ML20062C699
| ML20062C699 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 07/30/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8208050332 | |
| Download: ML20062C699 (2) | |
Text
.
TENNESSEE VALLEY AUTHORITYC pre '
CH ATTANOOG A. TENNESSEE 37401 l 'i f,[
' 's 400 Chestnut Street Tower II o
July 30,#pt98F// p 48 3
BLRD-50-438/81-38 BLRD-50-439/81-41 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 - STEAM PRESSURE REGULATOR MALFUNCIION - BLRD-50-438/81-38, BLRD-50-439/81 SIXTH 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 interim reports dated June 18, September 30, and December 17, 1981 and April 2 and June 29, 1982. Enclosed is our sixth interim report. We expect to submit our next report by October 12, 1982. 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 R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY p SW h L. M. Mills, Manager l
Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
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
$6
./
8208050332 820730 PDR ADOCK 05000438 f0 &
S PDR An Equal Opportunity Employer
p ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 STEAM PRESSURE REGULATOR MALFUNCTION NCR BLN NEB 8105 BLRD-50-438/81-38, BLRD-50-439/81-41 10 CFR 50.55(e)
SIXTH INTERIM REPORT Description of Deficiency During a May 6, 1981, telecon between TVA and B&W, B&W (Lynchburg, Virginia) was not able to specify the minimum departure from nucleate boiling ratio (DNBR) which would result should a steam pressure regulator malfunction occur. Therefore, TVA is unable to verify the extent of damage which 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 conditien II event and, as such, must have a minimum DNBR greater than 1.24, per section 4.2 3 3.5 of the FSAR. As stated above, B&W is unable to verify this.
This failure mode is being analyzed as a postulated design basis event. There is no evidence to believe that any deficiency exists which could result in a steam pressure regulator malfunction.
This condition may be applicable to other B&W-supplied NSSS; however, it affects no other TVA plants since BLN represents TVA's only B&W-supplied NSSS.
Interim Progress TVA has concluded a preliminary review of the B&W report and recommendations referenced in our previous response. TVA is in tentative agreement with the findings B&W submitbed, however, TVA has requested that B&W provide the details of the analysis performed including the input data used and details of the analytical model. TVA will base its final disposition of this matter on a review of the detailed data. TVA will provide a further response upon completion of this review.
3 0
,i
-