ML20197C553
| ML20197C553 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/27/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20197C555 | List: |
| References | |
| NUDOCS 8611060250 | |
| Download: ML20197C553 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 s[*~c,l/
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 109 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 September 11, 1986, complies with the standards and require-ments 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 Commission; i
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 i
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 Commission's regulations and all applicable requirements have been satisfied.
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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 Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and P, as revised through Amendment No.109, 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 NUCLEAR REGtlLATORY COMMISSIO!!
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Jack N. Donohew, Jr., Yroject Manager N, BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 27, 1986 i
, 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 P, as revised through Amendment No. 109, 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 NUCLEAR REGULATORY COMMISSION h
/
Jack N. Donohew, Jr., vroject Manager N BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 27, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 109 PROVISIONAL OPERATING LICENSE NO. OPR-16 DOCKET N0. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of chance.
REMOVE INSERT 4.4-1 4.4-1 4.4-2 4.4 2
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4.4 EMERGENCY COOLING Applicability: Applies to surveillance requirements for the emergency cooling systems.
Objective:
To verify the operability of the emergency cooling systems.
Specification: Surveillance of the emergency cooling systems shall be performed as follows:
Item Frequency A.
Core Spray System 1.
Pump Operability Once/ month.
Also after major maintenance and prior to startup following a refueling outage.
2.
Motor operated valve operability Once/ month 3.
Automatic actuation test Every three months 4.
Pump compartment water-Once/ week and after each entry tight doors closed 5.
Core spray header AP instru-mentation check Once/ day calibrate Once/3 months Test Once/3 months B.
Automatic Depressurization 1.
Valve operability Following a refueling outage
- 2.
Automatic actuation test Every refueling outage C.
Containment Cooling System 1.
Pump Operability Once/ month.
Also after major maintenance and prior to startup following a refueling outage CValve operability shall be demonstrated at system operating pressure prior to Gxceeding 5 percent power.
OYSTER CREEK 4.4-1 Amendment No.: 109
Item Frequency 2
2.
Automatic actuation test Every 3 months 3.
Pump compartment water-Once/ week and after each entry
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tight doors closed l
D.
Emergency Service Water System 1.
Pump Operability Once/ month.
Also after major maintenance and prior to startup following a refueling outage.
2.
Automatic actuation test Every 3 months E.
Control Rod Drive Hydraulic System 1.
Pump Operability Once/ month.
Also after major maintenance and prior to startup following a refueling outage.
F.
Fire Protection System 1.
Pump and Isolation Once/ month.
Also after major valve operability maintenance and prior to startup following a refueling outage.
1 i
Bases:
It is during major maintenance or repair that a system's design l
intent may be violated accidentally.
Therefore, a functional test is required after every major maintenance operation.
During an ex-tended outage, such as a refueling outage, major repair and mainten-ance may be performed on many systems.
To be sure that these repairs on other systems do not encroach unintentionally on critical standby cooling systems, they should be given a functional test prior to i
startup.
Motor operated pumps, valves and other active devices that are nor-mally on standby should be exercised periodically to make sure that they are free to operate.
Motors on pumps should operate long enough to approach equilibrium temperature to ensure there is no overheat problem. Whenever practical, valves should be stroked full length to ensure that nothing impedes their motion.
Engineering judgment based on experience and availability analyses of the type presented in appendix L of the FOSAR indicates that testing these components more often than once a month over a long period of time does not signifi-cantly improve the system reliability. Also, at this frequency of testing wearout should not be a problem through the life of the plant.
During tests of the electromatic relief valves, steam from the reactor vessel will be discharged directly to the absorption chamber pool.
Scheduling the tests in conjunction with the refueling outage permits the tests to be run at low power, prior to 5 percent power, enhancing the safety of the plant by assuring EMRV operability before higher power levels are reached.
0YSTER CREEK 4.4-2 Amendment No.: 109
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