ML20065G412
| ML20065G412 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/04/1994 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20065G421 | List: |
| References | |
| LCV-0321, LCV-321, NUDOCS 9404120267 | |
| Download: ML20065G412 (2) | |
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' Georgit Power Company 40 inverness Centar Parkway Pcst Othce Bax 1295 Rrrningharn. Alabarra 35201 Tetepnam 205 87/ 7122 L
Georgia Power C. K. McCoy v,ce e,esdent nuou N em*"crem voce erw a.
April 4, 1994 LCV-0321 Docket Nos. 50-424 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk.
Washington, D. C. 20555 Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT RPV SURVEILLANCE CAPSULE TEST RESULTS In accordance with the requirements of 10 CFR 50, Appendix H, paragraph III A, Georgia Power Company (GPC) hereby submits the enclosed summary report,.WCAP-13931,
" Analysis of Capsule Y from the Georgia Power Company Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program," which concerns reactor vessel surveillance materials testing for Vogtle Electric Generating Plant, Unit 1 (VEGP-1). Specifically, the summary report presents results of the examination of reactor vessel material contained in reactor -
pressure vessel (RPV) surveillance capsule "Y", the'second capsule to be removed from the VEGP-1 reactor in the continuing surveillance program which monitors the effects of neutron irradiation of the VEGP-1 RPV materials under actual operating conditions. The subject RPV surveillance capsule was removed from the VEGP-1 RPV on April 5,1993, during the fourth refueling outage.
An evaluation of pressurized thermal shock for the VEGP Unit I reactor vessel has also been completed and is enclosed as WCAP-13932, " Evaluation of Pressurized Thermal Shock for the Vogtle Unit 1 Reactor Vessel."
i The surveillance capsule Y test results indicate that the transition temperature increases and upper shelf energy decreases are less than the Regulatory Guide 1.99 predictions; therefore, the results do not require a revision to the Technical Specificationsf However, a revision to the Technical Specifications is being prepared to address nonconservatisms in low temperature overpressure protection setpoints that were identified in Westinghouse Nuclear Safety Advisory L tter, NSAL 93-005A and subsequent NRC information notice.
93-58. The revision to the Technical Specifications will apply to both Vogtle Electric Generating Plant units and will incorporate the results of the capsule Y surveillance.
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Georgia Power h The evaluations in WCAP-13931 and WCAP-13932 include the effects of ASME Code Case N-514, since it is anticipated that the proposed Technical Specification change will l
use the code case. This code case was incorporated into the 1993 addenda of the 1992 l
edition of ASME Section XI. Since this addenda has not yet been incorporated into 10 f
CFR 50.55a, it will be necessary to request an exemption to allow the use of the code case. The request for the exemption will be included with the request for the license amendments for Technical Specifications based on the code case.
j Sincerely, C. K. McCoy CKM/HWM/gmb, WCAP-13931
!, WCAP-13932 l
cc: Georgia Power Compan_y l
Mr. J. B. Beasley, Jr.
l Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Hood, Licensing Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle l
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