ML20148J889
| ML20148J889 | |
| Person / Time | |
|---|---|
| Issue date: | 03/22/1988 |
| From: | Wohl M Office of Nuclear Reactor Regulation |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20148J894 | List: |
| References | |
| NUDOCS 8803300421 | |
| Download: ML20148J889 (3) | |
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%g UNITE D STATES NUdLEAR REGULATORY COMMISSION y-2 g
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MAR 2 21988 i
MEMORANDUM FOR:"
Edward J. Butcher, Chief Technical Specifications Branch, DOEA THRU:
Richard L. Emch, Section Chief Review and Assessment Section Technical Specifications Branch, 00EA FROM.
Millard L. Wohl, Reactor Engineer Special Projects Section Technical Specifications Branch, 00EA
SUBJECT:
SUMRaov 0F MEETING WITH WESTINGHOUSE, WOG, BNL ON REVIEW 0F WCAP-10271, SUPPLEMENT 2, REV. 1, "EVALUATION OF SURVEILLANCE FREQUENCIES AND OUT OF SERVICE TIMES FOR THE ENGINEERED: SAFETY FEATURES ACTUATION SYSTEM" On January ~ 13, 1988, OTSB met with representatives of Westinghouse, the Westing-house Owners Group and Brookhaven National Laboratory to discuss the review of W Topical Report WC/P-10271, Supplement 2, Revision 1 "Evaluation of Surveillance Frequencies (STIs) and Out of Service Times (A0Ts) for the Engineered Safety Features Actuation System" (ESFAS). The principal areas discussed were the use of average risk vs. conditional risk calculations, support state descriptions, extrapolability of Millstone-3 results to other
}l plants, and staggered testing. A summary of each of these issues follows:
Average Risk vs. Conditional Risk j
J. Boccio of BNL explained the importanca of conditional risk (risk with reconfiguration due to equipment outage).
This risk can be substantially higher than the average risk for short periods of time.. The WCAP-10271 analyses are based on average risk. A consensus was reached that average risk is a sufficient criterion for decision making on WCAP-10271 proposals for STI and A0T extensions.
Support State Descriptions It was decided that Vestinghouse would furnish data to BNL on support state system sequence unavailability and related Boolean equation parameters for the risk evaluation part of the ESFAS analyses. This has now been done, and BHL is making core damage frequency estimates using this data. BNL's Technical Evaluation Report for WCAP-10271, Supplement 2, Revision 1 will be completed and sent to the NRC by the end of March.
g p #y CONTACT: Millard Wohl x21181 b
8803300421 880322 PDR TOPRP EMVWEST C
a Edward J. Butcher.
Extrapolability o_f Millstone 3 Resul,ts to Other W Plants Westirghouse believes that the risk es':imates for Millstone-3 bound the risk associated with the proposed changes in ESFAS A0Ts and STIs' for other-W plants. This belief includes the fact that the Millstone-3 risk estinates are based on solid state logic while many W plants have relay logic in the ESFAS design.
Representatives from BNL an3 the staff questioned the implication (from W's belief) that the relay systems are more reliable than the solid state syitems. We agreed to evaluate the W contention further.
R. Fitzpatrick has'since informad us that Bhl expects to be abler. to resolve this issue by means of risk calculations.
Staggered Testing BNL was tasked to evaluate Westinghouse's contention that staggered testing is not needed for RPS or ESFAS.
BNL has determined, subsequent to the meeting, that staggered testing is not necessary for the ESFAS extended STIs and A0Ts.
BNL is now revaluating the requirements for staggered testing en (RPS) channels included in the staff's SER for WCAP-10271, Supplement 1. is an attendance list; Enclosure 2 is the meeting announcement.
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- ./Yhgg Millard L. Wohl, Reactor Engineer Special Projects Section Technical Specifications Brancn, DOEA
Enclosures:
As stated cc: w/encls:
C. E. Rossi Distribution OTSB r/f DOEA r/f PDR
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WDLanning RBarrett SNewberry Meeting Participants C:0h5 TSBL:0E :'RR TSB: DOE NRR OEA:NRR
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ENCLOSURE 1 NAME' ORGANIZATION PHONE N0.
Bob Howard Westinghouse-TSS 412-374-4159 Chuck Brockhoff Westinghouse-TSS 412-374-5724 Gregg A. Sinders Carolina Power & Light Co.
.919-362-3250 Mike Hitchler Westinghouse PRA 412-374-5831 Bryan Dolan Duke Power Company 704-373-2937 John L. Boccio Brookhaven Nat'l Lab.
516-282-7690 Terrence W. Simpkin Commonwealth Edison 815-458-2801 Kadir Aliefendioglu Brookhaven Nat'l Lab.
516-282-2435 George Bozoki Brookhaven Nat'l Lab.
516-282-7771 Bob Fitzpatrick Brookhaven Nat'l Lab.
516-282-7204 Robert Liner SAIC 703-821-4514 Daniel Gallagher SAIC 703-821-4751 Eve Fotopoulas SERCH Licensing, Bechtel 301-258-3094 Lynn Connor Doc-5earch Associates 301-229-6553 Ed Butcher NRC, Tech. Spec. Branch 301-492-1183 Gerald Andre Westinghouse PRA 412-374-4095 Millard Wohl NRC, OTSB 301-492-1181 P
Rich Emch NRC, OTSB 301-492-1186 Ed Chow NRC, PRAB 301-492-1077 Bob Borsum B&W-Rockville 201-230-2100 Kevin Curley NYPA, Indian Pt-3 914-681-6867 Dick Robinson NRC/RES 301-492-3915 J
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