RC-05-0135, Submittal of Information Requested by NRC for Integrity Evaluation for Future Operation Reactor Vessel Nozzle to Pipe Weld Regions (C-00-1392)

Submittal of Information Requested by NRC for Integrity Evaluation for Future Operation Reactor Vessel Nozzle to Pipe Weld Regions (C-00-1392)

ML052450149
Person / Time
Site:	Summer
Issue date:	08/26/2005
From:	Archie J South Carolina Electric & Gas Co
To:	Martin R Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-05-0135, TAC MC5751
Download: ML052450149 (3)

Text

Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 August 26, 2005 RC-05-0135 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTN: Mr. R. E. Martin

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 SUBMITTAL OF INFORMATION REQUESTED BY NRC FOR INTEGRITY EVALUATION FOR FUTURE OPERATION REACTOR VESSEL NOZZLE TO PIPE WELD REGIONS (C-00-1392)

Reference:

1. R. E. Martin (NRC) Draft letter to J. B. Archie (SCE&G), "Virgil C. Summer Follow-Up Letter Regarding Inspection of Reactor Vessel Nozzle Welds" (TAC MC5751) [ADAMS Ascension Number ML051810662], dated 06/28/2005 - 08/08/2005 FAX copy

2. Stephen A. Byrne (SCE&G) letter RC-03-0231 to Document Control Desk (NRC), Submittal of Information Requested by NRC for Integrity Evaluation for Future Operation Virgil C. Summer Nuclear Station (VCSNS), dated November 6, 2003 On November 6, 2003, South Carolina Electric & Gas Company (SCE&G) submitted through Reference 2, the results of activities performed in refueling outage RF-14 as part of the 10 year ASME Inservice Inspection (ISI) for VCSNS. This submittal was a follow up to examinations initiated as a result of the NRC evaluation of VCSNS RF-12 for a cracked weld in the Reactor Coolant System "A" loop piping and RF-13 for implementation of Mechanical Stress Improvement Process (MSIP). SCE&G stated the position that from review and evaluation of the results of these activities that VCSNS was safe to start up and operate in the future in accordance with the requirements of ASME Code. Also, SCE&G requested through the\

referenced letter that the NRC allow SCE&G to resume ASME Code examinations and frequencies without any additional prescribed examinations.

The NRC VCSNS Project Manager has drafted the resultant safety evaluation (SE) to document the NRC acceptance of these activities and authorize resumption of ASME Code Inspections and frequencies (Reference 1). The referenced draft indicated the need for SCE&G to provide the inspection schedule and plant program source for future inspections of the hot leg and cold leg nozzle welds for the VCSNS reactor vessel.

0uQ1 SCE&G I Virgil CSummer Nuclear Station

• P.0.Box 88 . Jenkinsville, South Carolina 29065 .T(803) 345.5209 . www.scana.aom

I Document Control Desk C-00-1 392 RC-05-0135 Page 2 of 2 These inspections are identified and controlled through the Third Interval Inservice Inspection Program Plan for V. C. Summer Nuclear Station, VCS Manual ISE-5. Attached is the Reactor Vessel Nozzle Examination Schedule for Inspection Interval Ill.

For the Reactor Vessel A hot-leg and cold-leg nozzle to pipe welds, the B cold-leg nozzle to pipe weld, and the C hot-leg and cold-leg nozzle to pipe welds, reexamination will occur once in the third ISI interval. The inspections for these welds will be performed in the next 10-Year ISI Outage that is currently scheduled for RF-20 in the Fall of 2012.

For the B hot-leg, the accepted flaw will be reexamined during the next three successive inspection periods (as defined in the VCSNS Inservice Inspection [ISI] Plan) in accordance with IWB-2420 (b) and (c) requirements. These augmented inspections are scheduled through the VCSNS Maintenance Program, SAP-601, "Application, Scheduling and Handling of Maintenance Activities", and will be performed in RF-16 (Fall 2006, Work Order No. 0509708),

RF-18 (Fall 2009, Work Order No. 0509709), and RF-20 (in conjunction with the Third Inspection Interval 10 Year ISI, Fall 2012). If the results are acceptable, IWB-2420 (c) permits the utility to revert to the original ISI Plan after these reexaminations. This approach will provide definitive evidence that the B hot leg nozzle to pipe weld continues to be acceptable per the requirements of the Code. The three successive examination periods for the hot leg nozzle to pipe weld commenced in the third ISI Interval that began January 2004.

SCE&G has verified that information provided in Reference 1 is correct.

If you have any questions or require additional information, please contact Mr. Ronald B. Clary at (803) 345-4757.

Verytr Iyours, y B. rchie JT/JBAldr Attachment c: N. 0. Lorick S. A. Byrne N. S. Carns T. G. Eppink R. J. White W. D. Travers R. E. Martin NRC Resident Inspector K. M. Sutton RTS (C-00-1 392)

File (810.58)

DMS (RC-05-0135)

Document Control Desk Attachment C-00-1 392 RC-05-0135 Page 1 of 1 Reactor Vessel Nozzle Examination Schedule Interval III Component ID Component Description Category Item Outage 1-4100A-15 INCONEL WELD ELBOW/SAFE END R-A R1.20 RF20 1-410OA-16(DM) BIMETAL(INCONEL) WELD - RV LOOP A R-A R1.20 RF20 INLET NOZZLE TO SAFE END 1-41 OOA-33(DM) BIMETAL(INCONEL) WELD - RV NOZZLE R-A R1.15 RF20 BUTTER WELD 1-41 00A34(DM) BIMETAL(INCONEL) WELD - PIPE R-A R1.15 RF20 BUTTER WELD 1-41 OOA-35 NOZZLE-BUTTER TO PIPE-BUTTER R-A R1.15 RF20 WELD 1-4200A-1 (DM) SER COMMITTMENT, "B" LOOP HOT LEG AUG 02 RF1 6 1-41 OOA-1 (DM) SER COMMITTMENT, "B" LOOP HOT LEG AUG 02 RF1 8 1-4200A-1 (DM) BIMETAL(INCONEL) WELD - RV LOOP B R-A R1.15 RF20 OUTLET NOZZLE TO SAFE END WELD 1-420OA-2 SER COMMITTMENT, "B" LOOP HOT LEG AUG 02 RF1 6 1-4200A-2 SER COMMITTMENT, "B" LOOP HOT LEG AUG 02 RF18 1-4200A-2 INCONEL WELD - SAFE END TO PIPE R-A R1.15 RF20 1-4200A-1 5 INCONEL WELD - ELBOW TO SAFE END R-A R1.20 RF20 1-4200A-16(DM) BIMETAL(INCONEL) WELD - RV LOOP B R-A R1.20 RF20 INLET NOZZLE TO AFE END 1-4300A-1 (DM) BIMETAL(INCONEL) WELD - RVLOOP C R-A R1.15 RF20 OUTLET NOZZLE TO SAFE END 1-4300A-2 INCONEL WELD - SAFE END/PIPE R-A R1.15 RF20 1-4300A-15 INCONEL WELD - ELBOW TO SAFE END R-A R1.20 RF20 1-4300A-1 6(DM) BIMETAL(INCONEL) WELD - RV LOOP C R-A R1.20 RF20 INLET NOZZLE TO SAFE END