ML20195H675

Safety Evaluation Re Part 2 of Item 2.1 to Generic Ltr 83-28, Vendor Interface Programs - Reactor Trip Sys Components

ML20195H675
Person / Time
Site:	Hope Creek
Issue date:	11/22/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195H663	List: ML20195H657 ML20195H675
References
GL-83-28, NUDOCS 8811300543
Download: ML20195H675 (2)

Text

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

VENDOR INTERFACE PROGRAMS (RTS COMrjNENTS)

HOPE CREEK GENERATING STATION DOCKET NO. 50-354

1.0 INTRODUCTION

On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed 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 automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was cenerated 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 fJr Operations (E00), directed the staff to investigate the 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 these events 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 (NRC) requested (by Generic :.etter 83-28 dated July 8, 1983) all licensees of operating r6 actors, applicants for an operating license, and holders of construction permits to respond to generic issues raised by the analyses of these two ATWS events.

This report is an evaluation of the response submitted by Public Service Electric and Gas Company, the licensee for the Hope Creek Generation Station for Item 2.1 (Part 2) of Generic t.etter 83-28. The actual documents reviewed as part of this evaluatin are listed in the references of this report.

1 Item 2.1 (Part 2) requires the licensee to confira that an interface has been -

established with the NSSS or with the vendors of each of the components of the Reactor Trip System which includes:

• periodic conrnunication between the licensee / applicant and the 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 / applicant of transmittals of vendor technical information,,

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Mr. Miltenberger 2.0 EVALUATION The licensee provided responses to Generic letter 83-28 Item 2.1 (Part 2) regardino a vendor interface program in submittals dated March 30, 1984 and October 23, 1985. The vendor interface program is to ensure that the current technical information and data will be made available to those personnel responsible for developing and maintaining plant instructions and procedures.

Generic Electric Co. supplies the vendor information directly to the licensee such as Service Information Letters (Sils), Service Advice letters, Turbine Information letters (T!ls). Operation and Maintenance Manuals, and Application Information Documents. The licensee has established a Response Coordinating Team (RCT) for Hope Creek which evaluates and processes the above information notices and correspondence. The RCT reviews the documents listed above, transmits them to the affected departments for action or incorporation, and maintains the applicable records to document the disposition of said documents. The program described above ensures that reactor trip system vendor informatinn is reviewed and controlled, and will be continued throughout the life of the plant.

3.0 CMCLUSION Based on our review of these responses, we find the licensee's statements ccnfirm that a vendor interface program exists with the NSSS veMor for components that are reouired for performance of the reactor trip tunction.

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

4.0REFERENCQ

1. NRC Letter, D. G. Eisenhut to all Licensee of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction Permits.

"Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.

2. Letter, R. L. Mitt 1, 'ic Service Electric and Gas Company to A. Schwencer, NRC, Marc.. 30, 1984.

3. Letter, R. L. Mitt 1, Public Service Electric and Gas Company to A. Schwencer, NRC, December 17, 1984