ML18094B249

Forwards Rev to Attachment 1 of 891221 Revised Response to Generic Ltr 89-04 & Requests That 900115 Date Re Procedural Revs Be Extended to 900215 Due to Transfer of Inservice Insp Program & Upcoming NRC Insp on Stated Procedures

ML18094B249
Person / Time
Site:	Salem
Issue date:	01/11/1990
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-04, GL-89-4, NLR-N90011, NUDOCS 9001250331
Download: ML18094B249 (3)

Text

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Public Service Electric* and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operation~

JAN 11 1900 NLR-N90011 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REVISION TO ATTACHMENT 1 OF RESPONSE TO NRC GENERIC LETTER NO. 89-04 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) hereby submits a revision to Attachment 1 of our revised response to Generic Letter 89-04 dated December 21, 1989 (ref: NLR-N89240). Position 5 on page 2 of Attachment 1 states "Any procedural revisions brought about by design value changes or by the addition/deletion of any valves will be incorporated by January 15, 1990 (which corresponds to the current test frequency)". We request that the January 15, 1990 date be changed to read February 15, 1990. All appropriate procedures have been revised; however, since they must be technically reviewed by the Operations Department and approved by the Station Operations Review Committee (SORC) it is felt that the February 15, 1990 dated is more appropriate.

The need for this additional extension request is two-fold; a) the In-Service Inspection program is in the process of being transferred to the Salem Technical Department from In-Service Testing Group and b) the upcoming NRC inspection on Salem Emergency Operating Procedures (EOPs) which has delayed the required operations review.

Should you have any questions with regard to this submittal, we will be pleased to discuss them with you.

Sincerely, 4;t:J6~

Attachment r - - - - - * - ~----

9001250331 900111 PDR ADOCK 05000272 H * ".

P **** -***PDC

Document Control Desk 2 NLR-N9011 JAN __t 1 199) c Mr. J. c. stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

ATIACHMENT 1 NLR-N-~0011

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P9*it1on t

• PRESSUIE !SOLATIOW VALVE TESTIJG 2 The prea1ur1 i1olatton valves (P!V'!} at Salem Generating Station ~nits ar&

idtntititd in each plant's Teehnical Specit1cation1 CTSl along w1th their maximum allowable leakage. Tae rsT Pr09ra* w1s revitved to ensure that all of these v1lve1, ind their a11ociated allowable ltak19e values, are included in tts scope. Additionally, the test proceduret tor these valvea vere reviewed to ataure that t~* valves were beinq individually tested 11 required.

Pg1itiog S - LIMITING VALUES OF fULL*STIQCE TIMES FOl PQJIR OPE&lTED VALVES Tbt Code intent. with re1pect to measurinq the !ull*ttroke times of power operated v1lv11 i* to detect valve degradation. PSE*G's S&ltM Gtn1ratin9 Station preaently coaplie1 fully with ASME Stction XI, sub1ection IWV, re~ard1nq limitin9 stroke time values tor pover operated v1lve1 and required corrective action1. Presently, if the stroke time increaaes by the code *P*eified amount f rOlll the previous stroke time, the t11t frequency is incrta1ed to once per month (if the testinq in that operatinq mode i i po11i~le> until corrective action can b* taken. At Salem Station, the 4.0.5(Vl - 'aintenance Procedure controls the monthly testinq requiremtnts and issuance of vork requests tor corrective actions.

Because, u the Generic Letter states, "The code does not provide any

• requirements or 9u1del1nes tor establishinq the1e limit* nor dot* it identity the relationship that sbould exist between these limits and any limits identified for th* relevant valves in the plant TS or safety analysia, we na~e reviewed the licensin9 and/or desi9n bases for each power operated valve 1n cur proqram and taken the followin9 position:

ll All valves have been reviewed and provided ~ith a Rdeai~ ba1i1 or licensing value" for declaring valve operability {sources ire T!chn1~al Specifications, VFSAR. Manu.tacturer, NSSS v~ndor. etc.}.

2} The standard code requirtmtnt1 of IWV-34ll(a) and IWV-3417(b) will continue to be followed by comparing previous valve stroke times Wl~h present stroke time and taking tht appropriate actions.

Jl PSE'G continu11 to follow industry efforts and is pre11~tly revie~tnq our 4.0.S (V) Pr0Qram1 tor chanqes that w111 enhance our trending cap1bil1t1es tor power operated v1lvt1.

In summary, tor ucb power Ol)trated valve in our proc;ram, a 411i;D valu.e" t :c '

determinin; operability ha* bt*n e1tablishtd and if that value i* exceeded ~hac valve or its associated system will ~t declared inoperable in accordance *i~!.

tne rechnical Specifications. Any procedural revisions brouqht about by desLqn value chanqes or by the addition/deletion ot any valves will be incorporate~ b1

,: peI5rua 1~yl5, 1990 ., (vbicb. corresponds to the curr11nt test t requeney).

I 8a1td upon their r*view of our current 4.0.S CV> Proqram techniQUtl, an rsT ~3SK

• t*a* (coapriaed of a Central Preventative Maintenance Group and ftchnical Department personnel from*each station> vill detail improvement* in IST tesrlnq, trendin9 and trackinq by Karen 31. 1990. Th*** improvements vill be implemented in accordance with exi1tinq Rtliability Centered Maintenance m1thodolo9y.