ML15112B072
| ML15112B072 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/26/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B073 | List: |
| References | |
| DPR-38-A-114, DPR-47-A-114, DPR-55-A-111 NUDOCS 8211060651 | |
| Download: ML15112B072 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WAtHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated October 14, 1982, 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 pro visions 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.114 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
9211060651 821026 PDR ADOCK 050002DR
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- 3. This license amendment was effective October 14, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 26, 1982
UNITED STATES NUCMEAR REGULATORY COMMISSION WAtHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50- 270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated October 14, 1982, 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 pro visions 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 satis fied.
- 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 Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.114 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment was effective October 14, 1982.
FOR THE NUCLEAR REGUL TORY COMMISSION Jo F. Stolz, Chief Op rating Reactors Bran h #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 26, 1982
UNITED STATES NU AR REGULATORY COMMISSION WAtHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated October 14, 1982, 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 pro visions 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Fcility Operating License No. DPR-5 5 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 111are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment was effective October 14, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION Op rating Reactors Brach#
vision of Licensing Changes to the Technical Specifications Date of Issuance:
October 26, 1982
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 114 TO DPR-38 AMENDMENT NO. 114 TO DPR-47 AMENDMENT NO. 111 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace page 3.1-1 of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment numbers and contains vertical lines indicating the area of change.
3.1 REACTOR COOLANT SYSTEM Applicability Applies to the operating status of the reactor coolant system.
Objective To specify those limiting conditions for operation of the reactor coolant system components which must be met to ensure safe reactor operation.
Specification 3.1.1 Operational Components
- a. Reactor Coolant Pumps
- 1. Whenever the reactor is critical, single pump operation shall be pro hibited, single-loop operation shall be restricted to testing, and other pump combinations permissible for given power levels shall be as shown in Table 2.3-1.
- 2. Except for test purposes and limited by Specification 2.3, power operation with one idle reactor coolant pump in each loop shall be restricted to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.. If the reactor is not returned to an acceptable RC pump operating combination at the end of the 24-hour period, the reactor shall be in a hot shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. The boron concentration in the reactor coolant system shall not be reduced unless at least one reactor coolant pump or one low pressure injection pump is circulating reactor coolant.
- 1. One steam generator shall be operable whenever the reactor coolant average temperature is above 2500 F.
- c. Pressurizer Safety Valves
- 1. All pressurizer code safety valves shall be operable whenever the reactor is critical.
- 2. At least one pressurizer code safety valve shall be operable whenever all reactor coolant system openings are closed, except for hydrostatic tests in accordance with the ASME Section III Boiler and Pressure, Vessel Code.
- The requirements of Specification 3.1.1.c.1 are waived for Unit 1 until 11:59pm, October 29, 1982.
Amendment Nos. 114,114, & 111 3.1-1