ML20127P524

Forwards Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 & Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2

ML20127P524
Person / Time
Site:	Sequoyah
Issue date:	01/28/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127P527	List: ML20127P524 ML20127P546 ML20127P636
References
TAC-M81349, TAC-M81350, TAC-M83977, NUDOCS 9302010309
Download: ML20127P524 (5)

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Tennessee Valley Authonty. Post Omce Box 2000, Soddy Da sy. Tennence 37379-2000 Roben A. fenoch Vice Presdent. Secpoyah Nuclear Plant January 28, 1993

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - REVISED IN-SERVICE INSPECTION (ISI) PROGRAM

References:

1. NRC letter to 'IVA dated January 6,1993, " Request for Relief From American Society of Mechanical EngineersSection XI Code Requirements - First Ten-Year Interval Inservice Inspection - Sequoyah Nuclear Plant, Unit 1 (TAC M83977)"

2. NRC letter to TVA dated August 31, 1992, " Request for Relief From American Society of Mechanical EngineersSection XI Code Requirements - Reactor Vessel Nozzle to Vessel Weld Exams. Sequoyah Nuclear Plant Units 1 and 2 (TAC Nos. M81349 and M61350)"

3. TVA letter to NRC dated June 15, 1992 In the Referer.ce 3 letter, TVA sub:aitted Revision 17 to SQN's Unit 1 ISI pr. gram and Revision 16 to SQN's Unit 2 ISI program. These program revisions contained new requests for relief for each unit and were submitted for NRC review and approval betore implementation. NRC has evaluated the requests for relief at sociated with SQN Unit 1 in the Reference 1 and 2 letters. The requests for relief associated with SQN Unit 2 are under evaluation by NRC.

Beyond.the program revisions contained in TVA's Reference 3 letter, SQN's ISI program for each unit has undergone three additional revisions. The Unit 1 ISI program is currently at Revision Level 20 and the Unit 2 ISI program is at Revision Level 19. For the purpose of maintaining 3 continuity, a revision summary is provided in Enclosure 1.

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U.S._ Nuclear R'egulatory Commission Page12-January 28, 1993 Updated copies of SQN's current ISI procram are being provided to you for review,1 No-new relief requents were added to the Unit 1 ISI program.

Accordingly, this Unit 1 program revision is provided for information only. One new requeat for relief was added to the Unit 2 ISI program.

The new request for relief for Unit 2 is entitled "2-ISI-19." Relief Request 2-ISI-19 is associated with five welds that were examined during the Unit 2 Cycle 5 refueling outage. Full code examination coverage was not achieved because of system configuration.

Enclosure 2 contains a complete copy of SQN's Unit 1 ISI program.

Enclosure 3 contains a complete copy of SQN's Unit 2 ISI program, which includes Relief Request 2-IS1-19.

NRC review and appruval of 2-ISI-19 are requested to support ISI activities during the Unit 2 Cycle 6 refueling outage. The end of the first 10-year IGI interval for Unit 2 is February 21, 1995. Since the last scheduled outage before the end of the 10-year ISI interval is the Unit 2 Cycle 6 (U2C6) refueling outage, TVA requests NRC review and response be provided on a schedule to support preplanning of the ISI activities for the U206 refueling outage. This outage is currently scheduled to begin September 17, 1993.

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

Sincerely, bk$ M ^-

Robert A. Fenech ec (Enclosures):

Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockv111e Pike Rockville, Maryland 20852-2739 NRC Resident Inspector (w/o Enclosures)

Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3621 Mr..B. A. Wilson, Project Chief (w/o Enclosures)

U.S. Nuclear Regulatory Commission Region II' 101 Marietta Street, NW, Suite.2900 Atlanta, Georgia 30323-0199

ENCLOSURE 1 Revision Summary of Sequoyah Nuclear Plant 's In-Service Inspection Program; Unit _1-

1. Surveillance Instruction (SI) 114.1, "ASME Section XI Inservice Inspection Program," Revision 18 dated,May 8, 1992,_is a general

. l revision to incorporate organizational 1 changes, nuclear power standard changes, and references to procedures. . 'This revision also added the use of radiographic examination to the_ augmented section on feedwater nozzles. Revision 18 included'one integral attachment to the successive examination table. No new requests for relief (RFRs)-

were added.

2. SI-114.1, Revision 19, dated July 29, 1992, incorporated a reference to standardize the nondestructive examination (NDE) techniques.  :

personnel qualifications, weld reference system, and standards for examination evaluation to the American Society of Mechanical Engineers (ASME)Section XI,1986 Edition. The support count on SQN's essential raw cooling water (ERCW) and component cooling systems was updated because of modifications to these systems. The weld count on SQN's reactor coolant system (RCS) was revised because of a weld review. References to other procedures were updated, and a reference to preservice examinations in the augmented section on reactor vessel nozzles was added. No new RFRs were added.

3. SI-114.1, Revision 20, dated December 16, 1992, revised augmented Sections 5.3, 5.8, and 20.0 for clarification of responsibilities.- A typographical error in Section 16.6 was corrected. Sections 17.1.2, 7.1.3, 7.1.5, and Attachment 4 on the scheduling of the' reactor vessel nozzle-to-nozzle welds, nozzle inside radius sections, and nozzle-to-safe-end welds were revised. Organization titles were revised to reflect current titles. Section 7.3.8 was anved to Augmented Section 20.4. Appendix D, Sections 6.1.1, 6.1.2, 6.1.4, 6.1.6, 6.2.1, and Appendix A were. revised. Attachments 4, 5 6. and Developmental References 22.1.42 and 22.1.43 were added. ~~A definition for augmented examination was-added. Sections 20.1 and 20.11 were revised to add examination requirements by the site 1 Nuclear Engineering group. No new RFRs were added. l

. Unit _2

1. SI-114.2, Revision 17, dated May 8, 1992, is a general revision to.

incorporate organizational changes, nuclear power standard changes, and references to procedures. This revision also added the use of radiographic examination to the augmented section on feedwater nozzles. No new RFRs were added.

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2. SI-114.2, Revision 18.-dated July 29, 1992, incorporated a reference to standardize the NDE techniques, personnel qualifications, weld reference system, and standards for examination evaluation to the-ASME Section XI, 1986 Edition. This revision updated the weld and-support counts to SQN's residual heat removal system because-of-a- -

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system modification. Two ERCW supports =were added because of- '

modifications in the second' period. The weld count on RCS was revised because of a wold review. References to other procedures were updated and a reference--to preservice examinations in the augmented section on reactor vessel nozzles was added. - .RFR 2-JSI -

was added.~

3. SI-114.1, Revision 19, dated December 16,'1992, revised augmented' sections 5.3, 5.8 and 20.0 for clarification of responsibilities.- A typographical error in Section 16.6 was corrected. . Sections 7.1.2,_

7.1.3, 7.1.5. and Attachment 4 on the'acheduling of-the reactor vessel nozzle-to-nozzle welds, nozzle inside radius sections .and nozzle to safe end welds were revised.- Organization titles were revised to reflect current titles. Section 7.3.8 was moved to- ,

Augmented Section 20.4. Appendix D. Sections 6.1.1, 6.1.2, 6.1.4, 6.1.6, 6.2.1, and Appendix A were revised. Appendix A was revised for editorial changes, and information was transferred to the newly created Attachments 4, 5, and 6. References- 22.1.42, 22.1.43, and 22.1.44 were added.- Sections 20.1 and-20.11 were revised.to add examination requirements by-Nuclear Engineering. No new RFRs were added.

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ENCLOSURE 2 IN-SERVICE-INSPECTION PROGRAM FOR

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SEQUOYAll NUCLEAR. PLANT -~ UNIT' 1 '(REVISION 20)--

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