ML20207P655

SER Accepting Licensee Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing

ML20207P655
Person / Time
Site:	Beaver Valley
Issue date:	01/02/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207P645	List: ML20207P644 ML20207P655
References
GL-83-28, NUDOCS 8701160375
Download: ML20207P655 (3)

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j/pannu(4, UNITED STATES NUCLEAR REGULATORY COMMISSION t a wasHmoTow,0. c. 20sss

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SAFETY EVALUATinN RFp0RT RY THE OFFICE OF NUCLEAR REACTOR REGULATTON 4ENERic LtJTF9 83-7R, ITEP 2.1 (PADT 2) AND ITEM 4.5.?

BEAVER VALLEY POWFP STATION, UNIT 1 DOCKET NO. 5n-134 A

I igTRODUCTION On Februarv 95,19A3, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to 0;en upon an automatic reactor trip signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip sianal.

The failure of the circuit breakers was determined to be related to the sticking .< ;

of the undervoltage trip attachment. Prior to this incident, on Februarv ?7, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip sianal was oenerated based on steam generator low-low level durino plant start-up. In this case, the reactor was tripped ranua11y by the operator timost coincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (ED0) directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.

The results of the staff's inouiry into the generic implications of the Salem incidents are reported in NUREG-1000. " Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission requested (by Generic letter 83-28 dated .1ulv 8,1983) all licensees of operating reactors, applicants for operating licenses, and holders of construction permits to respond to generic issues raised bv the analyses of these two anticipated-transient-without-scram IATVS) events.

This = report is an evaluation of the response submitted by Duquesne Light Company, .the licensee for Reaver Vallev power Station, Unit 1 for items ?.1 (Part 2) and 4.5.2 of Generic Letter 83-28.

nISCUSSION AN9 FVALHATION Item ?.1, Vendor interface prooram for Reactor Trin System Components Item 9.1 (Part ?) requires the licensee to confirm that an inter # ace has been estabitshed with the N9Ss vendor or with the vendors of each of the comoonents of the reactor trip system (RT91 which includes:

periodic communication between the licensee / applicant and the NSSS vendor or the vendors of each of the components o' the reactor trio system, and a system of positive feedback which confirms receipt bv the licensee /

applicant of transmittals of vendor technical information.

8701160375 870192 '

PDR ADOCK 05000334 P PDR g

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d dated November 4, la'U.The licensee responded to the requirements..

submittal of It is the NSSS for the Braver Valley Power Station, linit I and included plant. as part of the Westinghouse interface program established for !t The response also confirms that this interface program includes both periodic communication between Westinghouse and the licenseec and p  ;

j from the licensee transmitted in the form by Vestinehouse. of sioned receipts for technical m infor on ati Rased on our review of this response, we find the licensee's stateme t n s confirm that a vendor interface program exists with the N9SS vendor for comnone that are renuired for performance of the reactor trip function. This procram meets the reouf is therefore rements of Item P.1 (Part 95 of Generic Letter 83-28, acceptable. and Item A.5.?, Reactor Trio System Reliability, On-Line Testina the reactor trip system, including independent tes features of the reactor trip breakers, for all plants.

applicants and licensees with plants not currently designed to permit thisItem periodic on-line testino to justify not making modifications to permit such testing.

position regarding Item 4.5.? of Generic Letter 83-28.By letter da The licensee states that Beaver Valley Power Station, Unit 1 is desioned to allow on-line testing of the reactor trip system and that' independent tes the undervoltaae and shunt trip attachments deoends on the implementation the1986 the reactor tripoutage).

refueling breaker shunt trio modifications (which was completed modifications and found that the design allows on-line indepen the undervoltage and shunt trio attachments.

operation is not .iustified because only one hvoass b at a time (for less than two hours per monthi, and that when a bypass breaker is in service which is tested the RTS will initiate a trip sianal to one of'the trip breakers bimonthly.

Also, the addition of components necessarv to eliminate the need to lift leads and install .iumpers (c system. The ,iustification is acceptable.

on-line functional testing of the reactor trip system, inc testing of the diverse trip features of the reactor trip breakers. Thus, the licensee meets the staff position of Item 4.5.9 of Generic letter 83-?A Conclusion Rased on the above discussion, the licensee has acceptably complied e with th reouf rements Furthermore, stated since as Generic the vendor interfaceletter 83-?8 program is Items already9.1 (Partand in effect 2) and sin on-line testing has been to track any further implementation. implemented, the staff concludes that there is no nee

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1 Principal Contributors:

-D. Lasher, NRC Staff Reviewer F. G. Farmer, . EGAG Idaho, Inc.

C. E. Rossi, Assistant Director Dated: .1anuary ?, 1987

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