ML15112A841
| ML15112A841 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/11/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A842 | List: |
| References | |
| NUDOCS 7901260046 | |
| Download: ML15112A841 (8) | |
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. 67 License No. DPP-2?
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated December 22, 1978, 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 author,-
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.
790I26eC a
-2
. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license a andment and paragraph 3.B of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
3.B Technical SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67 are hereby incorporated in the license. The licensee 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 Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
.Changes to the Technical Specifications Date of Issuance: January 11, 1979
UNITED STATES NUCLEAR REGULATORY COM.1.MISSION WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMEND.KENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated December 22, 1973, 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 aplication, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authcrized by this amendment can be conducted without endanger'ing the health and safety of the public, and (ii) that such activities will be conducted in compliance with the.Commissidn'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.
-2
- 2. Accordincly. the license is amended by chan.es to the Technical Specifications as indicated in the attachmcnt to this license am.endrent and paragraph 3.B of Facility Operating License Nc.
DPR-47 is hereby amended to read as follcws:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67 are hereby incorporated in the license. The licensee 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 kobert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
January -11, 1979 I
UNITED STATES NUCLEAR REGULATORY COMISSION W. ASHINGTON, D. C. 20555 DUKE PO'.:ER COMIPANY DOCKET N0.
50-287 OCOAEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No.
- 1. The Nuclear Regulatory Commissiori (the Commission) has found that:
A.
The application for amendment by Duke Poier Comoany (the licensee) dated December 2 2 1970, complies war, 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.
-2
- 2.
According3ly, the license is amended by chances to the Techni Specifications as. indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64 are hereby incorporated in the license.
The licensee 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 COM1MISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 11, 1979
0 0
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 67' TO DPR-38 AMENDMENT NO. 67 TO DPR-47 AMENDMENT NO. 64 TO DPR-55 DOCKETS NOS. 50-269, 50-270, AND 50-287 Revise Appendix A by removing page 3.3-3 and inserting the attached revised identically numbered page.
Changes on the revised page are indicated by a marginal line.
3.3.6 Exceptions to 3.3.5 shall be as follows:
(4)
Both core flooding tanks shall be operational above 800 psig.
(b) Both motor-operated valves associated with the core flooding tanks shall be fully open above 800 psig.
(c) One pressure instrument channel and one level instrument channel per core flood tank shall be operable above 800 psig.
(d) One reactor building cooling fan and associated cooling unit shall be permitted to be out of service for seven days provided both reactor building spray pumps and associated spray nozzle headers are in service at the same time.
(e) If the requirements of Specification 3.3.1(f) are not met, the borated water storage tank shall be considered unavailable and action shall be initiated in accordance with Specification 3.2.
(f) One reactor building spray pump and its associated spray nozzle header shall be permitted to be out of service for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided all Reactor Building Cooling Units are operable.
3.3.7 Prior to initiating maintenance on any of the components, the dupli cate (redundant) component shall be tested to assure operability.
3,3.8 (a) Reactor power shall not be increased above 60% FP unless three HPI pumps and two HPI flow paths are operable.
(b) During power operation above 60% FP, tests or maintenance shall be allowed on any one HPI pump, provided two trains of the HPI system are operable. If the inoperable HPI pump 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 />.
(c) If during power operation above 60% FP a high pressure injection flow path becomes inoperable, reactor power shall be reduced below 60% FP within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Bases The requirements of Specification 3.3 assure that, before the reactor can be made critical, adequate engineered safety features are operable. Two high pressure injection pumps and two low pressure injection pumps are required (except as specified in Specification 3.3.8 and as discussed further on in these bases.). However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident. Both core flooding tanks are required as a single core flood tank has insufficient in ventory to reflood the core. (1)
The borated water storage tanks are used for two purposes:
(a)
As a supply of borated water for accident conditions.
(b) As a supply of borated water for flooding the fuel transfer canal during refueling operation.(2) 3.3-3 Amendment Nos.
67
- G7 & 64