ML20058M464
| ML20058M464 | |
| Person / Time | |
|---|---|
| Issue date: | 12/06/1993 |
| From: | Alexander Adams Office of Nuclear Reactor Regulation |
| To: | Weiss S Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-684A NUDOCS 9312200336 | |
| Download: ML20058M464 (3) | |
Text
December 3,1993 l
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 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 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 t
change to the STS.
R. Lobel encouraged the Owners Groups and NUMARC to pronae additional suggestions on improvements to the containment leak testing practices for the staff to consider during the development of changes to Appendix J.
i Original signed by:
Christopher I. Grimes, Chief
,gggg Technical Specifications Branch 2
Division of Operating Reactor Support,NRR Attachments:
l
- 1. List of attendees
- 2. Meeting handout cc:
G. Lainas DISTRIBUTION:
D. Mathews Central Files MSchwarz, OGC K. Jabbour PDR CMarco, OGC A. Thadani OTSB R/F OTSB Members R. Barrett CIGrimes
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x' </- /, /h/ SU [=7N/WMf R. Lobel SHWeiss
- r(,9,gg,9fj laj.d'/ h,df4 J. pulsipher GHMarcus j
M. Dey AEChaffee J. Hayes KNJabbour ygiqp.
f "#g) d A. Chu K6#* 2 DOCUMENT NAME:
G:\\ CONT-ACT.CIG
- See previous-concurrence
'rQ 0TSB: DORS:NRR OTSB: DORS:NRR PDll-3/NR SC:SCSBTDSSA C:0TSB: DORS:NRR ATChu*
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i MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support, NRR i
FROM:
Christopher I. Grimes, Chief Technical Specifications Branch j
Division of Operating Reactor Support, NRR 1
SUBJECT:
SUMMARY
REPORT FOR MEETING WITH NUMARC AND OWNERS GROUP DN PRIMARY CONTAINMENT LEAKAGE RATE TECHNICAL SPECIFICATIONS i
On October 13, 1993, the staff met with NUMARC and the BWR Owners Group j
(BWROG) at the NRC OWFN office. The purpose of the meeting was to discuss industry and staff positions on primary containment leak rate standard 1
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 i
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 j
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.
j Christopher I. Grimes, Chief i
Technical Specifications Branch Division of Operating Reactor Support,NRR Attachments:
i'
- 1. List of attendees
- 2. Meeting handout DISTRIBUTION:
015B R/F DDRS R/F Central Files i
CIGrimes SHWeiss GHMarcus I
AEChaffee MSchwarz
)
CMarco OTSB Members DOCUMENT NAME:
G:\\ CONT.ACT OTSB:00 S':NRR M: DORS:NRR PDII-3/NRR C: DORS:NRR j
fHLo ATChu C
KNJabbour CIGrimes ll/J 9 ll/f/93 11/ /93 11/ /93 i
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UNITED STATES
[W'tj NUCLEAR REGULATORY COMMISSION
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'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 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 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 practice' for the staff to consider during the development of changes to Appendi J.
C23G Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support,NRR Attachments:
- 1. List of attendees
- 2. Meeting handout cc:
G. Lainas D. Mathews X. Jabbour A. Thadani R. Barrett R. Lobel J. Pulsipher M. Dey J. Hayes A. Chu
OTSB/NRR Meeting on Containment October 13, 1993 t
Ronnie to NRC/0TSB Jim Eaton NUMARC Steve Bethay Souterhn Nuclear Richard Lobel NRC/SCSB Theresa Meisenheimer Bechtel Jim Pulispher NRC/SCSB Moni Dey NRC/RES/EIB Chris Grimes NRC/0TSB
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Jack Hayes NRC/PRPB Angela Chu NRC/0TSB
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i NRC PRESENTA1 ION OCTOBER 13,1993
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IMPROVED TECHNICAL SPECIFICATIONS ~
f SECTION 3.6.1 - PRIMARY CONTAINMENT l
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BY i
STEVE BETHAY SOUTIIERN NUCLEAR OPERATING COMPANY I
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT PURPOSE TO ENSURE TIIAT TIIE REQUIREh1ENTS OF 10 CFR 50, APPENDLX J AND THE ASSUAIPTIONS OF THE LOCA RADIOLOGICAL ANALYSES ARE REFLECTED APPROPRIATELY IN TIIE TECIINICAL SPECIFICATIONS.
i OB.IECTIVE TO PROVIDE AN ACCEPTABLE ALTERNATIVE TO TIIE LANGUAGE FOUND IN SECTION 3.6.1 OF TIIE ITS NUREGs.
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i IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT l
LOCA RADIOLOGICAL ANALYSIS (BWR)
THE TOTAL OFF SITE DOSE RESULTING FROM A DESIGN BASIS LOCA CONSISTS OF CONTRIBUTIONS FROM:
SECONDARY CONTAINMENT DRAW DOWN (120 seconds)
PRIMARY CONTAINMENT LEAKAGE (La)
BYPASS LEAKAGE
(.009La)
MSIV LEAKAGE (11.5 SCFil)
TIIE 30 DAY LPZ TIIYROID DOSE FROM EACH CONTRIBUTION PATIIWAY WOULD BE ON TIIE ORDER OF:
SECONDARY CONTAINMENT DRAW DOWN 64 rem i
PRIMARY CONTAINMENT LEAKAGE 5 rem i
BYPASS LEAKAGE 101 rem MSIV LEAKAGE 8 rem TOTAL 178 rem
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t IMPROVED TECIINICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMEN'i' l
REGULATORY RELATIONSHIPS i
r r
TECIINICAL SPECIFICATIONS TIIE PURPOSE OF TIIE TECHNICAL SPECIFICATIONS (LCOs) IS l
TO PROVIDE,"... TIIELOliESTFUNCTIONAL CAPABILIT)'OR PERFORMANCE LEVELS OF EQUIPMENT REQUIRED FOR SAFE OPERATION OF THE FACILITY."
TIIE PURPOSE OF SURVEILLANCE REQUIREMENTS IS TO, "...
ASSURE T11A T FA CILITY OPERA TION lilLL DE IllTHIN THE SAFETYLIMITS AND THA T THE LIMITING CONDITIONS FOR OPERA TION ll7LL BE MET."
TIIE TECIINICM SPECIFICATIONS PROVIDE A LEVEL OF ASSURANCE TIIAT TIIE ASSUMPTIONS AND INPUTS OF TIIE ACCIDENT ANALYSIS REMAIN VALID DURING REACTOR l
OPERATION.
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q IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY ' ONTAINMENT C
l REGULATORY RELATIONSHIPS (CONTINUED) j e
l 10 CFR 50, APPENDLX J TIIE PURPOSE OF TIIE LEAKAGE RATE TESTING REQUIRED BY APPENDIX J IS TO, "... ASSURE THA TLEAKAGE THROUGH THE '
l PRIMAR Y REA CTOR CONTAINMENTAND COMPONENTS AND SYSTEMS PENETRA TING CONTAINMENTSHALL NOT EXCEED l
ALLOWABLE VALUES AS SPECIFIED IN THE TECHNICAL l
SPECIFICA TIONS... ".
APPENDIX J SPECIFIES TIIE FREQUENCY AND ACCEPTANCE CRITERIA FOR ROUTINE, PERIODIC SURVEILLANCE TESTS OF TIIE PRIMARY CONTAINMENT.
APPENDLX J REQUIRES TIIAT TIIE MAXIMUM ALLOWABLE LEAKAGE RATE (La) SIIALL BE DEFINED IN TIIE TECIINICAL SPECIFICATIONS.
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IMPROVED TECIINICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT PROPOSED TECHNICAL SPECIFICATION STRUCTURE TIIE FOLLOWING STATEMENTS REPRESENT A PIILLOSOPIIY OF TECII. SPEC. STRUCTURE WIIICII IS CONSISTENT WITII TIIE OFFSITE DOSE ANALYSES, REGULATORY REQUIREMENTS, AND GOOD ENGINEERING PRACTICE:
- 1. A VALUE FOR La SIIOULD BE DEFINED IN TIIE TECII. SPECS.,
TIIIS VALUE SHOULD BE CONSISTENT WITII AND INCLUDE ALL LEAKAGES ASSUMED IN TIIE VALUE OF La USED IN TIIE LOCA RADIOLOGICAL ANALYSIS.
- 3. TIIE FREQUENCY AND ACCEPTANCE CRITERIA SPECIFIED IN APPENDIN J SIIOULD BE INCORPORATED IN TIIE TECII. SPECS.
IN A METIIOD CONSISTENT WITII ALL OTIIER PERIODIC SURVEILLANCE REQUIREMENTS.
- 4. MSIVs AND BYPASS LEAKAGE PATIIS SIIOULD BE SUBJECTED TO LEAKAGE RATE TESTING CONSISTENT WITil APPENDIX J EVEN TIIOUGII TIIEY ARE NOT PART OF La.
- 5. AIRLOCKS MUST BE TESTED AS DESCRIBED IN APPENDIX J.
TIIEY ARE REQUIRED TO MEET BOTII TIIEIR OWN ACCEPTANCE CRITERIA (.05La) AND BE CONSIDERED IN TIIE t
TOTAL TYPE B&C LEAKAGE RATE.
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IMPROVED TECHNICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT l
PROPOSED TECIINICAL SPECIFICATION STRUCTURE i
(CONTINUED)
- 6. A RUNNING TOTAL OF PRIMARY CONTAINMENT LEAKAGE RATES SIIOULD BE MAINTAINED DURING REACTOR OPERATION. AS NEW INFOIDIATION IS OBTAINED, TIIE TOTAL SIIOULD BE ADJUSTED TO ENSURE IT REMAINS LESS j
TIIAN La. NOT 0.75La.
TILE RUNNING TOTAL CONTAINMENT LEAKAGE RATE (RTCLR) SIIOULD BE CALCULATED AS:
RTCLR = (SUM OF THE MOST RECENT TYPE B& C TEST RESUL TS)
+ ( UNTESTED PA THWA YLEAKA GE FROM THE MOST RECENT TYPE A TEST)
TIIE RTCLR DOES NOT INCLUDE MSIV OR BYPASS LEAKAGE.
- 7. AT NO TDIE DURING REACTOR OPERATION SIIOULD TIIE I
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 r
LEAKAGE RATE OF EACII MSIV MUST BE VERIFIED TO BE WITIIIN ITS LIMIT.
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.Ih1 PROVED TECHNICAL-SPECIFICATIONS l
SECTION 3.6.1 - PRIh1ARY CONTAINh1ENT l
Y PROPOSED TECHNICAL SPECIFICATION STRUCTURE (CONTINUED) l
- 10. PRIOR TO STARTUP FROh! EACII REFUELING OUTAGE, TIIE BYPASS LEAKAGE PATIlWAY TOTAL AIUST BE VERIFIED TO BE j
WITIIIN LI511TS.
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- 11. AT NO TI51E DURING REACTOR OPERATION ARE AISIV AND i
BYPASS LEAKAGE RATES ALLOWED TO EXCEED TIIEIR l
RESPECTIVE LI511TS.
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IMPROVED TECIINICAL SPECIFICATIONS l
SECTION 3.6.1 - PRIMARY CONTAINMENT L
PROPOSED REVISION TO ITS - NUREGS
THE MAX 1 MUM ALLO WA BLE PRIMARl' CONTAINMENT LEAKA GE RA TE A T THE CALCULA TED PEAK A CCIDENTPRESSURE La
)
SHALL BE EXPRESSED IN TERMS OF WEIGHTPERCENTPER 24 HOURS. FOR lPLANTHATCH UNIT 2] LaISEQUAL TO fl.2wt
(
%'DA Y]. l THE VALUE OFLa DOESNOTINCLUDEMSIVOR SECONDA R Y CONTAINMENT B YPASS LEAKA GES.]
(
- 2. SR 3.6.1.1.1 (BWR & PWR)
DELETE THE SECOND PARAGRAPH.
>l
- 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."
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- 4. REOUIRED ACTION 3.6.1.2.C.1 (PWR - REOUTRED ACTION 3.6.2.C.1 )
MODIFY TO READ,"...OVERALL LEAKAGE RATE AGAINST La, USING CURRENT AIR LOCK TEST RESULTS."
- 5. SR 3.6.1.2.1 ( PWR - SR 3.6.2.1. NOTE 2)
MODIFY NOTE 2 TO READ,".. EVALUATED AGAINST La."
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-l IMPROVED TECIINICAL SPECIFICATIONS SECTION 3.6.1 - PRIMARY CONTAINMENT i
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PROPOSED REVISION TO ITS NUREGS -(CONTINUED)
- 6. LCO 3.6.1.3 (PWR - LCO 3.6.3. NOTE 4) 1 FOR BWR'S, MODIFY NOTE 4 UNDER ACTIONS TO READ,"...
PCIV LEAKAGE RESULTS IN EXCEEDING La. MSIV AND BYPASS
-l LEAKAGE RATES ARE NOT CONSIDERED PART OF La."
I FOR PWR'S, MODIFY NOTE 4 UNDER ACTIONS TO READ,
... ISOLATION VALVE LEAKAGE RESULTS IN EXCEEDING La."
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SR 3.6.1.3.12 (Bw R)
DELETE THE NOTE. CHANGE FREQUENCY TO READ,."
CONSISTENT WITH THE FREQUENCY SPECIFIED IN 10 CFR 50 APPENDLX J FOR TYPE C TESTS."
- 8. SR 3.6.1.3.13 (BWR)
DELETE THE NOTE.
- 9. SR 3.6.1.3.14 (BWR)
DELETE THE NOTE 2.
- 10. SR 3.6.3.7 (PWR)
DELETE THE NOTE.
DELETE THE NOTE.
10