ML19312C542

Amends 43,43 & 40 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Deleting Requirement That Containment Integrity Be Maintained When RCS Is Open to Containment Atmosphere & Requirements for Refueling Shutdown Are Not Met

ML19312C542
Person / Time
Site:	Oconee
Issue date:	07/05/1977
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19312C539	List: ML19312C538 ML19312C542
References
NUDOCS 7912160099
Download: ML19312C542 (9)

Text

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UNITED STATES e

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DUKE POWER COMPA Y DOCKET NO. 50-26 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILYTY OPERATING LICENSE Amendment No. 43 License No. DPR-38 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Duke Power Company (the licensee) dated February 5,1976, 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; The facility will operate in conformity with the application, 3.

the provisions of the Act, and the rules and regulations of l

the Cortmission; There is reasonable assurance (i) that the activities authori:ed C.

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; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and E.

'Ihe 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.

Accordingly, the license is amended by a change to the Technical Specifications as indicated 'n the attachment to this license amendment.

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This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR BEGULATORY CC!allSSION YWZW$V '

o A. Schwencer, Chief l

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Divisien of Operating Reactors l

Attachment:

Changes to the Technical Specifications Date of Issuance: July 5, 1977 e

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J ATTACHMENT TO LICENSE AMENDENTS AMENDMENT NO. 43 TO DPR-38 AMENDMENT NO. 43 TO DPR-47 AMENDENT NO. 40 TO DPR-55 DOCKETS 20S. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:

Remove pages 3.6-1 and 3.6-2 and insert revised pages 3.6-1 and 3.6-2.

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m 3.6 REACTOR BUILDING L

Applicability Applies to the containment when the reactor is in conditions other than refueling shutdown.

Objective To assure containment integrity during shutdown (other than refueling shutdown), startup and operation.

Specification 3.6.1 Containment integrity shall be maintained whenever all three (3) of the following conditions exist:

Reactorcoolantpressureis300psfgorgreater a.

b.

Reactor coolant temperature is 200 F or greater c.

Nuclear fuel is in the core 3.6.2 Containment integrity shall be maintained whenever the reactor is subcritical by less than 1% Ak/k or whenever positive reactivity insertions are being made which would result in the reactor being suberitical by less than 1% ak/k.

3.6.3 Exceptions to 3.6.1 and 3.6.2 shall be as follows:

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a.

If either the personnel or emergency hatches become inoperable, except as a result of an inoperable door gasket, the hatch shall be restored to an 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:

1.

The remaining door of the affected hatch shall be closed and sealed.

If the inner door gasket is inoperable, momentary passage (not to exceed 10 minutes for each opening) is permitted through the outer door for repair or test of the inner door, provided that the outer door gasket is leak tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after opening of the outer door.

2.

The hatch shall be restored to operable status within seven days 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 />.

b.

A containment isolation valve may be inoperable provided either:

1.

The inoperable valve is restored to operable status within four hours.

2.

The affected penetration is isolated within four hours by the use of a deactivated automatic valve secured and locked in the isolated position.

3.6-1 Amendments Nos. 43, 43 4 40

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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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.6.4 The reactor building internal pressure shall not exceed 1.5 psig 1

or five inches of Hg if the reactor is critical.

3.6. 5 Prior to criticality following refueling shutdown, a check shall l

be made to confirm that all manual containment isolation valves which should be closed are closed and tagged.

Braes 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 pressure 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 dif terential 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 barcmetric pressure recorded is 29.05 inches of Hg and the highest if 30.85 inches of Hg.

Operation with a personnel or emergency hatch inoperable does not impair containment integrity since either docr meets the design specifications for structural integrity and leak rate. Momentary passage through the outer door is necessary should the inner door gasket be inoperative to install or remove auxiliary restraint beams on the inner door to allow testing of the hatch.

The time limits imposed permit cempletion of maintenance action and the performance of a local leak rate test when required or the orderly shutdcwn and cooldown of the reactor.

Timel:, corrective action for an inoperable containment isolation valve is also specified.

When containment integrity is established, the limits of 10CFR100 will not be exceeded should the maximum hypothetical accident occur.

REFERENCES FSAR, Secticn 5 3.6-2 Amendments Nos. 43, 43 5 40

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DUVE P': R C0"P ANY DOCKET No. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDENT TO FACILUY OPERATING LICENSE Amendment No. 43 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 February 5,1976, 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; The facility will operate in conformity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized j

C.

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and E.

'Ihe 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.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment.

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2-This license amendment is effective as of the date of its issuance.

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FOR THE NUCEAR REGULATORY CO'0!ISSIC.';

1ht/tl'Ot A. Schwencer, Chie f Operating Reactors Branch #1 Division of Operating Reactors i

Attachment:

Changes to the Technical Specifications Date of Issuance: July 5,1977 e

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4 NUCLEAR REGULATORY COMMISSION CASHIN tToN, o. C. 20656 DUKE P0h'ER C0"PANY DOCKET NO. 50- 287 OCONEE NUCLEAR STATION, U'JIT 3 AENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No, DPR.55 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

De application for amendment by Duke Power Company (the licensee) dated February 5,1976, 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; The facility will operate in conformity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; H ere is reasonable assurance (i) that the activities authorited C.

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; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and E.

De 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.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendnent.

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This license amendment is effective as of the date of its issuance.

1 FOR THE NU,fl2AR REGULATORY C04ilSSION (WL/WdL '

A. 'Schwencer, Chief

, ' Operating Reactors Branch 81 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 5, 1977 i

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