ML20058M436
| ML20058M436 | |
| Person / Time | |
|---|---|
| Issue date: | 12/03/1993 |
| From: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9312200326 | |
| Download: ML20058M436 (14) | |
Text
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December 3,1993 MEMORANDUM FOR:
Brian K.. Grimes, Director Division of Operating Reactor Support, NRR 1
FROM:
Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Suppe,t, NRR
SUBJECT:
SUMMARY
OF MEETI% ON PRIMARY CONTAINMENT LEAKAGE RATE L
TECHNICAL SPECIFICATIONS On October 13, 1993, the staff met with representatives from the BWR Owners Group (BWROG) and NUMARC to discuss primary containment leakage requirements in the standard technical specifications (STS).
Steve Bethay, a representative from Southern Nuclear Operating Company working on the Hatch STS conversion, stated that the industry had some concern regarding the applicai, ion of 10 CFR 50, Appendix J, leakage rate testing requirements in the improved STS.
The primary concerns relate to methods for treating the results of local leak rate tests performed at various times.
I recommended that the BWROG prepare a proposed change to the STS, in accordance with the process for such changes, and submit it for NRC i
consideration.
NUMARC agreed that this matter would be better resolved generically and agreed to work with the Owners Groups to develop a proposed change to the 5fS.
R. Lobel encouraged the Owners Groups and NUMARC to provide additional suggestions on improvements to the containment leak testing practices for the staff to consider during the development of changes to Appendix J.
Original signed by:
Christopher I. Grimes, Chief
- W 0 'd '2 Technical Specifications Branch 3
Division of Operating Reactor Support,NRR Attachments:
- 1. List of attendees
- 2. Meeting handout cc:
G. Lainas DISTRIBUTION:
D. Mathews Central Files MSchwarz, OGC K. Jabbour PDR CMarco, OGC A. Thadani 015B R/F OTSB Members R. Barrett CIGrimes
/- K /, JC)M SD(hM/eW-rI R. Lobel SHWeiss 7( py,y,y,x e lEffagg J. Pulsipher GHMarcus M. Dey AEChaffee 7,' w; g '
J. Hayes KNJabbour A. Chu E d# 'O &_I' DOCUMENT NAME:
G:\\ CONT-ACT.CIG
- See previoys ncurrence 0TSB: DORS:NRR OTSB: DORS:NRR PDil-3/NRR 3SC:SCS: SSA C:0TSB: DORS:NRR ATChu*
RHLo*
KNJabbour RMLobel CIGrimes 11/03/93 11/04/93 ll/g1/93 ll/fl/93 11/6/93 bm m 1
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MEMORANDUM FOR:
Brian K. Grimes, Director l
Division of Operating Reactor Support, NRR FROM:
Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR r
SUBJECT:
SUMMARY
REPORT-FOR MEETING WITH NUMARC AND OWNERS GROUP ON PRIMARY CONTAINMENT LEAKAGE RATE TECHNICAL SPECIFICATIONS On October 13, 1993, the staff met with NUMARC and the BWR Owners Group
-(BWRCG) at the NRC OWFN office. -The pur;:9se of the meeting was to discuss industij and staff posit' ions on primary containment leak rate standard technical specifications (TS).
Steve Bethay, a representative from Southern Nuclear Operating Company, stated that the industry had some concern regarding the application of 10 CFR 50, Appendix J, leakage rate testing requirements in the improved Standard Technical Specifications.
The BWROG's primary concern
[
was the need to clarify the method for adding test results from various leakage paths and to establish acceptance criteria with which these totals should be compared.
I recommended that the BWROG prepare a. generic TS change traveler in accordance with the agreed upon process and submit it for NRC consideration.
}
NUMARC agreed that this was the correct approach, and the industry will develop such a traveler.
Christopher I. Grimes, Chief I
Technical Specifications Branch Division of Operating Reactor Support,NRR Attachments:
l
- 1. List of attendees 1
- 2. Meeting handout DISTRIBUTION:
OTSB R/F DORS R/F Central Files CIGrimes j
SHWeiss i'
GHMarcus AEchaffee MSchwarz CMarco OTSB Members DOCUMENT NAME: G:\\ CONT.ACT OTSB:D0 S:NRR M: DORS:NRR PDIl-3/NRR C: DORS:NRR ATChu (
HLo KNJabbour CIGrimes 11/J 9 ll/f/93 11/ /93 11/ /93 i
)
pa arow
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, )t UNITED STATES
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E NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 20555 0001
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December 3, 1993 MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support, NRR FROM:
Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR
SUBJECT:
SUMMARY
OF MEETING ON PRIMARY CONTAINMENT LEAKAGE RATE TECHNICAL SPECIFICATIONS On October 13, 1993, the staff met with representatives froe the BWR Owners Group (BWROG) and NUMARC to discuss primary containment leakage requirements in the standard technical specifications (STS).
Steve Bethay, a representative from Southern Nuclear Operating Company working on the Hatch STS conversion, stated that the industry had some concern regarding the application of 10 CFR 50, Appendix J, leakage rate testing requirements in the improved STS. The primary concerns relate to methods for treating the results of local leak rate tests performed at various times.
I recommended that the BWROG prepare a proposed change to the STS, in accordance with the process for such changes, and submit it for NRC consideration. NUMARC agreed that this matter would be better resolved generically and agreed to work with the Owners Groups to develop a proposed change to the STS.
R. Lobel encouraged the Owners Groups and NUMARC to provide additional suggestions on improvements to the containment leak testing practices for the staff to consider during the development of changes to Appendix J.
CTTs a Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support,NRR Attachments:
- l. List of attendees
- 2. Meeting handout cc:
G. Lainas D. Mathews K. Jabbour A. Thadani R. Barrett R. Lobel J. Pulsipher M. Dey J. Hayes A. Chu r
I
OTSB/NRR Meeting on Containment October 13, 1993 Ronnie lo NRC/0TSB Jim Eaton NUMARC Steve Bethay Souterhn Nuclear Richard Lobel NRC/SCSB Theresa Meisenheimer Bechtel Jim Pulispher NRC/SCSB 1
Moni Dey NRC/RES/EIB-Chris Grimes NRC/0TSB Jack Hayes NRC/PRPB Angela Chu NRC/0TSB e
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NRC PRESENTATION OCTOBER 13,1993 IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT BY STEVE BETIIAY SOUTIIERN NUCLEAR OPERATING COMPANY i
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-1 IMPROVED' TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT l
PURPOSE i
i TO ENSURE TIIAT TIIE REQUIREMENTS OF 10 CFR 50, APPENDIX J j
AND TIIE ASSUMPTIONS OF TIIE LOCA RADIOLOGICAL ANALYSES ARE REFLECTED APPROPRIATELY IN TIIE TECIINICAL SPECIFICATIONS.
i OBJECTIVE TO PROVIDE AN ACCEPTABLE ALTERNATIVE TO TIIE LANGUAGE FOUND IN SECTION 3.6.I OF TILE ITS NUREGs.
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IMPROVED TECHNICAL SPECIFICATIONS j
SECTION 3.6.1 - PRIMARY CONTAINMENT LOCA RADIOLOGICAL ANALYSIS (BWR)
TIIE TOTAL OFF SITE DOSE RESULTING FROh! A DESIGN BASIS LOCA CONSISTS OF CONTRIBUTIONL i R031:
SECONDARY CONTAINMENT DRAW D'AVN (120 seconds)
PR131ARY CONTAIN51ENT LEAKAGE (La)
BYPASS LEAKAGE
(.009La)
MSIV LEAKAGE (11.5 SCFII) l TIIE 30 DAY LPZ TIIYROID DOSE FROSI EACII CONTRIBUTION PATIIWAY WOULD DE ON TIIE ORDER OF:
SECONDARY CONTAIN51ENT DRAW DOWN 64 rem PRI51ARY CONTAIN51ENT LEAKAGE 5 rem BYPASS LEAKAGE 101 rem AISIV LEAKAGE 8 rem TOTAL 178 rem 3
I
. IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT 1
REGULATORY RELATIONSHIPS TECHNICAL SPECIFICATIONS i
l THE PURPOSE OF THE TECHNICAL SPECIFICATIONS (LCOs) IS TO PROVIDE,"... TilELOlVESTFUNCTIONAL CAPABILITI'OR PERFORMANCE LEVELS OF EQUIPMENT REQUIRED FOR SA FE i
OPERATION OF THE FACILIT)'."
I THE PURPOSE OF SURVEILLANCE REQUIREMENTS IS TO, "...
l ASSURE THA T F4 CILITI' OPERA TION ll1LL BE lilTHIN THE SAFETY LIMIT'i AND THA T THE LIMITING CONDITIONS FOR OPERA TION ll1LL BE MET."
THE TECHNICAL SPECIFICATIONS PROVIDE A LEVEL OF ASSURANCE TflAT THE ASSUMPTIONS AND INPUTS OF THE I
ACCF0ENT ANALYSIS REMAIN VALID DURING REACTOR i
CPERATION.
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT REGULATORY RELATIONS 11IPS (CONTINUED) 10 CFR 50, APPENDIX J TIIE PURPOSE OF TIIE LEAKAGE RATE TESTING REQUIRED BY APPENDIX J IS TO, "... ASSURE THA TLEAKAGE THROUGH THE PRIMAR1' REACTOR CONTAINMENT AND COMPONENTS AND S1' STEMS PENETRA TING CONTAINMENTSHALL NOTEXCEED ALLOIl' BLE VALUESASSPECIFIEDIN THE TECHNICAL A
SPECIFICA TIONS... ".
i APPENDIX J SPECIFIES TIIE FREQUENCY AND ACCEPTANCE CRITERIA FOR ROUTINE, PERIODIC SURVEILLANCE TESTS OF TIIE PRI51ARY CONTAIN51ENT.
APPENDIX J REQUIRES TIIAT TIIE MAXI 5IUM ALLOWABLE LEAKAGE RATE (La) SIIALL BE DEFINED IN TIIE TECIINICAL SPECIFICATIONS.
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT PROPOSED TECHNICAL SPECIFICATION STRUCTURE THE FOLLOWING STATEh!ENTS REPRESENT A PHILOSOPIIY OF TECH. SPEC. STRUCTURE WHICH IS CONSISTENT WITII THE OFFSITE DOSE ANALYSES, REGULATORY REQUIREh1ENTS, AND GOOD ENGINEERING PRACTICE:
I. A VALUE FOR La SHOULD BE DEFINED IN THE TECH. SPECS.,
THIS VALUE SHOULD BE CONSISTENT WITH AND LNCLUDE ALL LEAKAGES ASSUh1ED IN THE VALUE OF La USED IN THE LOCA RADIOLOGICAL ANALYSIS.
- 2. THE VALUE OF La WOULD NOT TYPICALLY INCLUDE BYPASS OR 51SIV LEAKAGE FOR A BWR/4.
- 3. THE FREQUENCY AND ACCEPTANCE CRITERIA SPECIFIED IN APPENDIX J SHOULD BE INCORPORATED IN TIIE TECIL SPECS.
LN A h!ETHOD CONSISTENT WITH ALL OTHER PERIODIC SURVEILLANCE REQUIREh!ENTS.
- 4. h!SIVs AND BYPASS LEAKAGE PATHS SHOULD BE SUBJECTED TO LEAKAGE RATE TESTING CONSISTENT WITH APPENDLX J EVEN THOUGII THEY ARE NOT PART OF La.
- 5. AIRLOCKS 51UST BE TESTED AS DESCRIBED IN APPENDIX J.
THEY ARE REQUIRED TO h!EET BOTH THEIR OWN ACCEPTANCE CRITERIA (.05La) AND BE CONSIDERED IN TIIE TOTAL TYPE B&C LEAKAGE RATE.
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT
]
PROPOSED TECIINICAL SPECIFICATION STRUCTURE (CONTINUED)
- 6. A RUNNING TOTAL OF PRIMARY CONTAINMENT LEAKAGE RATES SIIOULD BE MAINTAINED DURING REACTOR OPERATION. AS NEW INFORMATION IS OBTAINED, TIIE TOTAL SHOULD BE ADJUSTED TO ENSURE IT REMAINS LESS TILAN La. NOT 0.75La.
TIIE RUNNING TOTAL CONTAINMENT LEAKAGE RATE (RTCLR) SIIOULD BE CALCULATED AS:
RTCLR = (SUM OF THE MOST RECENT TYPE B& C TEST RESULTS)
+ ( UNTESTED PA THWA Y LEAKA GE FROM THE MOST RECENT TYPEA TEST)
TIIE RTCLR DOES NOT INCLUDE MSIV OR BYPASS LEAKAGE.
- 7. AT NO TIME DURING REACTOR OPERATION SIIOULD TIIE RUNNING TOTAL CONTAINMENT LEAKAGE RATE (RTCLR)
EXCEED La.
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- 8. PRIOR TO STARTUP FROM EACII REFUELING OUTAGE, TIIE TOTAL TYPE B & C LEAKAGE RATES MUST BE VERIFIED TO BE LESS TIIAN 0.6La, EXCLUDING MSIV AND BYPASS LEAKAGE RATES.
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- 9. PRIOR TO STARTUP FROM EACII REFUELING OUTAGE TIIE LEAKAGE RATE OF EACII MSIV MUST BE VERIFIED TO BE WITIIIN ITS LIMIT.
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IMPROVED TECIINICAL SPECIFICATIONS i
SECTION 3.6.1 - PRIMARY CONTAINMENT i
i PROPOSED TECHNICAL SPECIFICATION STRUCTURE i
(CONTINUED)
- 10. PRIOR TO STARTUP FROM EACII REFUELING OUTAGE, TIIE BYPASS LEAKAGE PATIIWAY TOTAL MUST BE VERIFIED TO BE WITIIIN LIMITS.
II. AT NO TIME DURING REACTOR OPEi:4 TION ARE MSIV AND BYPASS LEAKAGE RATES ALLOWED TO EXCEED TIIEIR RESPECTIVE LIMITS.
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r IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT PROPOSED REVISION TO ITS - NUREGS l
THE MAXIMUM ALLO WABLE PRIMA Rl' CONTAINMENT LEAKA GE
\\
RA TE A T THE CALCULA TED PEAK A CCIDENT PRESSURE. La SHALL BE EXPRESSED IN TERMS OF WEIGHTPERCENT PER 24 HOURS. FOR [PLANTHATCH UNIT 2] La IS EQUAL TO [1.2n1
%'DAl'f. [ THE VALUE OFLa DOESNOTINCLUDEMSIV OR SECONDA RI' CONTAINMENT B l' PASS LEAIGt GES.]
- 2. SR 3.6.1.1.1 (BWR & PWR)
DELETE THE SECOND PARAGRAPII.
- 3. LCO 3.6.1.2 (PWR - LCO 3.6.2, NOTE 3)
MODIFY NOTE 2 UNDER ACTIONS TO READ,"... LEAKAGE RESULTS IN EXCEEDING La."
i
- 4. REOUIRED ACTION 3.6.1.2.C.1 (PWR - REOUTRED ACTION 3.6.2.C.1 )
i MODIFY TO READ,"...OVERALL LEAKAGE RATE AGAINST La, t
USING CURRENT AIR LOCK TEST RESULTS."
- 5. SR 3.6.1.2.1 ( PWR - SR 3.6.2.1, NOTE 21 j
MODIFY NOTE 2 TO READ,".. EVALUATED AGAINST La."
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT PROPOSED REVISION TO ITS NUREGS -(CONTINUED _}
- 6. LCO 3.6.1.3 (PWR - LCO 3.6.3. NOTE 4)
FOR BWR'S, MODIFY NOTE 4 UNDER ACTIONS TO READ, "...
PCIV LEAKAGE RESULTS IN EXCEEDING La. MSIV AND BYPASS LEAKAGE RATES ARE NOT CONSIDERED PART OF La."
FOR PWR'S, MODIFY NOTE 4 UNDER ACTIONS TO READ,
"... ISOLATION VALVE LEAKAGE RESULTS IN EXCEEDING La."
l 7.
SR 3.6.1.3.12 (BWR)
DELETE THE NOTE. CHANGE FREQUENCY TO READ,"
CONSISTENT WITH THE FRT.QUENCY SPECIFIED IN 10 CFR 50 APPENDLX J FOR TYPE C TESTS."
1
- 8. SR 3.6.1.3.13 (BWR)
DELETE THE NOTE.
- 9. SR 3.6.1.3.14 (BWR) j DELETE THE NOTE 2.
- 10. SR 3.6.3.7 (PWR) 1 DELETE THE NOTE.
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DELETE TIIE NOTE.
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