ML20212H754

Safety Evaluation Supporting Licensee 841104,850208 & 0726 Responses to Generic Ltr 83-28,Item 2.1,Part 1, Equipment Classification

ML20212H754
Person / Time
Site:	North Anna, 05000000
Issue date:	07/24/1986
From:	NRC
To:
Shared Package
ML20211N814	List: ML20211N807 ML20212H732 ML20212H754
References
GL-83-28, NUDOCS 8608140168
Download: ML20212H754 (2)

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SAFETY EVALUATION GENERIC LETTER 83-28, ITEM 2.1 (PART 1)

NORTH ANNA POWER STATION, UNITS 1 & 2 DOCKET NOS. 50-338/339 i

INTRODUCTION On February 25, 1983, both of the scram circuit breakers at Unit I 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 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 Operations (ED0) directed the staff to investigate and report on the generic implications of these occurrences at Unit I of the Salem Nuclear Power Plant.

The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATUS Events at the Salem Nuclear Power Plant." As a result of this investigatign, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983 )

all licensees of operating reactors, 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 responses submitted by Virginia Electric and Power Company, the licensee for the North Anna Power Station, Units 1 and 2, for Item 2.1 (Part 1) of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of this l report.

Item 2.1 (Part 1) requires the licensees to confirm that all Reactor Trip System components are identified, classified and treated as safety-related as indicated in the following statement:

Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities; including i maintenance, work orders, and parts replacement.

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8608140168 860724 PDR ADOCK 05000338 P PDR i

EVALUATION ThelicenseefortheNorthAnnaPowerStation, requirements of I Units 1and2,respondedgothe February 8,1985,jem and 2.1 July(Part 26, 1985. 1) witg The submittals licenseedated stated November 4,1983 ,

in these submittals that its program requires identification of RTS components as safety-related on all station documents, but did not include a complete itemized list of RTS components. The licensee does, however, have an evaluation process for use whara enmnnnants are not listed and a project to revise its program which will provide a complete itemized Ifsting of RTS components. This program is being undertaken with scheduled completion in the second quarter of 1987.

CONCLUSION Based on the staff's review of these responses, it finds the licensee's state-ments confirm that a program exists for identifying, classifying and treating components that are required for performance of the reactor trip function as safety related and that this program is being updated to provide a complete listing of the RTS components. This program and commitment meet the require-ments of Item 2.1 (Part 1) of the Generic Letter 83-28, and are therefore acceptable.

PRINCIPAL CONTRIBUTERS: D. Lasher and EG8G Idaho, Inc.

ATTACHMENT: EGG-NTA-7239 REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees 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, W. L. Stewart, Virginia Electric and Power Co., to D. G. Eisenhut, NRC, November 4, 1983.

3. Letter, W. L. Stewart, Virginia Electric and Power Co., to D. G. Eisenhut,

, NRC, February 8, 1985.

4. Letter, W. L. Stewart, Virginia Electric and Power Co., to H. L. Thompson, NRC, July 26, 1985.

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