ML20062J260
| ML20062J260 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 08/10/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8208160313 | |
| Download: ML20062J260 (2) | |
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[)g TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374of hh f,
400 Chestnut Street Tower II p
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U.S. Nuclear Regulatory Commission
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Attn:
Mr. James P. O'Reilly, Regional Administrator w
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Atlanta, Georgia 30303 n
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - BABCOCK & WILCOX'S NONCONSERVATIVE ANALYSIS OF NEUTRON FLUX - NCR BLN NEB 8007 - SIXTH INTERIM REPORT On November 5, 1980, R. W. Wright, NRC-0IE Region II, was informed that the subject nonconformance was determined to be reportable in accordance with 10 CFR 50.55(e). This was followed by our interim reports dated December 3, 1980, March 30 and September 21, 1981, and February 22 and April 27,1982. Enclosed is our sixth interim report. We consider 10 CFR Part 21 to be applicable to this deficiency. We expect to submit our next report by November 19, 1982.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY pS h jps L. M. Mills, Manager i
Nuclear Licensing Enclosure co; Mr. Richard C. DeYoung, Director (Enclosure)
Offico of luspcotion and Enforcement U.S. Nuclear Regulatory Commission L
Washington, DC 20555 Mr. James McFarland (Enclosure)
Senior Project Manager Babcock & Wilcox Company P.O. Box 1260 Lynchburg, Virginia 24505 h1CIAL COPY 8208160313 820810 E d[
PDR ADOCK 05000438 An Equal Opportunity Employer
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 BABC0CK AND WILCOX'S (B.iW) NONCONSERVATIVE ANALYSIS OF NEUTRON FLUX NCR BLN IIEB 8007 10 CFR 50.55(e)
SIXTH INTERIM REPORT Description of Deficiency B&W's measurement errors assumed in determining Reactor Protection System (RPS) setpoints may be nonconservative under specf.fic plant conditions. These errors may allow operation outside the established safety limits in certain design basis events.
The events of concern are:
small overcooling and small steam line break; large steam line break in containment; and the rod ejection accident.
Interim Progress a
B&W has provided both cost and schedule data for both the analytical software fix and the alternate power measurement ( APM) hardware fix to this problem. TVA has reviewed both options and has selected the analytical software fix. We have instructed B&W, through our purchasing agent, to proceed with the software fix. TVA will provide more information on this matter in our next report.
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