ML20127B863

Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 92-16,deleting TS Surveillance Requirement 4.4.10.b Re Supplemental Exam of Reactor Vessel Nozzles

ML20127B863
Person / Time
Site:	Sequoyah
Issue date:	01/08/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127B867	List: ML20127B863 ML20127B872
References
NUDOCS 9301130172
Download: ML20127B863 (3)

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1YA-SQN-TS-92-16 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Centlemen:

In the Matter of ) Docket Nos. 50-327 Tennesseu Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - TECHNICAL SPECIFICATION (TS) CHANGE 92 DELETION OF TS SURVEILLANCE REQUIREMENT (SR) 4.4.10.b - SUPPLEMENTAL EXAM OF REACTOR VESSEL N0ZZLES In accordance with 10 CFR Sd.90, we are enclosing a requested amendment to Licenses DPR-77 and DPR-79 to change the T5s of SQN Units 1 and 2.

The proposed change deletes a supplemental requirement (i.e.,

SR 4.4.10.b) associated with a 10-year in-service inspection (ISI) of the reactor vessel nozzios for underclad cracking.

The proposed TS change is identified in Enclosure 1. The justification for 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 provides the safety evaluation checklist (TVA-92-375 Revision 2) perf ormed by Westinghouse Electric Corporation in support of the proposed TS change.

This requirement is unique to the SQN TSs and is an additional requirement that was added during initial start-up. As discussed in Enclosures 3 and 4, sufficient technical information now exists to indicate that the supplemental exams required by the current TSs are no longer needed. TVA will be conducting the standard 10-year American Society of Mechanical Engineers (ASME)Section XI ultrasonic testing (UT) examination of the reactor pr sure vessel nozzles during the upcoming 9301130172 930108 / / 1 PDR ADOCK 05000327 Y P PDR -

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U.S. Nuclear Regulatory Cortunission Page 2 January 8, 1993 Cycle 6 refueling outages on both units. The ASME examinations, in conjunction with expanded UT examination coverage of the Unit 1. Loop 1 outlet nozzle, will bound the structurally significant underclad crack indications that were reported during the SQN preservice inspection.

The standard ASME 10-year ISI for SQN Units 1 and 2 is scheduled to be performed during their respective Cycle 6 refueling outages this year.

The supplemental TS inspections have been determined to add two days to the critieni path outage time for these refueling outages. Accordingly, NRC approval is requested before the Unit 1 Cycle 6 refueling outage, currently scheduled to begin April 2, 1993.

Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734 Sincerely, 9

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Robert A. Fenech Sworn to end substgibed before me h day of /

h u n y 1993 this _ h $ tu kcA Notary Public My Commission Expires 8 M h '

Enclosures '

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6 U.S. Nuclear Regulatory Commission Page 3 January 8, 1993 MAC:JDStDVG PMB Enclosures cc (Enclosures):

Mr. D._ E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 3

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 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199'

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