ML20126K666
| ML20126K666 | |
| Person / Time | |
|---|---|
| Issue date: | 12/29/1992 |
| From: | Russell W Office of Nuclear Reactor Regulation |
| To: | Beard P, Conway W, Cottle W, Mccoy K BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP, BWR OWNERS GROUP, C-E OPERATING PLANTS OWNERS GROUP, WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| References | |
| NUDOCS 9301070221 | |
| Download: ML20126K666 (4) | |
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{- ,i NUCLEAR REGULATORY COMMISSION c WASHINoToN, D.C. 20566 o\***' / December 29, 1992 Mr. Ken McCoy Mr. William F. Conway Westinghouse Owners Group Combustion Engineering Owners Group Georgia Power Company Arizona Public Service Birmingham, Alabama 35201 Phoenix, Arizona 85072-3999 Mr. P. M. Beard, Jr. Mr. W. T. Cottle Bab ock & Wilcox Owners Group C'?R Owners Group Florida Power Corporation Grand Gulf Nuclear Power Station P. O. Box 219-NA-21 P. O. Box 756 Crystal River, Florida 32629 Entergy Service Center Port Gibson, Mississippi 39150 Gentlemen:
SUBJECT:
CODE SAFETf VALVE DRIFT AND SETPOINT - STANDARD TECHNICAL SPECIFICATIONS ACTION ITEM #98 The purpose of this letter is to confirm and describe the staff's position with regard to Code safety valve drift during operation and the resetting of valve setpoints following calibration. This issue was discussed during our executive meeting on September 17, 1992. At that time, I indicated that the standard technical specifications (STS) should incorporate the position developed for the BWR plants in response to General Electric's topical report NEDC-31753P.
On November 23, 1992, the CRGR d4 cussed the staff's evaluation of that report, and approved a position on NEDC-31753P which is appropriate for generic implementation. Specifically, the CRGR approved a position which consists of the following relevant elements.
- A generic change of valve setpoint tolerance to i3% is acceptable, provided that the plant-specific accident analysis justifies such a change.
Licensees may propose license amendments t zaige the allowable drift tolerance to 13%, in conjunction with a st ered testing interval (one-i half of the valves at least once per 18 mh. ( and all valves within 40 months), provided that there is a requirement to conduct additional testing when a valve is found to exceed that tolerance (two additional valves for each valve found with a setpoint outside the 3% tolerance).
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- All valves removed for maintenance or testing must be reset to 11% prior ,g, to plant startup.
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December 29, 1992 Upon-issuance of the safet'y evaluation report for NEDC-31753P, which describes this position in greater detail, the staff will prepare proposed conforming changes to each of the STS for the Owners Groups'-review and comment. Based on the foregoing position, we consider the subject Action Item #98 resolved, Sincerely, hl -
William T. Russell, Associate Director for Inspection and Technical Assessment-Office of Nuclear Reactor Regulation cc: W. Hall, NUMARC i
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Decemberc '.9,1992 -
-l Upon issuance of the safety evaluation report for NEDC-31753P, which describes this position in greater detail, the _ staff will prepare proposed conforming changes to each of the STS for the Owners Groups' review and comment. Based on the foregoing position, we consider the subject Action Item #98 resolved.-
Sincerely, g,4 1nal Sbned B[
William T. Russell, Associate Director for Inspection and Technical Assessment Office of Nuclear Reactor Regulation cc: W. Hall, NUMARC DISTRIBUTION:
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. Given the above, we consider Action List Item #98 resolved. When available, my staff will provide each of the TS owners group' chairmen with a ccpy of the Staff's SER pertaining to our review of NEDC-31753P.
Sincerely, William T. Russell, Associate Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comraission DISTRIBUT10Hi OTSB R/F DORS R/F Central Files PDR WTRussell SHWeiss JGPartlow GHMarcus BKGrimes .AEChaffee CIGrimes '
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