ML20246E768

Forwards Rev 14 to Augmented & Accelerated Inservice Insp Program Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program

ML20246E768
Person / Time
Site:	Sequoyah
Issue date:	05/05/1989
From:	Fox C TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20246E773	List: ML20246E768 ML20246E777
References
NUDOCS 8905120014
Download: ML20246E768 (3)

Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place MAY 051989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority )

SEQUOYAH NUCLEAR PLANT (SQN) - AUGMENTED AND ACCELERATED INSERVICE INSPECTION (ISI). PROGRAM FOR UNIT 1

References:

1. TVA letter to NRC dated January 30, 1987, " Draft Copy of the NRC Safety Evaluation on Welding for Sequoyah Units 1 and 2"

2. NRC Safety Evaluatio'n Report on Tennessee Valley Authority:

Sequoyah Nuclear Performance Plan, dated May 1988

3. TVA letter to NRC dated November 9, 1988, "Sequoyah Nuclear Plant (SQN) - Augmented and Accelerated In-Service Inspection Program for Unit 2" Enclosed is TVA's revised ISI program (surveillance instruction [SI) 114.1, Revision 14) for SQN unit 1. Revision 14 incorporates the augmented and accelerated field weld program into TVA's ISI program for unit 1. Revision 14 ,

also contains programmatic changes that were provided by Revisions 12 and 13.

Revision 12 incorporated a revised component support appendix and added two supports. Revision 13 added support 1-RCH-130.

TVA, by Reference 1, committed to revise SQN's American Society of Mechanical Engineers (ASME) Code,Section XI ISI program to include the following features. The four items below are quoted directly from TVA's January 30, 1987, letter.

1. 100 percent of the ASME Class 1 and 2 piping field welds identified to be examined in the first 10-year in-service interval and which remain to be examined will be scheduled for examinatin (sic) in the next two consecutive refueling outages following the submittal of the rev' sed plan and the restart of any unit.

2. 100 percent of the ASME Class 1 and 2 pipe support field welds j identified to be examined in the first 10-year in-service interval and which remain to be examined will be scheduled for examination in the next two consecutive refueling outages following the submittal of the revised plan and the restart of r[

l any unit. ,

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MAY 051989 U.S. Nuclear Regulatory Commission

3. Major component support welds made in the field on the reactor vessel, steam generator, pressurizer, and reactor coolant pumps that have been identified to be examined in the first 10-year program and which remain to be examined will be scheduled for examination in the next two consecutive refueling outages following the submittal of the revised program and the restart of any unit.

4. Where possible, the program period examination percentages will be maintained as required by the code in the Tables IHB-2412-1 and IWC-2412-1 (Inspection Program B). Note that the required percentages may not be met on specific systems, categories, or item Nos because certain systems contain a large number of socket welds which are field welds and the majority of pipe support welds are field welds. Where conflicts with the code exam percentage requirements and the augmented / accelerated programs are identified specific requests for relief will be added in the revised program.

These program elements were paraphrased by NRC on pages 3-49 and 3-50 of NRC's May 1988 safety evaluation report (SER) on SQN's Nuclear Performance Plan.

Because of phraseology differences between the SER and TVA's January 30, 1987, response, each of the four elements of the program has been restated from TVA's January 1987 response. This was done to maintain the original level of detail anc to avoid any misinterpretation regarding the identification of the welds requiring examination under this accelerated program. In addition to the accelerated field weld program, TVA has incorporated new drawings; inspection requirements from NRC Bulletins 88-08, 88-09, and 88-11.; and a new section (Section 17.1) for selection of additional samples.

In accordant a with Reference 3, TVA completed its commitment for providing NRC the accelerated field weld program fc,r unit 2.

Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734.

Very truly yours, TENNESSEE VALLEY AUTHORITY Yh -I

?

7 dT C. H. Fox' Jr., Vice President and Nuclear Technical Director Enclosure cc: See page 3 j

U.S. Nuclear Regulatory Commission W 051989 cc (Enclosure):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555'Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II-101 Marietta Street, NW, Suite 2900 Atlanta . Georgia 30323 Sequoyah Resident Inspector -

Sequoyah Nuclear Plant 2600 Igou Ferry. Road Soddy Daisy, Tennessee 37379

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