ML20052G647
| ML20052G647 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 04/27/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8205180542 | |
| Download: ML20052G647 (2) | |
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m, TENNESSEE VALLEY AUTHORITY f?NRO REG!On -
"'LANTA.'GF~n $f 400 Chestnut Street Tower II April 27, D2%AY 2
^ S: 03 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. Jr.mes P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 j
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - BABC0CK & WILCOX'S NONCONSERVATIVE ANALYSIS OF NEUTRON FLUX - NCR BLN NEB 8007 - FIFTH INTERIM REPORT l
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, 1982.
Enclosed is our fifth interim report. We consider 10 CFR Part 21 to be applicable to this deficiency. We expect to submit our next report by August 9,-1982.
If you haw any questions concerning this matter, plea.se get in touch with 1
R. H. She.11 at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY
. M. Mi Is, fan ger j
Nuclear Regula tion and Safety i
Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. James McFarland (Enclosure)
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Senior Project Manager Babcock & Wilcox Company P.O. Box 1260 Lynchburg, Virginia 24505
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OFFICIAL C 8205180 W "g,2 I
An Equal Opportunity Employer '
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E!. CLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 BABC0CK AND WILC0X'S (B&W) NONCONSERVATIVE ANALYSIS OF NEUTRON FLUX NCR BLN NEB 8007 10 CFR 50.55(e)
FIFTH INTERIM REPORT Description of Deficiency B&W's measurement errors assumed in determining Reactor Protection System (RPS) setpoints may be nonconservative under specific 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 B&W has proposed both a hardware resolution and a software resolution to the. subject deficiency. TVA has instructed B&W to provide cost / benefit outlines for both proposed fixes.
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