ML20071N574
| ML20071N574 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 09/24/1982 |
| 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 8210080222 | |
| Download: ML20071N574 (2) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II~
September 24, 1982 BLRD-50-438/82-45 BLRD-50-439/82-41
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- a UC U.S. Nuclear Regulatory Comission Region II Attn
Mr. James P. O'Reilly, Regional Administrator 0o 7
- 1. 5 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Z
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Dear Mr. O'Reilly:
c.c BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - B&W DESIGN OF REACTOR COOLANT SYSTEM SUPPORTS AND RESTRAINTS - BLRD-50-438/82-45, BLRD-50-439/82-41 SECOND 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 first interim report dated July 19, 1982. Enclosed is our second interim report. We expect to submit our next report by December 20, 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 L. M. Mills, Manager Nuclear Licensing Enclosure oc:
Mr. Richard C. DeYoung, Director (Enclosure) i Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. James McFarland (Enclosure)
Senior Project Manager Babcock & Wilcox Company P.O. Box 1260 Lynchburg, Virginia 24505
!OfTl 8210000222 B20924
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PDR ADDCK 05000438 8A
.Q PDR An Equal Opportunity Employer
i ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 B&W DESIGN OF REACTOR COOLANT SYSTEM SUPPORTS AND RESTRAINTS 10 CFR 50.55(e)
NCR BLN BLP 8220 BLRD-50.438/82-45, BLRD-50-439/82-41 y;ECOND INTERIM REPORT Description of Deficiency The Babcock & Wilecx (B&W) design of the 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 kai). Thus, welds and shear bars at the interface points are potentially undersized and overstressed.
There have been no similar deficiencies in the past for B&W-designed t
supports and restraints.
Interim Progress TVA has received the recormnended disposition of the subject NCR from B&W.
TVA is continuing to review the B&W-proposed resolution. Our next report will contain the results of TVA's review.
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