ML17325A527
| ML17325A527 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/11/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A526 | List: |
| References | |
| NUDOCS 8712160134 | |
| Download: ML17325A527 (4) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELA ED RE U ST FOR C
DE L EF EXTENSION OR RHR SYS EM L ES INDIANA 5 MICHIGAN L CTRIC COMPANY DONALD C.
COOK NUCLEAR PLANT, UNIT NOS.
1&2 DOCKET NOS: 50-315/316 Introduction By a letter dated October 31, 1986, the Indiana 5 Michigan Electric Company (IMEC) requested permanent relief from testing of certain valves in its Inservice Testing (IST) program.
These valves, IM0-330,-331, -340, and -350, are presently subject to quarterly testing in accordance with ASME Code Section XI requirements.
The licensee contended that testing of these valves in the present test configuration would place the plant in an unanalyzed condition, would require the plant to enter into technical Specification 3.0.3 with only 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to complete the test and because the test has historically taken longer than an hour, might require a plant shutdown.
As a result, the 0
licensee requested permanent relief from quarterly testing of these valves, and proposed to test them during cold shutdowns and refueling outages.
In an NRC letter dated December 19, 1986, the IMEC was informed that the IMEC request for permanent relief was denied but an interim relief was granted until next respective plant scheduled refueling outages.
For further consideration of the permanent relief, the licensee should submit for NRC review the results of their additional analysis on the unanalyzed condition and/or develop alternative testing methods.
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Since the issuance of the NRC letter dated Oecember 19, 1986, the licensee has completed part of the requested analysis but requires more time to complete the last portion of this analysis pertaining to containment long-term pressure.
As a result, by letter dated November 20, 1987, the licensee requested an extension of the interm relief until the analysis is completed.
The additional time is needed because the interim relief for Unit I expired with the last refueling outage which occurred in October
- 1987, and the interim relief for Unit 2 will expire during the next refueling outage scheduled for May 1988.
Our evaluation of the request for extension of the interim relief is provided below.
Evaluation The ASME Code,Section XI allows testing a valve at cold shutdown in lieu of quarterly testing, if the licensee can demonstrate that testing the valve during power operation is not practical and can result in damage of other l
plant equipment.
As indicated above the licensee requested relief from quarterly testing of IM0-330, -331, -340 and -350 since the test configuration and time required for testing these valves may place the plant in a condition that may be inconsistent with the plant design basis and associated Technical Specification requirements.
In order to perform the required test, part of one RHR train needs to be isolated.
By isolating one train, the licensee states that operable flow paths will only be available to two reactor coolant loops rather than four as required in the safety analysis.
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Based on the previous staff evaluation of the licensee's original request for relief and additional discussion with the licensee on alternative testing methods, the staff has reconfirmed that testing of these valves in their present config-uration would place the plant in an unanalyzed condition.
It is therefore pru-dent to grant an extension of the interim relief to allow the licensee additional time to complete the requried evaluation of the unanalyzed condition.
Conclusions Based on the above discussion the staff concludes that the interim relief be granted for Unit 1 so that the licensee can complete its required analysis.
This relief should extend the surveillances presently expected in December 1987 and March 1988.
By the surveillance date in June 1988 the licensee's analysis of overpressurization of containment and our evaluation could be complete and actions finalized for future testing schedules.
However, the licensee should complete and submit its analysis results 'for staff review at least three months before extension expires so as to allow the staff sufficient time to complete its review.