ML20092P412
| ML20092P412 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/21/1984 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20090G641 | List: |
| References | |
| DPR-44-A-099, DPR-56-A-101 NUDOCS 8407060266 | |
| Download: ML20092P412 (10) | |
Text
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UNITED STATES N. g NUCLEAR REGULATORY COMMISSION i
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIL AND GAS COMPANY pELMARVA P0llER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated December 23, 1981, as supplemented by letters dated March 30, 1983, June 2, 1983, ar.d September 29, 1983, complies with the standards and requirements 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 confomity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasor'.sle 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 Comission's regulations; D.
Tne issuance of this license 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 applicable requirements have been satisfied.
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 Facility Operating License No. DPR-44 is hereby amended to read as follows:
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PDR ADOCK 05000277 P
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- Technical Specifications The Technical Specifications contained in Aopendices A and B, as revised through Amendment No.99, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ybydf?q+t SWL George W. Rivenbark, Acting Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 21,1984 u
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ATTACHMENT TO LICENSE AMENDMENT N0.99 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page and add the new page of the Appendix "A" Technical Specifications with the enclosed pages.
The pag'es are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 36 36 l
36a
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS C.
When it is determined that a channel has failed in the unsafe condition, the other RPS channels that monitor the same variable shal'1 be functionally tested immediately before the trip system containing the failure is tripped.
The trip system containing the unsafe failure may be placed in the untripped condition during the period in which surveillance testing is being performed on the other RPS channels.
The. trip system may be in the untripped position for no more that eight hours per functional trip period for this testing.
D.
Reactor Protection System Power Supply Power Supply 1** Reactor Protection System 1 **The following RPS power Power Supply:
supply (MG set) protective devices shall be' functionally tested at least once every One trip train
.once each refueling outage.
inoperative condition for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If this condition cannot be satisfied, Acceptable or if both trip trains are Device Setting inoperative, the RPS, bus shall be transferred to the alternate Undervoltage 113 + 2 Volts source or de-energized within Overvoltage 131 { 2 Volts 30 minutes.
Underfrequency 57 Hz +.2 Hz Underfrequency Time Delay 6 sec + 1 sec Am:ndment No. 75, 99
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2** One trip train
- of the RPS 2** The following RPS alternate alternate power supply may power supply protective be in the bypassed or devices shall be functionally inoperative condition for tested at least once every six a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If this months and calibrated once condition cannot be satisfied, each refueling outage.
or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS MG Acceptable set or de-energized within Device Setting 30 minutes.
Undervoltage 1131 2 Volts Overvoltage 1311 2 Volts Underfrequency 57 Hz i.2 Hz l
I A trip train consists of one breaker, one undervoltage relay, one' overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic.
Effective upon installation of the protective trip devices.
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Am;ndment No. 99
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NUCLEAR REGULATORY COMMISSION
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s-f PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LI_ CENSE Amendment No.101 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated December 23, 1981, as supplemented by letters dated March 30, 1983, June 2, 1983, and September 29, 1983, complies with the standards and requirements 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 regulations of the Comission; 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 Comission's regulations; D.
The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.
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 Facility Operating License No. DPR-56 is hereby amended to read as follows:
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_2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- 'h Ul'k Hub & A G or W. Rivenbark, Acting Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 21,1984
ATTACHMENT TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-278 Replace the following page and add the new page of the Appendix "A" Technical Specifications with the enclosed pages.
The pages are identified by Amendment number and contain a vertical line indicating the area of change.
i Remove Insert 36 36 l
36a 2
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I
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C. When it is determined that a channel has failed in the unsafe condition, the other RPS channels that moni. tor the same variable shall be functionally tested immediately before the trip system containing the failure is tripped.
The trip system containing the unsafe failure may be placed in the untripped condition during the period in which surveillance testing is being performed on the other RPS channels.
The trip system may be in the untripped position for no more that eight hours t
per functional trip period for this testing.
l D.
Reactor Protection System D. Reactor Protection System Power Supply Power Supply 1** Reactor Protection System
.l.**The following RPS power Power Supply:
supply (MG set) protective devices shall be functionally tested at least once every One trip train
.once each refueling outage.
inoperative condition for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If this condition cannot be satisfied, Acceptable or if both trip trains are Device Setting inoperative, the RPS bus shall be transferred to th'e alternate Undervoltage 113 + 2 Volts source or de-energized within Overvoltage 131 { 2 Volts 30 minutes.
Underfrequency 57 Hz +.2 Hz Underfrequency Time Delay 6 sec + 1 sec c Amendment No. H,101 y
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2** One trip train
- of the RPS 2** The fol' lowing RPS alternate alternate power supply may power supply protective be in th'. bypassed or devices shall be functionally inoperative condition for tested at least once every six a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If this months and calibrated once condition cannot be satisfied, each refueling outage.
or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS MG Acceptable set or de-energized within Device Setting 30 minutes.
Undervoltage 1131 2 Volts Overvoltage 1311 2 Volts Underfrequency 57 Hz i.2 Hz A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic.
Effective upon installation of the protective trip devices.
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Mtndment No.101
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