ML20235V221
| ML20235V221 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/31/1988 |
| From: | Burly W, Leitch G, Mcfadden J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903100090 | |
| Download: ML20235V221 (77) | |
Text
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LIMERICK GENERATING STATION C 9 03 l 0 0(~) ?('l) 88j.Jgi PDR ADOCL.' OS.O( > o ;
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I PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-352 I
SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 9 JULY 1, 1988 THROUGH DECEMBER 31, 1988 Submitted to The United States Nuclear Regulatory Commission I
Pursuant to Facility Operating License NPF-39 I
Prepared by:
R.
K. Barclay, Health Physicist - Effluent Surveillance I
L. A. Wells, Radwaste Supervisor Services Engineer Preparation Directed By:
I M. J. McCormick, Jr., Plant Manager Limerick Generating Station Technical Concurrences:
(For Accuracy of information)
',. b' /?ib'*
N5e >
3.Dt/ <9 f
/ e Dir 6 - Radiation Protection Date
- k iff h) !
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'Dir. - Radw5ste
// '
'Date
TABLE OF CONTENTS I.
Introduction II.
Tables A.
Summary of Radioactive Liquid and Gaseous Effluents B.
Solid Waste Disposition Report C.
Meteorological Measurements - Joint Frequency Tables D.
Offsite Radiation Dose Assessment III.
Attachments A.
Radiation Doses to Member of the Public Due to their Activities Inside Site Boundary B.
Supplemental Information - Assumptions Used in Dose
[
Assessments C.
Residual Heat Removal (RHR) Service Water R&diation l
Monitor Failure D.
Offsite Dose Calculation Manual, Revision 6 1
I.
INTRODUCTION This submittal complies with the format described 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 effluent releases for the report period.
(There were NO liquid releases to the Schuylkill River during the report period.)
Where "0.00E+00" is used, it denotes the less than detectable level for the given isotope.
This summary does not include the results of the quarterly particulate sample for gross alpha, Sr-89 and Sr-90.
A supplement report will be submitted if isotopes are identified.
A summary of solid waste dispositioned during the report period.
A summary of the meteorological measurements taken during che report period is submitted as joint frequency distributions of wind direction and wind speed by atmospheric stability class.
An assessment of the annual radiation doses due to f
radioactive gaseous effluents released from the Station, for the period January 1, 1988 through December 31, 1988.
This assessment does not include the results of the quarterly particulate sample for gross alpha, Sr-89 and Sr-90.
Doses will be recalculated and submitted as a supplement if isotopes I
are identified.
l The following information is included as Attachments to this report:
The status of inoperable Residual Heat Reaoval Service Water Radiation Monitors discussed in Semi-Annual Effluent Release Report No. 8.
Supplemental information, consistent with the format of Regulatory Guide 1.21, Appendix B.
i Page changes for Offsite Dose Calculation Manual revision 6 and an explanation of each change implemented during the report period.
i
/
1 II.
TABLES A.
SUMMARY
OF RADIOACi'IVE GASEOUS EFFLUENTS July 1, 1988 to December 31, 1988 l
I l
S
(
SITE: LIMERICN UNIT: U1 USER:-MGR DATE: 02/21/89 08:46 EFFLUENT AND UASTE DISPOSAL REPORT GASEQUS EFFLUENTS -- SUMMATION OF ALL RELEASES UNITS :
QUARTER QUARTER
!EST.
TOTAL:
3 4
- ERROR, A.
FISSION AND ACTIVATION GASES
_---------------------------------------0E+C2 1
- 1. TOTAL RELEASE CI
- 0.214E+01 : 0.599E+02 0 45 2.
AVERAGE RELEASE UCI/SEC: 0.270E+00 : 0.754E+01 :
RATE FOR PERIOD
- 3. PERCENT OF TECHNICAL:
- 0.000E+00 0.000E+00 :
SPECIFICATION LIMIT B.
10 DINES 1
- 1. TOTAL 10 DINE-131 CI 0.110E-02 : 0.322E-02 0.450E+02 :
2.
AVERAGE RELEASE
- UCI/SEC: 0 138E-03 : 0.405E-03 :*
I RATE FOR PERIOD l
3.
PERCENT OF TECHNICAL:
0 000E+00 : 0.000E+00 :
1 SPECIFICATION LIMIT :
1 C. PARTICULATE 1.
PARTICULATE UITH CI
- 0.000E+00 : 0.000Ef00 0.450Ef02 :
H ALF-LIVES > B D AYS
- 2. AVERAGE RELEASE
- UCI/SEC: 0 000E+00 0.000E+00 :
RATE FOR PERIOD 3.
PERCENT OF TECHNICAL:
- 0.000E+00 : 0.000E+00 :
SPECIFICATION LIMIT :
4.
GROSS ALPHA CI
- 0.000E+00 0.000E+00 :
RADI0 ACTIVITY D.
E+02
- 1. TOTAL RELEASE CI
- 0.000Et00 : 0.640E+02 : 0.450 2.
AVERAGE RELEASE
- UCI/SEC: 0.000E+00 : 0.805E+01 :*
I RATE FOR PERIOD l
3.
PERCENT OF TECHNICAL:
- 0.000E+00 0.000E+00 :
SPECIFICATION LIMIT :
-^--~
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__f_
{
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e
PAGE 1 0F 9
l SITE: LIHERICK UNIT: U2 USER: HGR DATE: 02/21/89 08:47 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT:
1 NORTH STACK CONTINUOUS MODE BATCH NODE NUCLIDES
- UNITS :
QUARTER QUARTER QUARTER GUARTER RELEASED 3
4 3
4 1.
FISSIGN GASES AR41 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 0 000E+00 :
KR83M CI
- 0.000E400 : 0.000E+00 : 0.000E+00 : 0.000E400 :
KR05M CI
- 0.000E400 : 0.000E+00 : 0.000Ef00 : 0.000E+00 :
KR05 CI
- 0.000Ef00 : 0.000E400 : 0.000E+00 1 0.000E+00 :
1 KR87 CI
- 0.000E400 0.000E+00 : 0.000E100 0.000E400 KR88 CI
- 0.000Ef00 : 0.000Ef00 : 0.000Ef00 : 0.000Et00 :
KR89 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
1 I
KR90 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 i
XE131M CI
- 0.000E+00 : 0.000Ef00 : 0.000E+00 1 0.000E+00
[
XE133M CI
- 0.000E400 : 0.000E+00 2 0.000E+00 0.000E+00 :
XE133 CI
- 0.000E+00 : 0.208E+01 : 0.000E+00 : 0 000Ef00 :
XE135M CI
- 0.000E+00 : 0.180E400 : 0.000E+00 0.000Ef00 ;
l XE135 CI
- 0.000E+00 : 0.115E+02 : 0.000Ef00 : 0.984E+00 1
XE137 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0 000Ef00 :
l 1
l XE138 CI
- 0.000E+00 : 0.000E+00 : 0.000Ef00 ; 0.000E+00 UNIDENT.
CI
- 0.000Ef00 : 0.000E+00 0.000E+00 : 0.000E+00 :
TOTAL FOR :
PERIOD CI
- 0.000E+00 : 0.138E+02 : 0.000E+00 : 0.984E+00 :
(ADOVE) l
.---._..m____..__%__.
PAGE 2 0F 9
SITE: LIMERICK UNIT: U1 USER: MGR DATE 02/21/89 08: 47 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT:
1 NORTH STACK CONTINUOUS MODE BATCH MODE
_---_-------_--_--------------__------____--------_-----ER NUCLIDES
- UNITS :
GUARTER GUARTER GUARTER QUART RELEASED 3
4 3
4 2.
10 DINES
--_---------_---_----------------------------------------_00E+00 I131 CI
- 0.951E-03 0.292E-02
- 0.000E+00 t 0.0
000E+00 I133 CI
- 0.177E-03 : 0.297E-02
- 0.000E+00 : 0
--- ----------------------------------------------------~~-----------:
TOTAL FOR :
PERIOD CI
- 0.113E-02 0.588E-02 1 0.000E+00 1 0.000E+00 (ABOVE)
~
l I
3.
PARTICULATE
00E+00 C14 CI
- 0 000E+00 : 0.000E+00 : 0.000Ef00 0.0
------------- +00 CR51 CI
- 0 000E+00 : 0.000E+00 1 0 000E 1 0.000Ef00 1
- --------------------- 0.000E+00 MN54 CI
- 0 000E+00 : 0.000E+00 : 0.000E+00 :
-------------------------------------------- 0.000E+00 FE59 CI
- 0 000E+00 1 0.000E+00 0.000E+00 :
l
-------------------- ----------------------- 0.000Ef00 C058 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 :
1
----------------------------------------------- 0.000Ef00 I
C060 CI
- 0 000E+00 0.000E+00 1 0.000E+00 :
ZN65 CI
- 0.000E+00 : 0.000E+00 0 000E+00 : 0.000E+00 :
0 SR89 CI
- 0.000E+00 0.000E+00 ; 0.000E+0
- 0.000E+00 :
------------------------- - ----------------------0.000E+00 SE90 CI
- 0.000E+00 : 0.000E+00 : 0 000E+00 1 1
-------------------- ----------------------- 0.000Ef00 ZR95 CI
- 0.000E+00 0.000Ef00 : 0 000E+00 :
0.000E+00 SB124 CI
- 0.000Ef00 0.000Ef00 1 0.000E+00 ;
_----_------------------_--------_-------_-_------_000E+00 CS134 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 :
0.
CS136 CI 0.000Ef00 : 0.000E+00 0.000E+00 : 0.000E+00 :
-- -------------- --- --000Ef00 CS137 CI
- 0.000E+00 1 0.000E+00 : 0.000E+00 :
0.
ENTER E C 3 TO ERASE SCREEN AND CONTINUE :
C
PAGE 3 0F 9
SITE: LIMERICK UNIT: U1 USER: MGR DATE: 02/21/89 08:48 EFFLUENT AND WASTE DISP 0in! REPORT GASEOUS EFFLUENTS FOR RELEASE POINT:
1 NORTH STACK CONTINUOUS MODE BATCH MODE NUCLIDES
- UNITS :
QUARTER QUARTER QUARTER QUARTER RELEASED 3
4 3
4
- 3. PARTICULATE (CONTD)
BA140 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 1 CE141 CI
- 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 CE144 CI
- 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0<000Ef00 l
UNIDENT.
CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 1
TOTAL FOR :
PERIOD CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
(ABOVE)
ENTER EC ] TO ERASE SCREEN AND CONTINUE :
C 1
l^
1
PAGE 4 ' 0F 9
SITE: LIMERICK U1 l UNIT:
USER: MGR I DATE: 02/21/89 08: 42
) EFFLUENT ANC WASTE DISPOSAL REPORT l ____--_-___________________ --_-__
i GASEQUS EFFLUENTS FOR RELEASE POINT:
2 UNIT 1 - SOUTH STACK CONTINUOUS MODE BATCH MODE l
i NUCLIDES
- UNITS :
QUARTER QUARTER GUARTER 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 :
l
!.KR85M CI
- 0 000E+00 : 0.000E+00 : 0.000E+00 : 0.000Ef00 :
i KR85 CI
- 0.000E+00 0.000E+00 : 0.126 E - 03 : 0.000E+00 :
-__-_________________-______-___--_-____-_-____-__-_________0.000E+00 KRB7 CI
- 0.000E+00 : 0.000E+00 0.000E+00
-__--____________--_--_______-__---_--_--_-__-__-___-_________0E+00 I
KR88 CI
- 0 000E+00 1 0.000E+00 0.000E+00 0 00 k
l
____--_-______--_--___-_-___-_-_____---_-____---_________------E+00 1
KR89 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000
_--____----------___-___-_________--______-_________-____-___0 l
KR90 CI
- 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+0 XE131M CI
- 0.000E+00 : 0.000E+00 : 0.000Ef00 ! 0.000E+00 :
1 ip XE133M CI
- 0.000E+00 : 0.000E+00 0.000E+00 : 0.000E+00 :
l XE133 CI
- 0.368E-01 : 0.537E+01 : 0.000E+00 : 0.000E+00 :
\\
XE135M CI
- 0.912E+00 0.192E+02 : 0.000E+00 0.000Ef00
______--__----____--_-___--__-__--__--_---_-_--_0 0.000E+00 XE135 CI
- 0.119E+01 : 0.206E+02 : 0.000E+0
--______-____--__-_---____---__--_----_--_-_______--__----___000E+00 XE137 CI
- 0.000E+00 : 0.000E+00 0.000E+00 0.
XE138 CI
- 0.000E+00 0 0.000E+00 : 0.000E+00 0.000E+00 :
UNIDENT.
CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 TOTAL FOR :
l PERIOD CI
- 0.214E+01 : 0.452E+02
- 0 128E-03 : 0.000E+00 :
r (ABOVE)
ENTER C C ] TO ERASE SCREEN AND CONTINUE :
C 1
PAGE 5 0F 9
SITE: LIMERICK UNIT: U1 USER: MGR DATE: 02/21/89 08:48 EFFLUENT AND WASTE DISPOSAL REPORT l
GASEOUS EFFLUENTS FOR RELEASE POINT:
2 UNIT 1 - SOUTH STACK l
CONTINUOUS MODE BATCH MODE 1
NUCLIDES
- UNITS :
QUARTER QUARTER QUARTER QUARTER RELEASED 3
4 3
4 2.
10 DINES 1131 CI
- 0.145E-03 : 0.297E-03 : 0 000Ef00 1 0.000E+00 :
1133 CI
- 0.132E-03 : 0.354E-04 : 0.000EiOO : 0 000E+00 TOTAL FOR :
PERIOD CI
- 0.276E-03 0.332E-03 : 0.000E+00 : 0 000E+00 :
(ADGUE) 3.
PARTICULATE C14 CI
- 0.000E+00 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 CR51 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0 000E400 :
HN54 CI
- 0.000E400 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
FE59 CI
- 0.000Ef00 : 0.000E400 : 0.000E+00 : 0 000E+00 1 C058 CI
- 0.000E+00 0.000Ef00 : 0.000E400 : 0.000E+00 :
C060 CI
- 0.000EiOO : 0.000E+00 : 0.000Ef00 : 0 000E+00 :
ZN65 CI
- 0.000Ef00 : 0.000Ef00 : 0.000E+00 0 000EiOO :
SR89 CI
- 0.000E+00 0.000E+00 : 0.000Ef00 : 0 000E+00 SR90 CI
- 0.000E+00 : 0.000E+00 1 0.000E+00 0 000E+00 ZR95 CI
- 0.000E+00 : 0.000E400 0.000E+00 : 0.000E+00 SB124 CI
- 0.000E+00 : 0.000Ef00 : 0 000E400 : 0 000E+00 :
CS134 CI
- 0.000E+00 0.000E+00 : 0.000Ef00 : 0.000Ef00 :
CS136 CI
- 0.000Ef00 : 0.000E+00 : 0.000E400 : 0.000E+00 :
f CS137 CI
- 0.000E+00 : 0.000Ef00 : 0.000E400 : 0 000Ef00 :
_----------------------_------------------~~---- -- --------------
ENTER E C ] TO ERASE SCREEN AND CONTINUE :
C
PAGE 6 0F 9-SITE: LIMERICK UNIT: U1 USER: MGR DATE: 02/21/89 08:49 EFFLUENT AND WASTE-DISPOSAL REPORT L
DASEOUS EFFLUENTS FOR RELEASE: POINT:
2 UNIT 1.-
SOUTH STACK l
CONTINUOUS MODE BATCH HODE 1'
NUCLIDES
- UNITS l-GUARTER QUARTER GUARTER QUARTER
- = RELEASED 3
4 3.
4 3.
PARTICULATE.(CONTD) l BA140 CI
- 0.000E+00.: 0.000E+00 1 0.000E+00 : 0.000E+00 8
CE141.
CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
CE144 CI
- 04000E+00 1.0.000E+00 0.000E+00 0.000E+00 UNIDENT.
CI
- 0.000E+00 : 0.000E+00 0.000E+00 0.000E+00 :
l TOTAL FOR :
PERIOD CI
- 0.000E+00 0.000E+00 : 0.000Ef00 : 0.000E+001:
(ABOVE)
ENTER E CJ TO ERASE SCREEN AND CONTINUE :
C l
~
1 i
PAGE 7 0F 9
SITE: LIMERICK UNIT: U1 USER: MOR DATE: 02/21/89 08: 49 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT:
4 HOT MAINTENANCE SHOP CONTINUOUS MODE BATCH MODE NUCLIDES
- UNITS :
GUARTER GUARTER GUARTER GUARTER RELEASED 3
4 3
4
- 1. FISSION DASES AR41 CI
- 0.000E+00 : 0.000E+00 : 0.000E400 0.000Ef00 KR83M CI
- 0.000E+00 1 0.000E+00 : 0.000Ef00 0.000Ef00 :
KR05M CI
- 0.000Ef00 : 0.000Ef00 : 0.000E+00 : 0.000E+00 :
KR85 CI
- 0.000E+00 : 0.000Ef00 : 0.000Ef00 0.000Ef00 :
KR87 CI
- 0.000E+00 : 0.000Ef00 0.000Ef00 : 0.000Ef00 1 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 : 0.000Ef00 :
1 1
KR90 CI
- 0.000Ef00 : 0.000E+00 : 0.000E+00 0.000Ef00 1
XE131M CI
- 0.000Ef00 : 0.000Ef00 : 0.000E+00 1 0.000Ef00 :
XE133M CI
- 0.000E+00 1 0.000Ef00 1 0 000E+00 1 0.000Ef00 XE133 CI
- 0.000E400 : 0.000Ef00 : 0.000Ef00 : 0.000Ef00 :
XE135M CI
- 0 000E+00 : 0.000E+00 : 0.000Ef00 1 0.000E+00 :
XE135 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 1 0.000Ef00 XE137 CI
- 0.000E+00 0.000Ef00 : 0.000E+00 : 0.000Ef00 1 XE138 CI
- 0.000E+00 : 0.000E+00 : 0.000Ef00 : 0.000Ef00 :
UNIDENT.
CI
- 0.000E+00 1 0.000E+00 0.000E+00 0.000E+00 TOTAL FOR :
l PERIOD CI
- 0.000E+00 : 0.000E+00 0.000E+00 1 0.000Ef00 :
(ABOVE) i ENTER C C 3 TO ERASE SCREEN AND CONTINUE :
C
PAGE 8 0F 9
SITE: LIMERICK UN11: U1 USER: MGR DA1E: 02/21/89 08:50 EFFLUENT AND WASTE DISPOSAL REPORT DASEOUS EFFLUENTS FOR RELEASE POINT:
4 HOT MAINTENANCE SHOP CONTINUOUS MODE BATCH MODE NUCLIDES
- UNITS :
QUARTER QUARTER QUARTER QUARTER RELEASED 3
4 3
4 2.
IODINES 1131 CI
- 0.000E+00 0.000Ef00 0.000E+00 1 0.000Ef00 :
I133 CI
- 0.000Ef00 : 0.000E+00 0.000E+00 0.000E+00 :
TOTAL FOR :
PERIOD CI
- 0.000E+00 0.000Ef00 0 000E+00 : 0.000E+00 :
(ABOVE) 7
- 3. PARTICULATE C14 CI
- 0.000Ef00 1 0.000Ef00 : 0.000E+00 : 0.000E+00 CR51 CI
- 0.000E+00 0.000Ef00 0.000Ef00 0.000E400 :
MN54 CI
- 0.000Ef00 : 0.000Ef00 0.000E+00 : 0.000Ef00 FE59 CI
- 0.000Ef00 1 0.000Ef00 : 0.000E+00 0.000E+00 :
7 C058 CI
- 0.000Ef00 1 0.000Ef00 0.000E+00 : 0.000Ef00 :
(
C060 CI
- 0.000Ef00 : 0.000E+00 1 0.000E+00 1 0.000Ef00 :
l l
ZN65 CI
- 0.000E+00 0.000E+00 : 0.000Ef00 0.000E400 :
1 SR89 CI
- 0.000Ef00 0.000E+00 0.000E+00 : 0.000Ef00 :
I SR90 CI
- 0 000E+00 : 0.000Ef00 1 0.000E+00 0.000Ef00 :
l i
ZR95 CI
- 0.000Ef00 0.000E+00 : 0.000E+00 : 0.000E+00 :
SB124 CI
- 0.000E+00 0.000E+00 : 0.000Ef00 : 0 000E+00 :
CS134 CI
- 0.000E+00 0.000E+00 0.000Ef00 : 0.000Ef00 CS136 CI
- 0.000Ef00 0.000E+00 0.000E400 : 0.000E+00 :
CS137 CI
- 0.000E+00 0.000Ef00 0.000Ef00 0.000Ef00 1
ENTER E C 3 TO ERASE SCREEN AND CONT CJE :
C a
PAGE 9 0F 9
SITE: LIMERICK UNIT: U1 USER: MOR DATE: 02/21/89 08:50 EFFLUENT-AND WASTE DISPOSAL REPORT DASEOUS EFFLUENTS FOR-RELEASE POINT:
4 HOT MAINTENANCE SHOP CONTINUOUS HODE BATCH HDDE l
NUCLIDES
- UNIls :
QUARTER GUARTER QUARTER QUARTER RELEASED 3
4 3
4 3.
PARTICULATE (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 s
CE144 CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
UNIDENT.
CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 0.000Ef00 TOTAL FOR :
PERIOD CI
- 0.000E+00 : 0.000E+00 : 0.000E+00 0.000E+00 :
i (ADOVE) 1 ENTER E C] TO ERASE SCREEN AND CONTINUE :
C l
t I
f I
]
i II.
TABLES B.
SOLID WASTE DISPOSITION REPORT l
July 1, 1988 to December 31, 1988
)
l l
l 1
)
l e
S u
T F
i l
N E
d i
0 0
M e
s%
1 1
P t
t
+
+
+
+
I a
o.
E E
E E
i T r 8
4 0
0 H8 8
8 0
0 S8 d
o
/
a
.r L1 r
t r 1
4 0
0 E3 r
sE i
E U/
F2 1
t D
o Eo N
hd 22 20 00 0 0 s
Tt
(
t o e+
+ +
+ +
++
r A
ni EE EE EE EE e
or 26 62 00 00 I8 l
t D8 a
Me 37 8 3 00 0 0 e
A/
s P
00 00 m
R1 o
6 1 1 1 1 R0 p
I/
s l
1l u
7 i
D0 D
c N
t AD r
i 3i 31 3i 3i O
o n
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II.
TABLES C.
METEOROLOGICAL MEASUREMENTS - JOINT FREQUENCY TABLES July 1, 1988 to December 31, 1988 1
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)
C.
METEOROLOGICAL MEASUREMENTS - JOINT FREQUENCY TABLES The joint frequency distributions of wind direction and speed, by atmospheric stability class are attach'ed under separate cover.
The distributions include all three wind levels from Limerick Meteorological Tower No. 1.
The distributions were developed on the Radiation and Meteorological Monitoring System -
RM-21A system.
Each of these " wind roses" consists of eight pages of joint frequency distributions.
There is one l
distribution for each of the seven Pasquill-Gifford stability classes, A through G, and a combined "All Classes" page.
The Pasquill-Gifford stability classes are determined by the temperature differences measured over the 266-26 feet and the 3
171-26 feet height intervals.
All meteorological data were finalized on the RM-21A system.
NRC format meteorological data tapes covering the periods January 1988 through June 1988 and l
July 1988 through December 1988 are currently retained on site.
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II.
TABLES D.
OFFSITE RADIATION DOSE ASSESSMENT January 1, 1988 to December 31, 1988
)
f
{-
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)
4
SITE: LIMERICK UNIT:~U1 USER
- NGR DATE: 02/22/89 08:28
SUMMARY
0F MAXIMUM INDIVIDUAL DOSES' TOTAL ACCUMU~.ATION FOR PERIODS !-
GASEOUS: FROM 01/01/88 0*00 TO 12/31/88 23:00 AIR:
FROM 01/01/88 0:00 TO 12/31/88 23:00 APPLICABLE ESTIMATED AGE LOCATION
% OF' LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MR)
(MREM)
(M) (TOWARD)
LIMIT
_----_---_--________--_-----_-__--_-___-______-_-_________-______-_ 0 LIGUID TOTAL BODY 0.00E+00 ADULT RECEPTOR 1 0 0Ef00 3.
LIQUID BONE 0.00E400 ABULT RECEPTOR 1 0.0E+00 10.0 NOBLE GAS AIR DOSE 5.70E-03 793.'ENE 5.7E-02 10.0 (GAMMA-MRAD)
NOBLE GAS-AIR DOSE 8.99E-03 1006. SSE 4.5E-02 20.0 (BETA-MRAD)
NOBLE GAS T. BODY (GAMMA) 2.82E-03 ALL 965. ENE 5.6E-02 5.0 NOBLE GAS SKIN (BETA) 5.94E-03 ALL 965. ENE 4.0E-02 15.0
....+..................................................................
IDDINE+
THYROID 1.73E-01 INFANT 965. ESE 1.2E+00 15.0 PARTICULATE
SUMMARY
OF POPULATION DOSES TOTAL ACCUMULATION FOR PERIODS:
l GASEOUS: FROM 01/01/88 0:00 TO 12/31/88 23:00 i
EFFLUENT APPLICABLE ESTIMATED r
ORGAN POPULATION D0.SE (PERSON-REM)
LIQUID TOTAL BODY 0.0E+00-LIQUID THYROID 0.0E+00 GASEOUS TOTAL BODY 2.5E-01
)
GASEQUS THYROID 1.3E+00
}
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ENTER C C 3 TO ERASE SCREEN AND CONTINUE :
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III.
ATTACHMENTS A.
RADIATION DOSES TO MEMBERS'OF THE PUBLIC DUE TO'THEIR~
ACTIVITIES INSIDE SITE BOUNDARY January'1, 1988 to Decembe'r 31, 1988 1
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ATTACHMENT A Page 1 of 1 A.
RADIATION DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES 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 shall include all persons who are 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 deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
There is one location within the SITE BOUNDARY that is accessible to MEMBERS OF THE PUBLIC for activities unrelated to the operation of Limerick.
This location is the railroad tracks which run along the river within the SITE BOUNDARY.
The maximum gaseous dose to MEMBERS OF THE PUBLIC as defined above is less than 1.0E-4 mrem and is based on the following assumptions:
1.
Real time meteorology and gaseous effluent releases.
2.
Beta air dose due to noble gas releases.
3.
Highest exposed sector (W) of those sectors within site boundary available for occupancy.
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4.
The maximum expected occupancy factor is a working year (or 25%) along the railroad tracks.
5.
Distance to the railroad tracks, which pass through Site Boundary in the W sector, is approximately 225 meters, i
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ATTACHMENTS B.
SUPPLEMENTAL INFORMATION Assumptions used in Dose Assessment Calculations l.
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Attcchm:nt B P gs 1
of 3 III.
ATTACHMENTS B._
SpFPLEMENTAL INFORMATION Facility: Limerich Generating Station - Unit 1 License:
NPF-39 1.
Regulatory Limits (Technical Specification Limits)
A.
Noble Gases:
1 5 500 mRems/Yr - total body
" instantaneous" limits per 5 3000 mRems/yr - skin Tech Spec 3.11.2.1 2
5 5 mRads - air gamma
- quarterly air dose limits per 5 10 mRads - air beta Tech Spec. 3.11.2.2 3
5 10 mRads - air gamma yearly air dose limits per 5 20 mRads - air beta Tech Spec. 3.11.2.2' B.
Iodines, tritium, particulate with half life > 8 days:
1 5 1500 mRems/yr - any organ
" instantaneous" limits per (inhalation path)
Tech Spec. 3.11.2.1
- 2. 5 7.5 mRems - any organ
- quarterly dose limits per Tech. Spec. 3.11.2.3 i
- 3. $ 15 mRems - any organ
- yearly dose limits per Tech. Spec. 3.11.2.3
)
C.
Liquid Effluents:
- 1. Concentration 5 10CFR20
" instantaneous" limits per 1
f Appendix B, Table II, Col. 2 Tech. Spec. 3.11.1.1 2
5 1.5 mRems - total body
- quarterly dose limits per l
5 5 mRems - any organ Tech. Spec. 3.11.1.2 3
5 3 mRems - total body
- yearly dose limits per 5 10 mRems - any organ Tech. Spec. 3.11.1.2 2.
Maximum Permissible Concentrations MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
I 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 per LGS Technical Specification 3.11.1.1.
1
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Attachmant B I
Pcgs. 2 of 3
! 3..
Average Energy Based on gaseous effluent releases for the report period, average b ta energy is 0.114 Mev and average gamma energy 0.317 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 System; PT - Air Particulate Sample, 47 mm filter.
I D.
Liquid Effluents:
The method used is the Canberra Series 90 Counting System and the Radwaste Liquid Discharge Pre-Release Method with i
a 3.5 Marinelli.
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} 5.
Batch Releases A.
Liquids l
There were no liquid batch releases during the third and fourth quarters of 1988.
B.
Gaseous 03 Q4
- of Batch Releases:
1 0
Total Time period for batch releases,
- 60 0
60 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,
- = Minutes l
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Attachment B I
Page 3
of 3 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 8.
Description of LGS Liquid Dose Receptors Receptor 1 = LGS Liquid Radwaste Discharge Point Receptor 2 = Citizens Home Water Company l
l Receptor 3 = Phoenixville Water Company Receptor 4 = Philadelphia Suburban Water Company Receptor 5 = City of Philadelphia Crew Course i
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k III.
ATTACHMENTS C.
RESIDUAL HEAT REMOVAL (RHR) SERVICE WATER RADIATION MONITOR FAILURES l
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Attachment-C Page 1 of 1 l
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C.
RESIDUAL HEAT REMOVAL (RHR) SERVICE WATER RADIATION MONITOR FAILURES During normal operations, the "A" and "B" RHR Service Water Radiation Monitors were declared out-of-service due to indications of low sample flow.
An' investigation of the problem 1
revealed the accumulation of corrosive materials on the walls of the piping.
Several factors were attributed to.the corrosion:
a.
small diameter (l"), pipe; l
b.
short pipe lengths; c.
numerous 90 degree elbows; d.
river water, which is highly aggressive to carbon steel, is used to supply service water.
The incorporation of new pipe material (from~ carbon steel to stainless steel) and reduced bendings in the' pipe lines (to facilitate system flushing).was evaluated as the long-term solutions to redeposition of corrosive products in the RHR Service Water Radiation Monitor sample lines.
The thirty (30) day Action described in Technical Specification Table 4.3.7.ll-lb Action.101 was exceeded because the corrective maintenance of replacing sample piping could not physically.be performed in'the time specified while observing all applicable station administrative controls.
At the present time, the piping modifications are completed j
and the "A",
"B" and "D" radiation monitors are operable.
The "C"
radiation monitor remains out-of-service until replacement-parts are installed and the monitor is recalibrates.
These parts are expected to arrive during the second quarter, 1989.
The Technical Specification requirement to take grab samples every eight hours has been observed during the entire period of RHR Service Water Radiation Monitor inoperability.
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III.
ATTACHMENTS D.
OFFSITE DOSE CALCULATION MANUAL, revision 6 i
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Attachment D page 1 of 28 1
III.
ATTACHMENTS l
D.
OFFSITE DOSE CALCULATION MANUAL, revision 6 Revision 6 of the ODCM incorporates the Unit 2 South Stack particulate, iodine and noble gas effluent monitors.
This revision was necessary to support tie-in and start-up testing of Unit 2 ventilation systems.
Unit 2 South Stack radiation monitor alarm setpoints are appropriately specified.
Ground exposure, ingestion and inhalation pathway dose calculations now provide for radionuclides concentrations released from the Unit 2 South Stack.
In addition to the South Stack monitors, the Unit 2 Service Water and RHR Service Water radiation monitors are identified in the radiation alarm setpoint calculations.
The Attachments to this section include: each revised page with an approval /date box and the ODCM cover sheet documenting review and acceptance of revision 6 by the Engineer-in-charge, Nuclear and Environmental Section and the Limerick Generating Station PORC.
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1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Limerick for controlling and monitoring normal radioactive material releases in accordance with the Limerick Technical Specifications are summarized as follows:
- 1) Liquid Radwaste Systent The liquid radwaste discharge monitor (RISH63-0K6N) provides an alarm and automatic termina-tion of radioactive material releases from the liquid radwaste system as required by Technical Specification 3.3.7.11.
Addi-tional design features of the liquid radwaste system which pre-vent inadvertent releases to the environment include 1) redundant discharge valves, 2) single discharge line with loop seal and l
siphon breaker to eliminate probability of inadvertent dis-l charges, 3) Low Cooling Tower Blowdown flow interlock which iso-lates the radwaste discharge line.
- 2) Service Water System-The Service Water discharge monitor (RISH10-lK605 and RISH10-2K605) provides an alarm upon indication of l activity in the service water system as required by Technical Speci-fication 3.3.7.11.
While the service water system is not a normal release pathway, the monitor provides an indication of potential problems due to excessive leakage of the heat exchangers. In addi-Engr 44 H.P. b[t.
Date 1 37-82 Rev. L
, f
- - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ -
l l
l tion, the service water side of the fuel pool heat exchangers is kept at a higher pressure than the shell side to prevent potential radioactive contamination of the service water.
- 3) RHR Service Water Systent The RHR Service Water Radiation (RHRSW) Monitors (RISH12-0K619A, RISH12-0K619B, RISH12-JK619C, RISH12-lK619D, RISH12-2K619C, and RISH12-2K619D) provide alarm and automatic termination of radioactive material release from the RHRSW system. While the RHRSW system is not a normal release pathway, the monitors provide indication of potential problems due to excessive leakage of the heat exchangers.
1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.7.11, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of Specification 3.11.1.1 are met (i.e., the concentration of radioactive material released in lig-I uid effluents to UNRESTRICTED AREAS shall be limited to the concentra-tions specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides and 2.0E-N #Ci/ml for dissolved or entrained noble gases).
1.2.1 Radwaste Discharge Monitor and Discharge Flow Rate - RISH63-0K6N The setpoint for the liquid radwaste discharge monitor and flow rate l
l at LGS are determined by the following equations. The radwaste Engr eg_
H. P. //M-Date Q D 85 Rev.
_6___
I-
SF
= 5; margin of safety factor to assure that
~
the release does not exceed 10 CFR 20 limits Il(Ci/MPCi) = the effective MPC ratio for the mixture of radionuclides in the liquid radwaste dis-charge line (unitiess) where:
Ci
= the concentration of each identified radio-nuclide i in the liquid effluent (undiluted)
(pCi/ml)*
MPCi = the MPC value corresponding to radionuclides i from 10 CFR 20 Appendix B, Table II, Col. 2, (dissolved and entrained noble gases (MPC =
2.0x10-4pCi/ml) (pCi/ml)
' NOTE: The concentration mix must include the most recent sample data for H-3, non-gamma emitters, and dissolved and entrained noble gases.
1.2.2 Service Water Radiation Monitor - RISH10-lK605,-2K605 The Service Water Monitor high-high setpoint is determined by the M.;.
following equation. The monitor high-high alarm setpoint is calcu-lated monthly based on the background count rate during the previous month. If the calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the set-point may remain at the existing setpoint or increased to the new value.
1.2.2.1 Setpoint Determination The setpoint for the Service Water Monitor is determined by l
l the following equation:
(I-3)
Engr 4 H.P. 5 Date 2 T'M Rev.
_6___ - ------
.m
where:
CPM w = Calculated Service Water Radiation Monitor s
(RISH10-lK605,-2K605) count rate, CPM l
Z,
= 3, multiplier to establish monitor setpoint 3
count rate above background count rate (unitiess)
CRB w = Service water monitor (RISH10-lK605,-2K605) l 3
count rate attributable to background radiation; CPM.
1.2.3 RHR Service Water Monitor - RISH12-OK619A,-OK619B,-lK619C,-lK619D,
-2K619C,-2K619D The RHR Service Water Monitor high-high setpoint is determined by the following equation. The monitor high-high alarm / isolation setpoint is calculated monthly based on the background count rate during the previous month. If the calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the existing setpoint or in-l creased to the new value.
1.2. 3.1 Setpoint Determination The setpoint for the RHR Service Water monitor is determined by the following equation:
CPM nnsw 5 htasw(CRBgggsw)
(1-4) a where:
CPMannsw - Calculated RHR Service Water Radia-tion Monitor (RISH12-0K619A,-0K619B,
-lK619C,-lK619D,-2K619C,-2K619D) count l
rate, CPM Z
= 3, multiplier to establish monitor RHRSW setpoint count rate above the background count rate (unitiess)
Engr &
H.P. h h l
Date _ :O22O3 f
Rev. L --
~
CRBRHasw = RHR Service Water Radiation Monitor
( RI SH 12-0K619 A,-0K619B,- 1 K619C,- l K619D,
-2K619C,-2K619D) count rate attributable to background radiation, CPM 1.3 Liquid Effluent Dose Calculation - 10 CFR 50 1.3.1 Members of the Public Dose Technical Specification 3.11.1.2 limits the dose or dose commitment -
to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Limerick Generating Station to:
- during any calendar quarter:
51.5 mrem to total body 55.0 mrem to any organ
- during any calendar year:
$3.0 mrem to total body 510.0 mrem to total organ 4
Per Surveillance Requirement 4.11.1.2 the cumulative dose contribu-tion from liquid effluents for the current calendar quarter and calendar year shall be determined at least once per 31 days in ac-cordance with the following calculational methods. These equations are for the three aquatic environment exposure pathways (potable 1
water, fish, shoreline exposure) in the Limerick aquatic environ-ment. Only real pathways are addressed for each receptor. The receptors and associated pathways are listed below. Doses from each real pathway are summed to give dose at the receptor. The monthly l
results are accumulated to give the quarterly doses and the quarter-t ly results are accumulated to give the annual doses.
HP Date9-D-03 Rev.
_6__ '
- 1) North Vent (Common): The plant gaseous discharges via this vent are monitored by two Particulate, Iodine and Gas (PIG) monitors (RY26-075A and RY26-075B) in parallel and by the Wide Range Accident Monite- (WRAM)
(RIX26-076). The PIGS have separate Particulate, Iodine, and gas sampling and monitoring channels but the Station i
Technical Specifications require only particulate and iodine sampling and noble gas monitoring. The WRAM has extended range (via three channels) noble gas monitoring and particulate and iodine sampling capability. In addi-tion, the WRAM provides an isolation of the large Drywell l
Purge and Vent valves.
L,
- 2) South Vent (one per unit): The plant gaseous dis-
- i. -
charges via each South Vent are monitored by two redundant PIG monitors (RY26-185A,B and RY26-285A,B). As is the l of the North Vent, each PIG has separate particulate, iodine, and gas sampling and monitoring channels but the Station Technical Specifications require only particulate and iodir,e sampling with noble gas monitoring.
l l
- 3) Hot Maintenance Shop (Common): Due to the composition of I
the radioactive materials in the effluent stream (i.e.,
L very low potential for noble gases), this release point is sampled by a Particulate and Iodine (P&I) Monitor (RY26-Engr 4HL H.P. %C Date '000 Rev. L _
?
025). The P&I monitor has separate particulate and iodine sampling and monitoring channels but the Station Technical Specifications require only particulate and iodine sampling.
2.2 Gaseous Effluent Monitor Setpoint Determination Technical Specification 3.3.7.12 requires that alarm set-point be established for the noble gas effluent monitorjng channels (RY26-075A,B; RY26-185A,B; RY26-285A,B; and RIX26-l 07-6) to ensure that the release rate of radioactive materials does not exceed the limits of Specification t
3.11.2.1, which corresponds to a dose rate at the SITE t
BOUNDARY of 500 mrem /yr to the total body or 3000 mrem />T to lL J, the skin. This specification also states that the dose rates from I-131, I-133, tritrium, and all radionuclides in particulate form with half-lives greater than eight days, shall be limited to a maximum of 1500 mrem /yr to any organ (inhalation pathway only).
Technical Specification limits are expressed in terms of dose rate, while the instruments which monitor effluents produce data in units of concentration of radioactivity 5
(i.e., FCi/cc). It is therefore necessary to calculate the Engr 4;BE H.P. }M98 A*V Date ' !
t i
2.2.1.1 Setpoint Determination The setpoint for the 14 orth Vent Noble Gas Ef-fluent Monitor is set at or below the lesser of Wue.
the NVSP aw3 or NVSPNasK g
[VF vNcIS00XEigv]
N SPNows 5 [3.4475 E+09]4(Ci y)(Ki)]
(2-1) l-g
[VF vNcI3000lTigv]
N N
[3.4475 E@]Q(Cigy)(L;+1.lM;)] I~)l NVSP csK 5 where:
NVSPNows = North Vent Setpoint - Noble Gas Whole Body (pCi/cc)
NVSP asx = North Vent Setpoint - Noble Gas N
Skin (pCi/cc)
Ic ~.
VF yga
- Fractional contribution to site y
boundary noble gas dose rate from the I
North Vent as calculated in equation 2-7. (unitiess).
500'
= Total body dose rate limit (mrem /yr) 3000
= Ekin dose rate limit (mrem />T)
Eigy
= Iotal noble gas activity from North Vent grab sample (pCi/ce) 3.4475 E@ = Conversion factor I
= (1.lE-05 s/m )(10 pCi/pCi) (664,000 cfm)(h min /sec) (2.832EW cc/ft ) (2-3) s 8
8 I
hith Date V-M-SS Rev. L I
j where:
1.lE-05 s/m8 = highest annual average relative concentration (NE Sector) 8 10 pCi/pCi = units conversion 664,000 cfm = maximum North Vent flow tate for two unit operation hmin/sec
= units conversion s
2.832E+04 cc/ft - units conversion Ciyy
- concentration of noble gas nuclide i as determined by radioanalysis of North Vent grab sample (pCi/cc)
K
- Total body dose conversion factor 3
for noble gas nuclide i (mrem /yr per pCi/m3, from Table 2-1)
L
= Beta skin dose conversion factor i
If.Q, for noble gas nuclide i (mrem /yr per pCi/m8, from Table 2-1).
h(
= Gamma air dose conversion factor for noble gas nuclide i (mrad /yr per -
pCi/m8 per Table 2-1).
2.2.2 South Vent Noble Gas Effluent Monitors,-
RY26-185A-3, RY26-185B-3, RY26-285A-3, and RY26-285B-3 Each unit's South Vent Noble Gas Effluent monitor high-high setpoint is calculated monthly based on the grab sample results performed in accordance with Specifica-tion 3.11.2.1.
Due to the incorporation of the ALARA philosophy in the design and operation of the Limerick I
effluent systems, release point grab samples may not Engr H.P Date,277 W I
identify any radionuclides. With this situation, plant staff may use the results of the last grab. sample y hich identified radionuclides or use the default setpoint which is based on expected concentration ratios as-reported in the FSAR. If any calculated alarm setpoint is less. than the existing monitor setpoint, the set-point will be reduced to the new value. If the calcu-lated setpoint value is greater than the existing value, the setpoint may remain at the lower value, or increased to the new value.
2.2.2.1 Setpoint Determination The setpoint for the South Vent Noble Gas Ef-fluent Monitor is set at the lesser of the a.
SYSP or SVSPNasK value.
3aws SVSP aws and SYSPNcsK are calculated 3
for each unit's South Vent.
IVFsync15001ECi,1 (2-4)
SYSP owB 6 N
{1.2149EW)Q(Ci,y)(K ))
i i
IVFsynclI30001ECi.,)
[1.2149E@)4(Ci,y)(L +1 l%)} (2-5)
SYSP I
NGsK f-i where:
[
SVSP own = South Vent Setpoint - Noble N
Gas Whole Body (pCi/cc) f-SVSP
- South Vent Setpoint - Noble NGsK Gas Skin (pCi/ce)
Engr ABG_,.
H.P. /dC Date 'J'?lE Rev.
.f__
s VFswa
= Fractional contribution to site boundary noble gas dose rate from the Unit's South Vent as calcu-lated in equation 2-8 or 2-Ba (unit-less) 500
= Total body dose rate limit (mrem /yr) 3000
= Skin dose rate limit (mrem /yr)
ECi,,
= Total noble gas activity from each unit South Vent grab sample l
(pCi/ce)
~ (pCi)(ce) 1.2149E49 = Conversion factor s
,,,. (m )(pCi)
- (1.lE-05 s/m )(10 pCi/pCi)(234,000 cfm)(h min /s)(2.832E44 cc/ft ) (2-6) 3 8
8 where:
1.lE-05 s/ms = highest annual average relative concentration (NE sector) 8 10 pCi/pCi = units conversion 234,000 cfm
= maximum South Vent flow rate hmin/s
= units conversion 8
2.832E+01 cc/ft
= units conversion Ci,,
= concentration of noble gas nuclide i, as determined by radioanalysis of South Vent grab sample (pCi/cc)
K
= total body dose conversion factor for g
noble gas nuclide 1 (mrem /yr per 8
pCi/m, from Table 2-1).
L
= Beta skin dose conversion factor for I
i noble gas nuclide i (mrem /yr per 8
pCi/m, from Table 2-1)
M
- Gamma air dose conversion factor for i
noble gas nuclide i (mrad /yr per 8
pCi/m, from Table 2-1)
Engr 4 H.P. UA Date 9-T-@
Rev.
_6___ __
} ft-
'2.2.3. Noble Gas Effluent Fractional Contribution-The noble gas effluent fractional contribution'is calcu-
'l
. lated monthly using the results of the grab samples ~ per-
~
formed in accordance with' Specification 3.11.2.1.
The results of this calculation are used in equations 2-1,-
2-2, 2-4, and 2-5.
This methodology assumes that the -
total body dose is the limiting factor for noble gas.
releases.
If equations 2-1,- 2-2, 2-4, and 2-5 show that the skin dose is limiting, fractional skin' doses should be substituted for the whole body values used in l'
equations 2-7, 2-8, and 2-8a.
2.2.3.1 Calculation of VFxvNG, VFISVNG' AUd W sv8G 2
4(Ci y)(K)]
p i
(
q(CjNV)(N )}+N(CI sV)(N+k(C5 sV)kN )} NYNG " i l i 2 i l 4(Ci sv)(N }} (2-8) l i VF sVNG " Q(Ci l8V)(K )]+ (Ci sV)(N }}' NV)(N)}+NkCi i g 2 i i (' ) 4(CissV)(K )] (2-h) i VF sVNG " Q(CiNV)(N )l+k(Ci y)(K ll+ (Ci sV)(K )} 2 i ls i s I t I where: VF,,ga.= fractional contribution to site bound-ary noble gas total body dose rate from the North Vent (unitiess) Engr E - H.P. hM l b cateQ.2789 Rev. L 4-^ E.'
i H WISVNG = fractional Contribution to site bound-ary noble gas total body dose rate from the Unit 1 South Vent (unitiess) VF:sv8G = fractional c. contribution to site bound-ary noble gas total body dose rate from the Unit 2 South Vent (unitiess) Ciuv = concentration of noble gas nuclide i as determined by rhdionnalysis of North Vent grab sample (pCi/cc) = total body dose conversion factor for noble gas 8 radionuclides i (mrem /yr per pCi/m ) { Ci v = concentration of noble gas nuclide i l ls as determined by radionanalysis of Unit 1 South Vent grab sample (pCi/ce) Ci y = concentration of noble gas nuclide i ss as determined by radionanalysis of Unit 2 South Vent grab sample (pCi/cc) 2.2.4 Noble Gas Effluent Default Setpoints .,? This methodology may be used when grab sample results from either the North Vent or the South Vent do not identify any radionuclides. This methodology is based on expected release concentration ratios as outlined in section 11.3 of the Limerick FSAR. 2.2.4.1 North Vent Noble Gas Monitors (RY26-075A-3 and RY26-075B-3) -The default setpoint for the North Vent noble gas ef-fluent monitor is set at or below the NVSP an g value. NGD < [8.90E-Il[500][1.15E-6] 2 9) NVSP - [3.4475E+9][4,30E-9] s 3.45E-5 pCi/cc where: Engr ABc-H.P., M Date Q S 8 Rev. _6__ I
l] i NVSPuco = Default North Vent Setpoint - Noble Gas (pCi/ce) 8.90E-1. = Default fractional contribution to site-l boundary noble gas total body dose rate frorn the North Vent (unitiess) 4.30E-9 (4.30E-9)+(131E-10) where: 4.30E-9 = Summation of the North Vent con-l centration of noble gas nuclide i multiplied by the corresponding whole body _ dose factor ~ 3 "(pCi)(mrem)(m ) (cc)(yr)(pCi) 5.31E Summation of the South Vents (Unit 1 & 2) concentration of noble gas nuclide i multiplied by the cor-responding whole body dose factor ~(pCi)(mrem)(m ) ~ 8 (cc)(yr)(pCi) Ref: a) Based on expected annual release from FSAR Table ei 'E 11.3-1 b) Based on maximum North Vent flow of 664,000 cfm and South Vent flow of 234,000 cfm for Unit I and Unit 2 vents l c) ODCM Table 2-1 500- - Total body dose rate limit (mrem /yr) )- i_ l.15E-6 - Total noble gas concentration from l' North Vent (pCi/ce) Ref: a) Based on FSAR Table 11.3-1 b) Based on maximum North Vent flow rate of 664,000 cfm. ) 3.4475E+9 - Conversion factor [ -(pCi)(cc) 8 _(m )(pCi) Ref: a) ODCM equation 2-3 Engr GER H.P. /M Date' V~M88 Rev. 6_ j
e ' 4.30E-9 = Summation of the North Vent concentration l: of noble gas nuclide i multiplied by the corresponding whole body dose factor s ~(pCi)(mrem)(m ) (cc)(yr)(pCi) Ref:
- 1) Based on FSAR Table 11.3-1
- 2) Based on' maximum North Vent flow of 664,000 cfm -
l
- 3) ODCM Table 2-!.
2.2.4.2 South Vent Noble Gas Monitors (RY26-185A-3, RY26-285A-3, RY26-185B-3 and-RY26-285B-3) The default setpoint for each Unit's South Vent noble gas effluent monitor is set at or below the SVSPgap value. SYSP cp $ ((5.49E-2]{500){7.14E-8) - (2- 0) 3 1.2149E+9][2.65E-10] s 6.09E-6 pCi/cc 3 where: SYSPugo = Default South Vent Setpoint - Noble Gas (pCi/cc) 5.49E-2 = Default fractional contribution to l site boundary noble gas total body l dose rate from the South Vent (unit-less) 2.65E-10 " (4.30E-9)M5.31E-10) where: 2.65E-10 = summation of each Unit's South Vent concentration of noble gas nuclide i multiplied by the cor-i responding whole body dose factor s ~ (pCi)(mrem)(m ) (cc)(yr)(pCi) Engr 4M H.P. ildl Date W?7-88 Rev. _6_,
il ( 4.30E-9 = summation of the North Vent con-l centration of noble gas nuclide i multiplied by the corresponding-whole body dose factor ~(pCi)(mrem)(m ) - s (cc)(yr)(pCi) 5.31E-10 = summation' of the South Vents (Units 1 & 2) concentration of noble gas nuclide i multiplied by the cor- . responding whole body dose factor ~(pCi)(mrem)(m ) s (cc)(yr)(pCi) Ref: a) Based on expected annual releases from FSAR Table 11.3-1 b) Based on maximum North' Vent' flow l of 664,000 cfm and South V nt flow i of 234,000 cfm for Unit I and Unit 2 Vents c) ODCM Table 2-1 500 = total body. dose rate limit (mrem /yr) 7.14E-8 = total noble gas concemration from l~ L South Vent (pCi/cc) Ref: a) Based on FSAR Table 11.3-1 b) Based on maximum South Vent flow of 234,000 cfm) 1.2149E+9 = Conversion factor ~ l ~ (pCi)(cc) s _ (m )(pCi) _ Ref: ODCM equation 2-6 2.65E-10 - Summation of each Unit's South Vent l concentration of noble gas nuclide i multiplied by the corresponding whole body dose factor ~(pCi)(mrem)(m ) - s (cc)(yr)(pCi) Ref: 1) Based on FSAR Table 11.3-1
- 2) Based on maximum South Vent flow of 234,000 cfm for Unit I and Unit 2 vents
- 3) ODCM Table 2-1 Engr %
Ed/ Era Rev. 6_, ..s. 2.2.5.1 Setpoint Determination - Containment Purge Operations ~ During routine purge operations the setpoint will be determined prior to initiation of the purge based on the containment noble gas grab sample required by Specification 3.11.2.1. The WRAM setpoint is set at or below the lesser of the WRSP cPWB or WRSPNGPSK value. N At no times will the setpoint be higher than 6.58 E+8 pCi/s (Ref. Specification Table 3.3.2-2 limit, of s 2.1 pCi/cc converted to pCi/s (2.1 pCi/cc is based on maximum 2 unit North Vent flow rate). h;:@., [VF vNo][500][ECic] N (~ } WRSP cPWB 5 [1.lE+1] E [(Cic)(Ki)] N [VF vNol[3000][ECic] l N I~} l WRSP cPSK I [1.10E+1] E [(Cic)(Li+1.lMi)] N l where: WRSP = WRAM Purge Setpoint - Noble Gas gapg3 Whole Body (pCi/sec) WRSP = WRAM Purge Setpoint - Noble Gas NGPSK skin (pCi/sec) 1 ) Fractional contribution to site VF = yyga boundary noble gas dose rate from North Vent as calculated in equation 2-7 (unitiess) Engr } ~ H. P. Date ?$ Rev. L (_ L:. 30 _ 1
The site boundary dose rate from noble gas effluent (. releases in the event of a noble gas effluent setpoint exceeding the value specified in ODCM sections 2.2-! (or 2.2.4.1), 2.2.2 (or 2.2.4.2), and 2.2.10 is calculated using the methodology stated below. This methodology is based on worst sector (NE) annual average meteorological dispersion but, if further refinement is required to meet the requirements of Specification 3.l!.2.la. actual meteorological data from the time period of concern may be used to calculate actual meteorological dispersion. f (((Fm)(Qig)+(F sy)(Qi sy)+(F sv)(Ql sv) ] Ki ] ?% (2-14) (( D,373 = (53.882)(X/Q) i t 2 z tsv)+(F sv)(Qi v) ] l i ) (111) + (((Fg)(Qi )+(F sv)(Qi 2 ss g i D sg = (53.882)(X/Q) [ [(Fm)(Qig)+(F sy)(Qi sv)+(F sv)(Qi sv) 3Mi ] _ p (SF) i i 2 s (2-15) where: D,p73 = Total Body Plume Dose Rate (rem /hr) D = Skin Plume Dose Rate (rem /hr) Psx I'~" "~"* 53.882 = Units conversion factor 8 s JCi-hr-mrem-m -sec-ft Engr E E. H.P. me, my g Rev., 6__.
e X/Q = 1.1E-05 highest annual average relative concentration (NE 8 ~ Sector) (s/m ) North Vent Flow Rate (cfm) Fw = = concentration of noble gas nuclide i during period Qig of release from North Vent (pCi/cc) Unit 1 South Vent Flow Rate (cfm) Fy = is Qi sy = Concentration of noble gas nuclide i during period t of release from Unit 1 South Vent (pCi/cc) Unit 2 South Vent Flow Rate (cfm) F sy = s Qi sy = Concentration of noble gas nuclide i during period s of release from Unit 2 South Vent (pCi/cc) Total body dose factor for noble gas nuclide i. Values K = i S'{.y*3 3 e listed in Table 2-1 p Li = Skin dose factor for the beta contribution for noble gas nuclide r 33 m m
- i. Values are listed in Table 2-1 the average ratio of tissue to air energy absorption coeffi-j 1.11
= cients (mrem / mrad) (Ref: Reg. Guide 1.109 Section 2.2) 0.7 is the attenuation factor that accounts for the dose reduc-SF = tion due to shielding provided by residential structures (dimensionless) (Ref. Reg. Guide 1.109, Table E-15) Gamma air dose factor for noble gas nuclide i. Values are Mi = s' e [-5 listed in Table 2-1 ,7 2.3.2 Site Boundary Dose Rate Radioiodine and Particulate Technical Specification 3.11.2.lb limits the dose rate to s 1500 mrem /yr to anf organ (inhalation pathways only) for I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents. Compliance with Specification 3.ll.2.lb will be determined monthly by performance of ODCM section 2.3.4. Engr E H.P. ..f Date 388 Rev. .s.__
Dgra = (0.ll4)(1.lE-5)(472) y' [(Fw)(Cig)4Fgy)(Cigy)(F:sv)(Ci sv) ] Mi (2-16) s 1 y - D,43g - (0.!!4)(1.lE-5)(472) y [(F,)(Cig)(F v)(Ci y)KF:sv)(Ci v):] Ni (2-17)$ a g ss I where: l DgIR = Gamma air' dose from noble gas releases (rad /hr) DAAIR = Beta air dose from noble gas releases (rad /hr) 0.!!4 = Units conversion- ,'hr d 1.lE-5 = Highest average annual relative concentration (NE s sector) (sec/m ) " min-ce ' 472 = Units cenversion 3 l sec-ft Fw = Average North Vent flow rate for period of l release (cfm) Ciw = Concentration of noble gas nuclide i from North- ) Vent effluent (pCi/cc) 1.-?h. Fuv = Average Unit i South Vent flow rate for period ) - of release (cfm) I-Ciuv = Concentration of noble gas nuclide i from Unit 1 South Vent effluent (pCi/ce) F sy = Average Unit 2 South Vent flow rate for period 3 of release (cfm) I I ' Ci:sv = Concentration of noble gas nuclide i from Unit 2 South Vent effluent (pCi/ce) Mi - Gamma air dose factor for noble gas nuclide i. Values Syf]** are listed in Table 2-1 Ni = Beta air dose factor for noble gas nuclide i. Values "yf;p" are listed in Table 2-1 Engr H.P. Date 7-8d? Rev. _6__ l L l e
2.3.4 Radiciodine and Particulate Dose Calculations r Technical Specification 3.11.2.3 limits the dose (from each reactor unit) to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the SITE. j BOUNDARY to: 5 7.5 mrem to any organ during any calendar quarter. 1 515 mrem to any organ during any calendar year As required by Surveillance Requirement 4.11.2.3 these doses are calculated at least once per 31 days using the results of the con-tinuous composite sample analysis performed in accordance with Spec-ification 3.11.2.1. Dur, to the incorporation of the ALARA philosophy in the design and operation of the Limerick effluent systems, these composite samples may not identify any radionuclides. j i #4 k?? Total release activity is based upon detectable concentration of the ) continuous composite samples and average appropriate vent flow dur-I ing the sampling period. The monthly dose calculation is performed ~ using the most limiting average annual meteorological dispersion values. The quarterly doses are based on the summation of the ap-plicable monthly results. The annual dose calculations are based upon actual release meteorological as described in Section 2.3.5. The monthly dose calculations are performed in accordance with the methodology and calculations below. Total organ dose is obtained by I the summation of the organ dose from each pathway for each receptor. f Engr H.P. Date 8 Rev. L - [u...- 5
t'l 2.3.4.1 Ground Pathway d DGPAR = (3.6E-6)(472)(1.82E-9) ss _,y,, [(F y)(Qi y)4(F,y)(Qi sv)+(F sy)(Qi v)4(F us)(Qi us) ](DFlx5N) (T,) (2-18) g g 3 t s ss u n 2.3.4.2 Vegetadon, Meat,' Cow Milk, and Goat Milk Pathway Dypig = (3.6E-6)(472) _ k((F y)(Qi y)+(F sv)(Qi sv)+(F,y)(Qi sv)(F HMs)(Qi us)](1.lE-5)(DFigg ), + n l s g g i ( T, s5 _,y,,[(F y)(Qi y)+(F sv)(Qi sv)4(F sv)(QI sv)+(F gs)(Qi us) ](1.82E-9)(DFig3p) g g i t s a n (2-19) 2.3.4.3 Inhalation Pathway Dipig = (3.6E-6)(472) V.2 _,{ [(F y)(Qi y)+(F sv)(Qi sv)+(Fssy)(Q ssy +) (FHMs)(QinMS) ](l.lE-5)(DFgyp) i + g g i l (Ti s5 _,y,, [(F y)(Qi y)+(F sv)(Qi v)+(F sv)(QI sv)4(Fnus)(QinMs) ](1.0E-5)(DFgyp) 3 g i ls s b (2-20) where: D = dose from ground pathway due to release of particu-j. GPAR lates and iodines (rem) dose from vegetation, meat, Cow milk, and goat DVPAR = L milk pathways due to releases of particalates, iodines, and tritium (rem) Engr E _b H.P.[bYO Date Rev. _6_.
L: 6 i , - ~ dose from inhalation pathway due to release of Dpa = i particulate, iodines, and tritium (rem) ] = units conversion factor h'r* $h 3.6E-6 'm n-ce ' 472 = units conversion factor esec-ft8 1.82E-9 = highest average annual deposition (ESE sector) a1n E = summation for each release time period (unitiess) + 4 8 Fw = average North Vent flow rate during release (cfm) concentration of nuclide i from North Vent ef-Qi = w fluent (pCi/cc) average Unit i South Vent flow rate during release F sy = i h (cfm) concentration of nuclide i from Unit i South Vent Qi sy = i effluent (pCi/ce) l f+.); - average Unit 2 South Vent flow rate during release F sy = s (cfm) 7 concentration of nuclide i from Unit 2 South Vent [- Qissy = effluent (pCi/ce) average Hot Maintenance Shop flow rate during F = HMs release (cfm) Qinus = concentration of nuclide i from Hot Maintenance Shop effluent (pCi/cc) DF ),= dose factor for organ type k, age group 1, g pathway number n; dose factors are based on results of a computer program that is based on and is similar to the NRC program GASPAR; results from this program provide }. input data in the form of a lookup table - values of DF, are provided in Table 2-2. I: y i = isotope number (1 through 35) (3 through 17 are noble gases) p k = organ type (1 through 8, where total body = 1, GI tract = 2, bone = 3, liver = 4, kidney = 5, thyroid = 6, lung = 7, skin = 8) Engr A LiiG H.P.'G-2798 Date x Rev.
- _6_,
. G' '
5 1 ~ the corresponding hourly averaged effluent release rate. Doses are then calculated for each hour ~ at the various receptors of interest (depending t:pon release direction). -Radioactive material release [ activity is calculated as deu:ribed in Sections 2.3.3 and 2.3.4. Dose at each receptor is ac vmulated for the year and the maximum dose for plume, inhalation, and ingestion pathways are reported. The gaseous effluent dose receptors are listed in Table 2-4'and the dose is calculated using the methodology below. 2.3.5.1 Plume Pathway [(Fg)(Qig)+(F y)(Qigy)+(F sv)(Qi sv) 3-j rucA = (3.6E-6)(472){(X/Q), D g 2 s . [e(
- )DFm,)(T,).
(2-21) ' 2.3.5.2 Ground Pathway l' -(Fw)(Qig)(Fay)(Qi v)+ ~ GPARA-(3.6E-6)(472){(D/Q),,,bs ls (DFu,)(T,) (2-22) D 3, p p )g; Engr 4dHL-H.P.,LLAT DateM U'h Rev. _6_. (~.
2.3.5.3 Vegetation, Meat, Cow Milk, Goat Milk' Fathway ~ -.s. VPARA=(3.6E-6)(472){ D _lf1[(Fyy)(Qi y)+(F v)(Qi sv)+(F,y)(Qi sv)+(Fag 3)(QiHMs)XX/Q.KDF gio) + g is l s 3 ( T, ). i,[(F y)(Qi y)+(F sy)(Qi y)+(F sv)(QI v)+(FHMs)(QiHMS) 3D/Q3s(DF gio) g g i 33 2 ss i (2-23) ' 2.3.5.4 Inhalation Pathway DIPARA = (3.6E-6)(472)E _ih, [(F y)(Qi y)+(F v)(Qi v)+(F gy)(Qi y)+(F us)(QIHMS) b/k)(DFiktn) + y g is ts a ss H (T ) g _,, [(Fgy)(Qi y)+(F sv)(Qi sv)+(F sv)(QI sv)+(FHMs)(QIHMS) ) h/k ept }DFigin) g i l 2 2 d (2-24) where: bo D - annual dose from plume pathway (rem) ptuar e I DcPARA = annual dose from ground pathway (rem) D = annual dose from vegetation, meat, cow milk, and VPARA goat milk pathways (rem) D = annual dose from inhalation pathway (rem) IPARA = units conversion factor (hr-m -pIi 3.6E-6 " min-ce
- 472
= units conversion factor ssec-ft*, Engr M H.P.,UN( DateV-N$$ Rev. 6_ _ ,7 - 1
i { = summation for each release time period (unitiess) s (X/Q),' = relative concentration for time period "t" (s/m ) Fw = average North Vent flow rate during release (cfm) Qip = concentration of nuclide i from North Vent effluent (pCi/cc) F sy = average Unit 1 South Vent flow rate during release (cfm) i = concentration of nuclide i from Unit 1 South Vent ef-Qilsv fluent (pCi/cc) F:sv = average Unit 2 South Vent flow rate during release (cfm) Qi y " concentration of nuclide i from Unit 2 South Vent ef-ss fluent (pCi/cc) Ai = decay constant of nuclide i (sec-1) dr = distance to receptor "r" (m) tr. = average windspeed for time period "t" (m/s) l h*g DFgy, = dose factor for organ type k, age group 1, path-way number n; dose factors are based on results of a com-puter program that is based on and is similar to the NRC program GASPAR; results from this program provide input data in the form of a lookup table - values of DF, are provided in Table 2-2. y i - isotope number (1 through 35) (3 through 17 are noble gases) k - organ type (1 through 8, where total body = 1, GI tract = 2, bone = 3, liver = 4, kidney = 5, thyroid = 6, lung = 7, skin = 8) l 1 - age group (1 through 4, where adult = 1, teen = 2, child = 3, infant = 4) f n = pathway number (1 through 7) 1 T, = time duration of release (hrs) f F - average Hot Maintenance Shop flow rate during release (cfm) Ns Qims = concentration of nuclide i from Hot Maintenance Shop effluent (pCi/cc) Engr 6H&_ [.. H.P.).D8[ M' Date (-/ Rev. _6__ '~.
i 8 (D/Q), = deposition concentration for time period "t" (1/m ) (X/Qa,g), = relative depleted concentration for time. period "t" - s (s/m )- j 2.4 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses from each reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day period. The appplicable gaseous processing systems for maintaining radioactive ~ material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2. N - A dose projection is performed at least once per 31-days by the follow-ou, ing equatiotr Dmaxp = (Dmax/d)
- 31d (2-25) where:
Dmaxp = maximum organ dose projection for current 31-day period (mrem) L Dmax = maximum organ dose to date for current calendar quarter as determined by equation (2-18) (2-19) or (2-20) (mrem) l d = number of days in current calendar quarter at the end of the release 31d = the number of days of concern Engr 6FUL A' M. E.P.}MW 63 Date' Rev. 6__ - 47 .s e
3893037260 T.S. 6.9.1.8 10CFR50.36a PHILADELPHIA ELECTRIC COMPANY (IMERICK GENER ATING STATION P. O. BOX A SAN ATOG A. PENNSYLVANIA A 19464 (215) 3271200 EXT, 3000. " 0".7".1,.'.'U* " ' February 28, 1989 Docket No. 50-352 License No. NPF-39 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555'
Subject:
Limerick Generating Station, Unit 1 1) Semi-Annual Effluent Release Report No. 9, July 1, 1988, through December 31, 1988 '~ 2) Annual Tower No. 1 Joint Frequency Distributions ~ of Wind Direction and Speed by Atmosphere Stability Report No. 4 Gentlemen: Enclosed are two copies of the Semi-Annual Effluent Release Report No. 9 for the period July 1, 1988 through December 31, 1988, for Limerick Generating Station (LGS), Unit 1. In addition, the Annual Tower No. 1 Joint Frequency Distributions of Wind Direction and Speed by Atmospheric Stability Class Report No. 4 is enclosed. This report covers the calendar year 1988. These reports are being submitted in compliance with the LGS Technical Specification 6.9.1.8 and 10CFR50.36a(a)(2). Very,u ' yours, J JJM/sp Enclosures Lk cc: William T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS 1 ( ln L_-_--____-_-_-____-________}}