ML20137J766
| ML20137J766 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/14/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137J768 | List: |
| References | |
| NUDOCS 8601230198 | |
| Download: ML20137J766 (5) | |
Text
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTET: CREEV NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 98 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Powe and Light Company (the licensees) dated June 19, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ccm ission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisicns of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment ;an 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 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 Comission's regulations and all appliceble requirements have been satisfied.
8601230198 860114 ADOCK 0 % y9 DR
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, 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 its issuance.
FOR THE UCLfAR REGULAT C0 FISSION
/
b Joh A. Zwolinski, Director BWR roject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 14, 1986 i
ATTACPMENT TO LICENSE AMENDMENT N0.98 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Revise Appendix A Teebrical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendnent number and contain vertical lines indicating the area of change.
REMOVE INSERT 11 ii 6-26
TABLE OF CONTENTS (cont'd) 3.5 Containment
- 3. 5-1 3.6 Radioactive Effluents
- 3. 6-1 3.7 Auxiliary Electrical Power
- 3. 7-1 3.8 Isolation Condenser 3.8-1 3.9 Refueling
- 3. 9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 3.12 Fire Protection 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1 Section 4 Surveillance Requirements 4.1 Protective Instrumentation 4.1 -1 4.2 Reactivity Control
- 4. 2-1 4.3 Reactor Coolant
- 4. 3-1 4.4 Emergency Cooling
- 4. 4-1 4.5 Containment
- 4. 5-1 4.6 Radioactive Effluents
- 4. 6-1 4.7 Auxiliary Electrical Power
- 4. 7-1 4.8 Isolation Condenser
- 4. 8-1 4.9 Refueling
- 4. 9-1 4.10 ECCS Related Core Limits.
4.10-1 4.11 Sealed Source Contamination 4.11-1 4.12 Fire Protection 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 Section 5 Design Features
(
5.1 Site 5.1 -1 5.2 Containment 5.2-1 5.3 Auxiliary Equipment
- 5. 3-1 Section 6 Administrative Centrols 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications 6-5 l
6.4 Training 6-7 6.5 Review and Audit 6-8 6.6 Reportable Event Action 6-14 6.7 Safety Limit Violation 6-15 6.8 Procedures 6-15 6.9 Reporting Requirements 6-16 6.10 Record Retention 6-22 6.11 Radiation Protection Program 6-23 6.12 (Deleted) 6.13 High Radiation Area 6-24 6.14 Environmental Qualification 6-24*
6.15 Integrity of Systems Outside Containment 6-25 6.16 Iodine Monitoring 6-25 l
6.17 Post Accident Sampling 6-26
- JAdddd bf MRC Otddt Ad%dd 70/24/B0 l
11 Amendment No. 84, 97,98
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6.17 The following program shall be established,,,
implemented, and maintained.
Post keident Sampling A program has been established which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1.
Trai.ning of personnel in sampling and analysis 2.
Procedures for sampling and analysis 3.
Provisions for verifying operability of the System.
e 1
i 6-26 Amenoment' No. 98
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