ML20041D133
| ML20041D133 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/18/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20041D134 | List: |
| References | |
| DPR-44-A-084, DPR-56-A-083 NUDOCS 8203040340 | |
| Download: ML20041D133 (8) | |
Text
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UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION n
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.I WASHINGTON, D. C. 20555 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS CoffANY DELMARVA POWER AND LIGHT. COMPANY 7 TLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.84 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated August 7,1981, 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 satified.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this-license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
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8203040340 820218 ADR ADOCK 05000277
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGUL.ATORY C0ffilSSION (d'
Jo n F. Stolz, Chief O rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 18, 1982 6
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ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50_277 Replace page 5 of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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PBAPS 1.0 DEFINITIONS (Cont'd)
Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1% rated power.
Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space detectors.
Refuel Mode - With the mode switch in the refuel pcsition, the reactor is shutdown and interlocks are established so that only one control rod may be withdrawn.
Refueling Outage - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the unit after that refueling.
For the purpose of designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding the 15% high flux trip) and RBM interlocks in service.
Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are l
assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory -Commission before resumption of unit operation.
Operation beyond such a limit may not in itself result in serious consequences, but it indicates an operational deficiency subject to regulatory review.
1 Secondary Containment Integrity - Secondary Containment integrity means that the reactor building is intact and the following conditions are met:
Amendment No. JS, 37, 84 _.
'o, UNITED STATES 8
NUCLEAR RCO',,.ATORY COMMISSION
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,E WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC CO WANY PUBLIC SERVICE ELECTRIC AND GAS COWANY DELMARVA POWER AND LIGHT C0@ANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE bR-56 cne o 1.
The Nucle.r Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated August 7,1981, 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 confamity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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; 5
and E.
The issuar.ce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment I
and paragraph 2.C,(2) of Facility Operating License No. DPR-56 is hereby amended to read as follcws:
l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revi:ed through Amendment No. 83, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
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dohh F. Stolz, Chief Operating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 18, 1982 D
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ATTACHMENT TO LICENSE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace page 5 of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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PBAPS e
1.0 DEFINITIONS (Cont'd)
Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above it rated power.
Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space detectors.
Refuel Mode - With the mode switch in the refuel position, the reactor is shutdown and interlocks are established so that only one control rod may be withdrawn.
Refueling Outage - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the unit after'that refueling.
For the purpose of designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding the 15% high flux trip) and RBM interlocks in service.
Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation, operation beyond such a limit may not in itself result in serious consequences, but it indicates an operational deficiency subject to regulatory review.
l Secondary Containment Integrity - Secondary Containment integrity means that the reactor building is intact and the following l
conditions are met:
l Amendnent No. JS, 37,83
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