ML20154M608
| ML20154M608 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/15/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154M613 | List: |
| References | |
| NUDOCS 9810200346 | |
| Download: ML20154M608 (4) | |
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION j
o WASHINGTON, D.C. 20666 0001 faEU NUCLEAR. INC.
AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear, Inc., et al., (the licensee),
dated May 28,1998, 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 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 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.
0 9810200 h h 19 PDR A
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Accordingly, the license is amended by changes to the Technical Specifications as j
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. 200, 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 l
within 30 days of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION l
GQ
.o%ecil O. Thomas, Director l
Project Directorate 1-3 Division of Reactor Projects -l/II l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 15, 1998 t -
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6 ATTACHMENT TO LICENSE AMENDMENT NO. 200 FAClLITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 i
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 4.5-1 4.5-1 1
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l 4.5 CONTAINMENTSYSTEM Aeolicabilitv:
Applies to containment system leakage rate, continuous leak rate monitor, functional testing of valves, standby gas treatment system
' operability,inerting surveillance,drywell coating surveillance, 1
instrument line flow check valve surveillance, suppression chamber i
surveillance,and snubber surveillance.
Obiectives:
To verify operability of containment systems,and that leakage
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values, as outlined in Appendix J of 10 CFR 50.
Soecificatiorr I
A. PrimaryContainmentLeakageTesting l
A Primary Containment Leakage Rate Testing Program shall be established to implement 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance Based Containment Leak Test Program," dated September 1995, as modified by the following exception:
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1.
The first Type A test required by this program will be performed during refuelmg outage 18R.
B. Type A Primary ContainmentIntegrated Leak Rate Test (PCILRT).
PCILRT shall be performed in accordance with the Primary Containment Leakage Rate -
Testing Program.
i C. Type B and Type C Local Leak Rate Tests (LLRT) 1.
LLRT shall be performed in accordance with the Primary Containment Leakage Rate Testing Program.
2.
The Drywell Airlock,Drywell Airlock electricalpenetration,and Drywell Airlock barrel seal shall be local leak rate tested in accordance with the i
Primary Containment Leakage Rate Testing Program.
l a.
When containment integrity is required,the airlock must be tested at 10 psig within 7 days after each containment access. If the airlock is opened more frequently than once every 7 days, it may be tested at 10 psig once per 30 days during this time period.
7 OYSTERCREEK 4.5-1 AmendmentNo.: 132, "'5, 200 9
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