ML20072C274

First Interim Deficiency Rept Re Max Temp Inside Containment.Initially Reported on 830513.Util Requested B&W to Respond to Nonconformance Rept by 830715.Next Rept to Be Submitted by 830826.Also Reported Per Part 21

ML20072C274
Person / Time
Site:	Bellefonte
Issue date:	06/13/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, NCR-R-30, NUDOCS 8306210005
Download: ML20072C274 (2)

Text

...

i TE'NNESSEE VALLEY AUTHORITM.

O CHATTANOOGA, TENNESSEE 374ol

'A

/0,,/

4

~400 Chestnut Street Tower II gyd8///

'5 0gM 8 - p8: g8 June 13, 1983 4

BLRD-50-438/83-36 BLRD-50-439/83-32

.U.S. Nuclear Regulatory Coinnission Region II Attn: Mr. James P. O'Reilly, Regional Administrator l

101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - MAX] MUM TEMPERATURE INSIDE l

CONTAINMENT PROVIDED BY BABCOCK & WILCOX - BLRD-50-438/83-36, BLRD-50-439/83-32'- FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Linda Watson on May 13, 1983 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8306. Enclosed is our first interim report. We expect to submit our next report by August 26, 1983 We consider 10 CFR Part 21 applicable to this deficiency.

I If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.

4 Very truly yours, TENNESSEE VALLEY AUTHORITY

.\\

L. M. Mills, Manager Nuclear Licensing Enclosure l

cc:

Mr. Richard C.~DeYoung, Director (Enclosure)

Office of Inspection and Enforcement i

U.S. Nuclear Regulatory Commission I

Washington, D.C.

20555 Records Center (Enclosure)

Institute of Nuclear Power Operations 1100 Circle 75 Parkw::y, Suite 1500 Atlanta, Georgia 30339 i

l i

I

~~

B306210005 B30613 i

PDR ADDCK 05000438 0FFICIALWpC S

PDR

[h t\\

i An Equal Opportunity Employer

s-s s

' r*

ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 MAXIMUM TEMPERATURE INSIDE CONTAINMENT PROVIDED BY BABC0CK AND WILCOX BLRD-50-438/33-36, BLRD-50-439/83-32 10 CFR 50.55(e)

NCR R-30 FIRST INTERIM REPORT Description of Deficiency In the description of nonconformance (NCR) BLN ASB 8301, " Qualification of Protective Coatings," (reported separately) changes to the environmental criteria inside conLainment as stattd in the Eclicfente FS.4F uere reted.

Upon evaluating this NCH TVA personnel found that one criteria, the maximum containment temperature of 286 F, was provided by Babcock and Wilcox, Lynchburg, Virginia, prior to 1977 However, in 1977, TVA questioned the fact that the Loss of Coolant Accident (LOCA) induced temperature of 286 F would be the maximum temperature. Rudimentary hand calculations done by TVA engineers at that time indicated that a Main Steam Line Break (MSLB) could cause a temperature of approximately 390 F.

In subsequent correspondence between TVA and B&W in 1978, B&W changed the maximum containment temperature to 425 F.

At that time, TVA's Division of Engineering Design (EN DES) personnel failed to identify this discrepancy as a nonconformance as required by Engineering Design Quality Assurance Procedure, EN DES QAP 1.5.

Interim Progress

.TVA has written B&W concerning this NCR and has requested that B&W respond by July 15, 1983 During the 1977-78 time period, TVA requested that B&W begin requalification of various safety-related electrical equipment inside l

rontainmenu to the higher MSLB temperature. In addition, TVA has been using the new MSLB temperature in its electrical equipment environmental l

qualification program (10 CFR 50.49).

(

l l

l l

l

- * ~ * * - 4

.m