ML20195G886

SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Reactor Trip Sys Components

ML20195G886
Person / Time
Site:	River Bend
Issue date:	11/18/1988
From:	NRC
To:
Shared Package
ML20155E375	List: ML20155E371 ML20195G878 ML20195G886 ML20196A661
References
GL-83-28, NUDOCS 8811300105
Download: ML20195G886 (2)

Text

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. UNITED STATES 3 , k/( ,i NUCLEAR REGULATORY COMMISSION

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E,N_ CLOSURE 1 UNIT 1 RIV29DOCM BEND STATION,k Tlib7 bb- W~ -

SAFEWilAll'AllDfikEPORT FOR GENERIC LETTI F BY-P Q ,TIl @ l,Q A,R,T,1) -

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1.0 INTRODUCTION

On February 25, 19P?, beth of the scrara circuit breakers at Unit 1 of the Salem i:uclear Power Plant failed to open upon an sutomat.it reactor trip signal fror. the reactor protection systeri. This incident was terrninated convally by the operator obcut 30 seccnds af ter the initiation of the automatic trip sigra1. The failure cf the circuit breakers was determined to be related to .

tte stic6irig of the undervoltage trip attachment. Prior to this incident, on  !

February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an autor.atic l trip signal was str.erated based on steam generator low-low level during plant startup. In this case, the reactor was tripped nanually by the operator,alrost coincidentally with the autoniatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (E00), directed the staff te investigate end report on the generic -

irplications of these occurrences at l' nit 1 of the Salem Nuclear Power Plant. i The result of the staff's inquiry into the generic irplications of the Salem.

Ur.it 1 it.cidents are reperted in NL' REG-1000. "Generic Implications of the AT):S 3 Everits et the Saler. Nuclear Power Plant". As a result of this investigation, the Comissien (NRC) requested (by Generic Letter 83-28 dated July 8,1983) all  !

licenstes of operatir.g reatters, applicents for an operatir.g license, and holders I of ccostruction perriits to respond to generic lssues raised by the analyses of these two AT6 S events.

This report is an evaluation of the responses submitted by Au H States Utilities Company, the licer see for tne Piver Bend Station, Unit 1, its item 2.1 (Part 1) of Generic Letter 63-28. The actual decurrents reviewed as part of this evaluation are listed in the referer.ces at the end of this report.

Ite'n 2.1 (Part 1) requires the licensee to confirm that all reactor trip system corronents arc identified, classified and treated as safety-related as iridicated in the following statenient:

Licensees and applicants shall confirm that all components whose functioning is required tc trip the reactor are identified as safety-related on docurients, procedures, and infore.ation handling syster.s used in the plant to control safety-related activities, incluving maintenance, wnrk crders, and pris replacerent.

8811300105 8811184B DR ADOCK OSC

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2 2.0 EVALUATION The licensee for the River Bend Station, Unit I responded to the requirements of  ;

Iten 2.1 (part 1) with subrittals dated August 3,1984, Pay 20,1985, and May 12, 1988. In the first subnrittel, the licensee described their proposed equipnent classification program for G. L. 83-28, Item 2.2.1 and stated that this prograri would also satisfy the requirements of Item 2.1 (Part 1). In their setor d submittal, the licensee described the Iten 2.1 (Part 1) program and stated l that it wculd be irplerented by August 15, 1965. In the May 12, 1988 submittal, the liceriste confirced that the equiptent classification program had been inplemented arid iricluded a list of procedures, which were to ensure that all cen.ponents required to trip the reactor are identified as safety-related on the relesent &curerits er.d it. the infern.aticn handlir'C systeras that are used to tuntrol safety-related activities. A copy of the Technical Evaluation Report prepared by the staff's centractor, EG8G Idaho., Inc., is enclosed.

3.0 , CONC,LUSION baseo on the review, the steff firids that the licensee's stater.(nts confirn;  !

that the licensee has a prograti for identifyirig, classifyirig, arid treatirig l t.orponents that tre reonired for perfort.orict of the reactor trip function as i safety-related. This progren: e.eets the requiren'ents of Iten P.1 (part 1) of l Ger:eric Letter 83-28, arid is, therefore, acceptable.  ;

4.0 REFERENCES

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1. bFC Letter D. G. Eisenhut to all Licensees of Operating Feactors, Aiplicants for Operatir.g Licerises, ard Holders of Coristruction Perrits, "Required Actions Eased on Generic Iriplicatioris of Salem ATWS Events" (Ger:eric Letter 83-?8), July 8,19f 3.

2. Letter, Gulf States Utilities Co. (J. E. Booker) to bFC (D. G. Eisenhut),

August 3, 19E4,

3. Letter, Gulf States Utilities Co. (J. E. Booker) to UFC (H. R. Denton),

March P0, 19ES.

4 Letter, Gulf States Utilities Co. (J. E. Booker) to NRC, May 12, 1988.

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