ML18031A741

Forwards Addl Info Re Generic Ltr 83-28,Items 3.1.1, 3.1.2,3.1.3,3.2.1,3.2.2 & 3.2.3,including Review of Test & Maint Procedures & Tech Specs & Check of Vendor & Engineering Recommendations for Testing & Maint

ML18031A741
Person / Time
Site:	Browns Ferry
Issue date:	08/28/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Muller D Office of Nuclear Reactor Regulation
References
GL-83-28, TAC-52901, TAC-52902, TAC-52903, TAC-53737, TAC-53738, TAC-53739, TAC-53964, TAC-53965, TAC-53966, NUDOCS 8609030305
Download: ML18031A741 (6)

Text

1 REQUL 3RY INFORNATION DISTRIBUTE, SYSTEN (RIDS)

ACCESSION NBR: 8609030305 DOC. DATE: 86/08/2$ NOTARIZED: NO DOCKET FACIL: 50-259 Brogans Ferry Nucleav'ouer Station> Unit 1> Tennessee 05000259 50-260 Brogans FerrM Nucleav'ommer Station> Unit 2> Tennessee 05000260 50-296 Brogans Fev v g Nuclear Pouer Station. Unit 3> Tennessee 05000296 AUTH. NAIVE AUTHOR AFFILIATION QRlDLEY, R. Tennessee Valley Authov itg RECIP. NAi'lE RECIPIENT AFFILIATION NULLER> D. R. BWR Pv object Div ectov ate 2

SUBJECT:

Fov wards addi inFo v e Qeneric Ltv 83-28> Items 3- i. 1>

3. i. 2> 3. i. 3> 3. 2. 1> 3. 2. 2 5 3. 2. 3> including review og test maint pv oceduv es 8< Tech Specs 5 check of vendor h engineev ing v ecommendations Nor testing 8c maint.

DISTRIBUTION CODE: A055D COPIES RECEIVED: LTR ENCL SI ZE:

TITLE: OR/Licensing Submittal: Salem ATWS Events QL-83-28 NOTES: NNSS/FCAF icy. NNSS/FCAF/PN icy. OIA icy. QROTENUIS> l1 icy.

1 cg. NNSS/FCAF/PN 1 c g. OIA 1 c g. QROTENHUIS> tj 1 cg. 05000260 05000259'NSS/FCAF NNSS/FCAF 1 c g. Nl ASS/FCAF/PN 1 c g. 0 IA 1 c g. QROTENHUIS, 5 1 c g. 05000296 REC IP IENT COPIES RECIPIENT C OP IES ID CODE/NANE LTTR ENCL ID CODE/MANE LTTR ENCL BWR ADTS 1 BWR EB 1 BWR EICSB 2 2 BWR FOB BWR PD2 LA 0 BWR PD2 PD 01 3 3 CLARK> R 1 BWR PSB 1 i BWR RSB 1 1 INTERNAL: ACRS 6 6 *DN/LFNB ELD/HDS4 0 IE/DI IE/DGAVT NRR LASHER> D NRR PWR-A ADTS 1 1 NRR PWR-B ADTS NRR D /RSIB 1 NRR /TANB F 04 RQN2 EXTERNAL: LPDR 03 NRC PDR 02 NSIC 05 TOTAL NUNBER OF COPIES REQUIRED: LTTR 36 ENCL 33

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place AUG 28 886 Director of Nuclear Reactor Regulation Attention: Mr. D. R. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Muller:

In the Matter of the Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 As requested by letters from D. R. Muller to S. A, White dated April 14, 1986, and Marshall Grotenhuis to 'S. A. White dated April 28, 1986, we are submitting the enclosed information regarding Generic Letter'3-28 for Browns Ferry Nuclear Plant. The above letters xequested additional information on Items 3.1.1, 3.1.2, 3.1.3, 3.2.1, 3.2.2, and 3.2.3 as contained in TVA letters dated November 7, 1983 and March 15, 1984. Programs are currently being developed which are intended to resolve Items 3.2.1 and 3.2.2. Therefore, responses to questions regarding these items will be provided when those progxams are finalized. This additional information will be provided by December 1, 1986.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, D'ctor Nuclear Safet and Licensing Enclosure cc (Enclosure):

Mr. R. J. Clark U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue Bethseda, Maryland 20814 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Q828 P<QQQQPS p>QQPP59 P

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Enclosure Request For Additional Information ITEM 3.1.1 Review of Test and Maintenance Procedures and Technical Specifications (Reactor Trip System Components).

Submit an unambiguous statement confirming that post maintenance test procedures were reviewed to ensure that the testing adequately verifies component capability to perform all safety functions.

R~es onse Post maintenance testing is accomplished for safety-related equipment by one or more of the following:

1. Testing specified by a standing maintenance procedure

2. Performance of appropriate surveillance testing on the affected system

3. Additional testing specified in a Maintenance Request (MR)

For the Reactor Protection System, the maintenance procedures and Surveillance Instructions are currently being reviewed. One aspect of the review is to ensure that post-maintenance testing adequately demonstrates that the equipment is capable of performing its intended safety function. This effort will be completed before restart of any unit. Unique testing requirements for MRs are written for specific maintenance tasks and are, therefore, outside the scope of this review.

ITEM 3.1.2 Check of Vendor and Engineering Recommendations for Testing and Maintenance (Reactor Trip System Components).

provide a statement confirming that the requirements of Action Item 3.1.2 have been completed. If not, submit a schedule for when this review will be completed.

R~es ense Browns Ferry is currently implementing a program establishing controlled vendor information for the Reactor Protection System. This vendor information will be reviewed to ensure that appropriate test guidance is reflected in plant procedures. This effort will be completed before restart of any unit.

ITEM 3.l.3 Post Maintenance Testing Requirements in Technical Specifications (Reactor Trip System Components)

Please state that TVA has searched their technical specifications Eor post maintenance test requirements that may degrade safety as requested by the generic letter. Also, state whether any were found. If none were found, then a clear statement to that effect is requested. If such requirements are found, proposed technical specifications changes should be submitted to resolve the degrading condition together with supporting justification. This item applies only to Reactor Trip Components.

R~es onse The Browns Ferry technical specifications for units l, 2, and 3 have been searched for post-maintenance test requirements. The review did not reveal any post-maintenance testing requirements which were determined to degrade safety of the Reactor Protection System Components.

ITEM 3.2.3 Post Maintenance Test Requirements in Technical Specifications (all other Safety Related Components)

Please state that TVA has searched their technical specifications Eor post maintenance test requirements that may degrade safety as requested by the generic letter. Also, state whether any were found. If none were found, then a clear statement to that effect is requested. If such requirements are Eound, proposed technical specifications changes should be submitted to resolve the degrading condition together with supporting justification. This item applies only to all other safety related components.

~Res ense The review of technical specifications described in response to Item 3.1.3 above did not reveal any post maintenance testing requirements which were determined to degrade safety of the affected systems.

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