ML20072V583
| ML20072V583 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/08/1994 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072V585 | List: |
| References | |
| NUDOCS 9409200059 | |
| Download: ML20072V583 (10) | |
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UNITED STATES -
5 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 0001 r
EllILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352' LIMERICK GENERATING STATION.' UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE.
Amendment No. 78 License No. NPF-39 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application _-for amendment by Philadelphia Electric' Company (the licensee) dated'Harch 28, 1994, complies with the standards and I
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.(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 commoni 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 ofL l
the Commission's regulations and all applicable. requirements-have been satisfied.
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9409200059'940908 PDR-ADOCK 05000352 P
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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, 4
and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
78, are hereby incorporated into this license.
Philadelphia Electric.
Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
)
ohan C. Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 8, 1994 i
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.c ATTACHMENT TO LICENSE AMENDMENT N0. 78 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 i
Replace the following pages of the Appendix A Technical Specifications with-the attached pages.
The revised page is idantified by Amendment number and'
.contains vertical lines indicating the area of change.
Remove Insert
.I 3/4 8-27 3/4 8-27*
i 3/4 8-28 3/4 8-28 1
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- ELECTRICAL-POWER SYSTEMS MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION
- 3.8.4.2 The thermal overload protection of'all-Class IE motor operated valves shall be either:
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a.
Continously bypassed for all valves with maintained position control switches; or, b.
Bypassed only under accident conditions for all valves with spring-return-to-normal control switches.
APPLICABILITY:
Whenever the motor-operated valve is required to be OPERABLE..
ACTION:
With the thermal overload protection for one or more of the above required valves not bypassed continuously or only under accident conditions, as applicable, restore the thermal overload bypass within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).
SURVEILLANCE REOUIREMENTS 4.8.4.2.1 The thermal overload protection for the above required valves which are continuously bypassed and temporarily placed in force.only,when the valve motor is undergoing periodic or maintenance testing shall be verified to be bypassed following periodic or maintenance testing.during which the thermal overload protection was temporarily placed in force..
4.8.4.2.2 At least once per 24 months, a. CHANNEL FUNCTIONAL 1 TEST.of all those o
valves which are bypassed only under accident conditions (valves with spring-return-to-normal' control switches) shall-be performed'to verify that the thermal overload protection will be bypassed under accident-conditions.
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- LIMERICK.- UNIT 1.
3/4.8 Amendment ' No. 71
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ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRICAL POWER MONITORING LIMITING CONDITION FOR OPERATION 3.8.4.3 Two reactor protection system (RPS) electric power monitoring channels for each inservice RPS Inverter or alternate power supply shall be OPERABLE.
APPLICABILITY:
At all times.
ACTION:
a.
With one RPS electric power monitoring channel for an inservice RPS Inverter or alternate power supply inoperable, restore the inoperable power monitoring channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS Inverter or alternate power supply from service, b.
With both RPS electric power monitoring channels for an inservice RPS Inverter or alternate power supply inoperable, restore at least one electric power monitoring channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or remove the associated RPS Inverter or alternate power supply from service.
SURVEILLANCE RE0VIREMENTS 4.8.4.3 The above specified RPS electric power monitoring channels shall be determined OPERABLE:
a.
By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLD SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 6 months.
b.
At least once per 24 months by demonstrating the OPERABILITY of overvoltage, undervoltage, and underfrequency protective instrumenta-tion by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic, and output circuit breakers and verifying the following setpoints.
1.
Overvoltage s 132 VAC, 2.
Undervoltage 2 109 VAC, 3.
Underfrequency 2 57 Hz.
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LIMERICK - UNIT 1 3/4 8-28 Amendment No. 7Z, 78
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kj NUCLEAR REGULATORY COMMISSION 8
WASHINGTON, D.C. 20555-0001 PHILADELPHIA ELECTRIC COMPANY DOCKET N0. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39.
License No.: NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated March 28, 1994, 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; 8.
The facility will operate in conformity with the application, the provisions'of the Act, a1d 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
.l 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 i
defense and security or to the health and safety of _the public; and 1
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 4
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 Facility Operating License No. NPF-85 1-s hereby-1 amended to read as follows:
Technical Soecifications The-Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment.No.
39, are hereby incorporated into this license. Philadelphia Electric.
Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION C
Mohan C. Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
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2' Date of Issuance:
September 8, 1994 I:
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ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY OPERATING LICENSE NO. NPF DOCKET-NO. 50-353' Replace the following pages of the Appendix A Technical Specifications with the' attached pages. The, revised page is identified by Amendment number'and
. contains vertical lines indicating the area of change.
Remove Insert 3/4 8-27 3/4 8-27*
3/4 8-28 3/4 8-28
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ELECTRICAL POWER SYSTEMS MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CON 0! TION FOR OPERATION 3.8.4.2 The thermal overload protection of all-Class IE motor operated valves shall be either:
a.
Continously bypassed for all valves with maintained position control-
'l switches; or, b.
Bypassed only under accident conditions for all valves with spring-return-to-normal control switches.
APPLICABILITY:
Whenever the motor-operated valve is required to be OPERABLE.
ACTION:
With the thermal overload protection for one or more of the above required valves not' bypassed continuously or only under accident conditions, as applicable, restore the thermal overload bypass within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or. declare' the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).
~ SURVEILLANCE RE0VIREMENTS 4.8.4.2.1' The thermal overload protection for the above required valves which are continuously bypassed and temporarily placed'in force only when the valve motor is undergoing periodic or maintenance testing shall be verified to be.
bypassed following periodic or maintenance testing during-which-the thermal 4
overload protection was temporarily placed in force.
4.8.4.2.2 At least once per 24 months, a CHANNEL FUNCTIONAL' TEST of'all;those valves which are bypassed only under accident conditions (valves with spring-return-to-normal control switches).shall be performed to verify that the thermal-overload ~ protection will be bypassed.under accident ' conditions.
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' LIMERICK - UNIT 2-
- 3/4 8-27 Amendment No.34 l
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ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRICAL POWER MONITORING LIMITING CONDITION FOR OPERATION
'3.8.4.3 Two reactor protection system (RPS) electric power monitoring channels for each inservice RPS Inverter or alternate power supply shall be OPERABLE.
APPLICABILITY:
At all times.
ACTION:
a.
With one RPS electric power monitoring channel for an inservice RPS Inverter or alternate power supply inoperable, restore the inoperable power monitoring channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS Inverter or alternate power supply from service.
b.
With both RPS electric power monitoring channels for an inservice RPS Inverter or alternate power supply inoperable, restore at least one electric power monitoring channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or remove the associated RPS Inverter or alternate power supply from service.
SURVEILLANCE REQUIREMENTS 4.8.4.3 The above specified RPS electric power monitoring channels shall be determined OPERABLE:
a.
By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLD SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 6 months.
b.
At least once per 24 months by demonstrating the OPERABILITY of overvoltage, undervoltage, and underfrequency protective instrumenta-tion by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic, and output circuit breakers and verifying the following setpoints.
1.
Overvoltage s 132 VAC, 2.
Undervoltage 2 109 VAC, 3.
Underfrequency 2 57 Hz.
t LIMERICK - UNIT 2 3/4 8-28 Amendment No. 34, 39