ML19312C513
| ML19312C513 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/08/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C511 | List: |
| References | |
| NUDOCS 7912160072 | |
| Download: ML19312C513 (8) | |
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DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMEtstENT TO FACILITY OPERATING LICENSE Amendment No. 60 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 February 8,1978, complies with the standards and require-ments of the Atcmic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of j
the Cormission; C.
There is reasonable assurance (i) that the activities authorized by this amencment 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 amencment will not be inimical to the common defense and security or to the health and safety of the public; and E.
Th'e issuance of this amendment is in accordance 'vith 10 CFR Part 51 of the Ccomission's regulations and all applicable re:;uirements j
have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragra;;h 3.B of Facility License No. DPR-38 is hereby an. ended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective February 8,1978.
FOR THE NU LEAR REGULATORY COMMISSION UW 2
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 8,1978 1
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NUCLEAR REGULATORY COMMISSION
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%,, '....f DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDriENT TO FACILITY OPERATING LICENSE Arnendment No. 50 License No. DPR-47 1.
The Nuclear Regulatory Cormiission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) da ted February 8, 1978, complies with the standards and require-ments 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 uperate 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 compliat.ce with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Par:
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 :ne attachment to tnis license amendment and paragraph 3.8 of Facility License no. DPR-47 is hereby an: ended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised-through Amendment No. 60, are hereby incorporatec in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective February 8,1978.
FOR THE NUCLCAR REGULATORY COMMISSION
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t'WA 8' W A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 8, 1978 9
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a 9g '.... jf DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. OPR-55 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated Februrry 6,1978, complies with the standarcs'and recuire-ments 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 cperate 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 realth and safety of the public, and (ii) that such activities rill 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 Ccemission's regulations and all applicable requirements have been satisfied.
i 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 License No. DPR-55 is hereby amended to read as folicvis:
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(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as rcvised through Amendment No.57, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective February 8,1978.
FOR THE NUC
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A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 8, 1978 4
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s ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 60 TO DPR-38 l
AMENDMENT NO. 60 TO DPR-47 i
AMENDMENT NO. 57 TO DPR-55 DOCKET NOS. 50-269, 50-270 AND 50-287 l
Revise Appendix A as follows:
Remove page 3.3-2 and replace with identically numbered page.
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3.3.2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350*F and irradiated fuel is in the core:
i (a) Two high pressure injection pumps shall be maintained operable to provide redundant and independent flow paths.
(b) Engineered Safety Feature valves and interlocks associated with j
3.3.2a above shall be operable.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall 1
be operable when the reactor coolant system is above 800 psig:
(a) The two core flooding tanks shall each contain a minimum of 131 3
.44 ft. (1040 1 30 ft ) of borated water at 600 1 25 psig.
(b) Core flooding tank boron concentration shall not be less than 1,800 ppm boron.
.(c) The electrically-operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
(d) One pressure instrument channel and one level instrument channel per core flood tank shall be operable.
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3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3.2, and 3.3.3 is operable.
(a) The other reactor building spray pump and its associated spray nozzle header.
(b) The remaining reactor building cooling fan and associated cooling unit.
(c)
Engineered Safety Feature valves and interlocks associated with 3.3.4a and 3.3.4b shall be operable.
Except as noted in 3.3.6 below, tests or maintenance shall be allowed during power operation on any component (s) in the high pressure injection, low pressure injection, low pressure service water, reactor building spray, reactor building cooling which will not remove more than one train of i
l each system from service.
Components shall not be removed frem service so that the affected system train is inoperable for more than 24* consecutive hours.
If the system is not restored to meet the requirements of c
Specification 3.3.1, 3.3.2, 3.3.3, or 3.3.4, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor l
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 re-quirements of Specification 3.3.1, 3.3.2, 3.3.3, or 3.3 4 are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a condition below that reactor coolant system coadition required in Specification 3.3.1, 3.3.2, 3.3.3, or 3.3.4 for the component degraded.
- In tne case of Reactor Building Spray Valve 3852, 72 consecutive hours are allowed to return the valve to coerable status on a one time basis only; this 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowance shall expire on February 10, 1978.
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Amendments 60, 60 & 57
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