ML20011A317
| ML20011A317 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 09/30/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8110090296 | |
| Download: ML20011A317 (2) | |
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de TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II j Septenbier 30, 1981 BLRD-50-438/81-38
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L-I Mr. James P. O'Reilly, Director Office of Inspection and Enforcement u.s.gr U.S. Nuclear Regulatory Cosmiission
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Region II - Suite 3100 y,
101 Marietta Street y/K,kg
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Atlanta, Gecrgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - STEAM PRESSURE REGULATOR MALFUNCTION - BLRL-50-438/81-38, BLRD-50-439/81 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on May 19, 1981, in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8105. This was followed by our first interim report dated June 18, 1981. Enclosed is our second interim report. We expect to submit our next report by December 31, 1981. We consider 10 CFR Part 21 to be applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE. VALLEY AUTHORITY b
LAA L. M. Mi'ls, Manager duelear R lation an afety Enclosure cc:
Mr. Victor Stello, Jr., Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. James McFarland (Enclosure)
Senior Project Manager
[8 Babcock & Wilcox Company pt f P.O. Box 1260 Lynchburg, Virginia 24505 0 ohg PDR
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I ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 j
1 STEAM PRESSURE REGULATOR MALFUNCTION l
BLRD 438/81-38, BLRD-50-439/81-41 10 CPR 50.55(e)
SECOND IlfrERIM REPORT Description of Deficiency
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During a May 6, 1981, telecon between TVA and B&W, B&W was not able to specify the minimum departure from nucleate boiling ratio (DNBR) which would result'should a steam pre sure regulator malfunction occur.
Therefore, TVA is unable to verify the extent of damage s,ttich would result from a steam pressure regulator malfunction. This is unacceptable since the Chapter 15 FSAR analysis states that the steam pressure regulator malfunction is bounded by the steam line break event. Also, the steam pressure regulator malfunction is a condition II event and, as such, must have a minimum DNER greater than 1.24, per section 4.2.3 3.5 of the FSAR. As stated above, B&W is unable to verify this.
i This condition may be applicable to other B&W-supplied NSSS; however it affects no other TVA plants since Bellefonte represents TVA's only B&W-supplied NSSS.
Interim Progress B&W has responded to the request for disposition noted in the first interim report. The response is being evaluated by TVA and preliminary indications are that further input from B&W will be necessary.
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