ML20071B907

Responds to NRC 820602 Request for Addl Info Re IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Action Item 2 Requirements for Unit 2 Will Be Performed During Refueling Outage Scheduled for Fall 1983

ML20071B907
Person / Time
Site:	Sequoyah
Issue date:	02/18/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8303010284
Download: ML20071B907 (2)

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%3M 3nY TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 40'0 Chestnut Street Tower II'

February 18, ykf EB 24 A10 : 08 U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Snice 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

SEQUOYAH NUCLEAR PLANT'- RESPONSE TO IE BULLETIN NO. 82 DEGRADATION OF THREADED FASTENERS IN THE REACTOR COOLANT PRESSURE BOUNDARY OF PWR PLANTS In response to your letter dated June 2, 1982, provided is additional information on the subject bulletin. Please refer to a letter from D. S. Kammer to you dated August 2, 1982 which provided our initial submittal.

In response to the requirement of action item 4.a of the subject bulletin, maintenance procedures and quality assurance measures, adequate to meet the criteria for action item 1, are established and are being implemented.

In response to action-item 2, the following threaded fasteners were examined during the first refueling outage at Sequoyah Nuclear. Plant unit 1:

1. 32 manway closure studs (2 manways) on steam generator 1,

2. 32 manway closure studs (2 manways) on steam generator 4, and 3 8 bonnet studs on valve 68-563 located in a 6-inch diameter reactor coolant line.

The above listed items were the only items opened for inspection or maintenance that were identified'in the scope of the bulletin.

A'VT-1 (visual) examination.in accordance with TVA procedure N-VT-1, revision 3, and a fluorescent liquid penetrant examination in accordance with TVA procedure N-PT-7, revision 0, which meets the requirements of IWA-2210 and IWA-2220 of the ASME code section XI as required by the subject bulletin, were performed on each stud. These examinations revealed no evidence of degradation of the studs.

8303010284 830218 ~

PDR ADOCK 05000327

@ PDR An Equal Opportunity Employer -

U. S. Nuclear Regulatory Commission February 18, 1983 This report completes the requirements of this bulletin for unit 1. Action item 2 requirements for Sequoyah Nuclear Plant unit 2 will be performed during its first refueling outage scheduled for fall 1983 and reported shortly thereafter.

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

To the best of my knowledge, I declare the statements contained herein are complete and true.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M.' Mills, Manager Nuclear Licensing cc: Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i

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