ML20082K411

Forwards Supplemental Response to Rev 2 to IE Bulletin 79-13.Results of Unit 1 Augmented Insp of Feedwater Sys Piping & Supports Submitted on 821229.Review of Unit 2 Radiographs Revealed No Indication of Cracking

ML20082K411
Person / Time
Site:	Sequoyah
Issue date:	11/14/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820 IEB-79-13, NUDOCS 8312050154
Download: ML20082K411 (2)

Text

,

TENNE 8SEEnVALLEY AUTHORITY

'?-

gr; CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tdwer II 03 Il01,'l$ p f9V GP '4 1903 s

U.S. Nuclear Regulatory Commission Region II Attn:

Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - 0FFICE OF INSPECTION AND ENFORCEMENT BULLETIN 79-13 REVISION 2 - RII: JP0 50-327, 50-328 - SUPPLEMENTAL

RESPONSE

In my January 31, 1980 letter to you, we agreed to perform the inspections required by item 2 of the bulletin during the first refueling outage for the respective units. A subsequent request for relief from the inspections was submitted by my September 15, 1982 letter to you.

The results of the augmented inspection of the feedwater system piping and.

supports for unit 1 of our Sequoyah Nuclear Plant were submitted by my December 29, 1982 letter to you. Enclosed are the results of the augmented inspection for unit 2.

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

. M. Mills, nager Nuclear Licensing Enclosure cc:

Mr. Richard C. DeYoung, Director (Enclo Office of Inspection and Enforcement U.S. Nuclear Regulatory Commissio(

Washington, D.C.

20555 Records Center (Enclosure)

Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8312050154 831114 DR ADOCK 05000 tlc 1983-TVA 5OTH ANNIVERSARY An Equal Opportunity Employer

"c' ENCLOSURE NRC-0IE BULLETIN 79-13, REVISION II SUPPLEMENTAL RESPONSE SEQUOYAH NUCLEAR PLANT, UNIT 2 In accordance with the reference bulletin, a radiographic examination was performed on all feedwater nozzle-to-pipe welds, the transition piece, and the transition piece-to-pipe welds including adjacent base metal equal to 1

two-wall thicknesses. In addition, a radiographic examination was l

performed on an area of base metal of the main feedwater line beginning at l

the centerline of the auxiliary feedwater to main feedwater weld and extending downstream one-pipe diameter. Evaluation of the radiographs was done in accordance with ASME Section III, Subsection NC, Article NC-5000, to 2-2T quality level in lieu of table NC-5111-1. A review of the radiographs revealed no indication of cracking.

The construction and/or vendor radiographs of the feedwater piping welds to the first support, excluding those listed above, were reviewed for compliance with the bulletin. One vendor radiograph (loop 1, elbow-to-pipe weld) did not comply with the 2-2T quality level; however, it should be noted that this weld was radiographed to meet the requirements thereof and did not indicate evidence of cracking. All other radiographs meet the bulletin requirements (i.e., 2-2T, quality level, weld quality, and technique) except in some instances where the base metal coverage of two-wall thicknesses was not attained on both cides of the weld. Since the thermal and geometric conditions do not exist at these locations to support stratification and striping and the radiographs were evaluated to the 2-2T quailty level, no additional radiograhy was performed on these welds.

Because of the limited access and the configuration of the feedwater line-to-containment penetration welds, an ultrasonic examination was performed in lieu of radiography. The ultrasonic examination was performed in accordance with TVA procedure SQ-UT-27, revision 0, which meets the requirements set forth by the ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition, Summer Addenda. The ultrasonic examination revealed no indication of cracking.

The radiographic and ultrasonic examination reports will be retained in permanent storage at the plant site.

_