ML20034C008
| ML20034C008 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/20/1990 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Comley S WE THE PEOPLE OF THE UNITED STATES (WE THE PEOPLE |
| Shared Package | |
| ML20034C009 | List: |
| References | |
| IEB-87-002, IEB-87-2, IEB-88-005, IEB-88-5, NUDOCS 9005010302 | |
| Download: ML20034C008 (3) | |
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April 20,1990 Mr. Stephen B. Comley Executive Director We The People, Inc. of the United Stt.tes P.O. Box 277 Rowley, Massachusetts 01969
Dear Mr. Comley:
I am replying to ycur letter of March 26, 1990, to Chairman Carr about condi-tions at the Seabrook Nuclear Station (Seabrook).
These conditions involved a steam valve problem reported on March 21, 1990, and elec'rical problems in a backup power supply controllirg fuel rods reported in the news media on March 22, 1990.
The steam valve problem to which you refer appears to be the March 21, 1990, body-to-bonnet leak on an isolation valve to the steam dump valves. Body-to-bonnet leaks on steam valves are not unusual, and this one was repaired before the next normal workday began.
None of the components involved a.re safety-grade, and they are not required to function to ensure safe rea : tor shutdown.
Routine U.S. Nuclear Regulatory Commission (NRC) onsite inspection has identi-fied no reason for further review 01 this occurrence.
The rod control backup power supply (which is not a safety-grade component) that failed was quickly replaced shortly af ter the reactor was brought to a subcritical condition. Failure of this supply did not jeopardize the plant, and it was replaced without difficulty.
Recognition of the potential for electrical component failures was a factor in the redundant power supply feature of the plant; that redundancy prevented this failure fron causing any rod drop. Even if une or rr.arr rods should drop, the resulting power decrease transient is one that has long been handled at U.S. nuclear power plants without equipment damage or a threat to nuclear safety.
Routine operator training adequately assures proper response to such events. Although routine HRC inspection of this power supply problem at Seab ook has not been completed, we have as yet found no reason to suspect any safety inadequacy.
In regard to your concern about counterfeit components, the NRC issued Bulletin e7-02, " Fastener Testing to Determine Conformance with Applicable Material Specifications," and Bulletin 88-05, " Nonconforming Materials Supplied by Piping Supplies Inc., at Folsum, New Jersey, and West Jersey Marrufacturing Company at Williamstown, New Jersey," on this subject.
The Seabrook licenree responded oppropriately to the associated concerns,.and we are satisfied that coanterfeit components do not represent a significant safety problem at Seabrook.
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4 Stephen B. Comley 2-in regard to your concern about public. notifications, the NRC practice for Seabrook is the same as it has been for other nuclear power plants under similar conditions in the initial phases of power operation.
Information is obtainable via licensee and NRC public affairs sources, and HRC inspection reports are accessible to the public.
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While we unde' stand that you are concerned about Seabrook operation, we did not find in your submittal i substantive basis for charging existing NRC practices. Therefore, we do not plan further action regarding the matters
.you identified.
Sincerely, i
m Original SQned Byg Thomas E. Murley, Direct.or Office of Nuclear Reactor Regulation y
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