ML20071E397
| ML20071E397 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/07/1983 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-SSINS-6820 AEP:NRC:0786, AEP:NRC:786, IEB-83-01, IEB-83-1, NUDOCS 8303150218 | |
| Download: ML20071E397 (4) | |
Text
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INDIANA & MICHIGAN ELECTRIC COMPANY P. O. BO X 18 BOWLING GREEN ST ATION N EW YORK, H. Y.10LO4 March 7, 1983 AEP:NRC:0786 Donald C. Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 IE BULLETIN NO. 83-01 FAILURE OF REACTOR TRIP BREAKERS (WESTINGHOUSE DB-50) TO OPEN ON AUTOMATIC TRIP SIGNAL Mr. James G. Keppler U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region III Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
This letter is in response to IE Bulletin No. 83-01, " Failure of Reactor Trip Breakers (Westinghouse DB-50) To Open on Automatic Trip Signal." Item 4 requested us to provide a written reply within 7 days of receipt of the bulletin.
Item 4.a Identify results of testing performed in response to Item 1.
Response
The Surveillance Testing required by IE Bulletin 83-01, Item 1, was completed in Units 1 and 2 on Saturday, February 26, 1983 prior to 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />. The results of the tests were satisfactory. It should be noted that the testing of the Reactor Trip Breakers is performed monthly (alternate trains) in accordance with our Technical Specifications.
Item 4.b Identify conformance of maintenance program to Westinghouse recommendation and describe results of maintenance performed directly as a result of this Bulletin in response to item 2.
Response
The Plant Maintenance procedure has been reviewed against the Westinghouse recommended practice (NSD Data Letter 74-2) as required by IE Bulletin 83-01, Item 2.
The Maintenance procedure was determined to
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Mr. James G. Keppler 2
AEP:NRC:0786 conform to the Westinghouse recommendations on all points with the exception of frequency. Westinghouse recommends a semi-annual maintenance frequency which can be extended to 9 to 12 months, based upon experience. The Plant Mair.tenance procedure is performed during refueling outages which is an a.iroximate 12 month frequency in Unit 1 and an 18 month frequency in Unit 2.
The Plant Maintenance procedure has been utilized'in Unit i since 1977 and in Unit 2 since 1978. No adverse findings have been identified during any past performances of the procedure in either Unit. Further, a review of past reportable occurrences in this area did not identify any failures of the subject breakers. In view of our operating experience with these Breakers, and the f requency of our surveillance testing, we consider the maintenance frequency to be adequate based upon these results.
A requirement to conduct breaker maintenance on a more frequent basis under our current Technical Specifications requires shutting the Units down. Plant shutdowns impose additional plant transients and component cycling, which are not conducive to improved reactor safety.
Should the NRC believe more frequent breaker maintenance is necessary, the NRC should, on a generic basis, modify technical specifications to permit operating with one protective train for a period adequate to perform breaker maintenance. We currently estimate that this minor preventative maintenance could be performed in approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
In this manner, i.e, necessary technical specification changes, it could be practical to perform breaker maintenance on a more frequent basis without the need to expose the plant to unnecessary transients.
Item 4.c Provide statement that provisions are in place to notify licensed operators of the Salem event and bring to their attention appropriate failure-to-trip emergency procedures upon their arrival on-shift.
Response
The notification to all Licensed Operators as required by IE Bulletin 83-01, Item 3, is in progress. All Licensed Operators who have been on shif t since the Bulletin's issuance on February 25, 1983 have been apprised of the event and the related plant operating procedures.
Provisions have been established to notify the remaining Licensed Personnel by March 11, 1983.
Very truly yours, b
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R. S. Hunter Vice President RSH/ sag cc: Attached
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Mr. James G. Keppler 3
AEP:NRC:0786 cc: John E. Dolan - Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff NRC Resident Inspector at Cook Plant - Bridgman Document Control Desk, U.S. Nuclear Regulatory Commission (original of cover letter) 1 I
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, being duly sworn, deposes and says that he is the Vice President of Licensee Indiana & Michigan Electric Company that he has read the foregoing response to IE Bulletin No. 83-01, AEP:NRC:0786 and knows the content thereof; and that said contents are true to the best of his knowledge and belief.
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