dose limits p '
5 20 mRads - air beta Tech Spec. 3.11.2.2 3 5 20 mRads - air gamma - yearly air dose limits per 5 40 mRads - air beta Tech Spec. 3.11.2.2 B. Iodines, tritium, particulates with half life > 8 days: l
- 1. $ 1500 mRems/yr - any organ " instantaneous" limits per (inhalation path) Tech Spec. 3.11.2.1
^
2 5 15 mRems - any organ - quarterly dose limits per Tech. Spec. 3.11.2.3 3 5 30 mRems - any organ - yearly dose limits per ;
Tech. Spec. 3.11.2.3 :
C. Liquid Effluents:
- 1. Concentration < 10CFR20 " instantaneous" limits per ;
Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.11.1.1 ,
2 5 3 mRems - total body - quarterly dose limits per
$ 10 mRems - any organ Tech. Spec. 3.11.1.2 3 5 6 mRems - total body - yearly dose limits per ,
5 20 mRems - any organ Tech. Spec. 3.11.1.2
- 2. Maximum Permissible Concentrations Per LGS Technical Specification 3.11.1.1, MPCs are not used to ,
calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10CFR20, Appendix B, Table II, Column 2 for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases.
S
- 3. Average Energy Based on gaseous effluent releases for the report period, average beta energy is 0.304 MeV and average gamma energy is 0.245 MeV.
- 4. Measurements and Approximations of Total Radioactivity l
A. Fission and Activation Gases The method used is the Canberra Series 90 Counting System; .
GS - Gas Marinelli.
B. Iodine: ,
The method used is the Canberra Series 90 Counting System; CH - Charcoal Cartridge.
C. Particulate:
The method used is the Canberra Series 90 Counting Systems PT - Air Particulate Sample, 47 mm filter. ,
D. Liquid Effluents:
The method used is the Canberra Series 90 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a 3.5 liter Marinelli.
- 5. Batch Releases i A. Liquid Q3 04
- of Batch Releases: 112 101 Total Time period for batch releases,
- 7518 6623 Maximum time period for a batch release,
- 94 99 ;
Average time period for batch release,
- 67 66 Minimum time period for a batch release,
- 45 45 l
[ Average stream flow (Schuylkill River) i during periods of release of effluents 7.66E5 7.89E5 l into a flowing stream, gpm
- = Minutes
B. Gaseous 03 04 4 of Batch Releases: 2 0 Total Time period for batch releases,
- 120 0 Maximum time period for a batch release,
- 60 0 Average time period for batch release,
- 60 0 Minimum time period for a batch release,
- 60 0
- = Minutes
- 6. Abnormal Releases A. Liquid None B. Gaseous None
- 7. Description of LGS _ Effluent Release Points Release Point 1 = North Stack, Common Release Point 2 = South Stack, Unit 1 Release Point 3 = South Stack, Unit 2 Release Point 4 = Hot Maintenance Shop -
Liquid Release Point = LGS Liquid Radwaste Discharge B. Description of LGS Liquid Dose Receptors Receptor 1 = LGS Liquid Radwaste Discharge Point Receptor 2 = Citizens Home Water Company Receptor 3 = Phoenixville Water Company Receptor 4 = Philadelphia Suburban Water Company Receptor 5 = City of Philadelphia Crew Course
I III.. ATTACHMENTS i B. RADIATION MONITOR OUT-OP-SERVICE CONDITIONS
- 1. The Unit I Residual Heat Removal (RHR)' Service L. Water Radiation Monitors were reported in SAERR #10 as being out-of-service due to flow problems.
These problems have been corrected and the monitors were operable for the duration of SAERR #11 reporting period. However the Unit II "D" RHR i
Service Water Radiation Monitor was inoperable for greater than thirty days due to circuitry problems within the detector itself. No sampling was required due to redundant monitors and the monitor was returned to service upon completion of detector trouble.
- 2. Service Water Radiation Monitor During the second quarter of 1989 the Service Water Radiation Monitor was removed from service for corrective maintenance and pipe replacement due to poor monitor design. Per technical Specification 3.3.7.11, Action 6101 was observed for the duration of the monitors inoperability. In November of 1989, the moniter was returned to service upon completion of maintenance and has been running without interruption for the duration of SAERR #11 reporting period.
5
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- l III. ATTACHMENTS .
C. PROCESS CONTROL PROGRAM (PCP), REVISION 8 >
No changes to the PCP were made during this period. No major i changes to Radioactive Treatn.ent Systems were effected during this period, as documented in the copy of the Surveillance Test !
(ST-0-RRR-990-0) included under separate cover. ,
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III. ATTACRMENTS D. O.D.C.M. Revision 7 No revisions were made to the O.D C.M. during this period.
A copy of documentation describing the relocation of a site environmental TLD station (36S1) is included under a separate cover. This relocation will be included in Revision 8 of the
! O.D.CM. , which wi'21 also incorporate Radiological Ef fluent Techr.ical Specification (RETS).
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PROCESS CONTROL PROGRAM (PCP), REVISIONS 8
- No changes to the PCP were made during this period. No major changes to Radioactive Treatment Systems were effected during this period, as documented in the copy of the Surveillance Test (ST-0-RRR-990-0) included within.
6
ST-0-RRR-990-0, ROV. O i
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2
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- PCg'> 1 of 5
'ws I/0t o PHILADELPHIA ELECTRIC COMPANY WFM/CBA/ds1 ;
W 1/65 @
- LIMERICK GENERATING STATION .
SURVEILLANCE TEST ,
M l ST-0-RRR-990-0: DETERMINATION OF MAJOR CHANGES TO' RADIOACTIVE WASTE TREATMENT SYSTEMS.
.,"~
t Tost Specification: 6.15 -OR- Initiating Event: 1. Reason i' TGst Frequency: 6 Months 2. MRP No.
Test Results:
Section A. All Steps Completed SATISFACTORILY Performed By (Sign - Time /Date) bm '8N 1030!s-9-9 0 Reviewed By: (Sign - Time /Date) h #f 3 5 / !/f/?p r Section B. One or More Steps / Test Results UNSATISFACTORY Performed By:(Sign /Date/ Time)
Reviewed By:(Sign /Date)
- NOTIFICATION:
Person Notified (Supervision)
Notified By (Sign Date)
Time Notified:
ADDITIONAL ACTION / TEST COMMENTS:
If any entry is made in Additional Action / Test Comments L Section, person making initial entry sign here.
(sign - Time /Date) om8 986fi[r' /ded// -a-90 p >mi- . .. . . . . . . _ .
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ST-0-RRR-990-0, R;v. 0
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WFM/CBA/ds1 1.0 PURPO$E To determine what constitutes a Major Change to -
Radioactive Waste Treatment Systems as required in plant )
Technical Specifications, Section 6.15. -
AND in Surveillance Test ST-0-107-992-0, Semi-Annual Radioactive Effluent Release Report. i
2.0 REFERENCES
2.1 Limerick Technical Specifications, Section 6.15, Major Changes to Radioactive Waste Treatment Systems.
2.2 Peach Bottom Technical Specification, Section 6.18, Major Changes to Radioactive Waste Treatment Systems.
2.3 Surveillance Test ST-0-107-992-0, Semi-Annual Radioactive Effluent Release Report.
3.0 TEST EQUIPMENT ,
i None >
~ 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The respo'nsible system engineer (s) for systems 61, 62, 63, 64, 66, 67, 69, and 70 need to be involved in the implementation of this procedure.
5.0 PREREQUISITES None 6.0 PROCEDURE -
IT IS THE RESPONSIBILITY OF THE PERSON OR PERSONS PERFORMING THIS TEST TO ENSURE ALL BLANKS AND DATA SHEETS ARE CORkECTLY AND COMPLETELY FILLED IN.
.. , 4 - ... . . . ,
ST-0-RRR-990-0, R;v. 0
,- P g3 3 cf 5 l WPM /CBA/ds1 6.1 Review all modifications implemented during the period ;
described in ST-0-107-992-0 to determine if any major changes to radioactive waste treatment systems have been made which need to be reported in the Semi-Annual !
Radioactive Effluent Release Report. Major changes shall include the following: ,,,, ,
i 6.1.1 Changes in process equipment, components, ,
structures and effluent monitoring instrumentation ,
i from those described in the Final Safety Analysis Report (FSAR) and evaluated in the NRC Staff's i Safety Evaluation Report (SER). -
- 6.1.2 Changes in the design of radwaste treatment systems that significantly alter the i characteristics and/or quantities of effluents ;
released from those previously considered in the FSAR and SER. _
- 6.1. 3 Changes in system design which invalidate the !
accident analysis as described in the SER.
6.1.4 Changes in system design that result in a ,
significant increase in occupational exposure of ;
operating personnel.
4 6.1.5 Changes in system design which require a change to the PCP (Process Control Program).
6.2 ALL modifications implemented during the period specified in ST-0-107-992-0 have been reviewed by the responsible test engineer:
TEST ENGINEER, SYSTEM 61
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i TEST ENGINEER, SYSTEM 62 & Me ( * ) _ -
TEST ENGINEER, System 63 l)Au r /+b( * ) ,
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. TEST ENGINEER, SYSTEM 64 Jhs/ /le(*)
TEST ENGINEER, SYSTEM 66 MF)f 1 0 4 * )
TEST ENGINEER, SYSTEM 67 % / + 4t$( * ) t TEST ENGINEER, SYSTEM 69 bhf I 340 (*)
TEST ENGINEER, SYSTEM 70 $Rf'l3ko(*)
6.3 IP no major changes to radioactive waste treatment systems Eave been implemented during the period specified in ST-0-107-992-0, THEN go to section 7.0 (return to normal).
e ST-0-RRR-990-0, R3v. 0 POg3 4 Cf 5 WFM/CBA/ds1 6.4 IP any major changes to radioactive waste treatment j systems have been implemented during the period specified
~
in ST-0-107-992-0, THEN prepare a discussion of the change ,
AND include this discussion in the ADDITIONAL ACTION / TEST I E6EMENTS section. This discussion shall contain the ;
following
]
6.4.1 A summary of the evaluation that led to the determination that the change could-be made in accordance with 10CFR 50.59.
6.4.2 Sufficient detailed information to totally support the reason for the change without the benefit of l additional or supplemental information.
l 6.4.3 A detailed description of the equipment, 1
, components, and processes involved and the interfaces with other plant systems.
6.4.4 An evaluation of the change which shows the predicted releases of radioactive materials.in .
liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.
6.4.5 An evaluation of the change which shows the expected maximum exposures to individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto.
6.4.6 A cotaparison of the predicted releases of !
radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual "
releases for the period prior to when the changes are to be made. ,
6.4.7 An estimate of the exposure to plant operating personnel as a result of the change. ,
6.4.8 Documentation of the fact that the change was reviewed and found acceptable by the PORC.
l ST-0-RRR-990-0, RGv. O F
Paga 5 ef 5 WFM/CBA/ds1 l
7.0 RETUR$4 TO NORMAL:
7.1 Notify responsible coordinator for Surveillance Test ST-0-107-992-0, OR Technical Support Health Physicist of the.results of t'Kis Major changes to Radioactive Waste Treatment Systems "',,,
Determination AND provide them with the description of any major changes, if applicable.
8.0 ACCEPTANCE CRITERIA ,
8.1 All steps marked with asterisk (*) completed.
8.2 Review of major modifications has been performed
- AND a discussion of major changes to radioactive waste treatments systems is attached (where applicable).
, 8.3 Coordinator for ST-0-107-992-0 O,R_ Technical Support Health Physicist has been notified of test completion.
NOTE: At test completion, ensure cover sheet is correctly and completely filled in.
NOTE: If any entry is made in this section, sign /datt. cover sheet under Additional Action / Test Comments.
ADDITIONAL ACTION / TEST COMMENTS: M o nl. h'e A+,'on Ges4 and :
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c,ha np s 4 wa mea + L c. ew.'+e,r l a of 3 m n3 n,-
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l O.D.C.M., Revision 7 No revisions were made to the O.D.C.M. during this period. ,
A copy of documentation describing the relocation of a site j environmental TLD station (36S1) late in 1989 is included within. l 4
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