ML13330B263
| ML13330B263 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/16/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13330B262 | List: |
| References | |
| GL-83-28, NUDOCS 8803210412 | |
| Download: ML13330B263 (3) | |
Text
SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 1)
EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
SAN ON0FRE NUCLEAR STATION, UNIT 1 DOCKET NO. 50-206 INTRODUCTION AND
SUMMARY
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 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 (EDO), 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 inquiry into the generic implications of the Salem unit 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 (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.
(0321041 880316 PDR 'ADOCK 05000206 P
PD _ ___
-2 This report is an evaluation of the response submitted by Southern California Edison Company, the licensee for the San Onofre Nuclear Station, Unit 1, 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 (Part 1) requires the licensee 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, in cluding maintenance, work orders, and parts replacement.
EVALUATION The licensee for the San Onofre Nuclear Station, Unit 1, responded to the require ments of Item 2.1 (Part 1) with a submittal dated November 28, 19832. The sub mittal stated that all components whose functioning is required to trip the re actor were classified as safety-related on the Q-list. All documents, procedures and information handling systems used to control safety-related activities, in cluding maintenance, work orders, and parts replacement, are based on the Q-list.
-3 CONCLUSION Based on our review of these responses, we find the licensee's statements con firm that a program exists for identifying, classifying and treating components that are required for performance of the reactor trip function as safety related.
This program meets the requirements of Item 2.1 (Part 1) of the Generic Letter 83-28, and is therefore acceptable.
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)," July 8, 1983.
- 2. Letter, M. 0. Medford, Southern California Edison Co., to D. M. Crutchfield, NRC, November 28, 1983.