ML20248J900
| ML20248J900 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/05/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248J895 | List: |
| References | |
| GL-83-28, NUDOCS 8904170139 | |
| Download: ML20248J900 (2) | |
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UNITED 'liATEs g
NUCLEAR REGULATORY COMMISSION E
WASHING TON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING GENERIC LETTER 83-28, ITEM 2.1 (PART 2)
SYSTEM ENERGY RESOURCES, INC.
GRAND GULF NUCLEAR STATION, UNITS 1 AND 2
_ DOCKET NOS. 50-416 AND 50-417
1.0 INTRODUCTION
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 in'ident was terminated manually by c
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 startup.
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 (ED0), 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 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.
This report is an evaluation of the responses submitted by System Energy Resources Inc., the licensee for the Grand Gulf Nuclear Station Units 1 and 2 forItem2.1(Part2)ofGenericLetter83-28.
Item 2.1 (Part 2) requires the licensee to confirm that an interface has been established with the NSSS vendor 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 vendor or the vendors of each of the components of the Reactor Trip i
System, and, o a system of positive feedback which confirms receipt by the licensee / applicant of transmittals of vendor technical information.
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o a system of positive feedback which confirms receipt by the '
l licensee / applicant of transmittals of vendor technical information.
I 2.0 EVALUATION i
The licensee provided responses to Generic Letter 83-28 Item 2.1 (Part 2) in their submittals dated November 4,1983, November 19, 1984, and April 1, 1988.
j The licensee uses vendor interface programs between the utilities and the i
nuclear steam supply system vendors and owners' groups. As a part of this interface program with General Electric Co. (NSSS Vendor) the licensee receives Service Information Letters (SILs) concerning technical items or conditions that may be applicable to the Grand Gulf Nuclear Station. The SILs are evaluated as part of the onsite and offsite document review procedure. The results of the evaluation and any recommendations are documented and transmitted to the appropriate organization of the licensee for disposition. All SILs sent to the licensee are addressed to the Grand Gulf Nuclear Station Site Director i
with a receipt acknowledgement form attached.
In addition to the above, GE sends approximately~ every six months a listing of all SILs issued to date.
3.0 CONCLUSION
Based on our review of these responses, we find the licensee's statements f
l 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.
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