ML15112A938
| ML15112A938 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/20/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A939 | List: |
| References | |
| NUDOCS 8009160502 | |
| Download: ML15112A938 (7) | |
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.
86 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 7, 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;
- p. 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 a5 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.B Technical Specifications The Technical Specifications contained in Appenlices A and B, as revised through Amendment No. 86 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8009160
-2
- 3. This license ameniderit is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technicil Specificatiohs Date of Issuance' Aog-ut 20, 1980
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UNITED STATES NUCLEAR REGULATORY COMMISSION 9
WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 7, 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 (1) 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-47 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. 86 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 Licensing
Attachment:
Changes to the Technical Specifications
.'Date of Issuance: August 20, 1980
, 3 0UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 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 7, 1980, complies with the standards and requirements of the Atomic Energy Aq) of 1954, as amended (the Act), and the Comission'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 licynse is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operoting 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. 83 are hereby incorporated in the license. The licensee shall operate the facility In accordance with the Technical Specifications.
- 3. This license amendment it effective as 6f the date 6f its issuance.
FOR THE NULAR REGULATdk tOM#ilid ROb et W. Rid, thieff operati R art I fc Diviti6n 6f Lic Asing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 2Oj 1980
- a. Personnel hatch
- b. Emergency hatch
- c. Equipment hatch seals
- d. Fuel transfer tube seals
- e. Reactor Building normal sump drain line
- f. Reactor coolant pump seal outlet line
- g. Reactor coolant pump seal inlet line
- h. Quench tank drain line
- i. Quench tank return line
- j. Quench tank vent line
- k. Normal makeup to Reactor Coolant System
- 1. High pressure injection line
- m. Electrical penetrations
- n. Reactor Building purge inlet line
- o. Reactor Building purge outlet line
- p. Reactor Building sample lines
- q. Reactor coolant letdown line 4.4.1.2.2 Conduct of Tests
- a. Local leak rate tests shall be performed at a pressure of not less than 59 psig.
- b. Acceptable methods of testing are halogen gas detection, soap bubbles, pressure decay, hydrostatic flow or equivalent.
4.4.1.2.3 Acceptance CriteriaI The total leakage from all penetrations and isolation valves shall not exceed 0.125 weight percent of the Reactor Building atmosphere per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.1.2.4 Corrective Action and Retest
- a. If at any time it is determined that the criterion of 4.4.1.2.3 above is exceeded, repairs shall be initiated immediately.
- b. If conformance to the criterion of 4.4.1.2.3 is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following detection of excessive local leakage, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion as demonstrated by retest.
4.4.1.2.5 Test Frequency Local leak detection tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than 2 years except that:
- a. The equipment hatch and fuel transfer tube seals shall be additionally tested after each opening.
- b. The personnel hatch and emergency hatch outer door seals shall be tested.
at four-month intervals, except when the hatches are not opened during that interval.
In no case shall the test interval be longer than 12 months.
4.4-3 Amendments Nos. 86, 86 & 83