ML20073G092

Amend 170 to License DPR-16,revising TS 3.4.B.1 to Be Consistent W/Tss 1.39 & 4.3.D

ML20073G092
Person / Time
Site:	Oyster Creek
Issue date:	09/27/1994
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20073G093	List: ML20073G092
References
DPR-16-A-170 NUDOCS 9410040004
Download: ML20073G092 (4)

Text

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I UNITED STATES ye-NUCLEAR REGULATORY COMMISSION i

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GPU NUCLEAR CORPORATION ale JERSEY CENTRAL POWER & LIGHT COMPANY f

DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE l

t Amendment No. 170 License No. DPR-16 j

1.

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

A.

The application for aw,0ndment by GPU Nuclear Corporation, et al.

(the licensee), dated April 19, 1994, complies with the standards and requirements of the Atomic Energy Act 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 provisions of the Act, and the rules and regulations of the Comission; j

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 Comission's regulations D.

The issuance of this amendment will not be inimical to the comon l

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

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E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

of the Comission's regulations and all applicable requirements have been satisfied.

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9410040004 940927 PDR ADOCK 05000219 p

PDR_

. I 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.170, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ohh F. Stolz, Director

[DivisionofReactorProjects-1/II Pro' ject Directorate I-4

._ Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 27, 1994 1

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ATTACHMENT TO LICENSE AMENDMENT NO.170 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

Remove Insert Page 3.4-4 Page 3.4-4 P

automatic depressurization function) Gay be inoperable or bypassed during Reactor Vessel Pressure Testing consistent with Specifications 1.39 and 3.3.A.(i).

2.

If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.

3.

If Specifications 3.4.B.1 and 3.4.B.2 are not met; reactor pressure shall be reduced to 110 psig or less, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.

The time delay set point for initiation after coincidence of low-low-low reactor water level and high drywell pressure shall be set not to exceed two minutes.

C.

Containment Sorav System and Emeraency Service Water System 1.

1he containment spray system and the emergency service water system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications 3.4.C.3, 3.4.C.4, 3.4.C.6 and 3.4.C.8.

2.

The absorption chamber water volume shall not be less than 82,000 ft in order for the containment spray and emergency service water system to be considered operable.

3.

If one emergency service water system loop becomes inoperable, its associated containment spray system loop shall be considered inoperable.

If one containment spray system loop and/or its associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days provided the remaining containment spray system loop and its associated emergency service water system loop each have no inoperable components and are verified daily to be operable.

4.

If a pump in the containment spray system or emergency service water system becomes inoperable, the reactor may remain in operation for a period not to exceed 15 days provided the other similar pump is verified daily to be operable. A maximum of two pumps may be inoperable provided the two pumps are not in the same loop.

If more than two pumps become inoperable, the limits of Specification 3.4.C.3 shall apply.

5.

During the period when one diesel is inoperable, the containment spray loop and emergency service water system loop connected to the operable diesel shall have no inoperable components.

6.

If primary containment integrity is not required (see Specification 3.5.A), the containment spray system may be made inoperable.

0YSTER CREEK 3.4-4 Amendment No.:J'I, )d,,J4rf,170