Text

Revised Tech Specs Re RCIC Sys Actuation Instrumentation
	ML20072G561
Person / Time
Site:	Brunswick
Issue date:	06/23/1983
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20072G502	List: ML20072G499; ML20072G561;
References
	RTR-NUREG-0737, RTR-NUREG-737 GL-83-02, GL-83-2, NUDOCS 8306280544
	Download: ML20072G561 (21)
	v • d • e

.

ENCLOSURE 2 TO LAP-83-227 RESPONSE TO GENERIC LETTER NO. 83-02 (NUREG-0737 TECHNICAL SPECIFICATIONS)

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 i

4 I

I

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i E306280544 830623 PDR ADOCK 05000324 P

PDR

9 INDEX lit {1 TING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIRE!!ENTS s

SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION...............

3/43-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.....................

3/4 3-9 3/4.3.3 EtiERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRU!!ENTATION............

3/4 3-39 3/4.3.5 MONITORING INSTRUMENTATION S eismi c Monitoring In s t rume ntat ion......................

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

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

3/4 3-50 Sou r c e Rang e Mo ni t o r s...................................

3/4 3-53 C hlo rine De t e c t io n Sy s tem...............................

3/4 3-54 Chlo rine Int rus io n Mo ni t o rs.............................

3/4 3-55

' F ire De tection Ins t rumentation..........................

3/4 3-59 3/4.3.6 ATWS RECIRCULATION PUtiP TRIP SYSTE!! INSTRUMENTATION.....

3/4 3-62 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTE!! ACTUATION INSTRUMENTATION.........................................

3/4 3-66 3/4.4 REAC10R COOLANT SYSTEtt 3/4.4.1 RECIRCULATION SYSTEM R e c i r cu l e. t i o n Lo o p s.....................................

3/44-1 Je t Pump s...............................................

3/44-2 Idle Re circulation Loop St artup.........................

3/44-3 3/4.4.2 SAFETY / RELIEF VALVES....................................

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTE!! LEAKAGE Le akage De t e c t ion S y s t ems...............................

3/44-5 Op e ra t i o na l In aka g e.....................................

3/4 4-6 BRUNSWICK - UNIT 1 V

Amendment No.

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

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGlN...............................

B 3/4 1-1 3/4.1.2 RE ACTIVITY AN0?!ALIES..........................

B 3/41-1 3/4.1.3 CONTROL R0DS..................................

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

B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEt!.................

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

B 3/4 2-1 3/4.2.2 APRt! SETP01NTS................................

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

B 3/4 2-3 3/4.2.4 LINE AR HEAT GENERATION RATE...................

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

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

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

B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK I NST RUMENTATION..................... '.......

B 3/4 3-2 3/ 4. 3.5 MONITORING INSTRUMENTATION....................

B 3/4 3-2 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INST RU!!ENTAT!0 N............................

B 3/4 3-4 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTE!!

ACTUATION INST'tUMENTATION..................

B 3/4 3-4 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECI RCULATION SY STEM..........................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES..........................

B 3/4 4-1 3/4.4.3 RE ACTOR COOLANT SYSTEM LEAKAGE................

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

Amendnent No.

INSTRUMENTATION 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEf t ACTUATION INSTRU?!ENTATION LIMITING CONDITION FOR OPERATION 3.3.7 The reactor core isolation cooling (RCIC) system actuation instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with ther trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.7-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 113 psig.

ACTION:

a.

With a RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.7-2, 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 one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.7-1.

SURVEILLANCE REQUIREMENTS 4.3.7.1 Each RCIC rfstem actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the f requencies shown in Table 4.3.7.1-1.

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

l l

BRUNSWICK - UNIT 1 3/4 3-66 Amendment No.

co N'

TABLE 3.3.7-1 E

REACTOR CORE ISOLATION 00 LING SYSTEM ACTUATION INSTRUMENTATION D

!!INIMUM y

OPERABLECllANNEL{)

r FUNCTIONAL UNIT AND INSTRUMENT NUMBER PER TRIP SYSTEM ACTION g

a.

Reactor Vessel Water Level - Low, Level 2 2

50

( 8 21 -LT-NO31 A, B, C,D)

( B 21 -LTM-NO3 la-1, B-1, C-1,D-1) b.

Reactor Vessel Water Level - liigh 2(b) 51

( B 21-LT-N017 A-2, C-2)

( B 21-LTM-N017A-2, C-2)

Condensate Storage Tank Water Level - Low (

2("

52 u

c.

];

( E51-LSL-4463,E51-LSL-4464)

Y 0

(a)

A channel may be placed in an inoperble status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placind the trip systen in the tripped condition provided at least one other OPERABLE channel in the same t rip system is monitoring that paramater.

(b) One trip system with two-out-of-two logic.

(c)

One t rip system with one-out-of-two logic.

(d)

Provides signal to RCIC pump suction valves only.

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TABLE 3.3.7-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTE!!

ACTUATION INSTRTIENTATION ACTION 50 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system place the inoperable channel (s) and/or that trip system in the tripped condition within one hour or declare the RCIC system inoperable.

b.

For both trip systems, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERABLE channels less than required by the Mininum OPERABLE channels per Trip System requirement, declare -

the RCIC system inoperable.

I ACTION 52 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within one hour or declare the RCIC system inoperable.

4 5

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

to h

TABLE 3.3.7-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRIMENTATION SETPOINTS n

i ALLOWABLE FUNCTIONAL UNIT AND INSTRUMENT NUMBER RIP SETPOINT VALUE 4

Reactor Vessel Water Level - Low, Level 2

> +112 inches *

> +112 inches

g a.

( B 21-LT:1-NO31 A-1, B-1, C-1, D-1 )

b.

Reactor Vessel Water Level - liigh

< +208 inches *

( B 21-LTM-N017A-2,C-2)

~

c.

Condensate Storage Tank Level - Low

> 23 feet 0 inches

> 23 feet 0 inches (E51-LSL-4463, E51-LSL-4464) t'>

Vessel, water levels refer to REFERENCE LEVEL ZERO.

n 8'

an

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a

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=

l TABLE 4.3.7.1-1 a

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS s

b CHANNEL c:

CllANNEL FUNCTIONAL CHANNEL N

FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK TEST CALIBRATION H

a.

Reactor Vessel Water Level -

Low, Level 2

)

b)

( B 21-LT-NO31 A, B,C,D)

NA NA R

( B 21-LTri-NO31 A-1,B-1,C-1, D-1)

D M

M o.

Reactor Vessel Water Level - liigh

( B 21-L T-N017 A-2, C-2)

NA(a)

NA R

( B 21-LTM-N017 A-2,C-2)

D M

M v2 30 c.

Condensate Storage Tank v2 Level - Low b

(ES I-LSL-4463, E51-LSL-4464)

NA M

Q 1

o (a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.

(b) Transnitters are exempted from the monthly channel calibration.

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PLANT SYSTEMS 3/4.7.4 REACTOR CORE ISOLATION COOLINC SYSTE!!

LIMITING CONDITION FOR OPERATION 3.7.4 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel.

APELICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 113 psig.

ACTION:

With the RCIC system inoperable, operation may continue and the provisions of Specifications 3.0.4 are not applicable provided the HPCI system is OPERABLE; restore the RCIC system to OPERABLE status within 31 days or be in at least ROT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam done pressure to less than or equal to 113 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REOUIREMENTS 4.7.4 _ The RCIC system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

-Verifying by venting at the highpoint vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

2.

Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

At least once per 92 days by verifying that the RCIC pump develops a flow of greater than or equal to 400 gpm in the test ficw path with a system head corresponding to reactor vessel operating pressure when steam is being supplied to the turbine at 1000 + 20, - 80 psig.*

The provisions of Specification'4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter reactor steam pressure is adequate to perform the test.

BRUNSWICK - UNIT 1 3/47-7 Amendnent No.

PLANT SYSTE?tS SURVEILLANCE REOUIRE!!ENTS (Continued) 4.,

c.

At least once per 18 months by:

1.

Performing a system fu tetional test which includes simulated automatic actuation and restart + and verifying that each l

I automatic valve in the flow path actuates to its corract position, but may exclude actual injection of coolant into the reactor vessel.

2.

Verifying that the system will develop a flow of greater than or equal to 400 gpm in the test flow path when steam is suppled to the turbine at a pressure of 150 + 15 psig.*

l 3.

7erifying that the suction for the RCIC system is automatically transferred f rom the condensate storage tank to the suppression pool on a condensate storage tank water level-low signal.

The provisions of Specifications 4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter reactor steam pressure is adequate to perform the tests.

+ Automatic restart on a low water level signal which is subsequent to a high water level trip.

i BRUNSWICK - UNIT 1 3/47-8 kr endment No.

I

INSTRUMENTATION BASES MONITORING INSTRU?iENTATION (Continued) 3/ 4. 3. 5. 6 CHLORINE INTRUSION tiONITORS The chloride intrusion monitors provide adequate warning of any leakage in the condenser or hotwell so that actions can be taken to mitigate the

. consequences of such intrusion in the reactor coolant system.

With only a minimum nu.ber of instruments available, increased sampling frequency provides adequate information for the same purpose.

3 / 4. 3. 5.7 FIRE DETECTION INSTRU!!ENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrunentation is inoperable, increasing the frequency of fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTE!! INSTRU lENTATION The ATWS recirculation pump trip system has been added at the suggestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within General Electric Company Topical Repo'the envelope of study events given in rt NEDO-10349, dated liarch,19 71.

3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEtt ACTUATION INSTRTRIENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core

. cooling equipment.

r BRUNSNICK - UNIT I B 3/4 3-4 Anendment No.

INDEX LIf tITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTE!! INSTRUMENTATION................ 3/43-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTAT10M......................

3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.. 3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.............

3/4 3-39 3/4.3.3 MONITORING INSTRUMENTATION Seismic ?!o nitoring In s trume ntation....................... 3/4 3-44 Remote Shutdown ifonitoring Ins trumentation...............

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

3/4 3-50 So u r c e Ra n g e Mo n i t o r s....................................

3/4 3-53 Chlo rine De t e c t io n Sys t em................................ 3/4 3-54 Chloride Int rus io n ifonito rs..............................

3/4 3-55 F ire De tection In s t rume ntation........................... 3/4 3-59 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUliENTATION ATWS Recirculation Pump Trip System Instrumentation......

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

3/4 3-66 3/4.3.7 REACTOR ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................................

3/4 3-72 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTE!!

3/44-1 Re c i r c ul a t i o n Lo o p s......................................

3/44-2 Jet Pumps................................................

Id l e Re c i rcula t io n Lo o p S t a r t-u p......................... 3/44-3 3/4.4.2 S AF ET Y / RELIEF VALV E S.....................................

3/44-4 BRUNSWICK - UNIT 2 V

Anendment No.

t

INDEX BASES SECTION PAGE 3/4.0 AP P L I C AB I L I T Y..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN....................................

B 3/4 1-1 3/4.1.2 REACT IV ITY AN0tiALIE S............................... B 3/41-1 3/4.1.3 CONTROL R0DS.......................................

B 3/4 1-1 3/4.1.4 CONTROL ROD PROGRA!! CONTR0LS....................... B 3/41-3 3/4.1.5 STANDBY-LIQUID CONTROL SYSTE51...................... B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AV ERAGE PLANAR LINEAR HEAT GENERATION RATE......... B 3/4 2-1 3/4.2.2 A P RM S ET P01NT S..................................... B 3/4 2-3 3/4.2.3 ti1NIi1UI! CRITICAL POWER RAT 10....................... B 3/4 2-3 3/4.2.4 L I N E AR H E AT G ENERAT IO N RATE........................

B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.......... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATIO N INSTRUMENTATION................

B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEtt ACTUATION IN ST RU!iENT ATION............... -................. B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION....... B 3/4 3-2 3/4.3.5 MONITORING INSTRU'IENTATION.........................

B 3/4 3-2 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION..................................

B 3/4 3-4 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTE!!

ACTUATION INSTRU:1ENTATION........................

B 3/4 3-5 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RE C I RCUL AT ION S Y STEf t............................... B 3/4 4-1 3/4.4.2 S AF ETY /RE LIEF V ALV ES...............................

B 3/4 4-1 3/4.4.3 RE ACTOR COOLANT SYSTE!! LE AKAGE..................... B 3/4 4-1 BRUNSWICK - UNIT 2 X

Amendment "o.

1 INSTRUMENTATION 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7 The reactor core isolation cooling (RCIC) system actuation

' instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with ther trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.7-2.

^

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam done pressure greater than 113 psig.

ACTION:

a.

With a RCIC system actuation im trumentation channel trip setpoint less conservative than the value shown in the Allowable Values column I

of Table 3.3.7-2, 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 one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.7-1.

SURVEILLANCE REOUIREMENTS

~

4.3.7.1 Each RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3. 7.1-1.

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

I i

r BRUNSWICK 1 UNIT 2-3/4 3-72 Amendment No.

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g-d TABLE 3.3.7-1 v1 s:

REACTOR CORE ISOLATION COOLING SYNTEM ACTUATION INSTRUMENTATION 9

1 e'

c.

Er

/

MINIMUM i, y

)*'

PER TRIP SYSTEM ACTION DPERABLE CittJINEL{"

i

'ra 4,'[UNCTIONAL UNIT AND INSTRUMENT NUMBER f,

i Reactor Vessel Water Level - Low, Level 2, 2

50 a.

)~-

( B 21-LT-NO31 A, B,C,D)

/

^

/'

( B 21-L'IM-N O31 A-1, B-1, C-1,D-1 )

s a,.

2(b) 51 b. '-

Reactor Vessel Water Level - liigh

( B 21 -LT-N017 A-2,C-2)

/ fS21-LTM-N0174-2, C-2) 2(c) 52 f

Condensate Stnrage Tank Water Level - Low (d) '

w c.

E51 -),SL-4464 )

~

5 u,s

/.

(E51-LSL-4463;I '

/

7 O

'/

- 'f.

'f r

=,

-(a). A cha'ni 1 may be placed in an inoperble status, for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for require'd surveillance without

',plac[3d the,tets system in the tripped condition provided at'least one other OPERABLE channel in the

_ -sa.ne t rip.sy, stem is monitoring that parameter.

( b) (Onetripsisteq.withtwo-out-of-twologic.

(c)

One t rip System 'ylth one-out-of-two logic.

Provides tilgri3 [tv i(CIC pamp suction.v,alhes only' (d) 1

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s-4 p.

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TABLE 3.3.7-l (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION j

1

' ACTION 50 -

With the number of GPERABLE channels' leis than required by the y

!!ir.i.wn OPERABLE Channels per Trip Syste's requirement: l

~

r.

a.'

For one trip system, place the inoperable channel (r? and/or

' that; trip system in the tripped condition within one hour 'o'r decl'are the RCIC system inoperable.

l b.

For, both trip systems, declare the RCIC system inoperable.

ACTION Sie With the number of OPERABLE chaanels less than required by the 2

4

!!inimum OPERABLE channels per Trip System requirement, declare the RCIC system inoperable.

. s*

j ACTION 524.

+

With the number of OPERABLE channels less than required by the Mininum OPERABLE Chadnels per Trip System requirement, place at least onc. inoperable ihhnnel in the tripped condition within one hour or declare the PCIC system inoperable.

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' l BRUNSWICK - UNIT 2 3/4 3-74 Amendment No.'

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REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRiffENTATION SETPOINTS ~%.

'[ALLOWkBLE

(

,., ' O FUNCTIONAL UNIT AND INSTRUMENT-NUMBER TRIP SETPOINT

% ^/ALUE m

H to a.

Reactor Vessel Water Level - Low, Level 2

> +112 inches * -

-; N112 iinehes*

( B 21 -LTM-NO31 A-1, B-1,C-1, D-1 )

b.

E2 actor Vessel Water Level - liigh

< +208 inches *

'x

< ;+ 208 inches *

( B 21-LTM-N0173-2,C-2) s 4

c.

Condensate Storage Tank Level - Low

~

)_ 23 feet 0 inches

> 23 feet 0 ing as (E51-L:1L-4463, E51-LSL-4464) b e

~

y

)

5 u

Vessel water levels refer to REFERENCE LEVEL ZERO.

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y w

h f

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a to l3 ft M

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TABLE 4.3.7.1-1 E!

5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS W

CHANNEL E

CHANNEL FUNCTIONAL CHANNEL U

c'UNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK TEST CALIBRATION to a.

Reactor Vessel Water Level -

Low, Level 2

( 821-LT-NO31A,B,C,D)

NA NA R

( B 21-LTM-NO31 A-1, B-1,C-1,D-1)

D M

M b.

Reactor Vessel Water Level - High R(

( B 21-LT-N017A-2, C-2)

NA(a)

NA

( B 21-LTM-N017A-2,C-2).

D M

M c.

Condensate Storage Tank w

Level - Low L

(E51-LSL-4463, E51-LSL-4464)

NA M

Q m

i I

(a) The transmitter channel check is satisfied by the trip unit channel check. ' A separate transmitter check is not required.

l (b) Transmitters are exempted f rom the monthly channel calibration.

N e

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PLANT SYSTEMS 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of automatically taking suction f rom the suppression pool and transferring the water to the reactor pressure vessel.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 113 psig.

ACTION:

With the RCIC system inoperable, operation may continue and the provisions of Specifications 3.0.4 are not applicable provided the HPCI system is OPERABLE; restore the RCIC system to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to less than or equal to 113 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.4 The RCIC system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying by venting at the highpoint vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

2.

Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

At least once per 92 days by verifying that the RCIC pump develops a flow of greater than or equal to 400 gpm in the teat flow path with a system head corresponding to reactor vessel operating prescure when steam is being supplied to the turbine at 1000 + 20, - 80 psig.*

The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter reactor steam pressure is adequate to perform the test.

BRUNSWICs - UNIT 2 3/47-7 Amendaent No.

f

-PLANT SYSTE!iS SURVEILLANCE REOUIRE!!ENTS (Continued) c.

At least once per 18 months by:

s 1.

Performing a system functional test which includes simulated 4

automatic actuation and restart + and verifying that each l

automatic valve in the flow path actuates to its correct position, but may exclude actual injection of coolant into the i

reactor vessel.

2.

Verifying that the system will develop a flow of greater than or equal to 400 gpm in the test flow path when steam is suppled to the turbine at a pressure of 150 + 15 psig.*

l 3.

Verifying that the suction for the RCIC system is automatically transferred f rom the condensate storage tank to the suppression pool on a condensate storage tank water level-low signal.

I Ine provisions of Specifications 4.0.4 are not applicable provided the surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter reactor steam pressure is adequate to perform the tests.

+ Automatic restart on a low water level signal which is subsequent to a high water level trip.

1 i

T f

4 -

BRUNSWICK - UNIT 2 3/47-8 Amendment No.

l

INSTRUMENTATION BASES RECIRCULATIOP PUMP TRIP ACTUATION INSTRUMENTATION (Continued) feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

A fast closure sensor f rom each of two turbine control valves provides input to one EOC-RPT system; a fast closure sensor fron each of the other two turbine control valves provides input to the second E00-RPT system.

Similarly, a position switch for each of two turbine stop valves provides input to one E00-RPT system; a position switch for each of the other two turbine stop valves provides input to the other EOC-RPT systenL For each

- E00-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for closure of the turbine stop valves.

The operation of either logic will actuate the E00-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled.

The manual bypasses and the automatic operating bypass at < 30% of RATED THERI!AL POWER are annunciated in the control room.

3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation f rom its primary heat sink and the loas of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

BRUNSUICK - UNIT 2 13/43-3 haendment No.

ML20072G561

Text

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