ML20086U232

Amend 156 to License DPR-16,revising TS 4.2.A & 4.2.C.1 to Delete Restriction That Refueling Outage Interval Not to Exceed 20 Months

ML20086U232
Person / Time
Site:	Oyster Creek
Issue date:	12/27/1991
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20086U237	List: ML20086U232 ML20086U241 ML20086U251
References
DPR-16-A-156 NUDOCS 9201070275
Download: ML20086U232 (4)

Text

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NUCLE AR REGULATORY COMMISSION 5[

l W ASHING TON, D. C. 20$55

1. a U$9 * *...,0 GPU tlVCLEAR,, CORPORATION OME

' E RS E Y C E qP!)., PpW E R J, Lj GyT, C0fjP ApY DOCKET tt0. 50-219 0YSTER CREEK pVC).E,AR GEpERA, TING,,ST,AT10p AMEWpEplJp,,fACLLJJLpfE3ATJpp,M[EpSE Amendment No. 156 License No. DPR-16 1.

The Nuclear Regulatory Concission (the Commission) has four.d that:

A.

The application for amendment by GPU Nuclear Corporation, et al.,

(the licensee), dated August 19, 1991, as revised August 29, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conunission'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 Conuni sion; 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 cournon 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.

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9201070275 911227 PDR ADOCK 03000219 PDR P

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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 paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby arrended to read as follows:

t (2) _ Technj caljpe,ci,figations -

e The Technical Specifications contained in Appendices A and B, as revised through Amendment l'o,156, are nereby 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 30 days of issuance.

TOR THE NUCLEAR REGULA10RY COMMISSION

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'oh 'F. Stolz, Director Pr ject Directorate 1 te 0Avision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Icsuance: December 27, 1991 L

A TT A L Ht' E NT.T.O L.I.C.E.N.S..E..AM.E.t4.D.M..E..N.T..t10.,.15 6 FACILITY OPERATit:0 LICEt15E NO. OPR-16 DOC KET NO_.__5 0.21_9 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.

The revised pages are identified by amendment nurber at:d contain vertical lines ir,dicating the areas of change.

Remove Insert Page 4.2-1 Page 4.2-1

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4.2 R[AflLU.ll_GNTR0L Angliqitbil tiy:

Applies to the surveillance requirements for reactivity cont rol.

QMeetive:

To verify the capability for controlling reactivity.

Specifi qt.ipfp A.

Following a reactor refueling when core alterations were performed, sufficient ccntrol rods shall be withdrawn to demonstrate with a margin of 0.25% 4 k that the core can be made suberitical at any time in the subsequent fuel cycle with the strongest operaole control rod fully withdrawn and all other operable rods fully inserted.

8.

The control rod drive housing support system shall be inspected.after reassembly.

C.

1.

After each major refueling outage and p* lor to resuming power i

operation, all operrble control rods shall be scram time tested froa the fully withdrawn position with reactor pressure above 800 psig.

2.

Following each reactor scram from rated pressure, the mean 90%

insertion time shall be determined for eight selected rods.

If the mean 90%' insertion time of the selected control rod drives does not fall within the range of 2.4 to 3.1 seconds or the measured scram time of any one drive 'or 90% insertion does not fall within the range of 1.9 to 3.6 seconds, an evaluation shall be mtde to provide reasonable assurance that proper control rod drive performance is maintained.

3.

Following any outage not initiated by a reactor scram eight rods shall be scram testad with reactor pressure above 800 psig provided these have not been measured in six months.

The same criteria of 4.2.C(2) shall apply.

D.

Each partially or fully withdrawn control rod shall be exercised at least once each week.

This test shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event of power operation is continuing with two or more inoperable control rods or in the evenc power operation is continuing with one fully or partially withdrawn rod which cannot be noved and for which control rod drive mer.hanism damage has not been ruled out.

The surveillance need l

not be completed uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the number of inoperable rods has I

been reduced to less than two end if it has been demonstrated that control rod drive mechanism col' lect hotsing failure is not the cause of an immovable control rod.

l E.

Surveillance of the standby liquid control system shall be as fol' lows:

1.

Pump operability 0nce/ month Scron concentration 0nce/ month l

determination l

Corrected:

12/24/84 l

OYSTER CREEK 4.2-1 Amendment No.: 13, 75, 144, 156

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