ML18033B335

Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability. Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issues Subj to Listed Conditions

ML18033B335
Person / Time
Site:	Browns Ferry
Issue date:	05/25/1990
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-83-28, NUDOCS 9006010139
Download: ML18033B335 (3)

Text

ACCELERATED DIRIBUTION DEMONS'IKTION SYSTEM~g ci 5 gV REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9006010139 DOC.DATE: 90/05/25 NOTARIZED:

NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH.NAME AUTHOR AFFILIATION WALLACE,E.G.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides basis for closure of Generic Ltr 83-28,Item 4.5.3,"Reactor Trip Sys Reliability." DISTRIBUTION CODE: A055D COPIES RECEIVED:LTR I ENCL 0 SIZE: TITLE: OR/Licensing Submittal:

Salem ATWS Events GL-83-28 NOTES:1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw, R.Pierson,B.Wilson D S 05000260/RECIPIENT ID CODE/NAME LA ROSS,T.INTERNAL: ACRS NRR/DLPQ/LPEB10 NRR/DST/SICB 7E OC G FILE 01 EXTERNAL: LPDR NSIC NOTES COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD NRR/DEST/ESB 8D NRR/DOEA/OGCBll NRR/DST/SPLB 8D OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL D D D NOTE TO ALL"RIDS" RECIPIENTS:

A 9'PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL TENNESSEE VALLEY AUTHORITY CHATTANOOGA.

TENNESSEE 37401 SN 157B Lookout Place MAY 25't%0 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket No.50-260 BROWNS FERRY NUCLEAR PLANT'(BFN)

UNIT 2-GENERIC LETTER 83-28, REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS;ITEM 4.5.3, REACTOR TRIP SYSTEM RELIABILITY (GSI.75, MPA B093)This letter is to provide the basis for closure of Generic Letter 83-28, Item 4.5.3, for BFN Unit 2.The staff has reviewed the General Electric Topical Reports NEDC-30844, BWR Owners'roup (BWROG)Response to NRC Generic Letter 83-28, Item 4.5.3, and NEDC-30851P, Technical Specifications Improvement Analysis for BWR Reactor Protection System, and on July 15, 1987 issued a favorable Safety Evaluation Report.The staff has concluded that the analyses presented in the BWROG reports are acceptable for resolving this.issue, subject to the conditions discussed below: Condition:

Confirm the applicability of the generic analysis to its plant.Response: Condition:

Response: Condition:

90060ioi39 PDR ADOCK P The generic analyses presented in NEDC-30851P are applicable to BFN.Demonstrate, by use of current drift information provided by the equipment vendor or plant-specific data, that the drift characteristics for instrumentation used in RPS channels in the plant are bounded by the assumption used in NEDC-30851P when the functional test interval is extended from monthly to quarterly.

BFN's Reactor Protection System (RPS)functional test and instrument calibration frequencies are specified in Tables 4.1.A and 4.1.B of the BFN TSs.No extensions to these intervals are proposed at this time.)or~l0 An Equal Opportunity Employer Confirm that the differences between the parts of the RPS that perform the trip functions in the plant and those of the base case plant were included in the analysis for its plant done using the procedures of Appendix K of NEDC-30851P (and the results presented in Enclosure 1 to letter OG5-491-12 from L.Rash (GE)to T.Collins (NRC)dated November 25, 1985), or present plant-specific analyses to demonstrate no appreciable change in RPS availability or public risk.900525 05000260 PDC U.S.Nuclear Regulatory Commission MAY RS 1880 Response: The procedure which was used by BFN to evaluate plant specific applicability is provided in Appendix K of NEDC-30851P.

A list of BFN RPS configuration data was compiled, differences between the BWR generic model and BFN's specific configuration were identified, and the effects on system reliability were evaluated.

Using this method, TVA verified the BWROG generic analysis bounds the BFN RPS.This review has been documented and is available for staff review.Based on the above, TVA considers Generic Letter 83-28, Item 4.5.3, complete for BFN Unit 2.TVA requested the Safety Issues Management System be updated to reflect TVA's completion.

TVA also requests the issuance of a Safety Evaluation Report documenting the closure of this item.There are no commitments contained in this letter.If you have any questions, please telephone Patrick P.Carier, Manager of Site Licensing, (205)729-3570.Very truly yours, TENNESSEE VALLEY AUTHORITY cc: Ms.S.C.Black, Assistant Director for Projects TVA Projects Division U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 E.G Wa la e, anager Nuclear Licensing and Regulatory Affairs Mr.B.A.Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S.Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323