ML13305A950
| ML13305A950 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/28/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13305A949 | List: |
| References | |
| GL-83-28, NUDOCS 8711030386 | |
| Download: ML13305A950 (3) | |
Text
ENCLOSURE 1 NP REGU bUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)
VENDOR INTERFACE PROGRAMS (RTS COMPONENTSI SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2&3 DOCKET NOS. 50-361/362 1.0 INTPODUCTION 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, 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.
.8711030386 871028 PDR ADOCK 05000361 PPDR
.. I
-2 This report is anevaluation Of the response submitted by Southern California Edison Company, the licensee for the Sarn Onofre Nuclear Generating Station, Units 2&3, for Item 2.1 (Part 2) 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 2) requires the licensee to confirm 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 communication 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.
2.0 EVALUATION The licensee for the San Onofre 2&3 plants responded to the requirements of Item 2.1 (Part 2) with submittals dated November 29, 1983 and June 18, 1987.
The licensee stated in these submittals that Combustion Engineering is the NSSS vendor for the San Onofre 2&3 plants and that the RTS is included as part of the Combustion Engineering interface program established for these plants.
The response also confirms that this interface program includes both periodic communication between Combustion Engineering and the licensee and positive feedback from the licensee in the form of signed receipts for technical information transmitted by Combustion Engineering.
3.0 CONCLUSION
Based on our review of these responses, we find the licensee's statements confirm that a vendor interface program exists with the NSSS vendor for components that are required for performance of the reactor trip function.
This program meets the requirements of Item 2.1 (Part 2) of the Generic Letter 83-28, and is 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),"
July 8, 1983.
- 2. Southern California Edison Company letter to NRC, R. Dietch to Office of Nuclear Reactor Regulation, November 29, 1983.
- 3. Southern California Edison Company letter to NRC, M. 0. Medford to Document Control Desk, June 18, 1987.