ML17334B025
| ML17334B025 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/19/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17326B273 | List: |
| References | |
| NUDOCS 8612230142 | |
| Download: ML17334B025 (3) | |
Text
SAFETY EVALUATION REPORT D. C.
COOK NUCLEAR PLANT UNIT NOS. I AND 2 DOCKET NOS. 50-315 AND 50-316 Backqround By a letter dated October 31, 1986, the Indiana 5 Michigan Electric Company requested permanent relief from testing of certain valves in its Inservice Testing
( IST) program.
These valves are in the Residual Heat Removal System and 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 licensee requested relief from quarterly testing of these valves, and proposed to test them during cold shutdowns.
Our evaluation of the licensee's request is provided below.
Evaluation Section 50.55a, "Codes and Standards",
of 10 CFR Part 50 requires, in part, that certain safety-related pumps and valves meet the testing requirements of ASME Code,Section XI.
In conformance with this regulatory requirement, the
,licensee has approved IST programs for the D. C.
Cook Nuclear Plant.
Under those
- programs, valves IM0-330, -331, -340 and -350 mounted on discharge lines from Residual Heat Removal (RHR)
Pumps are reouired to be tested quarterly.
- Recently, the licensee has discovered that the plant 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.
Ry 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.
8612230142 861219 PDR ADOCK 05000315 PDR
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 plant equipment.
The staff's review of the licensee's basis for requesting the relief indicates that fur ther analysis could be performed to evaluate the consequence of flow to two reactor coolant loops versus four or to determine if another alternative testing procedure can be developed for performing the test required 'by regulation.
The licensee has indicated that an analysis is being performed but will not be available in time to permit the tests to proceed on schedule.
Since the testing of these valves would place the plant in an unanalyzed condition, it is prudent that interim relief be granted from the quarterly testing requirement until the next refueling outage.
This temporary relief would allow the licensee additional time to complete its evaluation of the unanalyzed condition and/or develop an acceptable alternative method for testing these valves quarterly.
Further, the extension of time to complete the tests should not be a significant factor in any valve failure and any additional degradation would be small.
Me have discussed the temporary relief with the licensee.
The next refueling outages are scheduled for May 1987 for Unit I and about February 1988 for Unit 2.
The licensee has further agreed to perform the tests during any intervening outage of sufficient duration that the plant is in a condition where the test could be performed.
Conclusion Rased on the above discussion, the staff concludes that a permanent relief from auarterly testing for the valves IM0-330, -331, -340 and -350 should not be granted at this time.
However, interim relief from the quarterly testing of these valves is recommended until the next refueling outages.
For permanent relief, the licensee should submit for NRC review the results of their additional analysis on the unanalyzed condition and/or alternative testing method.
Attachment 5 to AEP:NRC:1024 NRC Information on Use of Westinghouse NOTRUMP Code