ML20085D842
| ML20085D842 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 07/21/1983 |
| 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 8307290135 | |
| Download: ML20085D842 (2) | |
Text
N TEN gE VAtt!EM AUTHORITY p
pwANCO,G.b[d SEE 374ol 00 Chestnut Street Tower II BLRD-50-438/83-43 N
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 WILCOX - BLRD-50-438/83-43, BLRD-50-439/83 FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Linda Watson on June 23, 1983 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8307 Enclosed is our first interim report. We expect to submit our next report by January 17,198'i.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY D5 L (
h L. M. Mills, Manager
[
Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission L
Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 l
830729 5
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P'1 1983-TVA 5OTH ANNIVERS ARY l\\
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)
FIRST 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 percent of total volume). While performing this recalculation in response to NRC's FSAR Cuestion 281.2, B&W has found some problem areas. Depending on where the break is assumed, the RB pH may exceed the li: nits set by the NRC (8.5 < pH < 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 is studying the concern to determine the actual extent of the problem. On completion of this study, TVA will determine what must be done to resolve the concern and proceed to implement any design changes.
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