ML20094L367

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Proposed TS SR 4.8.2.5.a,modifying RPS Electrical Protective Assemblies Channel Functional Test Surveillance Interval
ML20094L367
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/15/1995
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20094L366 List:
References
NUDOCS 9511200193
Download: ML20094L367 (16)
v • d • e


Text

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'. ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS ELECTRICAL PROTECTIVE ASSEMBLIES SURVEILLANCE INTERVAL , PER GL 91-09 MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 l

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9511200193 951115 PDR ADOCK 05000324 p _ PDR ,

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Sff.10N PMiE 3/4 h PLANT SYSTEMS (Continued) 3/4.7.3- FLOOD PROTECTION........................................ B 3/4 7-lh 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.............$.....B 3/4 7-lh 3/4.7.5 SNUBBERS................................................ B 3/4 7-2

'3/4.7.6' SEALED SOURCE CONTAMINATION............................. B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS (Deleted)...................... B 3/4 7-4 l 3/4.7.8 FIRE BARRIER PENETRATIONS (Deleted)..................... B 3/4 7-5 l 3/4.8 i ELECTRICAL POWER SYSTEMS., ............................. B /4 B-1 3/4.s.2.f Rwe. , pg.re r..a sy5vua ecec.rcc wwEA som ru,+ . a 3/at 8- A

/4.9 REFUELING OPE IONS 3/4.9.1 REACTOR MODE SWITCH..................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 P0SITION....................................

3/4.9.3 CONTROL R0D B 3/4 9-1 3/4.9.4 DECAY TIME.............................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS.......................................... B 3/4 9-1 3/4.9.6 CRANE AND H0IST OPERABILITY............................. B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE PMI B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL and 3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L................... B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL..................................... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................... B 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM (DELETED)................... B 3/4 10-1 3/4.10.3' SHUTDOWN MARGIN DEMONSTRATIONS.................... ..... B 3/4 10-1  !

3/4.10.4 RECIRCULATION L00PS..................................... B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER..................................... B 3/4 10-1 BRUNSWICK - UNIT 1 XII . Amendment No. 169 4

i I

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ELECTRICAL POWER SYSTEMS 4

REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING LIMITING CONDITION FOR OPERATION

'j 3.8.2.5 Two RPS electric power monitoring channels for.each inservice RPS MC set or alternate source shall be OPERABLE. ,

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j APPLICABILITY: Whenever the respective power supply is supplying power to a f RPS bus.

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ACTION
  • 1 i a. With one RPS electric power monitoring channel for an inservice RPS  !

j MG set or alternate pbwer supply inoperable, restore the inoperable  ;

i 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 l

RPS HC set or alternate power supply.from service.

  • i With both RPS electric power monitoring channels for an inservice RPS t

b.

MG set or alternate power supply inoperable, restore at least one to l

I OPERABLE status within 30 minutes or remove the associated RPS MG set or alternece power supply from service.  :

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j SURVEILLANCE REQUIRiliEWTS i T i The above specified RPS power monitori.ng system instrumentation shall

/ 4.8.2.5

be determged g g y ( , , .,., ,. j ,; ,., e ,q u g g ;

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... ._ .. ... ,.. P__^1 4"_'.-h t'T.d.*!*.".$9. 1.?.?'h...%_...TThi' ~. _. .

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t l b. At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage, and under-frequency protective j instrumentation by performance of a CHANNEL CALIBRATION including  ;

I simulated automatic actuation of the protective relays, tripping 1 l logic, and output circuit breakers and verifying the following 1 setpoints. )

f RPS MC SET ALTERNATE SOURCE

1. Over-voltage $ 129 VAC < 132 VAC
2. Under-voltage 3 105 VAC 3 108 VAC
3. Under-frequency 3 57 Hz 3 57 Hz i

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SRUNSWICK - UNIT 1 3/4 8-15 . Amendment.No. 92

5 l

l

'. b/4.8ELECTRICALPOWERSYSTEMS BASES i

The OPERABILITY of the A.C. and D. C. power sources and associated  !

distribution systems during operation ensures that sufficient power will be 4 available to supply the safety-related equipment required for 1) the safe l shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the-requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the  :

Power sources provide restriction upon continued facility operation f comunensurate with the level of degradation. The OPERABILITY of the power sources is consistent with the initial condition assumptions of the accident analyses and is based upon maintaining at least one of each of the onsite A.C.

and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and '

single failure of the other onsite A.C. source.

r The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that

1) the facility can be maintained in the . shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintain the facility status.

The requirement of Specification 4.8.1.1.1.b to demonstrate the operability of the independent circuits between the offsite transmission network and the onsite Class IE distribution system may be satisfied by transferring unit loads from the unit auxiliary transformer (UAT) to the start-up auxiliary transformer (SAT). The requirement to perform this i

, demonstration "during shutdown" implies that this testing may be performed by l

the normal power switching evolutions during unit shutdown or while shutdown.
The requirement of Specification 4.8.1.1.2.d to demonstrate the OPERABILITY of each diesel generator at least once per 18 months during
shutdown may be satisfied by performing the required surveillances on diesel

! A generators number 1 and 2 while Brunswick Unit 1 is shutdown, and diesel

, y generators number 3 and 4 while Brunswick Unit 2 is shutdown. While 4

g performing the required surveillances of a given diesel generator, the loads associated with that diesel generator are subject to the Limiting Condition -

1 for Operation requirements for each system or component that obtains its i emergency power from that diesel generator.

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BRUNSWICK - UNIT 1 d N SsfVs' ills a [811 B 3/4 May$0, 1990 t- 4t e j

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ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 i OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS ELECTRICAL PROTECTIVE ASSEMBLIES SURVEILLANCE INTERVAL , PER GL 91-09  ;

EQKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2 l

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SECTION Eeff  ;

3/4.Y PLANT SYSTEMS' (Continued) l 3/4.7.3 FLOOD PROTECTION........................................ B 3/4 7-lh  !

3/4.7.4 REACTOR CORE ISOLATION' COOLING SYSTEM................... B 3/4 7-lh

]

3/4.7.5 B 3/4 7-2 SNUBBERS................................................

f 3/4.7.6 SEALED SOURCE CONTAMINATION............................. B 3/4 7-4 i

3/4.7.7 FIRE SUPPRESSION SYSTEMS (Deleted)...................... B 3/4 7-4 . l l

. i 3/4.7.B FIRE BARRIER PENETRATIONS (Deleted)..................... B 3/4 7-5 l .

1

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+ 3/4.8 ELECTRICAL POWER SYSTEMS................................. 4 B-1 f 3/4 B S F REA= m Pa* fit.r..d synT.m am.ran P,wea. m.weam a sh s-A ,

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3/4.9.1 REACTOR MODE SWITCH..................................... B 3/4 9-1 ,

l 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 l

) 3/4.9.3 CONTROL R00 P0SITION.................................... B 3/4 9-1 4

l 3/4.9.4 DECAY TIME.............................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS.......................................... B 3/4 9-1 i

3/4.9.6 CRANE AND HOIST OPERABILITY............................. B 3/4 9-2 i

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L....................

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL. and

. 3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L................... B 3/4 9-2 i

3/4.9.10 CONTROL R0D REM 0 VAL..................................... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS

3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................... B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................... B 3/4 10-1 i 3/4.10.3 SHLITDOWN MARGIN DEMONSTRATIONS.......................... B 3/4 10-1 i

_ 3/4.10.4 RECIRCULATION L00PS..................................... B 3/4 10-1

, 3/4.10.5 PLANT SERVICE WATER..................................... B 3/4 10-1 BRUNSWICK - UNIT 2 XII Amendment No. 200 n

1 l

EUECTRICAL POWER SYSTEMS

) . REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING LIMITING CONDITION FOR OPERATION

^

3.8.2.5 Two RPS electric power monitoring channels for each inservice RPS MC set or alternate source shall be OPERABLE.

APPLICABILITY:

Whenever the respective power supply is supplying power to a  ;

- RPS bus. ,

ACTION! ,

a. With one RPS electric power monitoring channel for an inservice RPS MC set or alternate power supply inoperable, restore the inoperable 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 MC set or alternate power supply"from service.

b. With both RPS electric power monitoring channels for an inservice RPS 4 HC set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set l or alternate power supply from service.

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SURVEILLANCE REQUIREMENTS 4.8.2.5 The above specified RPS power monitoring system instrumentation shall j

be determined OPERABLE: ,s edad*L. #ddcrad as rase e.ek 4.,.. . +k pl..d .,s .,. ce s a sdyne.id for =

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. b. At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage, and under-frequency protective instrumentation 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:

RPS MG SET ALTERNATE SOURCE i

1. Over-voltage $ 129 VAC $ 132 VAC 1
2. Under-voltage 3 105 VAC 3 108 VAC i

Under-frequency > 57 Hz > 57 H 1 3.

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a 3/4 8-15 Amendeent No. 117 BRUNSWICK - UNIT 2 i

3/4.8 ELECTRICAL POWER SYSTEMS BASES f

The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for 1) the safe shutdown of the facility, and 2) the mitigation and control of accident '

conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power _ 3

' sources is consistent with the initial condition assumptions of the accident analyses and is based upon maintaining at least one of each of the onsite A.C.

and D.C. power sources and associated distribution systems OPERABLE during

. accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. source.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that l

< 1) the facility can be maintained in the shutdown or refueling condition for '

extended time periods, and 2) sufficient instrumentation and control I capability is available for monitoring and maintaining the facility status.

4.

p The requirement of Specification 4.8.1.1.1.b to demonstrate the operability of the independent circuits between the offsite transmission g network and the onsite Class lE distribution system may be satisfied by s transferring unit loads from the unit auxiliary transformer (UAT) to the 4

start-up auxiliary transformer (SAT). The requirement to perform this demonstration "during shutdown" implies that this testing may be performed by y the normal power switching evolutions during unit shutdown or while shutdown. .

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Cp ro <:ot<A h Genr.'<. L.H.c9l-o9 l

BRUNSWIr" dUIT 2 B 3/4 8-1 May 25, 1989

. 6 ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 i

OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS ELECTRICAL PROTECTIVE ASSEMBLIES SURVEILLANCE INTERVAL , PER GL 91-09  :

TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 L

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1N.Dfl BAS.ES

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SECTION Eeff 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION........................................ B 3/4 7-lh 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM................... B 3/4 7-lh ,

3/4.7.5 SNUBBERS................................................ B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION............................. B 3/4 7-3 i 3/4.7.7 FIRE SUPPRESSION SYSTEMS (Deleted)...................... B 3/4 7-4 3/4.7.8 FIRE BARRIER PENETRATIONS (Deleted)..................... B 3/4 7-5 ,

4 3/4.8 ELECTRICAL POWER SYSTEMS.................................. B 3/4 8-1 l  !

i 3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING..... B 3/4 8-2 l

! '3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH....................... ............. B 3/4 9-1 i j 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 i 3/4.9.3 CONTROL ROD POSITION............... ..... .............. B 3/4 9-1 l 3/4.9.4 DECAY TIME.............................................. B 3/4 9-1 l 3/4.9.5 COMMUNICATIONS...................................... . . B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY............................. B 3/4 9-2 i 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L.................... B 3/4 9-2 4 3/4.9.8 WATER LEVEL-REACTOR VESSEL. and

3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L................... B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL................................ .... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................... B 3/4 10-1 l 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM (DELETED)................... B 3/4 10-1 l 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.......................... B 3/4 10-1 j 3/4.10.4 RECIRCULATION L00PS..................................... B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER................... ................. B 3/4 10-1 ,

BRUNSWICK - UNIT 1 XII Amendment No. i l

_i

ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING

~

LIMITING. CONDITION FOR OPERATION 3.8.2.5 Two RPS electric power monitoring channels for each inservice RPS HG set or alternate source shall be OPERABLE.

APPLICABILITY: Whenever the respective power supply is supplying power to a RPS bus.

ACTION:

a. With one RPS electric power monitoring channel for an inservice RPS HG set or alternate power supply inoperable, restore the inoperable 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 HG set or alternate power supply from service.
b. With both RPS electric power monitoring channels for an inservice RPS HG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS HG set or alternate power supply from service.

SURVEILLANCE REQUIREMENTS 4.8.2.5 The above s)ecified RPS power monitoring system instrumentation shall be determined OPERAB_E:

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, and
b. At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage and under-frequency 3rotective instrumentation 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:

RPS MG SET ALTERNATE SOURCE

1. Over-voltage s 129 VAC s 132 VAC
2. Under-voltage a 105 VAC = 108 VAC
3. Under-frequency a 57 Hz a 57 Hz BRUNSWICK - UNIT 1 3/4 8-15 Amendment No. I

3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING The CHANNEL FUNCTIONAL TEST is only required to be performed while the plant is in a condition in which the loss of the RPS bus will not jeo)ardize steady state power operation (the design of the system is such that tie power source must be removed from service to conduct the surveillance). The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is intended to indicate an outage of sufficient duration to allow scheduling and proper performance of the surveillance.

The above requirements of the surveillance frequency are based on i guidance provided in Generic Letter 91-09.

l l

1 4

i BRUNSWICK - UNIT 1 B 3/4 8-2 Amendment No. I

_ _ l

i

  • n
  • i i

~

ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 - '

' NRC DOCKETS 50-325 AND 50-324 .

OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS ELECTRICAL PROTECTIVE ASSEMBLIES SURVEILLANCE INTERVAL , PER GL 91-09 TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2

. 9 h

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1 r

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t INDEX

. BASE.S, _ - , . . _ . . - , _ . . _ _ - ..

3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION........................................ B 3/4 7-lh 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...................

B 3/4 7-lh 3/4.7.5 SNUBBERS................................................ B 3/4 7-2 3/4.7.6 SEALE0 SOURCE CONTAMINATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS (0eleted)...................... B 3/4 7-4 3/4.7.8 FIRE BARRIER PENETRATIONS (0eleted)..................... B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS.................................

B 3/4 8-1 1 1

3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING.. . . B 3/4 8 3/4.9 REFUELING OPERATIONS B 3/4 9-1 3/4.9.1 REACTOR MODE SWITCH......................................

3/4.9.2 INSTRUMENTATION..................................... ... B 3/4 9-1 B 3/4 9-1 3/4.9.3 CONTROL R00 P0SITION....................................

........................ B 3/4 9-1 3/4.9.4 DECAY TIME.....................

3/4.9.5 COMMUNICATIONS.......................................... B 3/4 9-1 3/4.9.6 CRANE AND H0IST OPERABILITY............................. B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L....... ............ B 3/4 9-2 i 3/4.9.8 WATER LEVEL-REACTOR VESSEL. and i 3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L...................

B 3/4 9-2 ,

3/4.9.10 CONTROL R00 REM 0 VAL..................................... B 3/4 9-2 1

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................... B 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM (DELETED)................... B 3/4 10-1 3/4.10.3 SHUTOOWN MARGIN DEMONSTRATIONS.......................... B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.....................................

B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER.....................................

B 3/4 10-1 BRUNSWICK - UNIT 2 XII Amendment No. l

ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING

~

, LIMITING CONDITION FOR OPERATION ,

3.8.2.5 Two RPS electric power monitoring channels for each inservice RPS HG set or alternate source shall be OPERABLE.

APPLICABILITY: Whenever the respective power supply is supplying power to a RPS bus.

ACTION:

a. With one RPS electric power monitoring channel for an inservice RPS MG set or alternate power supply inoperable, restore the inoperable 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 MG set or alternate power supply from service.
b. With both RPS electric power monitoring channels for an inservice RPS MG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.

SURVEILLANCE REQUIREMENTS 4.8.2.5 The above s)ecified RPS power monitoring system instrumentation shall be determined OPERAB_E:

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, and
b. At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage, and under-frequency arotective instrumentation 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:

RPS MG SET ALTERNATE SOURCE

1. Over-voltage s 129 VAC s 132 VAC
2. Under-voltage = 105 VAC = 108 VAC
3. Under-frequency a 57 Hz a 57 Hz I

f 3/4 8-15 Amendment No. l BRUNSWICK - UNIT 2

~

P .

3/4.8 ELECTRICAL POWER SYSTEMS  !

- i

, BASE.S 4

3/4.8.2.5 REACTOR PROTECTION SYSTEM ELECTRIC POWER MONITORING The CHANNEL FUNCTIONAL TEST is only required to be performed while the plant is in a condition in which the loss of the RPS bus will not jeo)ardize steady-state power operation (the design of the system is such that tie power source must be removed from service to conduct the surveillance). The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is intended to indicate an outage of sufficient duration to allow scheduling and proper performance of the surveillance.

The above requirements of the surveillance frequency are based on guidance provided in Generic Letter 91-09.

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BRUNSWICK - UNIT 2 B 3/4 8 Amendment No. l

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