ML20206N567

Amends 134 & 96 to Licenses NPF-39 & NPF-85,respectively, Revising Overvoltage,Undervoltage & Underfrequency Allowable Values Associated with RPS Monitoring Channels & Add Supporting Details to TS Bases 3/4.8.4

ML20206N567
Person / Time
Site:	Limerick
Issue date:	05/13/1999
From:	Clifford J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206N570	List: ML20206N567 ML20206N576
References
NUDOCS 9905170271
Download: ML20206N567 (10)

Text

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WASHINGTON, D.C. 20566 4001 o

PECO ENERGY COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 3

Amendment No.134 License No. NPF-39 1.

The Nuclear Regulatory Commission (the Commission) has found that:

]

A.

The application for amendment by PECO Energy Company (the licensee) dated October 30,1998, as supplemented February 22,1999, complies with the i

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; 1

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 ce 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 satisfied.

i l

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4 9905170271 990513 PDR ADOCK 0 32 J

. 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-39 is hereby 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.134, are hereby incorporated into this license. PECO Energy 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 cate of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION J mes W. Clifford, Chief, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: fty 13,1999

E.

ATTACHMENT TO LICENSE AMENDMENT NO.134 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 8-28 3/4 8-28 B 3/4 8-3 8 3/4 8-3 i

l 1

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ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRICAL POWER MONITORING LIMITING CONDITION FOR OPERATION i

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 j

4.8.4.3 The above specified RPS electric power monitoring channels shall be d;termined 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 i

performed in the' previous 6 months.

I i

b. At least once per 24 months by demonstrating the OPERABILITY of I

overvoltage, undervoltage, and underfrequency protective instrumenta-I 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 Allowable Values.

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i 1.

Overvoltage s 127.6 VAC, l

l 2.

Undervoltage a 110.7 VAC, l

3.-

Underfrequency a 57.05 Hz.

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l LIMERICK - UNIT 1 3/4 8-28 w m. n, 78,134 I

t.

1 ELECTRICAL POWER SYSTEMS BASES

-3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Bypassing motor operated valves thermal overload protection ensures that the i

thermal overload protection will not prevent safety related valves from performing their function. For motor operated valves with spring return-to-center control associated with the Class 1E valves. passed by the automatic control signalsFor Clas switches', the thermal overload is by maintained contact control switches, the thermal overloads do not interrupt the valve motor power circuit, but they alarm on an overload condition in the control room. The Surveillance Requirements for demonstrating the bypassing of the thermal overload protection continuously are met by functionally testing the automatic operation of the motor operated valve and ensuring that the motor thermal overload protection design does not change and is in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for-Electric Motors on Motor Operated Valves", Revision 1, March 1977.

The RPS Electric Power Monitoring System is provided to isolate the RPS bus from the RPS/UPS inverter or an alternate power supply in the event of overvoltage, undervoltage or underfrequency. This system protects the loads connected to the RPS bus from unacceptable voltage and frequency conditions. The essential equipment powered from the RPS buses includes the RPS logic, scram solenoids, and valve isolation iogic.

The' Allowable Values are derived from equipment design limits, corrected for calibration and instrument errors. The trip setpoints are then determined, accounting for the remaining instrument errors (e.g.,-drift. The trip setpoints derived in this manner provide adequate protection and inclu)de allowances for instrumentation uncertainties, calibration tolerances, and instrument drift.

The Allowable Values for the instrument settings are based on the RPS providing power within the design ratings of the associated RPS components (e.g.,

RPS logic, scram solenoids). The most-limiting voltage requirement and associated line losses determine the settings of the electric power monitoring instrument channels.

I LIMERICK - UNIT 1 B'3/4 8-3 Anentent No. 33, 93, hes.

Ltr 11/10/00,134

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..k UNITE 6 STATES NUCLEAR REGULATORY COMMISSION M

WASHINGTON, D.C. 20555-0001

%,a,vu,.if PECO ENERGY COMPANY DOCKET NO. 50-353

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LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l

1

' Amendment No. 96 License No. NPF-85

)

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PECO Energy Company (the licensee) dated j

October 30,1998, as supplemented February 22,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the j

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 satisfied.

j 1

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 Facility Operating License No. NPF-85 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. 96,are hereby incorporated in the license. PECO Energy 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 and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION dBy James W. Clifford, hief, Section 2 -

Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation

~

Attachment:

. Changes to the Technical Specifications Date of issuance: Ity 13,1999

ATTACHMENT TO LICENSE AMENDMENT NO. m FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 8-28 3/4 8-28 B 3/4 8-3 8 3/4 8-3 i

.i i

4, 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 fer 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.

j

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 Allowable Values.

l 1.

Overvoltage s 127.6 VAC, l

2.

Undervoltage a 110.7 VAC, l

3.

Underfrequency a 57.05 Hz.

l i

LIMERICK - UNIT 2 3/4 8-28 trmtent 2. 34, 39, 96

c-

~

{

ELECTRICAL POWER SYSTEMS BASES 3/4.8.4 ELECTRICAL E0VIPMENT PROTECTIVE DEVICL Bypassing motor operated valves. thermal overload protection ensures that the thermal overload protection will not prevent safety related valves from performing _

c their function. For motor operated valves with spring return-to-center control switches, the thermal overload is bypassed by the automatic control signals c

associated with the Class IE valves.

For Class 1E motor operated valves with maintained contact control switches, the thermal overloads do not interrupt the valve motor power circuit, but they alarm on an overload condition in the control room. The Surveillance Requirements for demonstrating the bypassing of the thermal overload protection continuously are met by functionally testing'the automatic operation of the motor operated valve and ensuring that the motor thermal overload protection design does not change and is in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.

The RPS Electric Power Monitoring System is provided to isolate -the RPS bus from the HPS/UPS inverter or an alternate power supply in the event of overvoltage, undervoltage, or underfrequency. This system protects the loads connected to the RPS bus from unacceptable voltage and frequency conditions. -The essential equipment powered from the RPS buses includes the RPS logic, scram solenoids, and valve isolation logic.

The Allowable Values are derived from equipment design limits, corrected for calibration and instrument errors. The trip setpoints are then determined, accounting for the remaining instrument errors (e.g., drift.

derived in this manner provide adequate protection and inclu)de allowances forThe trip setp instrumentation uncertainties, calibration tolerances,. and instrument drift.

The Allowable Values for the instrument settings are based on the RPS providing power within the design ratings of the associated RPS components (e.g.,

RPS logic, scram solenoids).

The most limiting voltage requirement and associated line losses determine the settings of the electric power monitoring instrument channels.

LIMERICK - UNIT 2 B 3/4 8-3 Amntent tb. 57, Cass Ltr 11/10/T,

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