ML18150A263
| ML18150A263 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Surry |
| Issue date: | 07/21/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML18150A262 | List: |
| References | |
| GL-83-28, NUDOCS 8707300392 | |
| Download: ML18150A263 (3) | |
Text
1.0 INTRODUCTION
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 1)
EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
SURRY POWER STATION, *UNITS 1&2 DOCKET NOS. 50-280/281 ENCLOSURE 1 On February 25, 1983, both of the scram circuit breakers at Un1t 1 of the Sdlem 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 Sdlem 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 1 the NRC Executive Director for Operations (EDD), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Saiem 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 ATWS Events at the Salem iuclear Power Plant."
As a result of this investigation, the CofliTlission (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 permits to respond to generic issues raised by the analyses of these two ATWS events.
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r 8707300392 B68oo~ao II PDR ADOCK O PDR.
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e This report is dn evaluation of the responses submitted by Virginia Electric &
Power Company, the 1 icensee for the Surry Power Station, Units 1&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 the report.
- Item 2.1 (.Pdrt 1) requires the licensee to corifini, that all reactor trip system components are identified, classified and treated as safety-related as indicated in the fo 11 owing statement:
Licen~ees and applicants shall confinn that all components whose*
functioning is required to trip the redctor are identified dS safety-related on documents, procedures, and infonnation handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.
2.0 EVALUATION The -1;censee for the Surry Power Station, Units 1&2 responded to the requirements of I~em 2.1 (Part 1) with a submittal dated November 4, 19832 and a revised submittal dated May 20, 19853* Th~ submittals included infonnation aescribing the licensee's equip~nt classification program and procedures.
Review of this information showed that this program requires identification of RTS components as safety-related on all station documents, however, they state that their procedure does not now itemize the RTS components, but does include an evaluation process for use where components are not specificaliy listed. They further state that the program is being.revised-to include a more complete listiny uf components.
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3.0 CONCLUSION
Based on our review of these responses, we find the licensee's surrmary program de~cription and the procedural revision to provide a more complete listing of RTS components, meet the requirements of Item 2.1 (Part 1) of the Generic Let;er 83-28, and are therefore acceptable.
4.0 REFERENCES
- 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, "Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28),"
Ju 1 y 8, 1983.
- 2.
Letter, W. L. Stewart, Virginia_Electric & Power Company, to H. R. Denton, Director, Office of Nuclear Reactor Regulation, NRC, November 4, 1983.
- 3.
Letter, W. L. Stewart, Virginia Electric & Power Company, to H. R. Denton, Director, Office of Nuclear Reactor Regulation, NRC, May 20, 1985.