ML20128E835
| ML20128E835 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 02/05/1993 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9302110099 | |
| Download: ML20128E835 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION h,8( ,t g
WA$HINoTON, D. C. 20$55 February 5, 1993 k.....
Docket No.52-001 APPLICANT: GE Nuclear Energy (GE)
PROJECT: Advanced Boiling Water Reactor (ABWR)
SUBJECT:
HEETING WITH GE ON JANUARY 20 AND 21, 1993, CONCERNING PROBABI-LISTIC RISK ASSESSMENT (PRA)
A public meeting was held on January 20 and 21,1993, between the U.S. Nuclear Regulatory Commission (NRC) staff and GE at the GE offices in San Jose, California. The meeting was originally noticed for one day but was extended to a second day to complete the required discussions. The purpose of this meeting was to discuss issues relatad to the ABWR PRA. Areas of discussion included PRA input into inspections, tests, analyses, and acceptance critoria (ITAAC), PRA insights, containment overpressure protection system (COPS),
capability of the emergency core cooling system (ECCS) pumps to pump saturated water, PRA-based seismic margin analysis, draft final safety evaluation report open and confirmatory issue resolution, and GE's submittal schedule.
A significant amount of time was spent on determining how to incorporate PRA insights into ITAAC. GE estimates that its first cut at a list of PRA-based insiahts will be available within a month. Each safety-related insight will include a basis. It was agreed that the insights will be located in a specific section in the standard safety analysis report (SSAR) to facilitate their use by the combined license (COL) applicant. GE will choose the Tier 1 ;
and Tier 2 level insights which will then be audited by NRC staff. The insights will address such areas as: (1) important assumptions in the PRA; (2) importance measures assigned to various structures, systems,. and compo-nents; (3) containment and suppression pool bypass;-(4) features identified in SECY-90-016, " Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements;" (5) containment performance goals assessment; (6) external events; (7) shutdown events; (8) discussions un core damage sequences including what keeps them low, where large uncertainties exist, and those sequences which, in extreme circumstances, could become an important contributor.
The staff questioned GE on what would happen if the volume space between the COPS rupture discs were to be pressurized prior to or during an accident. GE committed to provide an answer. In addition, the staff requested clarifica-tion on the capability of the ECCS pumps to pump saturated water. The staff's understanding of the GE response is that the ECCS pumps are capable of pumping saturated water at up to 350 F.
The staff and GE agreed upon the need for a COL applicant plant to submit a plant-specific PRA that incorporates design changes or improvements which affect the current PRA models. This would include the final heat sink design.
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February 5, 1993 GE also agreed to withdraw a submittal which provided an initial response to a December 22,199E, staff request for clarification of information contained in SSAR Section 19E.2.3.3 on " Suppression Pool Bypass Paths."
In order to ensure that all PRA questions are being addressed by GE, the staff agreed to resend all of them.
GE stated that the SSAR will be revised to state that penetrations bttween safety divisions containing both safety and non-safety equipment will be qualified to the same standards. This is a fire and flooding concern.
Original Signed By-Chester Poslusny, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
See next page DISTRIBUTIQN w/enclosurgi:
(Docket file ~ t PDST R/F PShea PDR CPoslusny BHuffman MJanus RBorchardt DISTRIBVTION w/o enc 1q1eres:
IMurley/FMiraglia DCrutchfield GKelly, 10E4 JNWilson GGrant, EDO EJordan, MNBB3701 ACRS (11) LShao, RES J0'Brien, RES BHardin, RES p 0FC: LA:PDST: DAR PE:PDST:ADAR PM: ST:ADAR SC: 6 iR NAME: PShea 7 ) MJanus:t CPoslusny JNWil so'n, DATE: 02// '3 02/f/9 02/j/93 02/g/93' 0FFICIAL RECORD COPY: MTSM1201.MJ 1
GE Nuclear Energy Docket No.52-001 I cc: Mr. Patrick W. Marriott, Manager Mr. Joseph Quirk Licensing & Consulting Services GE Nuclear Energy GE Nuclear Energy General Electric Company 175 Curtner Avenue 175 Curtner Avenue, Mail Code 782 San Jose, California 95125 San Jose, California 95125 Mr. Robert Mitchell General Electric Company 175 Curtner Avenue San Jose, California 95125 Mr. L. Gifford, Program Manager Regulatory Programs GE Nuclear Energy 12300 Twinbrook Parkway _.
Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs V. S. Environmental Protection Agency 401 M Street, S.W.
Washington, D.C. 20460 Mr. Daniel F. Giessing U. S. Department of Energy NE-42 ..
Washington, D.C. 20585 Mr. Steve Goldberg !
Budget Examiner 725 17th Street, N.W. l Room 8002 Washington, D.C. 20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 Washington, D.C. 20006 Marcus A. Rowden, Esq. f Fried, Frank, Harris, Shriver & Jacobson 1001 Pennsylvania Avenue, N.W.
Suite 800 Washington, D.C. 20004 Jay M. Gutierrez, Esq.
Newman & Holtzinger, P.C.
1615 L Street, N.W.
Suite 1000 Washington, D.C. 20036
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GE ABWR PRA MEETING JANUARY 20 and 21, 1993 MAMI ORGANIZATION
- G. Kelly NRR/ADT/SPSB' J. N. Wilson NRR/ADAR/PDST J. Duncan GE C. Buckholtz GE D. Knecht GE-J. Chambers GE T. Buhl GE B. Raftery GE G. Ehlert GE I
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. DECEMBER 9,1992 -
RESPONSE TO SPSB QUESTIONS ON THE ABWR PRA OCTOBER 5,1992 QUESTION:
PRA Requantification Based on the LOOP and SBO event tree (Figure 19D.4-4), the sequence involving LOOP, followed by successful scram and recovery of offsite power v,ithin 30 minutes, has a frequency of 5.79E 2/yr. - In GE's original PRA submittal, this -
sequence was transferred to the Reactor Shutdown event tree (Figure 19D.4-1). The staff has recommended that this sequence be transferred to the Isolation / Loss of FW event tree instead. In the revised submittal (May 21,1992), this sequence was neither transferred to
, the Reactor Shutdown tree nor the Isolation / Loss of FW tree. Please explain this discrepancy.
RESPONSEt In the May 21,1992 submittal, the sequence frequency of 5.79E 2/yr was inadvertently' omitted from the Figure 19D.41 event tree. The transfer was, however, accounted for in the calculation of core damage frequency. This graphic oversight has been corrected in Chapter 19 of the ABWR SSAR as shown on attached Figure 19D.4-1.
The basis for transferring this sequence to the Reactor Shutdown event tree was previously provided in response to Question 725.1 of the-initial NRC' request for additional information dated November 28,1989. ;
Enclosure 2
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