ML20150C131
| ML20150C131 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/21/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150C088 | List: |
| References | |
| GL-83-28, NUDOCS 8807120322 | |
| Download: ML20150C131 (2) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHING TON, D. C. 20555 e
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SAFETY EVALUATION BY THE OFFICE OF NL' CLEAR REACTOR REGULATION WISCO'NSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKEl NOS. 50-266/301 G_ENERIC LETTER 83-28, ITEM 2.1 (PART 1)
EQUIPMENT CLAS?IFICATION (RTS COMPONENTS)
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 i
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 J
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 (ED0), 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 implication of the Salen 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 (NoC) requested (t,y 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 l
analyses of these two ATWS events.
This report is an evaluation of the response submitted by Wisconsin Electric Power Company, the licensee for the Point Beach Nuclear Plant, Units 1 and 2, for Item 2.1 (Part 1) of Generic Letter 83-28.
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 are identified. as safety-related on documents, procedures, and infonnation handling systems used in the plant to control safety-related activities, in-ciuding maintenance, work orders, and parts replaceme'nt.
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.j EVALUATION The licensee for the Point Beach Nuclear Plant, Units 1 and 2 responded to the requirements of Item 2.1 (Part 1) with submittals dated November 7, 1983, 4
April 11, 1986, and May 11, 1988. The licensee confirmed in the May 11, 1988 submittal that all components whose function is required to trip the reactor are identified as safety-related on documents which control safety-related activities, j
i CONCLUSION Based on its review of these responses, the staff finds the licensee's statements confinn 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.
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