ML15112A930
| ML15112A930 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/01/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A931 | List: |
| References | |
| NUDOCS 8008140208 | |
| Download: ML15112A930 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 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 July 16, 1980,,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.
8008140208
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This license amendment is effective July 16, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1, 1980
- 4
- .0 UNITED STATES NUCLEAR REGULATQRYCOMMISSION WASHINGTON, D. C. 20655 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-47
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 16, 1980, 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 (i) 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 Specifi cations 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:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
84, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This license amendment is effective July 16, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION.
W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1, 1980
S nee UNITED STATES NUCLEAR REGULATORY COMMISSION WAIGTaN. D C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 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 July 16, 1980, 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 Comission; 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 (it) 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 fled.
- U
- 2. Accordingly, the license is amended by changesto the Technical Specifi sas Indicated ithe attachment to thisliceNse amendment, and paragraph 3.B. of Facil ty Op erating L ens
. DPR-55 Is hreby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci fications.
- 3. This icense amendment s effective July 16, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION Robert Reid, Chief Operating Reactors Branch 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1, 1980 3/
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 84 TO DPR-38 AMENDMENT NO.
p4 TO DPR-47 AMENDMENT NO. R1 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A by replacing page 3.3-2 with the enclosed revised page.
Page 3.3-1 is also provided to maintain document completeness. The changes on the revised page are indicated by a marginal line.
3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, REACTOR BUILDING SPRAY, AND LOW PRESSURE SERVICE WATER SYSTEMS Applicability Applies to the emergency core cooling, reactor building cooling, reactor building spray, and low pressure service water systems.
ObJective To define the conditions necessary to assure immediate availability of the emergency core cooling, reactor building cooling, reactor building spray and low pressure service water systems.
Specification 3.3.1 High Pressure Injection (EPI) System
- a. -Prior to initiating maintenance on any component of the HPI system, the redundant component shall be tested to assure operability.
- b. When the reactor coolant system (RCS), with fuel in the core, is in a condition with temperature above 350*F and reactor power less than 60% FP:
(1) Two independent trains, each comprised of an EPI pump and a flowpath capable of taking suction from the borated water storage tank and discharging into the reactor coolant system automatically upon Engineered Safeguards Protective System (ESPS) actuation (HPI segment) shall be operable.
(2) Test or maintenance shall be allowed on any component of the HPI system provided one train of the HPI system is operable.
If the HPI system is not restored to meet the requirements of Specification 3.3.1.b(1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the requirements of Specification 3.3.1.b(1) are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following hot shutdown, the reactor shall be placed in a condition with RCS temperature below 3500F within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. For Unit 2, when reactor power is greater than 60% FP:
(.1)
In addition to, the requirements of Specification 3.3.l1b(1) above, the remaining HI pump shall be operable and valve*
HP-99 and HP-100 shall be open.
(2) PI Pump Operability (a)- Tests or maintenance shall be allowed on any one EPI pump, provided two trains of HP system are operable.
Amendments Nos. 8181 1 & 78 3.3-1 t
E No 8
- (b) If the inoperable,PI pump is not restored o operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, reactor power shall be reduced below 60% FP within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(3) PI Floupath Operability (a) If one automatic EPI flowpath becomes inoperable, then either restore the inoperable flowpath-to operable status within one hour, or reactor power shall be reduced to below 60% FP within an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- d. For Units 1 and 3, when reactor power is greater than 60% FP:
(1) In addition to the requirements of Specification 3.3.1.bl) above, the remaining HP. pump and valves 3P-409 and 3HP-410 shall be operable and valves HP-99 and HP-100 shall be open.
(2) Tests or maintenance shall be allowed on any component of the RPI system, provided two trains of HPI system are operable.
If the inoperable component is not restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, reactor power shall be reduced below 60% FP within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.3.2 Low Pressure Injection (LPI) System
- a. Prior to initiating maintenance on any component of the LPI system the redundant component shall be tested to assure operability.
- b. When the RCS, with fuel in the core, is in a, condition with pressure equal to or greater than 350 psig or temperature equal to or greater than 250F:
(1) Two independent LPI trains, each comprised of an LPI pump and a flowpath capable of taking suction from the borated water storage tank and discharging into the RCS automatically upon ESPS actuation (LPI segment), together with two LPI coolers and two reactor building emergency sump isolation valves (manual or remote-manual) shall be operable.
(2) Tests or maintenance shall be allowed.on any component of the LPI system provided the redundant train of the LPI system is operable. If the LPI system is not restored to meet the re quirements of Specification 3.3.2.b(1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the requirements of Specification 3.3.2.b(1) are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following hot shutdown, the reactor shall be placed in a condition with RCS pressure below 350 psig and RCS temperature below 2500 withih an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.3.3 Core Flood Tank (CFT) System When the RCS is in a condition with pressure above 800 psig both CFT's shall be operable with the electrically operated discharge valves open Amendments Nos..84, 84 & 81 3.3-2
- For HPI pump B, this specification does not apply until 2220 hour0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />.s, July 18, 1980.