ML20086P836
| ML20086P836 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 02/17/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-84-160-000 PT21-84-160, PT21-84-160-000, NUDOCS 8402270357 | |
| Download: ML20086P836 (2) | |
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BLRD-50-438/83-59 BLRD-50-439/83-52 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101'Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 -DEFICIENT SQUARE ROOT EXTRACTOR MODULES FOR REACTOR PROTECTION SYSTEM BY BAILEY METER COMPANY
- BLRD-50-438/83-59, BLRD-50-439/83 SECOND INTERIM REPORT The subject deficiency was initially mported to NRC-0IE Inspector Linda Watson on November 14, 1983 in accordance with 10 CFR 50.55(e) as NCR 2517. This was followed by our interim report dated December 8,1983 Enclosed is our second frterim report. We expect to submit our next report by June 8,1984. We consider 10 CFR Part 21 applicable to this deficiency.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, nager Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339
'yFICI AL COPY 8402270357 840217 PDR ADOCK 05000438 O
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An Equal Opportunity Employer i
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ENCLOSURE BELLEFONTE NUCLEA9 PLANT UNITS 1 AND 2 DEFICIENT SQUARE ROOT f.XTRACTOR MODULES FOR REACTOR PROTECTION SYSTEN BY BAILEY METER COMPANY BLRD-50-438/83-59, BLRD-50-439/83-52 NCR 2517 10 CFR 50.55(e)
SECOND INTERIM REPORT Description of Deficiency Square root extractor modules were returned to the manufacturer, Bailey Meter Company, Wickliffe, Ohio, for rework to incorporate Babcock & Wilcox (B&W) field change package (FCP) No. 54. The rework was to add an enhanced input filter which would help to suppress turbulence-induced noise in the reactor protection system (RPS) rnsurement of reactor coolant system (RCS) flow, and thus, increase overall accuracy of the flow measurement.
When the reworked modules were returned from Bailey to the site, it was discovered that the module suboircuit board retaining hardware was loose, missing, or improperly installed.-
The cause of the deficiency is not known at this time.
Interim Progress TVA is still awaiting B&W's response to TVA letter K-8029 which requested B&W to determine root cause, corrective action, and action required to pmvent mourrence. TVA will provide more information after receipt and review of B&W's mply.
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