ML19331E135
| ML19331E135 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/23/1974 |
| From: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19331E131 | List: |
| References | |
| NUDOCS 8009050548 | |
| Download: ML19331E135 (9) | |
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UNITED STATES (5
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DUKE POWER COMPANY DOCKET No. 50-269 CCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. DPR-33 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for amendment by Duke Power Company (the licensee) dated September 4,1974, complies with the standards and require-ments of the Atomic Ener9y Act of 1954, as amended, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformi y with the application, the provisions of th...ct, and the rules u " 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.
Prior public notice of this amendment is not required since the amendment does not involve a significant hazards consideracion.
2.
Accordingly, the license is amended by a change 'to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-38 is hereby amended to read as follows:
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"B.
Technical Specifications The Technical Specifications contained in Appendices A and:B, as revised, ere hereby incorporated in the license.
The licensee shall op..,.a the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No.L5."
l 3.
This license amendment is effective as of the date of its issuance.
EUR THE ATOMIC ENERGY COMMISSION Karl R. Goller, Assistant Director for Operating Reactors Directorate of Licensing
Attachment:
Change No.15 to Technical Specifications Date of Issuance: October 23, 1974 f
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ATOMIC ENERGY COMMISSION l
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I or DUKE POWER COMPANY DOCK 2T NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. DPR-47 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for amendment by Duke Power Company (the lice.3see) dated September 4,1974, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended, 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 ragulations 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 C menission'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; i
and E.
Prior public notice of this amendment is : ot required since the amendment does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-47 is hereby amended to read as follows:
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. "B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license.
The licansee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No.10."
3.
This license amendment is effective as' of the date of its issuance.
FOR THE ATOMIC ENERGY COMMISSION Y
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Karl R. Coller, Assistant Director for Operating Reactors Directorate of Licensing
Attachment:
Change No.10 to Technical Specifications Date of Issuance: October 23, 1974 f
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"B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license.
The licensea shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 2."
3.
This license amendment is effective as of the date of its issuance.
FOR THE ATOMIC ENERGY CONKISSION Karl R. Coller, Assistant Director for Operating Reactors Directorate of Lxcensing
Attachment:
Change No. 2 to Technical Specifications Date of Issuance: October 23, 1974 9
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WASHINGTON, D.C. 20545 ATOMIC ENERGY COMMISSION a
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DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. DPR-55 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for amendment by Duke Power Company (the licensee) dated September 4,1974, complies with the standards and require-ments of the Atomic Energy Act of 1954, as mended, 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 iss mace of this amendment will not be inimical to the common defen~se and security or to the health and safety of the public; and E.
Prior public notice of this amendment is not requirad since the amendment does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical specifications as indicated in the t.ttachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-55 is hereby amended to read as follows:
f ATTACHMENT TO LICENSE A!ENDMENTS AMENDMENT No. 5 TO FACILITY LICENSE NO. DPR-38, CHANGE NO. 15 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 5 TO FACILITY LICENSE NO. DPR-47, CHANGE NO. 10 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 2 TO FACILifY LICENSE NO. DPR-55, CHANGE NO. 2 TO TECHNICAL SPECTFICATIONS; DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 Revise Appendix A as follows:
Replace pages 3.6-1 and 3.6-2 with the attached pages.
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10/23/74 3.6 REACTOR BUILDING Applicability Applies to the containment when the reactor is subcritical by less than 1% ak/k.
Objective To assure containment integrity during startup and operation.
1pecification 3.6.1 Containment integrity shall be maintained whenever all three (3) of the following conditions exist:
a.
Reactor coolant pressure is 300 psig or greater b.
Reactor coolant temperature is 2000F or greater c.
Nuclear fuel is in the core 3.6.2 Containment integrity shall be maintained when the reactor coolant system is open to the containment atmosphere and the requirements for a refueling shutdown are not met.
3.6.3 The containment integrity shall be intact whenever positive
' reactivity inserrions which would result in the reactor being auberitical by less than 1% ak/k are made by control rod motion or boron dilution.
3.6.4 Exceptions to 3.6.1, 3.6.2, and 3.6.3 shall be as follows:
If either the personnel or emergency hatches become inoperable, a.
except as a result of an inoperable door gasket, the hatch shall be restored to un operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If a hatch is inoperable due to an inoperable door gasket:
f 1.
The remaining door of the affected hatch shall be closed and sealed.
2.
The hatch shall be restored to operable status within seven days or the reactor shall be in cold shutdown L5/10/2 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, b.
A containment isolation valve may be inoperable provided either:
1.
The inoperable valve is restored to operable status within four hours.
2.
The af fected penetration is isolated within four hours by the use of a deactivated automatic valve secured and locked in the isolated position.
3.6-1
10/23/74 3.
The affected penetration is isolated within four hours by the use of a closed manual valve or blind flange.
4.
The reactor is in the hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within 24 houes.
15/10/2 3.6.5 The reactor building internal pressure shall not exceed 1.5 psig or five inches of Hg if the reactor is critical.
3.6.6 Prior to criticality following refueling shutdown, a check shall be made to confirm that all manual containment isolation valves which should be closed are closed and tagged.
Bases The Reactor Coolant System conditions of cold shutdown assure that no steam will be formed and hence no pressure buildup in the containment if the Reactor Coolant System ruptures.
The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.
The reactor building is designed for an internal pressure of 59 psig and an external pressura 3.0 psi greater than the internal pressure. The design external pressure of 3.0 psi corresponds to a margin of 0.5 psi above the differential pressure that could be developed if the building is sealed with an internal temperature of 120 F with a barometric pressure of 29.0 inches of Hg and the building is subsequently cooled to an internal temperature of 800F with a concurrent rise in barometric pressure to 31.0 inches of Hg.
The weather conditions assumed here are conservative since an evaluation of National Weather Service records for this area indicates that from 1918 to 1970 the lowest bs.rometric pressure recorded is 29.05 inches of Hg and the highest if 30.85 inches of Hg.
Operation with a personnel or emergency hatch ineperable does not impair containment integrity since either door meets the design specifications for structural integrity and lesk rate. The time limits imposed permit 19/10/2 completion of maintenance action and the performance of a local leak rate cost when required or the orderly shutdown and cooldown of the reactor.
Timely corrective action for an inoperable containment isolation valve is also specified.
When containment integrity is established, the limits of 10CFR100 vill not be exceeded should the maximum hypothetical accident occur.
REFERENCES FSAR, Section 5 3.6-2
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