ML17201M235
| ML17201M235 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/23/1988 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17201M234 | List: |
| References | |
| GL-83-28, NUDOCS 8811300092 | |
| Download: ML17201M235 (3) | |
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1.0 INTRODUCTION
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION GENERIC LETTER 83-28, ITEM 2.1 (PART 2)
VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)
DRESDEN STATION, UNITS 2 AND 3 DOCKET NOS. 237/249 ENCLOSURE 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 the 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 these events are reported in NUREG 1000 "Generic Implications of the ATWS Events at the Salem Nuclear Powe~ 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.
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- 2 This evaluation is based on the response submitted by Commonwealth Edison Company, the licensee for the Dresden Station Units 2 and 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 this 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:
o periodic communication between the licensee/applicant and the NSSS or the vendprs of each of the components of the Reactor Trip System, and o a system of positive feedback which confirms receipt by the licensee/applicant of transmittals of vendor technical information.
- 2. 0 EVALUATION The licensee provided responses to Generic Letter 83-28, Item 2.1 (Part 2) in submittals dated November 5, 1983 and July 26, 1985.
The licensee stated that the present vendor interface program consists of a review of General Electric and Westinghouse service advisories and information letters. The program assures that vendor technical information is current, complete, and controlled throughout the life of the plant.
In order to comply with this commitment, the licensee has revised Administrative Procedure OAP 2-10 (Control of Vendor Equipment Technical Information).
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 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 Licenses, and Holders of Construction Permits, "Required Actions Based on Generi~ Implications of Salem ATWS Events (Generic Letter 83-28),
11 July 8, 1983.
- 2.
Letter, P. L. Barnes, Conunonwealth Edison Company to H. R. Denton, NRC, November 5, 1983.
- 3.
Letter, G. L. Alexander, Conunonwealth Edison Company to H. R. Denton, NRC, July 26, 1985
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