ML20033E272
| ML20033E272 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/23/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033E273 | List: |
| References | |
| NUDOCS 9003120039 | |
| Download: ML20033E272 (4) | |
Text
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UNITED STATES
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\\, w.,.....f SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA pUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER MICLEAR STATION, UNIT NO.1 t.MENDMENT TO FACILITY OPERATING LICENSE Amentient No. 87 License No. NPT-12 1.
The Nuclear Regulatory Comission (i.he Comission) has found that:
A.
The application for anendment by South Carolina Electric & Gas Comparty (the licensee), dated July 24,1989, as supplemented October 27 and Decenter 11, 1989, and January 5.1990, conplies with the standards and requirenents 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; C.
The facility will operate in conformity with the application, j
the provisions of the Act, and the rules and regulations of l
the Comission; l
i C.
There is reasonable assurance (1) that the activities authorized l
by this amendnent 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 ard sewrity or to the health, and safety of the public; and E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l
have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachnent to this license amendment; and paragraph 2.C.(2) of Facility Operating License ho. NPF-12 is hereby anended to read as follows:
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(2) Technical Specifications and Environnental Protection Plan The Technical Specifications contaired in Appendix A, as revised through Anendnent ho. 87
, and the Environnental Protection Plan contained in Appendix B, are hereby inr.orporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environnental Protection Plan.
3.
This anenenent is effective as of its date of issuance, and shall be implepented within 30 days of issuance, j
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By*
Elinor G. Adensam. Director Project Directorate 11 1 l
Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 23, 1990
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ATTACHMENT TO LICENSE W.NDMENT NO. 87 TO FACILITY OPERATING ~ LICENSE NO. NPF-12 DOCKET HO. 50-395
.i Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Pages Insert Pages i
3/4 4-15 3/4 4-15 k
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e REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS-(Continued) 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the' equipment and techniques expected to be used during subsequent inservice inspections.
10.
F* Distance is the distance into the tubesheet from the face of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively chosen to be 1.6 inches.
11.
F* TUBE is the tube with degradation, below the F* distance, Equal to or greater than 40%, and not degraded (i.e.,~no indica-tions of cracking) within the F* distance.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging limit) required by Table 4.4-2.
4.4.5.5 Reports Within 15 days following the completion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a.Special Report pursuant to Specification.6.9.2.
b.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged or repaired.
c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to 10 CFR 50.72(b)2(i) prior to resumption of plant operation.. A report pursuant to 10 CFR 50.73(a)2(ii) shall be submitted to provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
d.
The results of inspections of F* tubes shall be reported to the Commission in a report to the Director, ONRR, prior to the restart of the unit following the inspection.
This report shall include:
1.
Identification of F* tubes, and 2.
Location and size of the degradation NRC approval of this report is not required prior to restart.
SUMMER - UNIT 1 3/4 4-15 Amendment No. 35, 5#, 59 87