ML20211D870
| ML20211D870 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/17/1997 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211D873 | List: |
| References | |
| NUDOCS 9709290271 | |
| Download: ML20211D870 (4) | |
Text
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UNITED STATES
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,i NUCLEAR REGULATORY COMMISSION F
WASHINGTON, D.C. 300eH001 kg..... /
SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50 395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.138 License No. NPF 12 e
1.
The Nuclear Regulatory Commission (the Commission) has found that:
l L
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated March 26,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's tules 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 w;ll 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C (2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
9709290271 970917 PDR ADOCK 05000395 P
1 I
2 (2) Technical Soecifications and Environmental Protection Plarl The Technical Specifications contained in Appendix A, as revised through Amendment No.138, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. South Carolina Electric &
Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Gordon E. Edison, Acting Director Project Directorate ll-1 Division of Reactor Projects - l/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: September 17, 1997
ATTACHMENT TO LICENSE AMENDMENT NO.138 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revision is indicated by a marginal line.
Remove Paae Insert Paae 1-2 1-2 4
4
DEFINITIONS
- CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
a.
- All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valvas, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.4, b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 6.8.4.g and The sealing mechanism associated with each penetration (e.g.,
e welds, bellows, or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
- CORE ALTERATION 1.9 -
CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor pressure vessel with the vessel head removed and fuelin the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT (COLR) is the unit specific document that provides core operating limits for the current operating reload cycle. The cycle specific wre operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.11. Plant operation within these operating limits is addressed in individual specifications.
DOSE EQUIVAl.ENT l 131 1,10 DOSE EQUIVALENT l 131 shall be that concentration of I 131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131,1 132,1 133,1134, and 1 135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
SUMMER - UNIT 1 1-2 Amendment No. 68,444; 4%,138
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