ML20211D198

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Review of Seabrook PRA, Monthly Mgt Ltr 13 for May 1985
ML20211D198
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 06/27/1985
From: Cummings G, Ariuska Garcia
LAWRENCE LIVERMORE NATIONAL LABORATORY
To: Davis S
Office of Nuclear Reactor Regulation
Shared Package
ML20209C800 List:
References
CON-FIN-A-0801, CON-FIN-A-801, FOIA-87-6 RARE-85-114, NUDOCS 8702200351
Download: ML20211D198 (5)


Text

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Lawrence Livermore National Laboratory NUCLEAR SYSTEMS SAFETY PROGRAM RARE 85-114 June 27, 1985 Ms. Sarah M. Davis Reliability and Risk Assessment Branch Division of Safety Technology U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Monthly Management Letter #13 Month of May 1985 NRC FIN-A0801 Review of the Seabrook Probabilistic Risk Assessment q

Dear Ms. Davis:

I

1. Project Description and Objective The Office of Nuclear Reactor Regulation is conducting a probabilistic risk assessment (PRA) review program in which PRAs performed and submitted to the NRC by license applicants and licensees receive comprehensive review and evaluation. The program is the responsibility of the Reliability and Risk Assessment Branch (RRAB).

A PRA of the Seabrook Nuclear Power Plant (Seabrook PRA) has been submitted to the NRC by Public Service Company of New Hampshire, an operating license (OL) applicant. The review of this document, whose title is "Seabrook Station Probabilistic Safety Assessment," is being performed as one project in the larger NRC program.

The objective of this project is to perform an expeditious and cost effective review of those aspects of the Seabrook PRA leading to the estimates of the frequencies of each plant damage state and the associated uncertainty spread to determine the accuracy of these estimates. The review will cover method-ology, assumptions, data, information sources, models, plant understanding, completeness of the analysis and other areas where inconsistencies may arise which could affect the quantitative or qualitative results.

2. Progress for Period None. fC3N-Sl*CCb ,
3. Work to be Accomplished Next Month h.5'c None.

8702200351 PDR FOIA 870211 SHOLLYB7-6 ppg i An Eaua'Conort.nt> Ew Lnety ot Cat *0rrha e PO Bos 606 Lmmere Cattma 94550

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e RARE 85-114 June 27, 1985 h

4. List of Subcontractors and Consultants
a. Subcontractors (1) Applied Risk Technology Corporation (ARTECH); P. J. Amico (2) Jack R. Benjamin and Associates, Inc. (JBA); J. W. Reed, M. W.

McCann, Jr.

b. Consultants (1) P. R. Davis
5. Concerns None.
6. Other None.

Abel A. Garcia Principal Investigator l ,' ,.-

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Garth E. Cummings Program Leader /

Nuclear Systems Safety Program sr jlp i

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't. RARE 85-114 June 27, 1985 Enclosures (2)

Distribution:

NRC DOE LLNL R. Frahm, DST W. J. Gallagher G. E. Cuaunings J. Halvorsen, DST J. M. Johnson F. Rowsome, DST C. A. Meier L. Solander, NRR A. C. Thadani, DST

RARE 85-lle June 27, 1985 t

ATTACHMENT A ESTIMATED PROJECT FINANCIAL STATUSs* May-85 (Figures given in thousands. )

FIN A0801 Summary Cost Analysis 8* May-85 Year to Date

! Direct Staff Effort (FTE's ) 0.0 1.3 **

!! Direct Labor Costs 0.0 43.0 Material & Services 0.0 1.7 ADP Support 0.0 0.0 Subcontracts 0.8 56.5 Travel Expenses 0.0 2.4 Indirect Labor Costs 0.0 43.5 Other ( Recharge ) 0.0 4.5 Other (FY84 Unbilled Costs) 0.0 0.0 General & Administrative 0.0 21.1 Total Costs 0.8 172.7 Liens 28.9 28.9 Total Costs & Liens 29.7 201.6 Percentage of Available Funds 117.3%

III Funding Status Prior Year FY 1985 Projected FY 1985 Funds FY 1985 Funding Carryover Funding Level Rec'd to Date Ba1. Needed 121.9 261.9 50.0 90.0

  • Notes These figures are for cost analysis only, and may differ slightly from final billing figures.

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RARE 85-114 June 27, 1985 ATTACHMENT B 4

FEE RECOVERY COST STATUS FIN: A0801 TITLE: Review of the Probabilistic Risk Assessment for the Seabrook Nuclear Power Plant PERIOD: May 1985 Docket Costs Facility Name Number Period Cumulative Seabrook 50-443 $ 0.8K $201.6K Common Costs 50-900 $ 0.0 0.0 Total Expenses S 0.8K $201.6K l

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b .

SEABROOK STATION Engineering Office Put2c Service of New HampsNro July 12, 1985 Now Hompshire Yonkee Dhielen SBN-842 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensi..g

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter, dated May 18, 1984, *$eabrook Station Probabilistic Risk Assessment," J. DeVincentis to G. W. Knighton (c) PSNH Letter, dated October 17, 1984, "Seabrook Station Probabilistic Safety Assessment (SSPSA)," J. DeVincentis to G. W. Knighton (d) USNRC Letter, dated April 4,1985, "Seabrook PRA Review,"

G. W. Knighton to R. J. Harrison (e) PSNH Letter, dated May 29, 1985, "Seabrook Station Technical Specification improvement Program,"

J. DeVincentis to G. W. Knighton

Subject:

Seabrook Station Probablistic Safety Assessment (SSPSA)

Dear Sir:

In our letters [ References (b) and (c)], we indicated to you our position regarding further support of the "Seabrook Station Probabilistic Safety Assessment (SSPSA)." Due to financial constraints put on the Project over the last year, we had reluctantly terminated our contract with our consultant and were only able to provide minimal support to the NRC in its review of the SSPSA. Subsequently you responded via Reference (d) in which you and the staff determined that the review of our SSPSA would be terminated and a draf t review report was provided therein.

We agree with the conclusion of your review which did not identify any safety issues which serit immediate action or errors which could significantly change the quantitative results of our SSPSA. Additionally, we have reviewed in detail those concerns which were identified in the Lawrence Livermore

  • Laboratories (LLNL) draft review report and believe those concerns could i

easily be addressed with closer interaction among the technical staffs involved. Such interaction would lead to a final review report which would show a greater appreciation of our SSPSA.

f%:t- 27-tc4 P.O Box 300 Seobrook.NHO3874

  • TeWhone(603) A74 9521
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f e United States Nuclear Regulatory Commission Attention: Mr. George W. Knighton Page 2 Though it is understood that a Probabilistic Safety Analysis (PSA) is not a licensing requirement, we recognize the, significance and usefulness of a completed PSA. We intend to support the completion of the NRC SSPSA review. We feel that supporting the completion of the review will supply both us and the NRC with a set of technical tools that will aid in evaluating activities and modifications which provide plant enhancements aimed at improving safety.

 -                               As noted in Reference (e), we are presently evaluating various improvements in the Technical Specifications area which will be contingent upon risk analysis and engineering judgment. A successful attempt to improve Technical Specifications using risk analysis would be sided by an effective PSA review. Therefore, we have initiated those efforts needed to support the continuation of the SSPSA review.

Based on our preliminary review of the LLNL report and our efforts to make improvements to Technical Specifications, we have recently contracted with our PSA consultants to continue the support of the SSPSA. We would like to meet specifically with your staff to discuss completion of the SSPSA review. Our goal is to support the schedules of activities which could realize the benefits of a completed PSA. We believe Laat with such a meeting, we can begin the resolution of the LLNL draf t review report concerns and establish the schedules and action items necessary for supporting the completion of the SSPSA review. It would be most appreciated if you would inform us as to when we could meet. We would be most amenable to meet with you in July or early August. Should you have any questions regarding this issue, please do not hesitate to contact us. Ve,ry truly yours,

                                                                                                                                             /               S John DeVincentis, Director Engineering and Licensing cc: ASLB Service List l

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William S. Jordan, 111 Donald E. Chick Town Manager Diane Curran Hamon, Weiss & Jordan Town of Exeter 20001 S. Street, N.W. 10 Front Street Suite 430 Exeter, NH 03833 Washington, D.C. 20009 Brentwood Board'of Selectmen Robert G. Per11a RED Dalton Road Office of the Executive Legal Director Brentwood, NH 03833 U.S. Nuclear Regulatory Commission Richard E. Sullivan, Mayor Washington, DC 20555 City Hall Robert A. Backus, Esquire Newburyport, MA 01950 116 Lowell Street Calvin A. Canney P.O. Box 516 Manchester, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Augusta, NE 04333 Dana Bisbee, Esquire Assistant Attorney General 2 Mr. John B. Tanzer Office of the Attorney General Designated Representative of the Town of Hampton 206 State House Annex 5 Morningside Drive Concord, NH 03301 Hampton, NH 03842 Anne Verge, Chairperson Roberta C. Fevear Board of Selectmen ' Designated Representative of Town Hall the Town of Hampton Falls South Hampton, NH 03827 Drinkwater Road Hampton Falls, NH 03844 Patrick J. McKeon Selectmen's Office Mrs. Sandra Gavutis 10 Central Road Designated Representative of Rye, NH 03870 the Town of Kensington Carole F. Kagan, Esquire RFD 1 Atomic Safety and Licensing Board Panel East Kingston, NH 03827 U.S. Nuclear Regulatory Commission i Jo Ann Shotwell, Esquire Washington, DC 20555 Assistant Attorney General Mr. Angi Machiros Environmental Protection Bureau Chairman of the Board of Selectmen Department of the Attorney General Town of Newbury . One Ashburton Place, 19th Floor Boston, MA 02108 Newbury, MA 01950 Senator Gordon J. Humphrey Town Manager's Office Town Hall - Friend Street U.S. Senate Amesbury, MA 01913 Washington, DC 20510 (ATTN: Tom Burack) Senator Gordon J. Humphrey 1 Pillsbury Street Diana P. Randall Concord, NH 03301 70 Collins Street (ATTN: Herb Boynton) Seabrook, NH 03874

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