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MONTHYEARML18031A4941986-06-17017 June 1986
Requests TVA PRA & Critical Analysis of Strengths & Weaknesses of Pra,For Current Evaluation & as Condition for Restart
Project stage: Other
ML18031A6081986-07-21021 July 1986
Responds to 860617 Request for Formal Submittal of Documentation Re Facility Risk Assessment Performed by Util. Study Currently in Draft Stage & Will Be Forwarded Once Updated.Summary Rept Will Be Provided by Sept 1986
Project stage: Draft Request
ML18031A7021986-08-15015 August 1986
Discusses Importance of TVA-sponsored Draft PRA as Condition for Restart of Plants.Util Commitment to Provide Plan for Review of PRA & to Conduct Addl Analysis by 860930 Confirmed,Per 860731 Meeting.Copy of Draft PRA Requested
ML18031A7401986-08-28028 August 1986
Notification of 860904 Meeting W/Util in Bethesda,Md to Discuss Pending & Projected Licensing Actions Involving NRR
Project stage: Request
ML18031B0261986-11-17017 November 1986
Responds to Summarizing Results of 860731 Meeting Re PRA & Request for Documentation Concerning Util Risk Assessment of Facility.Preliminary Draft PRA Document Will Be Forwarded Under Separate Cover.Other Commitments Listed
ML20214G6491986-11-20020 November 1986
Forwards Vols 1-7 to Browns Ferry Nuclear Plant Unit 1 Pra. PRA Unsuitable for Docketing as Part of Official Record Due to Incomplete & Unreviewed Status of Document
Project stage: Other
ML18031B2151987-02-25025 February 1987
Comments on 870130 Discussions W/C Fox & W Lau Re General Status of Facility PRA Review & Agrees Proposal for Risk Based Critical & Priority Component List Agreeable Method to Expedite Program Needed for Timely Restart of Unit 2
Project stage: Other
ML18032A3631987-06-0909 June 1987
Responds to RM Bernero Re Plant Pra.Util Agrees That Bases of PRA Analyses Suspect Until Verification of Sys Configuration Complete.Util in Process of Finalizing as-configured Drawings at Plant
Project stage: Other
ML18032A5811987-10-0101 October 1987
Forwards NRC Comments on Core Damage Accident Analysis Portion of Plant PRA for Consideration in Preparation for Any Revised PRA or Individual Plant Evaluation to Be Submitted for NRC Review
Project stage: Other
ML20154D0491988-05-11011 May 1988
Advises That Meeting W/Util Scheduled for 880518 to Discuss NRC ,Including Scope of Needed Responses to Tables 1,2 & 3 of Subj Ltr & Required Scehdule for Responses to Support Unit 2 Restart Schedule
Project stage: Meeting
ML20155B0711988-05-27027 May 1988
Summary of 880518 Meeting W/Tva Re Resolution of Restart Item Identified as Plant Pra.List of Attendees & Slides Encl
Project stage: Meeting
ML20196K7671988-06-28028 June 1988
Confirms Actions Agreed to During 880518 Meeting W/Nrc Re Pra.Util Will Provide Summary Document to NRC by 880830, Including Rationale for Concluding That Revised PRA Will Conservatively Reflect Configuration of Unit 2 at Restart
Project stage: Meeting
ML20155F6091988-10-0707 October 1988
Advises That NRC Will Perform Audit of PRA During 881101-02. Objective & Scope of Audit Discussed in Encl
Project stage: Other
ML18033A6891989-03-29029 March 1989
Forwards Request for Addl Info Based Upon NRC Audit of Plant Pra,Section III.11.0 Re Core Melt Frequency for Plant When Compared to Similar Plants of Similar Vintage.Potential Single Failure Vulnerability Noted
Project stage: RAI
ML20245A3221989-06-15015 June 1989
Forwards Response to PRA Audit on 881101-02
Project stage: Other
ML20247K0161989-07-26026 July 1989
Documents Closure of PRA Commitments in Rev 2,Section III.11.0 of Plant Nuclear Performance Plan & PRA Actions Required for Restart.Util Will Address plant-specific Accident Vulnerabilities Per Generic Ltr 88-20
Project stage: Other
ML18033B3271990-05-24024 May 1990
Forwards Info to Resolve Restart PRA Commitments,Per NUREG-1232 (SER on Nuclear Performance Plan).Util Will Confirm Adequacy of RHR Pump W/Rhr Motor Cooler Unavailable to Meet short-term Pump Combination Requirements
Project stage: Other
1987-06-09
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REGULATORY FORMATION DISTRIBUTION B EM (RIDB)
ACCESSION NBR: 87061604'P2 DOC. DATE: 87/06/09 NOTARIZED:
NO FACIL: 50-259 Broens Ferry Nuclear Poeer Stationi Unit 1i Tennessee 50-260 Broujns Ferry Nuclear PouJer Stationi Unit 2i Tennessee 50-2'P6 Broujns Ferry Nuclear Poeer Stations Unit 3I Tennessee AUTH. NAME AUTHOR AFFILIATION WHITEI S. A.
Tennessee Valley Authority REC IP. NAME RECIPIENT AFFlLIATION Document Control Branch (Document Control Desk)
DOCKET 0 05000259 05000260 05000276
SUBJECT:
Responds to RM Bernero 870225 ltr re plant plant PRA. Util agress that bases of PRA analyses suspect until verification of sos configuration complete. Util in process of finali zing "as-configured" draeings at plant.
DISTRIBUTION CODE:
D0300 COPIES RECEIVED: LTR Q ENCL Q SIZE:
TITLE:
TVA Facilities Routine Correspondence NOTES: Zeolinski 5 cg.
1 cg ea to: Axelradi Ebneteri S. Richardsoni Liauji G. Zechi OII OIA.
Zeolinski 5 cg. 1cg ea to: Axelradi Ebneteri S. Richardsoni Liauji G. Zechi OII OIA.
Zeolinski 5 cg. 1cg ea to: Axelradi Ebneteri S.
Richardson'iaei G. Zechi Oli OIA.
05000259 05000260 05000296 REC IP lENT ID CODE/NAME JAMERSONs C GEARS' COP IES LTTR ENCL REC IP IENT ID CODE/NAME PD STANGs J COPIES LTTR ENCL INTERNAL: ACRS EG FILE ADM/LFMB OQC/HDS2 EXTERNAL:
LPDR NSIC NRC PDR NOTES:
TOTAL NUMBER QF COPIES REQUIRED:
LTTR 24 ENCL
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 6N 38A Lookout Place June 9, 1987 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) PROBABILISTIC RISK ASSESSMENT (PRA)
This letter is in response to the letter from Robert M. Bernero to me dated February 25, 1987, concerning the BFN PRA.
As you requested, three copies of the October 1986 version of the BFN PRA will be sent to you under separate cover.
TVA agrees that the bases of the PRA analyses are suspect until the verification of the BFN system configuration is completed.
He are now starting to finalize "as-configured" drawings at BFN.
Once the Design Baseline and Verification Program progresses to the point that the reliability sensitive configuration is well understood, TVA will apply the IDCOR Individual Plan Evaluation Methodology to BFN unit 2 before restart as previously committed.
TVA will, as a post-restart commitment, perform a full scope PRA.
A schedule for the full PRA update will be provided before unit 2 restart.
Please refer any questions to C.
H. Fox, Jr., of my staff.
Very truly yours, TENNESSEE VALLEY AUTHORITY cc:
See page 2
W. G.~Q~
S. A. White Manager of Nuclear Power 870blb0492 870b09 PDR ADDCK 05000259 P
PDR An Equal opportunity Employer gag s/y
l
U.S. Nuclear Regulatory Commission June 9,
1987 cc:
Mr. G.
G. Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U:S. Nuclear Regulatory Commission Region II 101 Marietta St.,
NH, Suite 2900 Atlanta, Georgia 30323 Mr. J.
A. Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S.
Nuclear Regulatory Commission 4350 East Hest Highway EWH 322
- Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 2, P.O.
Box 311
- Athens, Alabama 35611
I t
