ML20095F027

Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05

ML20095F027
Person / Time
Site:	Sequoyah
Issue date:	12/12/1995
From:	Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20095F028	List: ML20095F027 ML20095F106
References
GL-95-05, GL-95-5, NUDOCS 9512180249
Download: ML20095F027 (3)

Text

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IUA Tenressee Vaney Authority Post omce Boa 20C0 Scody Dasy Tennessee 37379 December 12,1995 TVA-SON TS-95-23 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50 328 Tennessee Valley Authority )

SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)

CHANGE 95-23, " ALTERNATE PLUGGING CRITERIA (APC) FOR STEAM GENERATOR (S/G) TUBING - UNIT 2" In accordance with 10 CFR 50.90 we are enclosing a requested amendment to License DPR-79 to change the TSs of SON 2. The proposed change revises TS surveillance requirements and bases to incorporate alternate S/G tube plugging criteria at tube support plate (TSP) intersections. The approach taken is based on the guidance provided in Generic Letter (GL) 95-05, ' Voltage-Based Repair Criteria For Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking," for APC. TVA's proposed changes are similar to the SON Unit 1 TS amendment that was submitted on September 7,1995. The basis for the change is that APC maintains the structuralintegrity of the tubing during normal operating, transient, and postulated accident conditions.

The proposed TS change is identified in Enclosure 1. The justification of the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in Enclosure 3.

Enclosure 4 contains commitments that are made for Unit 2. Enclosure 5 provides TVA's responses to the guidance contained in GL 95-05 for Unit 2.

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l U.S. Nuclear Regulatory Commission Page 2 December 12,1995 J'

While S/G TSP tube degradation at SON is not expected to be significant, TVA is submitting this TS change in advance of the upcoming Unit 2 Cycle 7 refueling outage 4

to prevent an exigent request for APC implementation. If a sufficiently high number of TSPs outside diameter stress corrosion cracking indications are detected during SON's Unit 2 Cycle 7 refueling outage, use of the proposed APC will be preferred.

Therefore, NRC approval of this TS change is requested prior to the Unit 2 outage that is currently scheduled for April 1996.

Please note that the proposed TS change is based principally on the methodology documented in WCAP-13990. This WCAP was docketed to NRC under TS 9L09 on June 28,1994. As WCAP-13990 contains information proprietary to Westinghouse Electric Corporation, the application for withholding the affidavit (CAW-94-641) signed by Westinghouse, the proprietary information notice, and the copyright notice provided in Enclosure 7 of the June 28,1994, letter are in effect. Additional supporting methodology is provided in WCAP-14277, " Steam Line Break Rate and Tube Burst Probability Analysis Method for ODSCC at TSP Intersections, January 1995."

TVA requests a 45-day implementation period for this TS change following issuance.

Based on the unresolved industry issues on probe wear and variability, this proposed change will be limited to Unit 2 Cycle 8 operation only.

Please direct questions concerning this issue to W. C. Ludwig at (615) 843 7460.

Sincerely, kt Y.

, R. H. Shell Manager SON Site Licensing Sworn to and subscrged bef9re me

/c2d day of IVMNw///411995 006'A Y '

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i Notary public /

My Commission Expire's h /f[

Enclosures cc: See page 3

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1 U. S. Nuclear Regulatory Commission Page 3 December 12,1995 Enclosures cc (Enclosures):

D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 2739 Mr. Michael H. Mobley, Director (w/o Enclosures)

Division of Radiological Health 3rd Floor L & C Annex '

401 Church Street Nashville, Tennessee 37243-1532 NRC Resident inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379 3624 Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711