ML18150A493

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SER Supporting Util 850208 Response to Generic Ltr 83-28, Item 2.1 (Part 2), Vendor Interface Programs - Reactor Trip Sys Components
ML18150A493
Person / Time
Site: 05000000, Surry
Issue date: 07/21/1987
From:
NRC
To:
Shared Package
ML18150A262 List:
References
GL-83-28, NUDOCS 8707300560
Download: ML18150A493 (3)


Text

  • e ENCLOSU~E 2*

SAFETY EVALUATION.REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)

VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)

SURRY POWER STATION, UNITS l,2 DOCKET NOS. 50-280/281 On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant faiiec to open 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 ~utomatic trip signal.

The failure of the circuit breakers was determined to be related to the sticking of the undervcltage trip attachment.

Prior to this incident, en February 22, 1983, at Unit l of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up.

In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive*Director for Operati6ns (EDD), 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 1s inquiry into* the generic implications of the Salem unit incidents are reported in NUREG-1000, "G~neric Implications of the ATWS Events at the Salem Nuclear Power Plant."

As a result of this investigation, the Corrnnission (NRC) requested (by Generic Letter 83-28 dated July 8, 19831) all licensees of operating reactors, applicants for an operating license, and holders of construction pennits to respond to generic issues raised by the analyses of these two ATWS events.

r 8707300560 870721 *..

PDR ADOCK 05000280 p

PDR This report is an evaluation of the response submitted by Virginia Electric srd Power Company, the licensee for the Surry Power Station, Units.1,2 for Ite~ 2.1 (Part 2) of Generic Letter 83-28.

The actual documents reviewed as part of this evaluation are listed in the references at the end of the report.

Item 2.1 (Part 2) requires the licensee to confirm that an interface has been established with the ~SSS or with the vendors of each of the components of the React0r Trip System which includes:

EVALUATION periodic commurication between the 1~rensee/applicant and tr.e NSSS or the vendors of each of the components of the Reactor Trip System, and a system of positive feedback which confirms receipt by the licensee/applircr.t of transmittals of vendor technical inforrr.etion.

The licensee for the Surry Power Station, Unit5 1,2 responded to the require~ents of Itew 2.1 (Part 2) with a submittal dated February 8, J9852. The licensee stated in this submittal that Westinghouse is thP NSSS vendor for the Surry Power Station, Units 1,2 and that the RTS is included as part of the Westinghouse in-terface program established for this plant. The response also confirm~ that this interface program inc l.udes both periodic comrr,uni ca ti on between Westinghouse and the licensee and positive feedback from the licensee in the form of signPd receipts for technicr.~ information transmitted by Westinghouse.

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e CONCLUSION Based on our review of the licensee's response, we find the licensee's statements confirm that a vendor intuface program exists \\'dth the NSSS vendor for cori-ponents that are required for performance of the reactor trip function.

This program meets the requirements of Item 2.1 (Part 2) of the Generic Letter 83-28, and is therefore acceptable.

kEFERENCES

i.

~RC Letter, D. G. Eisenhut to all Lice~sees of Operating Reactors, Applicants for Oper2ting License, and Holders of Construction Permits, "Required Actions Based or, Generic Implications cf Salem ATWS Events (Generic Letter 83-28),

11 July 8, 1983.

2.

Virgi-nia Electric and Power Company letter to NRC, W. L. Stewc1rt, to Harold R. Denton, Director, Office of Nuclear Reactor Regulatior:,

"Revision to Generic Letter 83-28," February 8, 1985.