ML20149M404
| ML20149M404 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/12/1996 |
| From: | Quay T NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9612160350 | |
| Download: ML20149M404 (4) | |
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UNITED STATES 1
NUCLEAR REGULATORY COMMISSION
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f WASHINGTON, D.C. 206e64001 December 12, 1996
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Mr. Nicholas J. Liparulo, Manager i
Nuclear Safety and Regulatory Activities
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Nuclear and Advanced Technology Division Westinghouse Electric Corporation i
P. O. Box 355 1
Pittsburgh, Pennsylvania 15230
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON WESTINGHOUSE A SPECIFICATIONS OPTIMIZATION METHODOLOGY
REFERENCE:
LETTER, N. J. LIPARULO TO T. R. QUAY, " WESTINGHOUSE AP600 l
TECHNICAL SPECIFICATIONS APPROACH, ATTACHMENT 1 DATED j
MAY 3, 1996" l
Dear Mr. Liparulo:
l Based on our review of the optimization methodology, we found that, while
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conceptually your approaches appear adequate your submittal lacks the detailed justification discussions necessary,for the NRC staff to review and i
approve the proposed approaches.
Discussed below are examples of the types of i
additional information we will require in order to be able to adequately j
review your proposals.
i 630.11. A detailed discussion needs to be proposed about how from a 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
" anchor point" for the Completion Time Logic of Figure 1, the four other possible outcomes were selected. That discussion shculd address specifically j
i how repair times where arrived at, how uncertainties in such judgements were 4
accounted for, how and why thermal-hydraulic criteria varied from the prece-l dents of the STS, specifically how PRA was used to justify the selection of longer completion times and where that was done, and finally a discussion of the differences between the " conservative" and " realistic" analysis referred
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to in the Notes to Figure 1.
I 630.12. A detailed discussion needs to be provided about how 31 days was I
i established as the " baseline" for surveillance frequency and what constitutes a " baseline chance". The discussion should provide justification for the other three possible outcomes on the upper branch of Figure 2, as well as an answer to the question in our "NSD-NRC-96-4739, Forwards Draft Mark Up of Chapter 54 of AP600 Probabilistic Risk Assessment (PRA) Covering Low Power & Shutdown PRA Assessment.Pra Section Revised to Incorporate Commitments [[Manufacturer" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Made in Response to RAIs|June 6, 1996 letter]] concerning the appropriate-i ness of only having a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency outcome for the lower branch of Figure 2.
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630.13. The discussion of the sections labeled "Probabilistic Risk Assess-l ment-AP600 Baseline" and "Probabilistic Risk Assessment-AP600 Importance Ranking" can only be fully evaluated by the staff after the submittal of the response to RAI 630.10 (which the first section implies has been made, when in
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fact, it has not been) and the finalization of the PRA Final Report. There-i fore, those submittals need to be made and the response to the RAI should l
NRC ytf CENTER COM o9 180083 gh
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9612160350 961212 PDR ADOCK 05200003 A
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Mr. Nicholas J. Liparulo December 12, 1996 1
include not only the original information requested but also, as discussed in 1
our November 20, 1996 meeting, a discussion of how PRA information was used in the TS and on what basis its use was justified.
630.14. There are a number of differences between Table 1 and the AP600 TS l
Rev. 2 that need to be explained as does the difference between the MODE 4 time of Table 2 and that of the STS.
The above comments are fully consistent with the conclusion we reached in our "NSD-NRC-96-4739, Forwards Draft Mark Up of Chapter 54 of AP600 Probabilistic Risk Assessment (PRA) Covering Low Power & Shutdown PRA Assessment.Pra Section Revised to Incorporate Commitments [[Manufacturer" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Made in Response to RAIs|June 6, 1996 letter]].
In that letter, we stated that "we cannot conclude on 1
the methodology because of the degree of subjectivity involved." We hope that these additional comments will help clarify our concerns about the subjectivi-ty of the proposals and result in a prompt and complete response.
If you have any questions, please contact Bill Huffman at (301) 415-1141.
i Sincerely, i
original signed by: Jerry N. Wilson Theodore R. Quay, Director Standardization Project Directorute Division of Reactor Program Management Office of Nuclear Reactor Regulation 4
Docket No.52-003 cc:
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OFFICIAL RECORD COPY
Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.
P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. John C. Butler Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy "ockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.
NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 1
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Letter to Mr. Nicholas J. Liparulo. Date: December 12. 1996 Docket: File PUBLIC i
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