ML13316A918
| ML13316A918 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/30/1986 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A916 | List: |
| References | |
| DPR-13-A-094, TAC-61130 NUDOCS 8606130243 | |
| Download: ML13316A918 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.94 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated March 28, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8606130243 660530 7
PDR ADOCK 05000206 P
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Provisional Operating License No. DPR13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94, are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Richard F. Dudley, roject Manager Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 30, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 94 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 60-B 60-C 60-C
60-B 4.10 AUGMENTED INSERVICE INSPECTION OF HIGH ENERGY LINES OUTSIDE CONTAINMENT APPLICABILITY:
Applies to welds in piping systems or portions of systems located outside containment where protection from the consequences of postulated pipe breaks is not provided by a system of pipe whip restraints, protective enclosures, or other measures specifically designed to cope with such breaks.
OBJECTIVE:
To provide assurance of the continued integrity of the piping systems over their service lifetime.
SPECIFICATION:
A. For the welds in the main steam, main feedwater, and first point extraction lines identified in Reference 1, Table 1 and Table IA, Column: "Break Point Location",
for which inservice inspection is specified in Column:
"Solution":
(1) At refueling outage No. 4, a baseline inspection consisting of a volumetric examination of all specified welds shall be performed in accordance with the requirements of ASME Section XI Code, "Inservice Inspection of Nuclear Reactor Coolant Systems" 1971, up to and including 1972 addenda.
(2) Subsequent to the baseline examination, the inservice inspection of each weld shall be performed in accordance with the requirements of the Edition and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components" as required by Technical Specification 4.7, with the following schedule:
(a) During the first 3-1/3 years (or nearest refueling outage), volumetric examination of 100% all welds.
(b) Every 10 years thereafter (or nearest refueling outage), volumetric examination of 33-1/3% of the welds at the expiration of each 1/3 of the inspection interval with a cumulative 100% coverage of all welds every 10 years.
Amendment No.
72 94
60-C NOTE:
The welds selected during each inspection period shall be distributed among the total number to be examined to provide a representative sampling of the conditions of all specified welds.
(3) Any evidence revealed by the examinations specified in (1) or (2) that indications have developed or grown shall be investigated, including evaluation of comparable areas of the applicable system. It may be determined that the condition can be tolerated or that repair is necessary. In the event that repair is required, restoration shall be governed by the original acceptance standards.
(4) In the event repair of any weld is required following an examination, the inspection schedule for the repaired weld will be changed to provide for its inspection at the following inspection.
B. For all welds in the main steam lines, main feedwater lines, and first point extraction lines located outside containment:
(1) A visual inspection of the surface at the insulation joints nearest to all weld locations shall be performed on a monthly basis for detection of leaks. Any detected leaks shall be investigated and evaluated. If the leakage is caused by a through-wall flaw, either the plant shall be shut down or the leaking piping isolated. Repairs shall be performed prior to return of this line to service.
Amendment No. 23, 94