ML20079J730
| ML20079J730 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte |
| Issue date: | 12/20/1982 |
| 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 8212280328 | |
| Download: ML20079J730 (2) | |
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TENNESSEE VALLEY AUTHORITY
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- D saber 20, 1982 BLRD-50-438/82-45 BLRD-50-439/82-41 U.S. Nuclear Regulatory Commission Region II=
Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - B&W DESIGN OF REACTOR COOLANT SYSTEM SUPPORTS AND RESTRAINTS - BL*tD-50-438/82-45, BLRD-50-439/82 THIRD INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on June 18, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN BLP 8220. This was followed by our interim reports dated July 19 and September 24, 1982. Enclosed is our third interim report. We expect to submit our next report by June 20, 1983 If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY c
L. M. Mills, anager Nuclear Licensing i
Enclosure
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t'm. Richard C. DeYoung, Director (Enclosuro)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commissien Washington, D.C.
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l Mr. James McFarland (Enclosure)
Senior Project Manager Babcock & Wilcox Company P.O. Box 1260 Lynchburg, Virginia 24505
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8212280328 821220 PDR ADOCK 05000438 S
PDR 1 g elf An Equal Opportunity Employer
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 B&W DESIGN OF REACTOR COOLANT SYSTEM SUPPORTS AND RESTRAINTS 10 CFR 50.55(e) 7-NCR BLN BLP 8220 BLRD-50-438/82-45, BLRD-50-439/82-41 THIRD INTERIM REPORT Description of Deficiency I
The Babcock & Wilcox (B&W) design of Reactor Coolant System (RCS) supports and restraints was based on an erroneous assumption at the B&W-TVA interface. The B&W stress report for the RCS supports and restraints assumes that the TVA-supplied embedments are of equivalent strength to the B&W-designed attachments (FY = 50 ksi). TVA-supplied embedments are of lesser strength (FY = 36 ksi). Thus, welds and shear bars at the interface points are potentially undersized and overstressed.
There have been no similar deficiencies in the past for D&W-designed supports and restraints.
Interim Progress TVA has reviewed B&W's recommended disposition of the subject NCR and has returned comments to B&W for evaluation. Our next report will contain additional information.
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