ML20101F193

Forwards Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program Unit 1 & Rev 16 to Surveillance Instruction SI-114.2, ASME XI Inservice Insp Program Unit 2

ML20101F193
Person / Time
Site:	Sequoyah
Issue date:	06/15/1992
From:	Joshua Wilson TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101F196	List: ML20101F193 ML20101F201 ML20101F208
References
TAC-M59457, TAC-M59458, TAC-M80597, NUDOCS 9206240327
Download: ML20101F193 (5)

Text

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. - l June 15, 1992 U.S. Nuclear Regulatery Comnission ATTN: Document Control Desk Washingten D.C. 20555 Gentlemen:

In the Matter of ) Docket Noa. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - REJISED IN-SERVICE INSFECTION (ISI) PROGRAM

References:

1. NRC letter to TVA dated October 21, 1991, "First Ten-Year Interval Inservice Inspection Program Relief Request ISI-4, Sequoyah Nuclear Plant, Unit 1 (TAC NO. 80597)"

2. NRC letter te TVA dated February ): 1991, "First 10-Year Interval Inservice Inspection Program (TAC 59457) -

Sequoyah Nuclear Plant, Unit 1"

3. NRC letter to TVA dated February 7, 1991, "First 10-Year Intersal Inservice Inspectica Program, Revision 14 (TAC 59458) - Sequoyah Nuclear Plant, Unit 2" 4 NRC tter to TVA dated April 19, 1990, "First 10-Year Int - 'al Inrervice Inspection Prog en (TAC 59458) -

Src :jah Nuclear Plant, Unit 2" Ey References 1 through 4, NRC submitted to TVA the safety evaluation reports (SERs) for SQN's ISI program on Units 1 and 2. The referenced SERs state that, "any significant program changes such as additional requests for relief should be submitted for staff review and should not be implemented prior to approval by the staff." In accordance with this provision, TVA is submisting revisions to SQN's ISI program that contain new requests for relief for each unit.

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U.S. Nuclear Regulatory Commission Page_2 June 15, 1992 i

NRC review and isauance of the SERs for SQN's ISI program were based on Revision 14. For the purpose of maintaining historical continuity from Revision 14 to the present, an outline describing the changesffor each revision to the program is provided itc Enclosure 1.

l 1

Enclosure 2 contains Revision 17 to SQN's Unit 1 IS1 program. Five new '

relief requests (ISI-14, -15, -16, -17, and -18) were added under i Revision 17. Enclosure 3 contains Revision-16 to SQN's Unit 2 ISI )

pregram. Four new relief requests (ISI-15. -16, -17, -18) were added l under Revision 16.

The end of the first 10-year ISI interval is September 15, 1994, for Unit 1 and February 21, 1995, for Unit 2. The last scheduled refueling l outage within the first 10-year interval is the Cycle 6 refueling outage I for each unit. Consequently, TVA requests NRC review and response be 2 provided by October 1, 1992, in order to support preplanning of the ISI activities for the Cycle 6 refueling outage on Unit 1.

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

E Sincerely,  ;

(3 e 3

1 k .

/ SAb

7. L. Wilson .

Enclosures cc: Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North i 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Sequoyah Nuclear Plant 7 .2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 ,

Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II '

101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 o

f

ENCLOSURE 1 DESCRIPTION OF CHANCES TO SEQUOYAH NUCLEAR PIANT IN-SERVICE INSPECTION PROGFAM e

a

1 Uni.t 1 In-SerYicLInspentlon_(ISILErogram. Revisions I. Revision 15, dated November 14, 1990, was a general revision that incorporated references to TVA's Nuclear Power Standard; revised various ISI drawings; tevised sections of the program to better define code requirements; incorporated a statement to allow use of ,

the 1984 Edition of American Society of Nondestructive Testing l (ASNT), SNT-TC-1A; incorporated Code Cases N-435-1 and N-460; and .

corrected a typographical error in the inspection requirement of  ;

request for relief (RFR) ISI-13.

II. Revision 16. dated October 2, 1991, was a general revision that incorporated organizational title changes, various requirements from TVA Nuclear Power Standards, and system configuration changes

• to reflect various plant modifications. This revision also updated augmented inspection sections; incorporated Code Cases N-402, N-426, and N-461; added ref erences to the NRC safety evaluation  ?

report on RFRs; and removed ISI drawings for issuance through SQN's Document Control and Records Management system. f III. Revision 17, doted February 12, 1992, was a general revision that E defined organizational responsibilities, incorporated System configuration changes to reflect various plant modifications, revised program sections to better define code requirements, included an NRC safety evaluation report summary on each ISI RFR, I and added five new RFRs (ISI-14, -15, -16, -17, and -18 ) . ,

The five Unit 1 RFRs requiring NRC review and approval are as follows l (reference Enclosure 2 Attachment 3, to Surveillance Instruction

{SIl 114.1):  ;

• RFR ISI-14 addresses the reactor vessel (RV) outlet nozzle, inside I radius sections, and nozzle-to-vessel weld 10-year examination l frequency. RFR ISI-14 was previously submitted to NRC for review by TVA letter dated August 21, 1991.

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• RFR ISI-15 addresses the main steam system integrally welded support l attachments. Design configuration prohibits examination of four i attachments. j

• RFP ISI-16 addresses the residual heat removal (RHR) heat exchanger c'rcumferential shell welds. Design configuration limits examination ,

on one shell weld for each RHR heat exchanger.

-* RFR ISI-17 addresses piping integrally welded support attachments.

Design configuration limits examination on one attachment.

I

• RFR ISI-18 addresses the RV closure head-to-flange weld. Design f configuration limits examination of the RV closure head weld.

Unill_lSLErogram_ Revisions ,

I. Revision 15, dated November 14, 1990, was a general revision that incorporated references to TVA's Nuclear Power Standard; revised various ISI drawings; revised sections of the program to better l l define code requirements; incorporated a statement to allow use of  !

the 1984 Edition of ASNT, SNT-TC-1A; incorporated Code Cases N-435-1 and N-460; and corrected a typographical error in the j inspection requirement of RFR ISI-13.

1

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II. Revision 16, dated February 12, 1992, was a general revision to define organizational responsibilities, incorporate system configuration changes to reflect various plant modifications, and to revise program sections to better define code requirements.

This revision also updated augmented inspection sections; incorporated Code Cases N-402, N-426, and N-461; added NRC safety evaluation report summary on each RFR; and removed ISI drawings to issue through SQN's Document Control and Records fianagement system. This revision added four new RFRs (ISI-15, 17, and

-18).

Note: In accordance with the technical evaluation report submitted with the NRC safety evaluation report (see page 22) for Unit 2 dated April 19, 1990, RFR ISI-3 piping weld RC-33 has been selected in lieu of SIF-128 for the ISI sample during the first 10-year ISI _

interval.

The four Unit 2 RFRs requiring NRC review and approval are as follows (reference Enclosure 3, Attachment 3, of SI-114.2):

• RFR ISI-15 addresses the RV outlet nozzle, inside radius sections, and nozzle-to-vessel weld 10-year examination f requency. RFR ISI-15 was previously submitted to NRC for review by TVA letter date4, August 21, 1991, i'

• RER ISI-16 addresses the FHR heat exchanger circumferential shell welds. Design configuration limits examination on one shell weld for each RHR heat exchanger.

• RFR ISI-17 addresses piping integrally welded support attachments.

Design configuration limits namination on three attachments.

• RFR ISI-18 addresses the RV closure head-to-flange weld. Lesign configuration limits examination of the RV closure head weld. -