ML20215D370
| ML20215D370 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/10/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215D372 | List: |
| References | |
| NUDOCS 8612160342 | |
| Download: ML20215D370 (1) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place DEC 10 886 Director of Nuclear Reactor Regulation Attention:
Mr. B. Youngblood, Project Director PWR Project Directorate No. 4 Division of Pressurized Water Reactors (PWR)
Licensing A U.S. Nuclear Regulatory Cosumission Washington, D.C. 20555
Dear Mr. Youngblood:
In the Matter of
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Docket Nos. 50-327 j
Tennessee Valley Authority
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50-328 SEQUOTAH NUCLEAR PLANT - REVISED IN-SERVICE INSPECTION PROGRAM As a follow-up to our March 12, 1986 response to your rcquest for additional infornation, we have enclosed our revised In-service Inspection (ISI) Program Surveillance Instructions (SI) 114.1, Revision 7 and 114.2, Revision 7, for Sequoyah Nuclear Plant units 1 and 2, respectively. These are the current revis*.ons as indicated in the March 12, 1986 response with the exception that the program request for relief (RFR) ISI-6 was not withdrawn but was revised.
The decision to revise the RFR ISI-6 is based on a teleconference held on May 5,1986 between your program review staff and our ISI program section represtntatives and as a result of the information in an EPRI Report NP-4242, "Long-term Inspection Requirements for Nuclear Power Plants," dated March 1986. Also, the revised programs have new RFRs ISI-12 and ISI-13 for your review and approval.
f In addition, a review of our file information on Sequoyah unit 1 and 2 reactor i
vessels showed that the manufacturer, Rotterdamsche Droogdok Maatschappij (RDM), performed ultrasonic examinations of both vossel's beltline region segments and found no flaws in the base material that required repair welding. These reports are part of the reactor vessel design contract files supplied under the original RDM order Nos. 30.616 and 30.624, unit 1 and i
unit 2 respectively, and ordered by Westinghouse Electric Corporation (reference 54 F8 49966 BP).
In response to the item No. 2 of the request for 1
additional information made in the letter to H. C. Parris from E. C. Adensam dated November 18, 1985, this confirms that there are no base metal weld repairs in the vessel beltline region.
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i An Equal Opportunity Employer i
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r Director of Nuclear Reactor Regulation (N[CjQlggg This response and enclosure should complete all outstanding items from the original request.
If you have any questions concerning this issue, please call D. V. Goodin, of the Sequoyah Site Licensing Staff, at (615) 870-7462.
Very truly yours, ThMNESSEE VALLEY AUTHORITY
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R. Gridley, irector Nuclear Safe y and Licensing Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW Suite 2900 Atlanta, Georgia 30323 Mr. Carl Stahle, Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. G. G. Zech Director, TVA Projects U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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