ML20054H496
| ML20054H496 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/11/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054H497 | List: |
| References | |
| NUDOCS 8206240134 | |
| Download: ML20054H496 (4) | |
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- o, UNITED STATES 8\\
3 NUCLEAR REGL".ATORY COMMISSION
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y WASHINGTON, D. C. 20555
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GPU '"' CLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 61 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated.May 28, 1982, 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; 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 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 satisfied.
8206240134 820611 PDR ADOCK 05000219 P
. 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 Provisional Operating License No. DPR-16 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 61, are hereby incorporated in the license. GPU Nuclear Corporation 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
' W.
Dennis M. Crutchfield. C ef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 11, 1982 l
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ATTACHMENT TO LICENSE AMENDMENT NO. g1 PROVISIONAL OPERATING LICENSE NO. DPR-16 i
DOCKET No. 50-219 Replace page 1.0-2 of the Appendix "A" Technical Specifications with the enclosed page 1.0-2.
The revised page contains the captioned amendment number and vertical lines indicating the area of change.
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1.0-2
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..s 1.8 PLACE IN SHUTDOWN CONDITION Proceed with and maintain an uninterrupted normal plant shutdown operation until the shutdown condition is met.
1.9 PLACE IN COLD SHUTDOWN CONDITION Proceed with and maintain an uninterrupted normal plant shutdown operation until the cold shutdown condition is met.
1.10 PLACE IN ISOLATED CONDITION 7 Proceed with and maintain an uninterrupted normal isolation of the reactor from the turbine condenser system including closure of the main steam isolation valves.
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1.I1 REFUEL MODE The reactor is in the refuel mode when the reactor mode switch is in the refuel mode position and there is fuel in el e reactor vessel.
In this l
mode the refueling platform inte'rlocks are in operation.
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1.12 REFUELING OUTAGE
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For the purpose of designating frequency of testing and surveillance, a
refueling outage shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the end of the previous refueling outage, the test or surveillance need not be performed uniti the next regularly scheduled outage.
Following the first refueling outage, the time between successive tests or surveillance shall not exceed 20 months.*
l 1.13 PRIMARY CONTAINMENT INTEGRITY Primary containment integrity mea $s that thedrywellandadsorption chamber are closed and all of the following conditions are satisfied:
l A.
All non-automatic primary containment isolation valves which are not required to be open for plant operation are closed.
B.
At least one door in the airlock is closed and sealed.
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'C.
All automatic containment isolation valves specified in Table 3.5.2 are operable or are secured in the closed position.
D.
All blind flanges and manways are closed.
1.14 SECONDARY CONTAINMENT INTEGRITY Secondary containment integrity means that the reactor buidling is closed and the following conditions are met:
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- The time between successive tests or surveillances shall not exceed 30 months prior to the cycle 10 refueling outage only.
AmendmentNo.fff4,[,61
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