ML20079K019
| ML20079K019 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 01/12/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8401240482 | |
| Download: ML20079K019 (2) | |
Text
l TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot Q h '~ g.S g (et Tower II 400 Chest January 12, 1984 BLRD-50-438/83-43 BLRD-50-439/83-36 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 - REACTOR BUILDING SUMP PH VALUES BY BABCOCK AND WILC0X - BLRD-50-438/83-43, BLRD-50-439/83 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector Linda Watson on June 23, 1983 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8337. This was followed by our interim report dateo July 21, 1983 Enclosed is our second interim report. We expect to submit our next report by July 18, 1984.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY D5 W fp L. M. Mills, Manager i
Nuclear Licensing Enclosure cc:
Mr. Michard 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 C'401240482 840112
'(
PDR ADOCK 05000438 8
PDR d((~ 17 1983-TVA SOTH ANNIVERSARY 19 An Equal Opportunity Employer
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 REACTOR BUILDING SUMP PH VALUES BY BABCOCK AND WILCOX BLRD-50-438/83-43, BLRD-50-439/83-36 NCR BLN NEB 8307 10 CFR 50.55(e)
SECOND INTERIM REPORT Description of Deficiency Babcock and Wilcox (B&W) is performing a recalculation of the Reactor Building (RB) sump pH values to include consideration of " dead" volumes not available for recirculation. The major contributor to the " dead" volume is the reactor vessel cavity (55 pcreent of total volume).
While performing this recalculation in response to NRC's FSAR Question 281.2, B&W has found some problem areas. Depending on where the break is assumed, the RB pH may exceed the limits set by the NRC (8.5 < pH 4: 11.0) for prevention of stress corrosion and for materials compatibility. Reference TVA letter K-7348 (NEB 821221 109) and B&W letter D-4535 (NEB 830328 633).
Interim Progress TVA has evaluated several options to resolve the concern. Based on this evaluation, TVA has chosen to perform an analysis in an attempt to show that the sump pH being outside the recommended limits set by the NRC is not detrimental to plant safety in either the short term or long term.
A f
4
+ -,,,
-