ML20115A365
| ML20115A365 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/06/1992 |
| From: | Skolds J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | George Wunder NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20115A367 | List: |
| References | |
| GL-91-01, GL-91-1, NUDOCS 9210140261 | |
| Download: ML20115A365 (2) | |
Text
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South Ce lina Eiretric & G:n Cornp:ny Johr L olds JenhnsWie, SC 290C5 Nuclear OM: eons (833; 345 4D40 GCE&G j
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October 6, 1992 f
Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. G. F. Wunder Gentlemen:
Subject; VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO NPF-12 TECHNICAL SPEClf! CATION CHANGE - TSP 910005 REACTOR Cu0LANT SYSTEM (RCS)
In accordance with 10CfR50.90, South Carolina Electric & Gas Company (SCE&G) is submitt;ng an amendment request to License NPf-12 to change the Technical Specifications (TS) for VC3NS.
The proposed change is a revision of TS 3/4.4.9, Figures 3.4-2 and 3.4-3 (P1 Curves). and the deletion of Table 4.4-5 and the referen e to it in Surveillance Requirement 4.4.9.1.2.
The purpose of this change is to provide new heat up and cool down curves consisteht with analysis performed on specimen X of VCSNS Pic'atton Surveillance Program. This analy!.5 (WCAP-12867) was sent to Ae USNRC via SCE&G letter of Apri' 26, 1992. The schedule for ren; oval of the reactor v2ssel material irradiation specimens is deleted from the TS based on the guidance provided by Generic Letter 91-01, Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimene. from Technical Specifications.
The amendment request is contained in the following enclosures:
Proposed TS Change Description and Safety Evaluation Deterrrination of No Significant flazards Consideration Also enclosed with this TS change is the VCSNS response to the revised Pressurized Thermal Shock Rule, 10CFR50.61 (Enclosure 4).
The report.
Evaluation of Pressurized Thermal Shock for V. C. Summer, WCAP-13209, indicates that the VCSNS nil-ductility reference temperature (RTPTS) values remain below the USNRC screening values for pressurized thermal shock (PTS) for the most limiting reactor vessel material, using the projected neutron fluence values for the end-of-life and 48 etfcctive full power years (EFPY).
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Document Control Desk Letter I
ISP 910005 Page 2 of 2 The proposed TS change has been reviewed and 0.pproved by the Plant Safety Review Conrnittee and tle Nuclear Safety Review ".ommittee.
I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information, and belief.
Should you have any questions concerning this issue, please call Mr. HN.;?el W. Gutierrez at (803) 345-4392 at your convenience.
Very truly yours, John L. Skolds MWG:1cd Enclosures c:
- 0. W. Dixon R. R. Mahan R. J. White S. D. Ebneter G. f. Wunder General Managers NRC Resident Inspector J. B. Knotts Jr.
H. G. Shealy NSRC RTS (TSP 910005)
File (813.20)
NUCLEAR EXCELLENCE A SUMMER TRADITION!
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