ML20237A705

Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 2 Requiring Confirmation That Interface Established W/Nsss or W/Vendors of Each Reactor Trip Sys Components.Response Acceptable

ML20237A705
Person / Time
Site:	Fermi
Issue date:	12/10/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237A694	List: ML20237A692 ML20237A697 ML20237A705
References
GL-83-28, NUDOCS 8712150183
Download: ML20237A705 (3)

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%, . >. p SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEM 2.1 (PART 2)

VENDOR INTERFACE PROGRAMS (RTS COMPONENTS)

FERMI-2 DOCKET NO. 50-341

1.0 INTRODUCTION

l 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 i 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, 1983I) I 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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4 This report is an evaluation of the response submitted by Detroit Edison Company, i the licensee for the Fermi-2 power plant 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 l' Reactor Trip System which includes:

i 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 Fermi-2 plant responded to the requirements of Item 2.1 ,

(Part 2) with a submittal dated March 19, 1967. The licensee stated in this submittal that General Electric is the NSSS vendor for the Fermi-2 plant and that the RTS is included as part of the General Electric interface program established for this plant. The response also confirms that this interface program includes both periodic communication between General Electric and the licensee and positive feedb6ck from the licensee in the form of signed receipts for technical information transmitted by General Electric.

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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 fcr Operating License, and Holders of Construction l Permits, " Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983. '

2. Detroit Edison Company letter to NRC, F. E. Agosti to Document Control Desk, " Additional Information Pursuant to Generic Letter ,

83-28," dated March 19, 1987. DEC0 Nr. VP-NO-87-0052 l

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