ML13305A876
| ML13305A876 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/26/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13305A875 | List: |
| References | |
| GL-83-28, NUDOCS 8608290079 | |
| Download: ML13305A876 (3) | |
Text
SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 PART 1 EQUIPMENT CLASSIFICATION (RTS COMPONENTS)
SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2,3 DOCKET NOS. 50-361/362 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 ifitiation 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 coin cidentally 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 generic implications of the Salem unit incidents are reported in NUREG-10000, "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.
PDR ADOC 05036 P
O=PDR
-2 This report is an evaluation of the response submitted by Southern California Edison Company, the licensee for The San Onofre Nuclear Generating Station, Units 2,3, for Item 2.1 (Part 1) of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the reference at the end of this 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 as identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders,, and parts replacement.
EVALUATION The licensee for The San Onofre Nuclear Generating Station, Units 2,3 of Item 2.1 (Part 1) with a submittal dated November 29, 19832. The licensee stated in this submittal that all components that are required to perform the reactor trip function are classified as safety-related equipment. The licensee further stated that these components are identified as safety-related on plant documents such as the Instrument Index, Valve Lists, Equipment Index and Line Lists; procurement documents such as requisitions and purchase orders and on plant worksheets.
-3 CONCLUSION Based on our review of these responses, we find the licensee's statements confirm 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, F. R. Nandy, Southern California Edison Co., to G. W. Knighton, NRC, November 29, 1983.