Text

Proposed Tech Spec Changes Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation & Main Turbine Trip Sys
	ML20080N166
Person / Time
Site:	Brunswick
Issue date:	09/29/1983
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20080N161	List: ML20080N159; ML20080N166;
References
	83TSB31, NUDOCS 8310040388
	Download: ML20080N166 (28)
	v • d • e

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5 ENCLOSURE 2 l

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 PROPOSED TECHNICAL SPECIFICATION CHANGES FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRLMENTATION AND MAIN TURBINE TRIP SYSTEM 4

REFERENCE No. 83TSB31 8310040388 830929 PDR ADOCK 05000 P

m

t INDEX DEFINITIONS SECTION 1.0 DEFINITIONS (Continued)

PAGE PRESSURE BOUNDARY LEAKAGE........................................ 1-4 P RIMARY CONTAINM ENT INTEGRITY.................................... 1-5 RATED THERMAL P0WER.............................................. 1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME.......................... 1-5 REFERENCE LEVEL ZER0............................................. 1-5 REPORTABLE O CCURRENCE............................................ 1-5 ROD DENSITY...................................................... 1-6 SECONIRRY CONTAINMENT INTEGRITY.................................. 1-6 S H LT DOWN MARGIN.................................................. 1 - 6 S P I RAL R E L0 AD.................................................... 1 - 6 S P I RAL UNL0 A D.................................................... 1 - 6 STAGGERE D T E ST B AS IS............................................. 1 - 7 THERMAL P0WER.................................................... 1-7 TOTAL P E AKI NG F ACT0R............................................. 1 -7 TURBINE BYPASS SYSTEM RESPONSE TIME.............................. 1-7 UNI DENTIF I E D L E AKAG E............................................. 1 -7 FREQ UENCY NOTATION, TABLE 1.1.................................... 1-8 OPERATIONAL CONDITIONS, TABLE 1. 2................................ 1-9 l

i l

BRUNSWICK - UNIT 1 II Amendment No.

l INDEX LL*f1 TING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION_

PAGE 3/4.3 INSTRU4ENTATION 3/4.3.1 REACTOR PROTECTION SYSTE!! INSTRuiENTATION...............

3/4 3-1 l

3/4.3.2 ISOLATION ACT UATION INSTRUMENTATION.....................

3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUiENTATION.

3/4 3-30 1

I 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUliENTATION............

3/4 3-39 l

l 3/4.3.5 MONITORING INSTRUMENTATION Seismic Mo nitoring Ins trumentation......................

3/4 3-44 Remote Shutdown Monitoring Instrumentation..............

3/4 3-47 Po s t-accident Monitoring Ins trumentation................

3/4 3-50 l

Source Range Monitors...................................

3/4 3-53 I

Chlo rine De t e c tio n Sy s t em...............................

3/4 3-54 Chlorine Intrusion Monitors.............................

3/4 3-55 Fire Detection Ins trumentation..........................

3/4 3-59 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRU:!ENTATION.....

3/4 3-62 3/4.3.8 FEEDRATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION......................................

3/4 3-71 3/4.4 REACTOR COOLANT SYSTEM l

l 3/4.4.1 RECIRCULATION SYSTEM l

Re c i r cul a t ion Lo o p s.....................................

3/4 4-1 Jet Pumps...............................................

3/4 4-2 Idle Recirculation Loop St artup.........................

3/4 4-3 3/4.4.2 S AFETY/ RE LIEF V ALVES....................................

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE l

Le akag e De t e c tio n Sy s t ems...............................

3/4 4-5 l

l Operational Leakage.....................................

3/4 4-6 r

i l

i BRUNSWICK - UNIT 1 V

Amendment No.

. -~

s INDEX.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.4 REACTOR CORE Is0LATION COOLING SYSTEM...................

3/4 7-7 3/4.7.5 KYDRA ULIC S N UB B ERS......................................

3/4 7-9 3/4.7.6 SEALED SO URCE CONTAMINATION.............................

3/4 7-32 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fi re Su ppression Wa t er Sys t em...........................

3/4 7-34 Spray and/or Sprinkler Systems..........................

3/4 7-38 Righ Pressure CO2 Systems...............................

3/4 7-40 Fire Hose Stations......................................

3/4 7-41 Fo am Sy s t ems............................................

3/4 7-44 3/4.7.8 FIRE BARRIER PENETRATIONS...............................

3/4 7-46 3/4.7.9 MAIN T URBINE BY PAS S SYSTEM..............................

3/4 7-47 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Op eration o f One o r Bo th Units..........................

3/4 8-1 Shutdown of Bo th Unit s..................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIB'JrION SYSTEMS A.C. Distribution - Operation of One o r Bo t h Un i t s.........................................

3/4 8-6 A.C Distribution - Shutdown of Both Units...............

3/4 8-7 D. C. Dis t ribution - Op e rating...........................

3/4 8-8 D. C. Dis t rib ution - Shu tdown............................

3/4 8-11 3/4.9 REFUELING OPERATIONS 2/4.9.1 REA CTO R MO DE S WITCH.....................................

3/4 9-1 3/4.9.2 IN STR UM ENT ATIO N.........................................

3/4 9-3 BRUNSWICK - UNIT 1 VIII Amendment No.

s INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 S H ITIDOWN M ARGIN...............................

B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES..........................

B 3/4 1-1 3/4.1.3 CO NTROL R0 D S..................................

B-3/4 1-1 3/4.1.4 CONTROL ROD PROGRAM CONTROLS..................

B 3/4 1-3 3/4.1.5 STANDBY LIQ UID CONTROL SYSTEM.................

B 3/4 1-4 3/4.2 POWER DISTRIBITTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATING RATE....

B 3/4 2-1 3/4.2.2 APRM SETP0INTS................................

B 3/4 2-3 3/4.2.3 MINIMIN CRITICAL POWER RATIO..................

B 3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE...................

B 3/4 2-5 3/4.3 INSTRIMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRIMENTATION.....

B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRtNENTATION...........

B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRINENTATION............................

B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRIM ENTATION............................

B 3/4 3-2 3/4.3.5 MONITORING INSTRINENTATION....................

B 3/4 3-2 l

3/4.3.6 ADIS RECIRCULATION PlHP TRIP SYSTEM INSTRIMENTATION............................

B 3/4 3-4 3/4.3.8 FEEDJATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION INSTRUMENTATION............................

B 3/4 3-5 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM..........................

B 3/4 4-1 t

3/4.4.2 S AFETY/ RELIEF VALVES..........................

B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE................

B 3/4 4-1 l

l

[

BRUNSWICK - UNIT 1 X

Amendment No.

=

s INDEX BASES SECTION PAGE 3/4.7 PLANT SfSTEMS (Continued) 3/4.7J FLOO D PROTE CTION..................................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.............

B 3/4 7-1 3/4.7.5 HY DRAULIC S N UB B ERS................................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION.......................

B 3/4 7-3 3/4.7.7 FIRE S UPPRESSION SYSTEMS..........................

B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS.........................

B 3/4 7-4 3/4.7.9 MAIN T URBINE BYPASS SYSTEM........................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS..................................

B/3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MO DE SWITCH...............................

B 3/4 9-1 3/4.9.2 IN STRIMENTATION...................................

B 3/4 9-1 3/4.9.3 CONTROL RO D P 0 SITION..............................

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 HOIST OPERABILITY.......................

B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L..............

B 3/4 9-1 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 ROD 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 SEQ UENCE CONTROL SYSTEM.......................

B 3/4 10-1 3/4.10.3 SH UIDOUN MARGIN DEMONSTRATIONS....................

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

B 3/4 10-1 3/4.10.5 P LANT S E RV IC E W ATER...............................

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

r l

DEFINITIONS j

i I

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:

s.

A test schedule for n systems, subsystens, trains or other designated components obtained by dividing the specified test interval into n equal subintervals.

l b.

The testing of one system, subsystem, train or other designated

)

component at the beginning of each subinterval.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TOTAL PEAKING FACTOR The TOTAL PEAKING FACTOR (TPF) shall be the ratio of local LHGR for any specific location on a fuel rod divided by the average LHGR associated with the fuel bundles of the same type operating at the core average bundle power.

TUREINE BYPASS SYSTEM RESPONSE TIME The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval from when

~

the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

UNIDENTIFIED LEAKAGE UNIDENTIFTED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

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f BRUNSWICK - UNIT 1 1-7 Amendment No.

I INSTRUMENTATION 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The feedwater/ main turbine trip system actuation instrumentation channels shown in Table 3.3.8-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a.

With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3.8-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

With the number of OPERABLE channels two less th'an required by the c.

Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REOUIREMENTS 4.3.8.1 Each feedwater/ main turbine trip systen actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CRANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.8.1-1.

j 4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

l BRUNSWICK - UNIT 1 3/4 3-71 Amendment No.

tn

.h TABLE 3.3.8-1 if FEEDWATER/ MAIN TtfRBINE TRIP SYSTEM ACTIIATION INSTRIINENTATInt3, s

Q MINIffffH y

OPER A RI.E TRIP FilNCTION AND INSTRift1Effr NIIMRERS CllAtlNEl.S 1.

Reactor Vessel Water Level - liigh 3

( C32-1.T-N004 A, B,C; C32-K600A,B,C; C32-1.A-K624A,B,C) o Y

d 17 9

R 0n g

4

.U

os TABLE 3.3.8-2 a

N FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTliATION INSTRiftfENTATION SETPOINTS 9

i E

ALLOWABLE TRIP FilNCTION AND INSTRifMENT NIIMBERS TRIP SETPOINT VAI.IIE I.

Reactor Vessel Water T evel - Illgh

< 208 inches *

< 209.5 inches *

(C32-LT-N004A,B,C; C32-K600A,B,C; C32-LA-K624A,B,C)

M Y,

~"

Vessel water levels refer to REFERENCE LEVEL ZERO.

11 3n

g:

5 m

n TABLE 4.3.8.1-1 7:

FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS E

1 r

CHANNEL CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION 1.

Reactor Vessel Water Level - High D

Q R

(C32-LT-N004A,B,C; C32-K600A,B,C; C32-LA-K624A,B,C)

Y' i

i

=

s9h E

.if

3.u.

a

.aa_.

a w

m s--

s as-2

-e

.u.

2

+

3 PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9 The main turbine bypass system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

t With the main turbine bypass system inoperable, restore the system to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or:

Determine MCPR to be equal to or greater than the applicable MCPR a.

limit without bypass within the next hour, or b.

Restore MCPR to within the applicable MCPR limit without bypass within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REOUIREMENTS 4.7.9 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

i 7 days by cycling each turbine bypass valve through at least one s.

complete cycle of full travel, and b.

18 months by:

1.

Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 300 milliseconds to a valve position equivalent to 80% of the total main turbine bypass system rated flow.

M e

i BRUNSWICK - UNIT 1 3/4 7-47 Amendment No.

p.

INSTRUMENTATION BASES 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system is utilized to terminate a transient initiated by a feedwater controller failure resulting in a maximum feddwater demand.

During this event, the resulting influx of excess feedwater flow

' results in an increase in core subcooling, which reduces the void fract; ion-and thus induces an increase in reactor power. The excess feedwater flow also increases reactor water level, which eventually leads to a main turbine trip ~

and feedwater turbice trip as a result of the high water level. The main turbine stop valve position switches actuate a reactor scram trip and the main turbine bypass system (refer to Base 3 3/4.7.9) which limits the neutron flux peak and fuel thermal transient such. that 'the Minimum Critical Power Ratio remains above the Safety Licit.

l

/

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BRUNSWICK, UNIT 1 B 3/4 3-5 Amendment No.

PLANT SYSTEMS BASES 3/4.7.9 MAIN TURBINE BYPASS SYSTEM The main turbine bypass system is required to be OPERABLE consisent with the assumptions of the feedwater controller failure analysis for FSAR Chapter 15.

Following closure of the main turbine stop valves initiated by the feedwater/ main turbine trip system actuation instrumentation, the main turbine bypass system actuates to the limit the pressure increase so that no excessive overpressurization of the nuclear system process barrier occurs.

(For Unit 1, which has a much smaller turbine bypass system capacity that Unit 2, the relief valves open briefly as steam line pressures reach the relief valve setpoints.) The turbine bypass valves subsecuently close to control the pressure in the vessel during reactor shutdown.

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3 BRUNSUICK - UNIT 1 B 3/4 7-5 Amendment No.

~

ENCLOSURE 3

/

RRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 I

PROPOSED TECHNICAL SPECIFICATION CHANGES FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION AND MAIN TURBINE TRIP SYSTEM

. REFERENCE No. 83TSB31 l

l

\\

l I

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.3 INSTR &fENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTR &!ENTATION................

3/4 3-1 3/4.3.2 ISOLATION ACT UATION INSTRGIENTATION......................

3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRU4ENTATION..

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.............

3/4 3-39 3/4.3.5 MONITORING INSTRGiENTATION Seismic !!onitoring Ins trtnectation.......................

3/4 3-44 Remote Shutdown Monitoring Instrumentation...............

3/4 3-47 Po s t-accident Monitoring Ins trumentation.................

3/4 3-50 Source Range Monitors....................................

3/4 3-53 Chl o rine De t e ctio n Sy s t em................................

3/4 3-54 Chloride Intrusion Monitors..............................

3/4 3-55 Fi re De t ection In s t rumentation...........................

3/4 3-59 3/4.3.6 RECIRCULATION PLSIP TRIP ACTUATION INSTRC!ENTATION ATWS Recirculation Pump Trip System Instrumentation......

3/4 3-62 End-of-Cycle Recirculation Pump Trip System Instrunentation........................................

3/4 3-66 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTR &fENTATION..................................

4...

3/4 3-77 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Re ci r cula t ion Lo o p s......................................

3/4 4-1 Jet Pumps................................................

3/4 4-2 Idle Re circula tion Lo op St a rt-up.........................

3/4 4-3 3/4.4.2 S AFETY/ REL IEF V ALVE S.....................................

3/4 4-4 l

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i BRUNSWICK - UNIT 2 V

Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.................

3/4 7-3 3/4.7.3 FLOOD PROTECTION.........................................

3/4 7-6 3/4.7.4 REACTOR CORE ISOLATION COOLING SY'aTEM....................

3/4 7-7 3/4.7.5 HY DRA ULIC S N UB BERS.......................................

3/4 7-9 3/4.7.6 SEALE D S O URCE CONTAMIN ATION..............................

3/4 7-37 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppres sion Wa te r Syr tem............................

3/4 7-39 Spray and/or Sprinkler Sfstems...........................

3/4 7-43 High Pressure CO2 Systems................................

3/4 7-45 Fire Hose Stations.......................................

3/4 7-46 Fo am Sy s t ems.............................................

3/4 7-49 3/4.7.8 FIRE BARRIER PENETRATIONS................................

3/4 7-51 3/4.7.9 MAIN T URBINE BY PAS S SYSTEM...............................

3/4 7-52 l

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Op e ration o f One o r Bo th Unit s...........................

3/4 8-1 Shutdown o f Both Unit s...................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operation of One or Bo th Units.......

3/4 8-6 A.C. Distribution - Shutdown of Both Units...............

3/4 8-7 D. C. Di s t ribution - Op e ra ting............................

3/4 8-8 D. C. Dis t rib u tion - Shu tdown.............................

3/4 8-11 3/4.9 REFUELING OPERATIONS 3/4.9.1 RE ACTO R MO DE S WITCH......................................

3/4 9-1 BRUNSWICK - UNIT 2 VIII Amendment No.

INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SH ITIDOWN M ARGIN....................................

B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES...............................

B 3/4 b l 3/4.1.3 C O NTROL R 0 DS.......................................

B 3/4 1-1 3/4.1.4 CONTROL R0D PROGRAM CONTR0LS.......................

B 3/4 1-3 3/4.1.5 STAND 3Y-LIQ UID CONTROL SYSTEM......................

B 3/4 1-4 3/4.2 POWER DISTRIBITTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERI. TION RATE.........

B 3/4 2-1 3/4.2.2 APRM SETP0INTS.....................................

B 3/4 2-3 3/4.2.3 MINIMD1 CRITICAL POWER RATIO.......................

B 3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE........................

B 3/4 2-5 3/4.3 INSTR &fENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRG!ENTATION..........

B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRLMENTATION................

B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRLMENTATION.................................

B 3/4 3-2 3/4.a.'

CONTROL ROD WITHDRAWAL BLOCK INSTRU!ENTATION.......

B 3/4 3-2 3/4.3.5

. "I TO RING IN STR LMENT ATION.........................

B 3/4 3-2 3/4.3.6 RECIRCULATION PG!P TRIP ACTUATION INSTRUfENTATION.................................

B 3/4 3-4 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRG!ENTATION.................................

B 3/4 3-5 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRC ULATION SYSTEM...............................

B 3/4 4-1 3/4.4.2 S AFETY/ RE LIEF VALVES...............................

B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE.....................

B 3/4 4-1 BRUNSWICK - UNIT 2 X

Amendment No.

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOO D P ROTE CTION...................................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM..............

B 3/4 7-1 3/4.7.5 HY DRAULIC S N CB B ERS.................................

B 3/4 7-2 3/4.7.6 SEALED SO URCE CONTAMINATION........................

B 3/4 7-3 3/4.7.7 FIRE S UPPRESSION SYSTEMS...........................

B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS..........................

B 3/4 7-4 3/4.7.9 KAIN T URBINE BYPASS SYSTEM.........................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS...................................

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTO R M O DE S WITCH................................

B 3/4 9-1 3/4.9.2 IN STR UM ENTATION....................................

B 3/4 9-1 3/4.9.3 CONTROL RO D P 0 SITION...............................

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 HOIST OPERABILITY........................

B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT F UEL STORAGE P00L...............

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER L EVEL-SPENT F UEL STORAGE P00L................

B 3/4 9-2 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 SEQ UENCE CONTROL SYSTEM........................

B 3/4 10-1 3/4.10.3 SH UTDOWN MARGIN DEMONSTRATIONS.....................

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

B 3/4 10-1 3/4.10.5 P LANT S E RV I CE W ATE R................................

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

INDEX DEFINITIONS SECTION 1.0 DEFINITIONS (Continued)

PAGE O DYN O PTION A............................................................. 1 -4 O DY N O P T I O N B............................................................. 1 - 4 OPERABLE - OPERABILITY.................................................... 1-4 OPERATIONAL C0NDITION..................................................... 1-4 PHYSICS TESTS............................................................. 1-4 P RE S S URE B O UN DARY LE AKAG E................................................. 1-5 PRIMARY CONTAINMENT INTEGRITY............................................. 1-5 RATE D T H E RMAL P 0W E R....................................................... 1 - 5 REACTOR PROTECTION SYSTEM RESPONSE TIME................................... 1-5 REFERENCE LEVEL ZER0...................................................... 1-5 REPORTABLE OCCURRENCE..................................................... 1-5 R O D D EN S ITY............................................................... 1 - 6 SECONDARY CONTAINMENT INTEG RITY........................................... 1-6 S H UT DOWN MARG IN........................................................... 1 - 6 SPIRAL REL0AD............................................................. 1-6 SPIRAL UNL0AD............................................................. 1-6 ST AGGE RE D TEST B AS IS...................................................... 1-6 THERMAL P0WER............................................................. 1-7 TOTAL PEAKING FACT 0R...................................................... 1-7 T URBINE BY PASS SYSTEM RESPONSE T L3E....................................... 1-7 l

UNIDENTIFIED LEAKAGE...................................................... 1-7 F REQ UENCY NOTATION, T ABLE 1.1............................................. 1-8 OPERATIONAL CON DITIONS, TABLE 1. 2......................................... 1-9 II Amendment No.

BRUNSWICK - UNIT 2

v DEFINITIONS STAGGERED TEST BASIS (Continued) b.

The testing of one system, subsystem, train or ut.her designated component at the beginning of each subinterval.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

- TOTAL PEAKING FACTOR The TOTAL PEAKING FACTOR (TPF) shall be the ratio of local LHGR for any specific location on a fuel rod divided by the average LHGR associated with the f uel bundles of the same type operating at the core average bundle power.

TURBINE BYPASS SYSTEM RESPONSE TIME The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval f rom when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

-UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

BRUNSWICK - UNIT 2 1-7 Amendment No.

l INSTRUMENTATION 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The feedwater/ main turbine trip system actuation instrunentation channels shown in Table 3.3.8-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.

l APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

a.

With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.8-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REOUIREMENTS I

4.3.8.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERABLE by the perfor=ance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIEPATION operations at the frequencies

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shown in Table 4.3.8.1-1.

I 4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

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BRUNSWICK - UNIT 2 3/4 3-77 Amendment No.

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TABLE 3.3.8-1 iA N

-FEEI) WATER / MAIN TURRINE TRIP SYSTEM ACTlfATION INSTRIIMENTATION R

i g

MINIMUM g

OPERABLE H

TRIP Fl!NCTION AND INSTRIIMENT NiiMRERS CilANNELS IJ 1.

Reactor Vessel Water Level Ifigh 3

(C32-LT-N004A,B,C; C32-K600A,B,C; C32-LA-K624A,B,C)

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Ya if u

Wn

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A cay TABLE 3.3.8-2 a

FEEDWATER/ MAIN TliRBINE TRIP SYSTEM ACTilATIOri INSTRilffENTATION SETPOINTS A

O ALLOWABLE N

TRIP FlINCTION AND INSTRiftfEPTT NilMBERS TRIP SETPOINT VALIIE to 1.

Reactor Vessel Water I.evel - liigh

< 208 inches *

< 209.5 inches *

(C32-LT-N004A,B,C; C32-K600A,B,C; C32-LA-K624A,B,C) l.

I M

n Ya

Vessel water levels refer to REFERENCE I.EVEL ZERO.

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TABLE 4.3.8.1-1 FEEIMATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

8 CHANNEL CHANNEL FUNCTIONAL CHANNEL 1

y TRIP FUNCTION AND INSTRUMEfff NUMBER CilECK TEST CALIBRATION w

1.

Reactor Vessel Water Level - liigh D

Q R

(C32-LT-N004A,B,C; C32-K600A,B,C; C32-LA-K624A,B,C) 4 1

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PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9 The main turbine bypass system shall be OPERABLE.

-APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

With the main turbine bypass system inoperable, restore the system to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or:

a.

Determine MCPR to be equal to or greater than the applicable MCPR limit without bypass within the next hour, or i

b.

Restore MCPR to within the applicable MCPR limit without bypass within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the f ollowing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.9 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

7 days by cycling each turbine bypass valve through at least one a.

complete cycle of full travel, and

]

b.

18 months by:

1.

Perf orming a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 300 milliseconds to a valve-position equivalent to 80% of the total main turbine bypass system rated flow.

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l BRUNSWICK - UNIT 2 3/4 7-52 Amendment No.

.. _ l

INSTRUMENTATION BASES 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system is utilized to terminate a transient initiated by a -feedwater controller failure resulting in a maximum feedwater demand..During this event, the resulting influx of excess feedwater flow results in an increase in core subcooling, which reduces the void fraction.~and thus induces an increase iu reactor power. The excess feedwater flow'aTso increases reactor water level, which eventually leads to a main turbine trip 4

and feedwater turbine trip as a result of the high water level. The main turbine stop valve position switches actuate a reactor scram trip and the main turbine bypass system (refer to Bases 3/4.7.9) which limits the neutron flux peak and fuel thermal transient such that -the Minimum Critical Power Ratio remains above the Safety Limit.

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4 BRUNSWICK - UNIT 2 B 3/4 3-5 Amendment No.

PLANT SYSTEMS BASES 3/4.7.9 MAIN TURBINE BYPASS SYSTEM The main turbine bypass system is required to be OPERABLE consisent with the assumptions of the feedwater controller failure analysis for FSAR Chapter 15.

Following closure of the main turbine stop valves initiated by the feedwater/ main turbine trip system actuation instrumentation, the main turbine bypass system actuates to the limit the pressure increase so that no excessive overpressurization of the_ nuclear system process barrier occurs.

(For Unit 1, which has a much smaller turbine bypass system capacity that Unit 2, the relief valves open briefly as steam line pressures reach the relief valve setpoints.) The turbine bypass valves subsequently close to control the pressure in the vessel during reactor shutdown.

J BRUNSWICK - UNIT 2 B 3/4 7-5 Amendment No.

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ML20080N166

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