ML20112F636
| ML20112F636 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte |
| Issue date: | 12/12/1984 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-84, REF-PT21-85-017-000 NCR-3675, PT21-85-017-000, PT21-85-17, NUDOCS 8501150453 | |
| Download: ML20112F636 (2) | |
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i U.S. Nuclear Regulatory Commission Region II
> Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNIT 1 - EXCESSIVE WIRING DEFICIENCIES IN BABCOCK
' AND WILCOX SUPPLIED CABINETS - BLRD-50-438/84 FIRST INTERIM REPORT
' The subject deficiency was initially mported to NRC-0IE Inspector
' P. E. Fredrickson on November 14, 198 4 in acocedance with 10 CFR 50.55(e) as NCR 3675. Enclosed is our.first interim report. We expect to a
submit our next sport on or about June 13, 1985. We consider 10 CFR Part
- 21. applicable to this deficiency.
-If"you have any questions, please get in touch with R. H. Shell at
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FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY i
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. Huf am Manager L
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W. Richard C. DeYoung, Director (Enblosure)
Office of Inspection and Enforcement -
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power. Operations i*
1100 Circle 75 Parkway,' Suite 1500 Atlanta, Georgia '30339 I
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNIT 1 OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE BLRD-50-438/84-58 NCR 3675 10 CFR 50.55(e)
FIRST INTERIM REPORT Descriptier. of Deficiency The essential safety features actuation system (ESFAS) control cabinets for Bellefonte Nuclear Plant (BLN) were supplied to TVA by Babcock and Wilcox (B&W) of Lynchburg, Virginia on the BLN NSSS contract. The initial site inspection of these cabinets resulted in at least 68 separate noncon-formance raports (NCR) being issued for wiring and drawing deficiencies. A large number of the NCRs identify installed wiring which does not conform to B&W drawings with respect to color codes, wire size or configuration.
Several NCRs idettify breakers which are of a higher rating than the B&W drawings show. While none of these 68 NCRs represent a significant condition adverse to quality on an individual basis, they collectively indicate a significant breakdown in B&W's quality assurance / quality control
, (QA/QC) program for BLN.
4 Interim Progress The subject condition has been referred to TVA's Office of Engineering (OE) for further evaluation. OE has forwarded. copies of the various individual NCRs to B&W and is awaiting a response from B&W to determine what corrective actions are necessary.
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