RC-04-0170, Reactor Vessel Radiation Surveillance Program

Reactor Vessel Radiation Surveillance Program

ML043010232
Person / Time
Site:	Summer
Issue date:	10/22/2004
From:	Archie J South Carolina Electric & Gas Co
To:	Cotton K Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-04-0170, WCAP-16298-NP, WCAP-16306-NP
Download: ML043010232 (2)

Text

Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY October 22, 2004 RC-04-0170 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Ms. K. R. Cotton Ladies and Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM Please find enclosed WCAP-16298-NP, Revision 0, "Analysis of Capsule Z from the South Carolina Electric & Gas Company V. C. Summer Reactor Vessel Radiation Surveillance Program" as required by 10CFR50 Appendix H Part IV. A. This technical report reflects the results of the tests performed on Capsule Z that was withdrawn from the reactor vessel during the 14th refueling outage at the V. C. Summer Nuclear Station (VCSNS). These tests are in accordance with the requirements of 10CFR50 Appendix H, Part IV. B. Additionally, per the requirements of 10CFR50 Appendix G, this WCAP contains the results that indicate that upper shelf energy greater than 50 ft-lbs is expected throughout the life of the vessel for all beltline materials.

Also enclosed is WCAP-16306-NP, Revision 0, "Evaluation of Pressurized Thermal Shock for V. C. Summer". This report was prepared to determine the RTPTS values for the VCSNS reactor vessel beltline based on the results of the Capsule Z evaluation. The conclusion of the report is that the beltline material in the VCSNS reactor vessel has end of life (EOL) RTpTs values below the screening criteria values of 2700 F for plates, forgings and longitudinal welds and below 300OF for circumferential welds at 56 EFPYs.

Based on the results of the testing, a change to the VCSNS Technical Specification heatup and cooldown curves, Figures 3.4-2 and 3.4-3, will be required. A Technical Specification change request will be submitted to the NRC to update these figures by June 30, 2005. As an interim measure, SCE&G will take prompt administrative control per the requirements of Administrative Letter 98-10 to temporarily address the necessary changes.

SCEUG I Virgil C.Summer Nuclear Station - P.0.Box 88 . Jenkinsville, South Carolina 29065

• T(803) 345.5209 *www.scanax.om

Document Control Desk 0-C-02-2822 RC-04-0170 Page 2 of 2 Should you have any questions, please contact Mr. Ron Clary at (803) 345-4757.

Ve~rulyyours, ey B. Arch AMM/JBA/mb Enclosures c: N. 0. Lorick N. S. Cams T. G. Eppink R. J. White W. D. Travers K. R. Cotton NRC Resident Inspector K. M. Sutton NSRC RTS (0-C-04-2135)

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