ML20099K137

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Part 21 & Sixth Interim Deficiency Rept Re Deformation of Auxiliary Feedwater Header & Damage to Header Supports of B&W Steam Generators.Initially Reported on 820830.Next Rept Will Be Submitted by 850325
ML20099K137
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 11/08/1984
From: Hufham J
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-84, REF-PT21-85-073-000 PT21-85-073-000, PT21-85-73, NUDOCS 8411290328
Download: ML20099K137 (2)


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TENNESSEE VALLCY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tcwer II BLRD-50-438/82-64 3

BLRD-50-439/82-57

-U.S. Nuclear Ragulatory Commission Region II Attn:

Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - DESIGN PROBLEMS WITH STEAM GENERATORS - BLRD-50-438/82-64, BLRD-50-439/82 SIXTH INTERIM REPORT The rubject deficiency was initially reported to NRC-0IE Inspector D. Quick on August 30, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8210.

This was followed by our interim reports dated September 28 and November 29, 1982; January 28 and October 19, 1983; and April 25, 1984.

Encicsed is our sixth interim report. We expect to submit our next report by March 25, 1985. We consider 10 CFR Part 21 applicable to this deficiency.

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

Very truly yours, TENNESSEE VALLEY AUTHORITY I

bd J, W. Hufh, Manager LWensing Regulations Enclosure V

cc:

Mr. Richard C. DeYoung, Director (Enclosure)

Office of Inspection and Enforcenent 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 Ofofog0438 08 S

0FFICIAL COPY PDR MOD -

s An Equal Opportunity Employer l

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ENCLOSURE BELLEFONTE NUCLEAR. PLANT UNITS 1 AND 2 DESIGN PROBLEMS WITH STEAM GENERATORS BLRD-50-438/82-64,. BLRD-50-439/82-57 10'CFR 50.55(e)

NCR BLN NEB 8210 4

SIXTH INTERIM REPORT j'

Description of Deficiency i.

At the' July 7,1982, Babcock and Wilcox (B&W) Owner's Group meeting, B&W

. (Lynchburg, Virginia) indicated that recent inspections of steam generators

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(SGs) at 177FA B&W operating plants revealed deformation of the auxiliary j

feedwater (AFW) header and damage to the header supports. There was also evidence of contact between-the header and some adjacent SG tubes.

4 Investigations are in progress to determine the cause of these conditions.

I The Bellefonte header design is similar to the 177FA plant design except j

that AFW is introduced to the header in the lower portion of the SG j

(beneath the steam outlet nozzles) whereas the 177FA plant headers are j

located toward the top of the SG (in the superheat region). The postulated cause of.the deficiency was a sudden drop ~ of the header internal pressure resulting from the injection of a cold slug of AFW into the header whils l

the header was dry.

l Interim Progress i;

B&W has submitted and TVA has approved the following revised field change packages (FCPs) since the'fifth interim report:

)

i FCP No.

a Unit 1 Unit 2 Subject i

l 226 Revs. 1 and 2 245 Rev. 1 Permanent Installation of l

Header, Risers, and Restraints j

234 Rev. 2 249 Rev. 1 Capping AFW Inlet Nozzles for Original Internal j

Headers t

I j

TVA reviewed and commented on B&W's reports of the results of the analyses i

of the new AFW piping configuration for units 1 and 2.

B&W will l

incorporate TVA's comments and resubmit the reports for review.

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The status of hardware required to complete header installation is as follows: unit 1 header restraints and units 1 and 2 caps for the original i

AFW inlet nozzles have been received en site. TVA is awaiting delivery of the unit 2 header restraints.

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