ML20154B426
| ML20154B426 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/01/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154B431 | List: |
| References | |
| NUDOCS 9810050213 | |
| Download: ML20154B426 (4) | |
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1 UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. was anni 44 ~...,o GPU NUCLEAR. INC.
AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMFEI.IO FACILITY OPERATING LICENSE Amendment No. 198 License No. DPR-16 1.
The Nuclear Regulatory Cornmission (the Commission) has found that:
A.
The application for amendment filed by GPU Nuclear, Inc., et al., (the licensee),
deted July 21,1998, 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; 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 reasonabla 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 cf 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.
9810050213 981001 PDR ADOCK 05000219 P
t b
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licensa amendment, and paragraph 2.C.(2) of Facility Opeiating License No. DPR-16 is hereby amended to read as follows:
(2)
Iechnical toecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
198, are hereby incorporated in the license. GPU Nuclear, Inc. 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.
FOR THE NUCLEAR REGULATORY COMMISSION Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissue ce: October 1,1998 l
l l
ATTACHMENT TO LICENSE AMENDMENT NO.198 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following page of the Appendix A, Technical Specifications, with the attached page as indicated.' The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 4.2-1 4.2-1 l
1
4.2 REACTIVITY CONTROL Anolicability: Applies to the surveillance requirements for reactivity control.
Obiective:
To verify the capability for controlling reactivity.
Specification:
A.
SDM shall be verified:
1.
Prior to each CORE ALTERATION, and 2.
Once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following the first criticality following any CORE ALTERATION.
B.
He control rod drive hoasing support system shall be inspected after reassembly.
C.
- 1. After each major refueling outage and prior to resuming POWER OPERATION, all operable control rods shall be scram time tested from the fully withdrawn position with reactor pressure above 800 psig; OR
- 2. a. Prior to resummg POWER OPERATION, scram time testing shall be conducted with the reactor depressurized. The 90% scram insertion time shall not exceed 2.2 seconds for each control rod tested; AND
- b. Prior to exceeding 40% reactor power operation, scram time testing shall be conducted with the reactor pressurized above 800 psig. The acceptance criteria of Section 3.2.B.3 shall be met.
- 3. Following each reactor scram from rated pressure, the mean 90% insertion time shall l
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 rneasured scram time of any one drive for 90% insertion does not fall within the range of 1.9 to 3.6 seconds, an evaluation shall be made to provide reasonable assurance that proper control rod drive performance is maintained.
4.
Following any outage not initiated by a reactor scram, eight rods shall be scram tested with 1 reactor pressure above 800 psig provided thee hwe not been measured in six months De 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 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event power operation is continuing with two or more inoperable control rods or in the event power operation is continuing with one fully or partially withdrawn rod which cannot be moved and for which control rod drive mechamsm damage has not been nited out. The surveillance need not be comple:ed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the munber ofinoperable rods has been reduced to less than two and ifit has been demonstrated that control rod drive mechanism colkt housing failure is not the cause of an immovable control rod.
I OYSTER CREEK 4.2-1 Amendment No: 499: 198
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