Text

Proposed Tech Specs Re Increased Instrument Surveillance Test Intervals & Allowable out-of-svc Times
	ML20081H548
Person / Time
Site:	Brunswick
Issue date:	03/22/1995
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20081H541	List: BSEP-95-0112, Forwards Supplemental Info Re 931028 Request for License Amends to Increase Instrument Surveillance Test Intervals & Allowable out-of-svc Times Addressed in TS 3/4.3,as Result of Discussions W/Nrc During 950208 Meeting & 950216 Telcon; ML20081H548;
References
	NUDOCS 9503240282
	Download: ML20081H548 (90)
	v • d • e

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ENCLOSURE 2

. BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1' AND 2' NRC DOCKETS 50 325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 L REQUEST FOR LICENSE AMENDMENTS '

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INCREASED INSTRUMENT SURVEILLANCE TEST INTERVALS AND ALLOWABLE OUT-OF-SERVICE TIMES TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 l

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9503240282 950322

PDR ADOCK 05000324 P PDR

i 3/4.3' INSTRUMENTAT10N !

j 3/4 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

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LIMITING CONDITION FOR OPERATION !

3.3.1 As a. minimum, the reactor protection system instrumentation channels I shown in-Table 3.3.1 shall be OPERABLE. Set points and interlocks are given. l in Table 2.2.1-1. t APPLICABILITY: As shown in Table 3.3.1-1.

ACTION: !

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a. With one channel less than the Minimum Number of OPERABLE Channels per :l Trip System required by Table 3.3.1-1 in one or more Functional Units. :

place the inoperable channel and/or that trip system .in the tripped

condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With two or more channels less than the Minimum Number of' OPERABLE i Channels per Trip System required by Table 3.3.1-1 in one or more !

Functional Units: i l

) 1. Within one hour, verify sufficient channels remain OPERABLE or in !

the tripped condition

to maintain trip capability in the !

Functional Unit, and

2. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the inoperable channel (s) in one trip system and/or that trip system ** in the tripped condition

and i

3. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip I l

system to an OPERABLE status or-place them in the tripped condition *.

1 Otherwise, take the ACTION required by Table 3.3.1-1 for the Functional-Unit. .-

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c. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5. f l

An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall-be taken.

This- ACTION a) plies to that tri) system with the most inoperable-channels: if Joth trip systems lave the same number of inoperable channels, the ACTION can be applied to either trip system. !

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

3/4.3 INSTRUMENTATION

.3/4.3:1 ' REACTOR PROTECTION SYSTEM INSTRUMENTATION-

.' SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor. 3rotection system instrumentation channel shall be demonstrated OPERABLE Jy the performance of the. CHANNEL' CHECK.-CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown'in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of.

all channels shall be performed at least once per 18' months and shall include calibration of lme delay relays and timers necessary for proper. functioning of the trip se tem.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME .of. each reactor trip-function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic' train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months.where N is the' total number of redundant channels in a specific reactor trip.

function.

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1 Neutron detectors are exempt from response time testing.

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

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-;q TABLE 3.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION E

A

- APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION

1. Intermediate Range Monitors:

a. Neutron Flux - High 2. 5* 3 1

3. 4 2 2

b. Inoperative 2. 5 3 1 y 3. 4 2 2

2. Average Power Range Monitor

{

a. Neutron Flux - High 15% 2. 5* 2 3

b. Flow Biased Simulated Thermal 1 2 4 Power - High

c. Fixed Neutron Flux - High 120% 1 2 4

d. Inoperative 1. 2. 5 2 5

e. Downscale 1 2 4

f. LPRM 1. 2. 5 (c) NA

3. Reactor Vessel Steam Dome Pressure.- High 1. 2'* 2 6

$s 4. Reactor Vessel Water Level - Low. Level 1 1. 2 2 6

[ 5. Main Steam Isolation Valve - Closure 1 4 4 O

6. Main Steam Line Radiation - High 1. 2'* 2 7.

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p; TABLE 3.3.1-1 (Continued) x REACTOR PROTECTION SYSTEM INSTRUMENTATION E

[ APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION

7. Drywell Pressure - High 1. 2 2 6

8. Scram Discharge Volume Water Level - High 1. 2. 5'" 2 5

9. Turbine Stop Valve - Closure l 4 8 R

10. Turbine Control Valve Fast Closure.

Control Oil Pressure - Low 1( 2 8

" 1,2.3.4.5

11. Reactor Mode Switch in Shutdown Position 1 9

12. Manual Scram 1.2.3.4,5 1 10

13. Automatic Scram Contactors 1,2.3.4.5 2 10 I y s.

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_ . _ _ _ _ . _ _ . m.. - -_ __.._m.... _ . . - . _ ..___ .m .c-._-__.,m_. _ . _ _ . _ . . _ _ . - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ - _ _ .- ...-s-- m -.-.w--=w.-.,, - - - - * ---. , -- - ~+%.- ..-- vr..-

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION i ACTION 10 - In OPERATIONAL CONDITION 1 or 2. be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . !

In OPERATIONAL CONDITION 3 or 4. lock the reactor mode switch in !

the Shutdown position within one hour. l In OPERATIONAL CONDITION 5. suspend all o)erations involving CORE ALTERATIONS or positive reactivity c1anges and fully insert '

all insertable control rods within one hour.

NOTES l (a) When a channel is placed in an inoperable status solely for performance !

of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability. ,

(b) The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin demonstrations.

(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per :

level or less than eleven LPRM inputs to an APRM channel. ;

(d) These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

(e) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required. ,

(f) With any control rod withdrawn. Not applicable to control' rods removed per Specification 3.9.10.1 or 3.9.10.2.

/ I (g) These functions are bypassed when THERMAL POWER is less than 30% of i RATED THERMAL POWER.

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l Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

BRUNSWICK - UNIT 1 3/4 3-5 Amendment No. j

p; TABLE 4.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS E

q CHANNEL OPERATIONAL

,_, CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH ,.

FUNCTIONAL UNIT CHECK TEST CALIBRATION"' SURVEILLANCE RE0VIRED

1. Intermediate Range Monitors:

a. Neutron Flux - High D S/U'6"*' . W(d) R 2 D W R 3. 4. 5

b. Inoperative NA W(* NA 2.3.4.5 y 2. Average Power Range Monitor:

Y

a. Neutron Flux - High 15% S S/US ""'. W(* Q 2 S W("' O 5

b. Flow-Biased Simulated Thermal S S/US '. Q W""" . Q 1 Power - High S

c. Fixed Neutron Flux - High. 120% S- S/U ). Q W") . Q 1 i

d. Inoperative NA Q'"""' NA 1. 2. 5 l

e. Downscale NA Q NA 1 l g -

s.

a f. LPRM D NA (g) 1. 2. 5 e -

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$ 3. Reactor Vessel Steam Dome Pressure - High z Transmitter: NA(" NA R"' 1. 2 P Trip Logic: D Q Q 1. 2 1

4. Reactor Vessel Water Level - Low. Level 1 Transmitter: NA(" NA R"' 1. 2 Trip Logic: D Q Q 1, 2 l m.u_.-m________.-+____---u_.n__m.Au____m____ _ - - _ - - ___-m.___ m m_ a v a -*f w = w wwwt- p --w usr

- w w= rim v'e -

s-u'-e W' tr ee v-ef -w '-rum- i- - aw----w '- se-w-'a-

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n BBLE 4.3.1-1 (Continuedl REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS C

h CHANNEL OPERATIONAL

- CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (*) SURVEILLANCE REQUIRED

5. Main Steam Line Isolation Valve - Closure NA Q R* 1 1

6. Main Steam Line Radiation - High S Q") R 1. 2 1

7. Drywell Pressure - High Transmitter: NA(" NA R"' 1. 2 Trip Logic: D 0 0 1, 2 1

8. Scram Discharge Volume Water Level - High NA Q R 1. 2. 5 b 9. Turbine Stop Valve - Closure NA Q R* l' ) I

10. Turbine Control Valve Fast Closure.

Control Oil Pressure - Low NA 0 R l'") I

11. Reactor Mode Switch in Shutdown Position NA R NA 1,2.3.4,5

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12. Manual Scram NA Q NA 1.2.3.4.5

13. Automatic Scram Contactors s, NA W NA 1,2.3.4.5I e

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. . - _ _ _ - , _ _ _ _ . . . _ _ . . _ -_.-.m____.._ .__ __ _ _ _ - _ . _ _ __.__._u- ___.._a ,_m____.__ __ m . -....-_-_.__ _ _ . ___ ,em,e,_ -

__.___=___m_-_.__---.._____._._.__m_._______.______m.__

c TABLE 4.3.1-1 (Continuedr REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILL NCE REQUIREMENTS' (a)- Neutron detectors may be excluded from CHANNEL CALI'BRATION.

(b) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup. if not performed within the previous 7 days.

(c) The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup. if not performed within the previous 7 days.

(d) . When changing from OPERATIONAL' CONDITION 1 to OPERATIONAL' CONDITION 2.

perform the required surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'after entering-OPERATIONAL CONDITION 2. if. not performed within the previous 7 days.

! (e) This calibration shall consist of the adjustment of the'APRM readout to

! conform to the power values' calculated by a heat balance during l OPERATIONAL CONDITION 1 when THERMAL POWER is greater than'or equal to l

25% of RATED THERMAL POWER.

(f) This calibration shall consist of _the adjustment of the-APPJi flow-biased-l simulated thermal power channel to conform to a calibrated flow signal. 1 (g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.

l (h) This calibration shall consist of a physical-inspection and actuation of these position switches.

(i) Instrument alignment using a standard current' source.

(j) Calibration using a standard radiation source. .

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

(1) Transmitters are exempted from the quarterly channel calibration. 1 (m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the-reactor to criticality.

(n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is

,- permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensionea.

(o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.

BRUNSWICK - UNIT 1 3/4 3-9 ,

Amendment No.

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l l l INSTRUMENTATION 3/4 3.2 ISOLATION ACTUATION INSTRUMENTATION I LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 4 i

shall be OPERABLE with their trip setpoints set consistent with the values shown i in the Trip Setpoint column of Table 3.3.2-2.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

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a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2. declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. For any isolation actuation Trip Function with less than the Minimum i Number of OPERABLE Channels per Trip System required by Table 3.3.2-1:

1. Within one hour, verify sufficient channels remain OPERABLE or are placed in the tripped condition

to maintain automatic isolation actuation capability for the Trip Function, and l 2. Place the inoperable channel (s) in the tripped condition

within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation Otherwise take the ACTION required by Table 3.3.2-1.

c. Deleted. I i

d. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS I

' 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and Et the frequencies shown in Table 4.3.2-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all :

channels shall be performed at least once per 18 months and shall include !

calibration of time delay relays and timers necessary for proper functioning of !

the trip system.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.2-1 for the Trip Function shall be taken.

I BRUNSWICK - UNIT 1 3/4 3-10 Amendment No.

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INSTRUMENTATION SURVEILLANCE; REQUIREMENTS (Continued) ;

4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation-fundtionshall be demonstrated to be within its limit at least once per 18 months. Each test i shall include at least one logic train such that both logic trains are tested at I :

least once per'36 months and one channel per function such that all' channels are' i tested at least once every N times'18 months where N is the total number of !

redundant channels in a-specific isolation function.

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1 Radiation monitors are exempt from response tine f.esting. f i

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i BRUNSWICK - UNIT 1 3/4 3-11 Amendment No.

' TABLE 3.3.2-1 (ContinuedF ISOLATION ACTUATION INSTRUMENTATION' NOTES ;

When handling irradiated fuel in the secondary containment.

(a) See Specification 3.6.3.'1.- Table' 3.6.3-1 for-valves in each valve group. !

(b) When a channel-is' placed in an inoperable status solely. for performance'of = i required Surveillances, entry into associated ACTIONS may be delayed as follows.

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(1) For u) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Trip Functions with a design that provides only a one clannel per-trip. system.

q (2) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions, ;

maintains isolation actuation capability. provided the Trip Function- i (c) Deleted. 1-(d) A channel is OPERABLE if 2' of 4 instruments'in the channel are OPERABLE.

f (e) With. reactor steam pressure a 500 psig.

'(f) Closes only RWCU outlet isolation valve.

(g) Alarm only. ,

1 (h) Isolates containment' purge'and vent valves.

(1) Does not isolate E11-F015A,B.

(j) Does not isolate B32-F019'or B32-F020.

(k) Valve isolation depends upon' low steam supply pressure coincident with high drywell pressure.-

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(1) Secondary containment isolation dampers as' listed in Table 3.6.5.2 .

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.i BRUNSWICK - UNIT 1 3/4 3-17a Amendment No.'

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p; TABLE 4.3.2-1 n

. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

H CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

~ 0 CHECK TEST CALIBRATION SURVEILLANCE REQUIRED TRIP FUNCTl0N

1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level -

1. Low. Level 1 Transmitter: NA NA R(b) 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 1

2. Low. Level 3 Transmitter: NA NA R(b) 1. 2. 3 w Trip Logic: D Q Q 1. 2._3 i s

b. Drywell Pressure - High Y Transmitter: NA(*) NA R(6) 1. 2. 3

$ Trip Logic: D Q Q 1. 2. 3 l

c. Main Steam Line

1. Radiation - High D Q' R* 1. 2. 3 l

2. Pressure - Low Transmitter: NA(') NA R(b) 1 Trip L ic: D Q Q 1 1

3. Flow - Hi h Transmi ter: NA(') NA R(b) 1 L> Trip Logic: D Q Q 1 I i6 d. Main Steam Line Tunnel .'

a Temperature - Hi Condenser Vacuum gh NA 0 R 1, 2. 3 i B e. Low a Transmitter: NA(') NA R(b) 1. - 2 .

z Trip Logic: D Q Q 1. 2(') I o

f. Turbine Building Area Temperature - High NA- 0 R 1, 2. 3 1

g. Main Stack Radiation - High NA Q R -1. 2. 3

h. Reactor Building Exhaust Radiation - High D Q R 1. 2. 3 1

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n TABLE 4.3.2-1 (Continued) i

. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL OPERATIONAL M CHANNEL FilNCTIONAL CHANNEL CONDITIONS IN WHICH

- TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED ,

2. SECONDARY CONTAINMENT ISOLATION

a. .Reacter Building Exhaust Radiation - High D Q R 1.2.3.5 and(" I i

b. Drvwell Pressure - High :

Transmitter: NA NA R(b' '1. 2. 3 '

Trip Logic: D Q Q 1. 2. 3 l l t' c. Reactor Vessel Water Level - !

Low. Level 2 '

ca . Transmitter: NA(*) NA R(b) 1. 2. 3 g Trip Logic: D 0 0 1. 2. 3 1

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High NA SA R 1. 2. 3 b .- Area Temperature.- High NA SA R 1. 2. 3

c. Area Ventilation A Temperature - High NA- SA 'R. 1. 2. 3

d. SLCS Initiation NA R- NA 1. 2 k

s

e. Reactor Vessel Water Level Low. Level 2 Transmitter:

NA NA R(b' LL3 .

f Trip Logic: D Q Q. 1. 2. 3 l

f. A Flow - High - Time Delay NA SA R 1. 2. 3 ,

g. Piping Outside RWCU ku s Area NA SA- R 1. 2. 3 i Temperature - High i

2

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n TABLE 4.3.2-1 (Continued)

. ISOLATION ACTUATION INSTRUMENTATION SUP"EILLANCE REOUIREMENTS E CHANNEL OPERATIONAL M CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

~ TRIP FUNCTION CliECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION

a. High Pressure Coolant Injection System Isolation

1. HPCI Steam Line Flow - High Transmitter: NA(*) NA R(" 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 l

2. HPCI Steam Line High Flow M Time Delay Relay NA R R 1. 2. 3 a

y 3. HPCI Steam Supply Pressure - Low NA Q R 1. 2. 3 i E 4. HPCI Steam Line Tunnel Temperature - High NA SA R 1. 2. 3

5. Bus Power Monitor NA R NA 1. 2. 3

6. HPCI Turbine Exhaust Diaphragm Pressure - High NA Q Q 1. 2. 3 l k

g

7. HPCI Steam Line Ambient Temperature - High NA- SA R 1. 2. 3

8. HPCI Steam Line Area A Temperature - High ,

NA SA R l'. 2. 3 z .

P 9. HPCI Equipment Area Temperature - High NA SA R 1. 2. 3

10. Drywell Pressure - High Transmitter: NA) NA R(" 1, 2. 3 Trip Logic: D 0 0 1. 2. 3 l

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS en E CHANNEL OPERATIONAL Bi CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

E b. Reactor Core Isolation Cooling System Isolation

~ 1. RCIC Steam Line Flow - High Transmitter: NA NA R* 1. 2, 3 Trip Logic: D Q Q 1, 2. 3 1

2. RCIC Steam Line Flow - High Time Delay Relay NA R R 1. 2. 3

3. RCIC Steam Supply Pressure - Low NA 0 0 1. 2. 3 1

4. RCIC Steam Line Tunnel w Temperature High NA SA R 1. 2. 3 E

a 5. Bus Power Monitor NA R NA 1. 2. 3 bl 6. RCIC Turbine Exhaust Diaphragm Pressure - High NA 0 R 1. 2. 3 l

7. RCIC Steam Line Ambient Temperature - High NA SA R 1. 2. 3

8. RCIC Steam Line Area A Temperature - High NA SA R 1. 2. 3 g 9. RCIC Equipment Room Ambient g Temperature - High + . NA SA R 1. 2, 3

10. RCIC Equipment Room ,

& A Temperature - High NA SA R 1. 2, 3

11. RCIC Steam Line Tunnel Temperature - High Time Delay Relay NA SA R 1. 2. 3

12. Drywell Pressure - High Transmitter: NA NA R(b' 1, 2. 3 Trip Logic: D Q Q 1. 2. 3 l

-. ___ _ _ . _ _ _ _ . _ _ - . _ _ _ . _ . _ . _ _ - _ _ _ _ _ . _ . _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . . _ . _ _ _ _ . - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._______m -

_a ___ .__.____.______m___m - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

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TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS -

C 5

CHANNEL OPERATIONAL CHANNEL. FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED ,

5. SHUTDOWN COOLING SYSTEM ISOLATION

, a. Reactor Vessel Water Level - 1 Low. Level.1 N Transmitter: NA NA R* 1, 2. 3 Trip Logic: D- Q -Q 1. 2. 3 -l

b. Reactor Steam Dome. Pressure - High NA Q R- . 1.~2. 3 l w

23 l

l

! l i a -,.

R

= ,

et .

s i

4

_. e .. . _ . +_~..,-m.4.. _n--..-, , , , ,m w. _. . + . - . , -J4,,-,,,,--.,mw..--. .~,.+,...-..%... .....,v-.-.-+w, ..,.%,-e,.,--sw..r...e- ..%..~,..u .- .-.>......w,.,.e.. . . . . ,

TABLE 4.3.2-1 (Continued)

i ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS .

~ -

NOTES 1

(a) The transmitter channel check is satisfied by the trip unit channel ,

check. A separate transmitter gheck is not required.

(b) Transmitters are exempted from the quarterly channel calibration. l (c) Deleted. 1 (d) Testing shall verify that the mechanical vacuum pump trips and the mechanical vacuum pump line valve closes.

(e) When reactor steam pressure = 500 psig.

(f) When handling irradiated fuel in the secondary containment. :

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BRUNSWICK - UNIT 1 3/4 3-32 Amendment No.

f INSTRUMENTATTON 3/4 3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emerge Core Coolin channels shown in ble 3.3.3-1 ska bekstem OPERABLE(ECCS) with actuation instrumentation their trip setpoints l ,

set consistent with the values shown in the Trip Setpoint column of Table i 3.3.3-2.

APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

a. With an ECCS actuation instrumentation channel trip setpoint less i conservative than the value shown in the Allowable Values column of Table 3.3.3-2. declare the channel inoperable until the channel is '

restored to OPERABLE status with its tri consistent with the Trip Setpoint value.p setpoint adjusted- ;

b. With one or more ECCS actuation instrumentation channels inoperable. ,

take the ACTION required by Table 3.3.3-1.

c. The provisions of S)ecification 3.0.3 are not applicable in !

OPERATIONAL CONDITION 5. l SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and ,

CHANNEL FUNCTIONAL TEST operations durin !

the frequencies shown in Table 4.3.3-1. g the OPERATIONAL CONDITIONS and at 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning i of the trip system.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS function shall be demonstrated tobewithinthelimitatleastonceper18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all chanhels are tested I at least once every N times 18 months, where N is the total number of l redundant channels in a specific ECCS function. j i

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BRUNSWICK - UNIT 1 3/4 3-33 Amendment No.

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C p; TABLE 3.3.3-1 x

.-- EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 5H MINIMUM APPLICABLE l

~ OPERABLECHANNElg r' TRIP FUNCTION PER TRIP FUNCTION CONDITIONS , OPERATIONAL ACTION l

1. CORE SPRAY SYSTEM-

a. Reactor Vessel Water Level - Low. Level 3 4 1.2.3.4.5 30 I

b. Reactor Steam Dome Pressure - Low (Injection Permissive) 4 1,2.3.4.5 30 I

c. Drywell Pressure - High 4 1. 2. 3 30 l 5 d. Time Delay Relcy 1/ pump 1.2.3.4.5 31 _ l

e. Bus Power Monitor'd' 1/ bus 1.-2. 3. 4. 5 32

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Drywell Pressure - High 4 1,2.3 30 i

b. Reactor Vessel Water Level - Low Level 3 4 1. 2. 3. 4*'. S'b' 30 l

c. - Reactor Vessel Shroud Level (Drywell Spray Permissive) 1/ valve 1. 2. 3. 4(b) S'b' 31 .I

} .

E d. Reactor Steam Dome Pressure - Low (Injection Permissive) 8 1. RHR Pump Start and LPCI Injection Valve Actuation -4 1. 2, 3. 4'b', 5*) 30 l A 2. Recirculation Loop Pump Discharge Valve Actuation -4 1. 2. 3. 4*'. 5*' 30 l

.E e. RHR Pump Start - Time Delay Relay 1/ pump 1. 2. 3. 4*'. 5*' 31 i

f. Bus Power Monitor'd' 1/ bus 1. 2. 3. 4*' . S'b' 32 i~

-_.m__2- _ .- _ _ _ _ . - ___m_-*--.-_.____m-m_-m___ - _ _ _ _ _ _._-%&_%_e-+-sw- , - + = m e-=% -si_._emw- w mm+-wd-es -r' arm--w-e- a _ -me --%e---_r--- m .m ei ._ _.mm.-em=.e- i-----='.+-u+w-w..-=.3- -m._ww+- -w w--

m n

TABLE 3.3.3-1 (Continued) i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 5

H MINIMUM APPLICABLE i OPERABLE CHANNELS OPERATIONAL

~ TRIP FUNCTION PER TRIP FUNCTION',' CONDITIONS ACTION I

3. HIGH PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level - Low. Level 2 4 1. 2. 3 30- I

b. Drywell Pressure - High 4 1. 2. 3 30 I

c. Condensate Storage Tank Level - Low 2 1, 2. 3 . 33 ,

y d. Suppression Chamber Water Level - High 2(*' 1. 2. 3 33 y e. Bus Power Monitor (d' 1/ bus 1. 2. 3 32

4. AUTOMATIC DEPRESSURIZATION SYSTEM l

a. ADS Inhibit Switch 2 1. 2. ' 3 36 I

b. Reactor Vessel Water Level - Low. Level 3 4 1. 2. 3 36 I

c. Reactor Vessel Water Level - Low. Level 1 2 1. 2. 3 36 l t $ d. ADS Timer 2 1. 2. 3 g 36 l

e. Core Spray Pump Dischargs Pressure - High (Permissive) 4 1. 2. 3 36 l g f. RHR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2/ pump. 1, 2. 3 36 1

g. . Bus Power Monitor (d' 1/ bus 1. 2. 3 32 4

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION r

ACTIONS l

ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement: I

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or -

are placed in the tripped condition to maintain automatic ECCS actuation capability for the Trip Function, and ,

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place all inoperable channels that do not '

cause the Trip Function to occur in the tripped condition.

I Otherwise, declare the associated ECCS inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the :

Minimum OPERABLE Channels per Trip Function requirement, declare l the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the l Minimum OPERABLE Channels per Trip Function requirement, verify I bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the associated ECCS inoperable. ;

ACTION 33 - With the number of OPERABLE channels less than required by tha

^

Minimum OPERABLE Channels per Tri) Function requiremcat. ) lace at l l

least one inoperable channel in tie tripped condition wit 11n one hour or declare the HPCI system inoperable. l ACTION 34 - With the number of OPERABLE channels less than the Total Number of '

Channels declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped j condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then continue until l performance of the next required CHANNEL FUNCTIONAL TEST. l ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to maintain actuation capability of either ADS Trip System A or ADS Trip System B and restore the inoperable channels to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare ADS inoperable.

I i

l BRUNSWICK - UNIT 1 3/4 3-37 Amendment No.

i TABLE 3.3.3-1 (Continued)- .

I EMERGENCY-CORE COOLING SYSTEM ACTUATION INSTRUMENTATION I

NOTES

]

(a) When a channel:is placed in an inoperable status solely for performance of l required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function or the redundant Trip Function ;

maintains ECCS actuation capability. !

(b) Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.

(c) Provides signal to HPCI pump suction valves only. l (d) Alarm only, j (e) Required when ESF equipment is required to be OPERABLE.

(f) Deleted.- i l

1

)

l l L l

\ l I

(

i i j

u i

1 l

l l

BRUNSWICK - UNIT 1 3/4 3-38 Amendment No.

1

E 5

$ TABLE 4.3.3-1 7 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL OPERATIONAL

1 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

- TRIP FUNCTION CHECK TEST CAliBPATION SURVEILLANCE RE0VIRED

1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level -

Low Level 3 Transmitter: NA( NA R(b' 1.2.3.4.5 Trip Logic: D Q Q 1.2.3.4.5 I

b. Reactor Steam Dome Pressure - Low Transmitter: NA(*) NA R(b' 1,2.3.4.5 W Trip Logic: D Q Q 1.2.3.4,5 i a

w c. DrYwell Pres:ure - High

& Transmitter: NA( NA R(b' 1. 2. 3 w Trip Logic: D 0 0 1. 2. 3 i

d. Time Delay Relay NA R R 1.2.3.4.5

e. Bus Power Monitor NA R NA 1,2.3.4.5

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM E a. Drywell Pressure - High 8 Transmitter: NA(*) NA R(b' 1. 2. 3 g Trip Logic: D 0 0 1, 2. 3 l a b. Reactor Vessel Water Level -

z Low. Level 3 o

Transmitter: NA( NA R(6' L 2. 1 4((**' 5(*

Trip Logic: D 0 0 1.2,3.4 . 5(* I

c. Reactor Vessel Shroud Level Transmitter: NA,,3 NA R,,3 1. 2. 3. 4,,,, 5,,,,

Trip Logic: D Q Q 1. 2. 3. 4 . 5 I u___________________.-_______________.________. -__ _ . - . . -__ .- .- - _ . _ -

j IE 5

n TABLE 4.3.3-1 (Continued)

. EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

!E Z CHANNEL OPERATIONAL

- CHANNEL FUNCTIONAL' CHANNEL CONDITIONS IN WHICH .

TRIP FUNCTION CHECK TEST - CALIBRATION SURVEILLANCE REQUIRED

~

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued)

d. Reactor Steam Dome Pressure - Low NA"'- NA- R(?' 1. 2 2 3. 4"', ' 5"'

1. RHR Pump Start and LPCI ,

Injection-Valve Actuation D Q Ql 1. 2. 3. 4"). 5"' '

I I

w 2. Recirculation Loop Pump 1, 2. 3. 4"). 5"'

2 . Discharge Valve Actuation D .Q Q' l '- i

e. RHR Pump Start - Time Delay Relay NA R R 1. 2. 3. 4") . 5"'

^

f. Bus Power Monitor NA R NA' 1..2. 3.'4"). 5"' --

3. HIGH PRESSURE COOLANT INJECTION SYSTEM ,

a. Reactor Vessel Water' Level -

Low. Level 2 4 Transmitter: NA") .NA R*) 1. 2. 3 (E Trip Logic: D- Q- ;Q

~

1. 2. 3 i

b. Drywell Pressure-~- High l Transmitter: NA") NA - R*' 1. 2, 3 r+ Trip Logic: D. Q Q- 1. 2. 3 - l. ;

.E c. Condensate Storage Tank Level - Low NA Q -Q 1. 2. 3 l'

d. Suppression Chamber Water Level - High_ NA .0 - 0 1.f 2. ' 3 .I j

e. Bus Power Monitor NA .R NA' . 1, 2. 3'-

t m-_______ . _ _ _ - . _ _ . _ - . __._-.---__-____--_..-.--r_-ws. --------,----,a .

..nm_,,-e,_v.,--_.--,,___-u._.,na. --- s.- s-, __a ._n,m.,,.m.--.-n

- .,,-,n.-, ,,ne._,n,-,,,,r v a-n - :

$ TABLE 4.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c-5 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

~ CHECK TEST CALIBRATION SURVEILLANCE REQUIRED TRIP FUNCTION

4. AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch D R NA 1. 2. 3

b. Reactor Vessel Water Level -

Low. Level 3 Transmitter: NA NA R'6' 1. 2. 3 Trip Logic: D Q Q 1, 2. 3 i g

ca c. Reactor Vessel Water Level -

1. Low. Level 1

Transmitter: NA' NA R( 1. 2. 3 Trip logic: D Q Q 1. 2. 3 1

d. ADS Timer NA R R 1. 2. 3

e. Core Spray Pum) Discharge Pressure - Hig1 NA Q Q 1. 2. 3 I W

8 f. RHR (LPCI MODE) Pump Discharge g Pressure - High NA Q Q 1. 2. 3 I E g. Bus Power Monitor NA R NA 1. 2. 3

E 5

n TABLE 4.3.3-1 (Continued)

' EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

5

. CHANNEL OPERATIONAL

~

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICil TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REOUIRED

5. LOSS OF POWER

a. 4.16 kv Emergency Bus NA NA R 1. 2. 3. 4(d). 5(d)

Undervoltage (Loss of Voltage)

b. 4.16 kv Emergency Bus NA M R 1, 2, 3. 4(d'. 5(d' w Undervoltage (Degraded 2 Voltage) w h

F 8

9 r

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

(b) Transmitters are exemated from the quarterly channel calibration. 1 (c)'The ADS Inhibit Switcles shall be maintained in the Automatic position.

(d) Required when ESF equipment is required to be OPERABLE.

TABLE 3.3.4-1 (Continued)

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION i

.N_QIES (a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains control rod withdrawal block capability.

(b) This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.

(c) This function is bypassed when the associated IRM channels are on range 8 or higher.

(d) A total of 6 IRM instruments must be OPERABLE.

(e) This function is bypassed when the IRM channels are on range 1.

(f) When (1) THERMAL POWER is greater than or ecual to 30% of RATED THERMAL POWER and less than 90% of RATED THERMAL P0kER and MCPR is less than 1.70, or (2) THERMAL POWER is greater than or equal to 90% of RATED THERMAL POWER and MCPR is less than 1.40.

(g) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(h) This signal is contained in the Channel A logic only.

BRUNSWICK - UNIT 1 3/4 3-49 Amendment No.

58 TABLE 4.3.4-1 c-

@ CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS N CHANNEL OPERATIONAL

. CHANNEL FUNCTIONAL- ' CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST- CALIBRATION $URVEILLANCE REQUIRED g

U 1. APRM '

~

a. Upscale (Flow Biased) NA S/U( ("

R(b)( 1~ l

b. Inoperative NA S/U('"'IQ .Q NA 1. 2. 5

c. Downscale NA S/U( NA 1 1

d. Upscale (Fixed) NA S / U('" Q. 0""" R( 2, 5 -

2. ROD B_0CK MONITOR

a. Jpscale NA S/U(c) .0 R( 1(* I

b. Inoperative NA S/U(')' .0 NA,' 1("

c. .Downscale NA S/U(* .0 R 1(* l

3. SOURCE RANGE MONITORS

(*

ca a. -Detector not full in NA S/U((*) NA 2. 5

b. Upscale NA S/U . (d' NA 2. 5 ca c. Inoperative NA S/U( . (* (* NA 4 y

d. Downscale NA S/U(*) . NA 2',

2 b

4. INTERMEDIATE RANGE MONITORS

a. Detector not full in NA S W[g'"W(d . NA 2 M M 5.

b. Upscale NA S/U( .W(* NA .2 m W M 5

& c. Inoperative NA . S/U( .W(* NA 2'

,5 NA W NA. 5 k d. Downscale NA - S/U(') .W(* NA 2 a -NA W- NA _5 z 5. SCRAM DISCHARGE VOLUME O

a. Wat'er Level - High NA- Q. R 1 . 2 , 5(h)

TABLE 4.3.5.5-1 l CONTR0_ ROOM EMER?ENCY VENTI.LATION SYSTEM INSTRUiENTATION 5. WEILLANCE RE0JIREMENTS l

CHANNEL !

CHANNEL FUNCTIONAL CHANNEL l FUNCTION CHECK TEST CALIBRATION !

1. CHLORINE ISOLATION: [

a. Local NA M A- !

Detection Trip !

System '!

b. Remote NA M A l Detection Trip i System l

2. RADIATION PROTECTION-Control Building _D 0 R I I

Air Intake [

3. CONTROL ROOM ENVELOPE i SM0KE PROTECTION: l F

a. Zone 4 NA 6 months (a) [

\

l

b. . Zone 5 NA 6 months (a)-

i (a) See Surveillance Requirement 4.7.2.d.2 7 1

BRUNSWICK - UNIT 1 3/4 3-64c Amendment No.-

i

INSTRUMENTATION l

3/4.3.6 ATWS RECIRCULATION PUMP TRIP (RPT) SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION l

3.3.6.1 The ATWS-RPT system instrumentation channels shown in Table 3.3.6.1-1 l l shall be OPERABLE with their trip setpoints set consistent with the values i shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a. With an ATWS-RPT system instrumentation trip setpoint less conservative than the value shown in the Allowable Values column of.

Table 3.3.6.1-2. declare the instrument channel inoperable until'the l channel-is restored to OPERABLE status with its trip setpoint adjusted-consistent with the Trip Setpoint value. j I

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

1. Verify that a sufficient number of channels remain OPERABLE or are in the triaped condition to maintain ATWS-RPT trip capability for both Trip unctions within one hour, and

2. Restore the. inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition within 14 days.

c.

With trip capability for one ATWS-RPT Trirestore trip capability within 72 ho l d. With trip capability for both ATWS-RPT Trip Functions not maintained, i restore trip capability for one Trip Function within one hour.

l Otherwise, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.6.1.1 Each ATWS-RPT system 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 4.3.6.1-1.

4.3.6.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. !

4 L ,

BRUNSWICK - UNIT 1 3/4 3-88 Amendment No.

TABLE 3.3.6.1-1 j ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION !

I

' l' MINIMUM OPERABLECHANNELj3 i TRIP FUNCTION PER TRIP SYSTEM !

i

1. . Reactor Vessel Water Level - Low. Level. 2 2 j

2. Reactor Vessel' Pressure - High 2 i

)

(

i I

l i

i l

t t

l i l t I

")

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed.for 'i up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains- ATWS-RPT capability.

l BRUNSWICK - UNIT 1 3/4 3-89 Amendment No.

i

, c-- . ~ . . . . . . . -

TABLE 4.3.6.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CHECK TEST CALIBRATION

1. Reactor Vessel Water Level -

Low. Level 2 Transmitter: NA") NA R*)

Trip Logic: D Q Q l

2. Reactor Vessel Pressure - High Transmitter: NA") NA R*)

Trip Logic: D 0 0 1 l

l l

i

") The transmitter channel check is satisfied by the trip unit channel check.

A separate transmitter check is not required.

) Transmitters are exempted from the quarterly channel calibration. I BRUNSWICK - UNIT 1 3/4 3-91 Amendment No.

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 their I 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 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.

BRUNSWICK - UNIT 1 3/4 3-92 Amendment No.

)

E 5

$n TABLE 3.3.7-1

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION

!5 U MINIMUM

~

OPERABLECHANNEly FUNCTIONAL UNIT PER TRIP SYSTEM ' ACTION

1. Reactor Vessel Water Level - Low Level 2 2 50

2. Reactor Vessel Water Level - High 2(b) 51

3. Condensate Storage Tank Water Level - Low (* 2") 52 ca 2

4 8

(a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry

. into associated ACTIONS may be delayed as follows:

$ (1) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Unit 2.

g 8-

.g (2) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Units 1 and 3. provided the Functional Unit maintains RCIC 1

m actuation capability.

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

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

(d) Provides signal to RCIC pump suction valves only.

4

-m-_m_._.___._____mm.__m_m___--__m --+----a m.- . . _-__ ..- - . - - - - .u--i _m--- - . _ . *vs=w-- - - ~

TABLE 3.3.7-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTIONS 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 31 ace the inoperable channel (s) and/or that trip system in tie tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or i declare the RCIC system inoperable.

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

ACTION 51 - With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System' requirement, restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise declare the RCIC system inoperable.

ACTION 52 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tri) System requirement -place at least one inoperable channel in tie trip)ed condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the RCIC system inoperaale.

BRUNSWICK - UNIT 1 3/4 3-94 Amendment No.

r

TABLE 4.3.7.1-1 l n

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

6 CHANNEL

- CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNIT CHECK TEST . CALIBRATION

1. Reactor Vessel Water Level - Low. Level 2 Transmitter: NA(') 'NA R(b' ' ;

Trip Logic: D Q Q l

2. Reactor Vessel Water Level - High Transmitter: NA( NA R(b) +

w Trip Logic: D Q 0- l l 2:

a 3. Condensate Storage Tank Level - Low NA- Q Q l' ,

h i

i g o if (a) The transmitter channel check is satisfied by the trip unit channel check. 'A separate transmitter check-is.not required.

(b) Transmitters'are exempted from the quarterly channel calibration. - l- ,

___-.-___---__..--._m__._m.__________.____..-____m________.__m___._ _-. _m.______s._.<m.______+_e _ - _-,_____-w.- _ _ _ _ _ _.__m.r--- --e.,-% _ . , _ - _ ___ _ w_m__.m_ _ _ - . -__=_s-_m_.,.m m_.<- ._______s

3/4.3 INSTRUMENTATION BASES 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:

l a. Preserve the integrity of the fuel cladding. )

l l b. Preserve the integrity of the reactor coolant system,

c. Minimize the energy which must be adsorbed following a loss-of-coolant

' accident. and prevent inadvertent criticality. l This specification )rovides the limiting conditions for operation necessary to preserve tie ability of the system to perform its intended I

' function even during periods when instrument channels may be out of service because of maintenance. When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests.

l Specified surveillance intervals and allowed out-of-service times were l established based on the reliability analyses documented in GE reports NEDC-30851P-A. " Technical Specification Improvement Analyses for BWR Reactor Protection System." March 1988 and MDE-81-0485. Rev.1. " Technical Specification Imarovement Analysis for the Reactor Protection System for Brunswick Steam Electric Plant. Units 1 and 2." August 1994, as modified by BWROG-92102. Letter from C. L. Tully (BWROG) to B. K. Grimes (NRC). "BWR Owners' Group (BWROG) Topical Reports on Technical Specification Improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844 and NEDC-30851P)." November 4. 1992.

The reactor protection system is made up of two independent trip systems.

There are usually four channels to monitor each parameter, with two in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both tria systems will produce a reactor scram. The system meets the intent of IEEE-279 for nuclear power plant protection systems.

The measurement of response time at the specified frequencies provides assurance that the )rotective, isolation, and emergency core cooling functions associated with eac1 channel are completed within the time limit assumed in the accident analysis. No credit was taken for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) inplace, onsite, or offsite test measurements, or 2) utilizing replacement sensors with certified response times.

The bases for the trip settings of the reactor protection system are discussed in the bases for Specification 2.2.

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

INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the trip settings for isolation of the reactor systems. When necessary, one channel may be l inoperable for brief intervals to conduct required surveillance. Some of the trip settings have tolerances exphcitly stated where both the high and low values are critical and may have a substantial effect on safety. The !

setpoints of other instrumentation where only the high or low end of the setting has a direct bearing on the safety, are established at a level away from the normal o systems involved.perating range to prevent inadvertent actuation of the Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30851P-A. Supplement 2. " Technical S)ecification Improvement Analysis for BWR Isolation Instrumentation Common to R)S and ECCS Instrumentation." March 1989 and NEDC-31677P-A. " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation." July 1990, as modified by 0G90-579-32A. l Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE). '

" Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Analysis." June 25, 1990 and supplemented by GE letter report GENE-A31-00001-02. " Assessment of Brunswick Nuclear Plant Isolation Actuation Instrumentation Against NEDC-31677P-A' Bounding Analyses."

August 1994.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION l The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control. This specification provides the tri) point settings that will ensure effectiveness of the systems to provide tie design protection. Although the instruments are listed by system, in some cases the same instrument is used to send the start signal to several systems at the !

same time. The out-of-service times for the instruments are consistent with ;

the requirements of the specifications in Section 3/4.5. l Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30936P-A. Parts 1 and 2. "BWR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation i Instrumentation)." December 1988 and RE-011. Rev.1. " Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant. Units 1 & 2." August 1994. l as modified by 0G90-319-320. letter from W. P. Sullivan and J. F. Klapproth (GE) to Millard L. Wohl (NRC), " Clarification of Technical Specification Changes Given in ECCS Actuation Instrumentation Analysis." March 22. 1990.

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

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l l INSTRUMENTATION j l BASES 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4. Rod Program Controls, and Section 3/4.2. i Power Distribution Limits. The trip lo the inputs will result in a rod block. gic is arranged so that a trip in any one of Specified surveillance intervals and allowed out-of-service times were !

established based on the reliability analyses documented in GE resort NEDC-30851P-A.

Supplement 1. " Technical Specification Improvement Analysis for BWR Control Rod j Block Instrumentation." October 1988.

3/4.3.5 MONITORING INSTRUMENTATION l l'

3/4.3.5.1 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitorin instrumentation ensures that sufficient capability is available to prompt y determine the magnitude of a seismic l event and evaluate the response of those fea ures important to safety. This !

capability is required to permit comparison of the measured response to that used in the design basis for the facility.

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

i INSTRUMENTATION BASES 3/4.3.5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

Surve111ances (Continued) instrumentation continues to o)erate properly between each CHANNEL ,

CALIBRATION. The CHANNEL CHEC( frequency is consistent with that performed for other radiation monitors with isolation functions.

The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the radiation actuation instrumentation. The quarterly frequency of the l CHANNEL FUNCTIONAL TEST was established based on Reference 7 and is consistent- :

with that performed for other radiation monitors with isolation functions.

The CHANNEL CALIBRATION verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 5). The frequency of the calibration is consistent with the frequency of calibration of other radiation monitors with isolation functions.

Chlorine Protection The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the s)ecific actions to be satisfied by the chlorine isolation instrumentation. T1e monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the sensor when the sensor is replaced. The test verifies the calibration of the existing sensor prior to removal and performs an installation calibration of the new sensor, including a complete channel calibration with the new sensor installed, to verify the channel responds to the measured parameter within the necessary range and accuracy. The CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 6).

The chlorine detectors use an amaerometric sensor consisting of a platinum cathode and silver anode joined )y an electrolytic salt bridge, all enclosed in a permeable membrane. This design eliminates the majority of the maintenance required on previous detectors. The detectors have been in service at other facilities and have provided reliable service. The annual replacement and calibration are based on a manufacturer recommendation. The ,

adequacy of the replacement interval has been confirmed through discussions i with other utilities.

Smoke Protection The CHANNEL FUNCTIONAL TEST for the Smoke Protection instrumentation is consistent with the testing performed in accordance with the existing Fire Detection Instrumentation requirements. CHANNEL CALIBRATION is performed in accordance with the requirements of the CREVS specification (4.7.2).

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

F l INSTRUMENTATION BASES 3/4.3.5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued) ,

References !

1.10 CFR 50. Appendix A. General Design Criterion 19. Control Room.

2. Regulatory Guide 1.95. Revision 1. Protection of Nuclear Power Plant ;

Control Room Operators Against an Accidental Chlorine Release.

3. Updated FSAR. Brunswick Steam Electric Plant. Units 1 & 2. l

4. NUS-3697. Revision 2. February 1983. Control Building Habitability Analysis.

5. CP&L Calculation 01534A-248. Control Room Radiation Monitor Setpoint l Evaluation.

! 6. BNP Design Basis Document (DBD)-37. Control Building Heating. Ventilation, '

and Air Conditioning System. ,

7. GENE-770-06-1-A. " Bases For Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

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

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INSTRUMENTATION ,

BASES 3/4.3.6 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION. l t

The ATWS recirculation pump trip system has been added at the suggestion of l ACRS as a means of limiting the consequences of the unlikely occurrence of a i failure to scram during an anticipated transient The response of the plant !

to this )ostulated event falls within the envelohe of study events given in General Electric Company Tropical Report NED0-10349, dated March, 1971. j Specified surveillance intervals and allowed out-of-service times were ;

established based on the reliability analyses documented in GE report GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." i December 1992.

3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION l 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 l cooling equipment. l 2

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reoort <

GENE-770-06-2P-A, " Bases for Changes to Surveillance Test Interva'is and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

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BRUNSWICK - UNIT 1 B 3/4 3-6 Amendment No.

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ENCLOSURE 3 l l

BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDM NTS l j INCREASED INSTRUMENT SURVEILLANCE TEST INTERVALS -l l AND ALLOWABLE OUT-OF-SERVICE TIMES i i -

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TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2 i

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3/4.3 INSTRUMENTATION. !

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION .

t LIMITING CONDITION FOR OPERATION l l !

i 3.3.1 As a minimum, the reactor l)rotection system inst"umentation channels !

l shown in Table 3.3.1-1 shall be OPERABLE. Set points and interlocks are given in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1. l ACTION:

a. With one channel less than the Minimum Number of OPERABLE Channels per i

. Trip System required b Table 3.3.1-1 in one or w.: Fulctional Ur.its, j place the inoperable c annel and/or that trip sy.cem f a the tripped condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. - With two or more channels less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.1-1 in one or more !'

Functional Units:

1. Within one hour, verify sufficient channels remain OPERABLE or in i the tripped condition

to maintain trip capability in the ,

Functional Unit, and l 2. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the inoperable channel (s) in one trip system l and/or that trip system ** in the tripped condition *. and

3. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip l system to an OPERABLE status or place them in the tripped :

condition *. ;

Otherwise. take the ACTION required by Table 3.3.1-1 for the Functional Unit. i

c. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL l CONDITION 5. )

An inoperable channel or trip system need not be placed in the l tripped condition where this would cause the Trip Function to i occur. In these cases if the inoperable channel is not restored

! to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall be taken.

- This ACTION a) plies to that tri) system with the most inoperable channels; if )oth trip systems lave the same number of inoperable channels, the ACTION can be applied to either trip system.

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

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATIOR SURVEILLANCE REQUIREMENTS l

4.3.1.1 Each reactor protection system instrumentation channel shall be l demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL l CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL 1

CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of l all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

! 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function8 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that both logic 4 trains are tested at least once per 36 months and one channel per function I such that all channels are tested at least once.every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

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' Neutron detectors are exempt from response time testing.

j BRUNSWICK - UNIT 2 3/4 3-la Amendment No.

p;. TABLE 3.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION EE q

m APPLICABLE MINIMlJM NUMBER OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION

1. Intermediate Range Monitors:

a. Neutron Flux - High 2. 5* 3 1

3. 4 -2 2

b. Inoperative 2, 5 3 -1 y 3. 4 2' 2

2. Average Power Range Monitor

{

a. Neutron Flux - High. 15% 2. 5* 2 3

b. Flow Biased Simulated Thermal- 1 2 4 Power - High

c. Fixed Neutron Flux -'High, 120% 1 2 4

d. Inoperative 1. 2. 5 2 5-

e. Downscale 1 2 4 ka f. LPRM 1. 2. 5 ' (c) NA

3. Reactor Vessel Steam Dome Pressure - High- - 1, 2(d' 2 6

[ 4. Reactor Vessel Water Level - Law. Level 1 1.'2 2 6 O

5. Main' Steam Isolation Valve - Closure 1 4 -4

6. Main Steam Line Radiation - High 1. 2'd' -2 7

,- . .--..--,_r -=__,-_.%-..._-.----_--.,r , _ , ,-,m-,,,ww--..,-..w.---.- -s4--.--a ~-- -,w-am .. . . . . , . _.u ez- ...- , ..., wm.,_,. -.,w.,,e

p; TABLE 3.3.1-1 (Continued) n REACTOR PROTECTION SYSTEM INSTRUMENTATION E

APPLICABLE MINIMUM NUMBER

[ OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION

7. Drywell Pressure - High 1. 2'" 2 6

8. Scram Discharge Volume Water Level - High 1. 2. 5'" 2 5-

9. Turbine Stop Valve - Closure l'O 4 8

Turbine Control Valve Fast Closure.

10.

Control Oil Pressure - Low I'O 2 8

[

11. Reactor Mode Switch in Shutdown Position 1.2.3.4.5 1 9

12. Manual Scram 1.2.3.4.5 1 10

13. Automatic Scram Contactors 1.2.3.4.5 2 10 1 5

8 8

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l TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION l l

i ACTION 10 - In OPERATIONAL CONDITION 1 or 2. be in at least HOT SHUTDOWN !

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5. suspend all onerations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

HQIES I (a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability.

(b) The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin demonstrations. .

(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.

(d) These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

4 (e) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(f) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(g) These functions are bypassed when THERMAL POWER is less than 30% of RATED THERMAL POWER.

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Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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

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p; TABLE 4.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

5 CHANNEL- OPERATIONAL CHANNEL FUNCTIONAL- CHANNEL CONDITIONS IN WHICH

" CHECK TEST CALIBRATION (*) SURVEILLANCE REQUIRED FUNCTIONAL UNIT

'1. Intermediate Range Monitors:

a. Neutron Flux - High D S/U(b"*), W(d) R 2 D W R 3,4,5

b. Inoperative NA W(d' NA 2.3,4.5 g 2. Average Power Range Monitor:

$ a. Neutron Flux - High 15% S S[gb"") W(d) . 0 2 4 S W Q 5

b. Flow-Biased Simulated Thermal S S/U(b),Q W('"", Q 1 Power - High

c. Fixed Neutron Flux - High, 120% S S/U(6', Q W(') . Q 1 l

-d. Inoperative NA Q("""' -NA 1,2,5 l

e. Downscale NA .. Q . NA 1 l a.

f. LPRM - D. NA (g) 1. 2, 5 z 3. Reactor Vessel Steam Dome Pressure - High P -Transmitter: NA(" NA R"' 1, . 2 Trip Logic: D Q Q 1, 2 l

4. Reactor Vessel Water Level - Low, Level 1 Transmitter: NA(" 'NA R"' 1, 2

. Trip Logic: D Q Q .

1. 2 l

- - . - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ . _ _ _ . - . - _ _ . _ _ _ . _ _ _ _ . _ _ _ . . _ _ . _ _ _ _ _ _ . . . . _ . . - ~ - _ _

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n TABLE 4.3.1-1 (Continued)

. ACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

3 CHANNEL OPERATIONAL y CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (') SURVEILLANCE REQUIRED

5. Main Steam Line Isolation Valve - Closure NA Q R(") 1 1

6. Main Steam Line Radiation - High S Q"' R(3' 1. 2 1

7. Drywell Pressure - High Transmitter: NA(" NA R"' 1, 2 y Trip Logic: D Q Q 1. 2 I

8. Scram Discharge Volume Water Level - High NA Q R 1, 2. 5

[

9. Turbine Stop Valve - Closure NA 0 R(") 1(*) i

10. Turbine Control Valve Fast Closure.

Control Oil Pressure - Low NA 0 R l' ' I g 11. Reactor Mode Switch in Shutdown Position NA R NA 1,2.3.4.5

{ 12. Manual Scram NA 0 NA 1.2.3,4.5 k 13. Automatic Scram Contactors NA W NA 1.2.3.4.5l 5

__-.-.-_----.____,_,------___--w__.---, -'_ _- - - >,ws - r -w-c.-_ _ , - - - - _ _ _ _ . - _ _ _ _ -

TABLE 4.3.1-1 (Continued) ;

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0UIREMENTS ms .

1 (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

f (b) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup, if not performed within the previous 7 days.

(c) The IRM channels shall be compared to the APRM channels and the SRM i instruments for overlap during each startup, if not performed within the !

previous 7 days. !

(d) When changinC from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2.

perform the recuired surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL C0hDITION 2 if not performed within the previous 7 days.

(e) This calibration shall consist of the adjustment of the APRM readout to l conform to the >ower values calculated by a heat balance during ;

OPERATIONAL CON)ITION 1 when THERMAL POWER is greater than or equal to i 25% of RATED THERMAL POWER. l

! (f) This calibration shall consist of the' adjustment of the APRM flow-biased ;

simulated thermal power channel to conform to a calibrated flow signal. l l (g) The LPRMs shall be calibrated at least once per effective full power ;

l month (EFPM) using the TIP system

(h) This calibration shall consist of a physical inspection and actuation of

these position switches .

i 4 (1) Instrument alignment using a standard current source. i (j) Calibration using a standard radiation source.

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

(1) Transmitters are exempted from the quarterly channel calibration. I 1

Placement of Reactor Mode Switch into the Startup/ Hot Standby position (m) is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

l (n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is l

permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts i

are tensioned.

(o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.

l l BRUNSWICK'- UNIT 2 3/4 3-9 Amendment No.

l l INSTRUMENTATION l 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION !

l l

l LIMITING CONDITION FOR OPERATION 1 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown

! in the Trip Setpoint column of Table 3.3.2-2.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION: ,

a. With an isolation actuation instrumentation channel trip setpoint less !

conservative than the value shown in the Allowable Values column of Table 3.3.2-2. declare the channel inoperable until the channel is i restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. For any isolation actuation Trip Function with less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.2-1:

1. Within one hour, verify sufficient channels remain OPERABLE or are l placed in the tripped condition

to maintain automatic isolation j actuation capability for the Trip Function, and

2. Place the inoperable channel (s) in the tripped condition

within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation Otherwise. take the ACTION required by Table 3.3.2-1.

c. Deleted. I

d. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5. i SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1. !

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

calibration of time delay relays and timers necessary for proper functioning of the trip system.

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An inoperable channel need not be placed in the tripped condition where this ,

would cause the Trip Function to occur. In these cases, if the inoperable '

channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.2-1 for the Trip Function shall be taken.

I BRUNSWICK - UNIT 2 3/4 3-10 Amendment No.

JNSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function' shall be 4 demonstrated to be within its limit at least once per 18 months. Each test !

shall include at least one logic train such that both logic trains are tested ~at l l least once per 36 months and one channel per function such that all channels are i tested at least once every N times 18 months, where N is the total number of I redundant channels in a specific isolation function. !

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BRUNSWICK - UNIT 2 3/4 3-11 Amendment No.

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TABLE 3.3.2-1 (Continued)

! ISOLATION ACTUATION INSTRUMENTATION 1-ND_IES 1

When handling irradiated fuel in the secondary containment. ,

l 1 (a) . See Specification 3.6.3.1. Table 3.6.3-1 for' valves J ni each valve group..

i (b) When a channel is placed in an inoperable status solely.for performance-u of required Surveillances, entry into associated ACTIONS may be delayed -)

as follows: ;

(1) For up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Trip Functions with a ' design that provides )

o only one channel' per trip system.

l (2)' For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions, provided the Trip Function !

maintains isolation actuation capability. ,

(c) Deleted. I l (d) A channel 1's OPERABLE if 2 of 4 instruments in the channel are OPERABLE. ,

(e) With reactor steam pressure = 500 psig.

.(f) Closes only RWCU outlet isolation valve. !

(g) Alarm only. )

(h) Isolates containment purge and vent valves. l (1) Does not isolate E11-F015A.B.

(j) Does not isolate B32-F019 or B32-F020. l 1

(k) Valve isolation depends upon low steam supply pressure coincident w'ith I high.drywell pressure. .!

(1) Secondary containment isolation dampers as listed in Table 3.6.5.2-1.

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BRUNSWICK - UNIT 2 3/4 3-17a Amendment No.

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TABLE 4.3.2-1 R ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL OPERATIONAL 5 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH H TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

~

1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level -

1. Low. Level 1 Transmitter: NA( NA R(b) 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 1

2. Low. Level 3 Transmitter: NA( NA R(b' 1. 2. 3 g Trip Logic: D Q Q 1. 2. 3 1

$ b. Drywell Pressure - High 4, Transmitter: NA( NA R(b' 1. 2. 3

~ Trip Logic: D Q Q 1. 2. 3 I

c. Main Steam Line

1. Radiation - High D 0 R(* 1. 2. 3 1

2. Pressure - Low Transmitter: NA(') NA R(b) 1 Trip Logic: D Q Q 1 1

3. Flow - High 3" Transmitter: NA(') NA R(b) 1 8 Trip Logic: D Q Q 1 1

& 4. Flow - High D 0 Q 2. 3 l

<u S d. Main Steam Line Tunnel g Temperature - High NA 0 R 1. 2. 3 1

e. Condenser Vacuum - LW Transmitter: NA(*) NA R(b) 1. 2(')

Trip Logic: D Q Q 1. 2(') I

f. Turbine Building Area Temperature - High NA Q R 1. 2. 3 I

g. Main Stack Radiation - High NA Q R. 1. 2, 3

h. Reactor Building Exhaust Radiation - High D Q R 1. 2. 3 l

F; TABLE 4.3.2-1 (Continued) n

. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

H CHANNEL -OPERATIONAL CONDITIONS IN WHICH CHANNEL FUNCTIONAL CHANNEL m TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE R't0VIRED

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High D -Q R 1.2.3.5. and(" l'

b. Dr.ywell Pressure - High .

Transmitter: NA NA R(b) 1;-2, 3 Trip Logic: D Q Q 1. 2. 3 I w

2 c. Reactor Vessel Water Level -

b Low. Level 2

-1. 2. 3 h Transmitter: NA NA R(b) m Trip Logic: D Q Q '1. 2. 3 l

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. -A Flow - High NA 'SA R 1. 2. 3

b. Area Temperature - High NA SA R 1. 2. 3 f c. Area Ventilation A Temperature - High NA SA R 1. 2. 3

{

d.

e.

SLCS Initiation Reactor Vessel Water Level -

NA. R NA 1.~2 ,

F Low. Level 2 Transmitter: NA NA R(b) 1. 2. 3 Trip Logic: D Q Q 1. 2. 3.' I

f. A Flow - High - Time Delay NA SA R 1. 2. 3

g. Piping Outside RWCU Rooms Area NA SA R, 1. 2. 3 Temperature - High

n TABLE 4.3.2-1 (Continued)

. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS b

H CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH N TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION

a. High Pressure Coolant Injection System Isolation

1. HPCI Steam Line Flow - High Transmitter: NA NA R*' 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 I ca 2. HPCI Steam Line Flow - High

,E Time Delay Relay NA R R 1. 2. 3

3. HPCI Steam Supply Pressure - Low NA Q R 1. 2, 3 1

4. HPCI Steam Line Tunnel Temperature - High NA SA R 1. 2. 3

5. Bus Power Monitor NA R NA 1. 2. 3

6. HPCI Turbine Exhaust Diaphragm Pressure - High NA Q Q 1, 2. 3 1

7. HPCI Steam Line Ambient g Temperature - High NA SA R 1. 2. 3 a

8. HPCI Steam Line Area y A Temperature - High NA SA R 1, 2. 3

[ 9. HPCI Equipment Area

,o Temperature - High NA SA R 1. 2. 3

10. Drywell Pressure - High Transmitter: NA( NA R*' 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 1

TABLE 4.3.2-1-(Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL - OPERATIONAL M CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 7 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED-c-

4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

.[ b. Reactor Core Isolation Cooling System Isolation-

1. RCIC Steam Line Flow --High Transmitter: NA( NA~ R*' 1, 2. 3 -

Trip Logic: D 0 Q 1. 2. 3 ~l

2. RCIC Steam Line High - Flow Time Delay Relay NA R R ~1. 2. 3

3. RCIC Steam Supply Pressure - Low NA -Q LQ 1. 2, 3. I M

^

4. RCIC Steam Line Tunnel Temperature - High NA SA R 1, 2, 3 -

Q 5. Bus Power Monitor NA R NA. 1. 2, 3~

6. RCIC Turbine Exhaust Diaphragm ~

Pressure - High NA Q R 1. 2, 3 1

7. RCIC Steam Line Ambient Temperature - High NA SA R ' 1, 2. '3 F

5

8. RCIC Steam Line' Area

^A Temperature - High ~NA SA- R. 1. 2, 3 8 9. RCIC Equipment Room Ambient .-

a Temperature - High NA- SA R 1, 2. 3

'.E 10. .RCIC Equipment Room A Temperature - High 'NA SA. RJ 1. - 2. ' 3

11. RCIC Steam Line Tunnel Tempera-ture --High. Time Delay Relay NA SA .R- 1, 2. 3

12. Drywell Pressure - High Transmitter: NA( NA R(6).' 1, 2. 3 Trip Logic: D Q -Q 1,2'3 l

E

TABLE 4.3.2-1 (Continued) n

.. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

H CHANNEL . OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH m TRIP FUNCTION CHECK TEST CALIBRATION . SURVEILLANCE REQUIRED

5. SHUTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Level -

Low. Level 1 W Transmitter: NA NA R* 1. 2, 3 Trip Logic: D Q Q 1. 2. 3 I

b. Reactor Steam Dome Pressure - High NA Q R 1. 2, 3 i-M u

E!

a

,8 a

E.

t

.~ .- .. .- - _- . . . . . . . . .. - - . -

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS ,

1 NOTES j (a) The transmitter channel check is satisfied by the trip unit channel check. j A separate transmitter check is not required. j (b) Transmitters are exempted from the quarterly channel calibration. l l

-(c) Deleted. I l

(d) Testing shall verify that the mechanical vacuum pump trips and the j mechanical vacuum pump line valve closes.

l (e)-When reactor steam pressure = 500 psig. ,

(f) When handling irradiated fuel in the secondary containment.

i i

l l

i 1

1 l

l BRUNSWICK - UNIT 2 3/4 3-32 Amendment No.

]

. \

l l

INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ,

LIMITING CONDITION FOR OPERATION t

3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation i i channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints l set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.

l APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

l l a. With an ECCS actuation instrumentation channel trip setpoint less l conservative than the value shown in the Allowable Values column of Table 3.3.3-2. declare the channel inoperable until the channel is I restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

, b. With one or more ECCS actuation instrumentation channels inoperable.

l take the ACTION required by Table 3.3.3-1.

l c. The provisions of Saecification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION, and CHANNELFUNCTIONALTESToperationsduringtheOPERATIONALCONDITIONSandat the frequencies shown in able 4.3.3-1 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at .

least once every N times 18 months, where N is the total number of redundant !

channels in a specific ECCS function. l l

1 l

BRUNSWICK - UNIT 2 3/4 3-33 Amendment No. j l '

l

I t

n TABLE 3.3.3-1

. EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E ,

U MINIMUM- APPLICABLE ,

N OPERABLE CHANNELg OPERATIONAL 'i TRIP FUNCTION PER TRIP FUNCTION , CONDITIONS ACTION ;

1. CORE SPRAY SYSTEM I

a. Reactor Vessel Water Level - Low. Level 3 4' 1 , 2. 3. 4. S' 30 1 -

b. Reactor Steam Dome Pressure - Low (Injection Permissive) 4 1.2.3.4.5 30 I

c. Drywell Pressure - High 4 1. 2. 3 30 11

d. Time Delay Relay 1/ pump 1,2,3.4.5 31 I

[ e. Bus Power Monitor"'

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM 1/ bus 1.2.3,4.5 32

a. Drywell Pressure - High 4 1. 2, 3 30 l

b. Reactor Vessel Water Level - Low.'.' Level'3 4 1. 2. 3. 4*). 5*) 30 i i c. Reactor Vessel Shroud Level (Drywell Spray Permissive). 1/ valve 1. 2, 3. 4*). 5*) 31 l'

.g a

g

d. Reactor Steam Dome Pressure - Low (Injection Permissive)

1. RHR Pump Start and LPCI Injection Valve-Actuation 4-

. 1. 2. 3. 4*)'. 5*) -30 g 2. Recirculation loop Pump. Discharge Valve-Actuation .4 1, 2. 3. 4* . 5*' 30 ..

E e. RHR Pump Start - Time Delay Relay 1/ pump 1. 2. 3. 4*'. 5*)

.31 I

f. Bus Power Monitor") 1/ bus l' 2.'3, 4*) 5.*' 32 y

4 4

1 i

1 .

kn TABLE 3.3.3-1 (Continued) i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION H

MINIMUM APPLICABLE OPERATIONAL OPERABLECHANNELp N TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION

3. HIGH PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level - Low. Level 2 4 1. 2. 3 30 i

b. Drywell Pressure - High 4 1. 2. 3 30 I

c. Condensate Storage Tank Level - Low 2(" 1, 2. 3 33 N d. Suppression Chamber Water Level - High 2(" 1. 2. 3 33

e. Bus Power Monitor (d' 1/ bus 1, 2. 3 32

4. AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch 2 1. 2. 3 36 I

b. Reactor Vessel Water Level - Low. Level 3 4 1, 2. 3 . 36 l g c. Reactor Vessel Water Level - Law. Level 1 2 1. 2. 3 '

36 l e

d. ADS Timer 2 1, 2. 3 36 l

% e. Core Spray Pump Discharge Pressure - High (Permissive) 4 1, 2. 3 36 I y f. RHR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2/ pump 1. 2. 3 36 I

g. Bus Power Monitor (d' 1/ bus 1. 2. 3 32

TABLE 3.3.3-1 (Continued) j EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTIONS

'~

ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement: I

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or !

are placed in the tripped condition to maintain automatic ;

ECCS actuation capability for the Trip Function, and-l

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months place all inoperable channels that do not- !

cause the Trip function to occur in the tripped condition. ;

Otherwise, declare the associated ECCS inoperable. {

ACTION 31 - With the number of OPERABLE channels less than required by the '

i Minimum OPERABLE Channels per Trip Function requirement, declare l' ;

the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels Der Trip Function requirement, verify I e bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the !

associated ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than required by the !

Minimum OPERABLE Channels per Tri) Function requirement, place at l. l l least one inoperable channel in t1e tripoed condition within one ,

I hour or declare the HPCI system inoperable. !

ACTION 34 - With the number of OPERABLE channels less than the Total Number !

of Channels, declare the associated emergency diesel generator i inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate. ,

1 ACTION 35. . With the number of OPERABLE channels one less than the 'l Total Number of Channels, place the inoperable channel in the '

tripped condition within 1 hour: operation may then continue !

until performance of the next required CHANNEL FUNCTIONAL TEST. :

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement. -verify 4 within one hour that a sufficient number of channels remain i OPERABLE to maintain actuation capability of either ADS Trip l

System A or ADS Trip System B and restore the inoperable channels-to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare ADS inoperable.

l l

L-i L BRUNSWICK - UNIT 2 3/4 3-37 Amendment No.

l

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION !

NOTES (a) When a channel is placed in an inoperable status solely for performance.of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function or the redundant Trip Function i maintains ECCS actuation capability. ;

(b) Not applicable when two core spray system subsystems are OPERABLE per ;

Specification 3.5.3.1. i (c) Provides signal to HPCI pump suction valves only. j (d) Alarm only.

l (e) Required when ESF equipment is required to be OPERABLE. ;

i l

l l

I l

BRUNSWICK - UNIT 2 3/4 3-38 Amendment No.

l

~

}

'$ TABLE 4.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

!!E CHANNEL OPERATIONAL q CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH m TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED-

1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level -

Low. Level 3 Transmitter: NA( NA R*' 1.2.3.4.5 Trip Logic: D Q Q 1,2.3.4.5 l

b. Reactor Steam Dome Pressure - Low R' Transmitter: NA(* NA R*' 1,2.3.4.5

Trip Logic: D Q Q 1. 2. 3. 4.-5 l w

A

" c. Drywell Pressure - High Transmitter: NA( NA R*) 1. 2. 3 ~

Trip Logic: D Q Q 1. 2. 3 i

d. Time Delay Relay NA R R 1.2,3.4.'5

e. Bus Power Monitor 1.2,3.4.5 '

NA R NA f 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Drywell Pressure - High g Transmitter: NA( NA R*' L1. 2, 3

, Trip Logic: D Q Q. 1. 2. 3 l-O

b. Reactor Vessel Water Level -

Low Level 3 i Transmitter: NA(* NA R*' ' 1, 2. 3, 4(*

Trip Logic: .D Q Q 1, 2. 3. 4!**. 5(*

5(* 1 i

' c. Reactor Vessel Shroud Level ~

Transmitter: ~ NA(* NA R)S 1. 2. 3, 4(*. 5(*

Trip Logic: D 0 0 1, 2. 3. 4(*. 5(* I

-E 5

n TABLE 4.3.3-1 (Continued)

. EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRtJMENTATION SURVEILLANCE REQUIREMENTS C

5 CHANNEL OPERATIONAL-CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH N

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued)

d. Reactor Steam Dome Pressure - Low NA NA R(b' 1, 2. 3. 4(d). 5(d'

1. RHR Pump Start and LPCI Injection Valve Actuation D Q Q 1. 2, 3. 4(d'. 5(d) I

2. Recirculation loop Pump g Discharge Valve Actuation D Q Q 1. 2. 3. 4(d'. 5(d) I h e. RHR Pump Start - Time Delay Relay NA R R 1. 2. 3. 4(d'. 5(d)

A f. ' Bus Power Monitor NA R NA 1. 2, 3. 4(d) 5(d'

3. HIGH PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level -

Law Level 2 Transmitter: NA(') NA R(b' l'. 2. 3 g Trip Logic: D Q Q 1. 2. 3 1 E b. Drywell Pressure - High j Transmitter: NA(') .NA R(*) L 2. 3 r+ Trip Logic: D Q. Q 1, 2. 3 l

c. Condensate Storage Tank Level - Low NA Q Q 1. 2. 3 I

d. Suppression Chamber Water level-High NA Q Q 1, 2. 3 I

e. ; Bus Power Monitor NA R NA 1. 2, 3

E 5

n TABLE 4.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c-5

CHANNEL OPERATIONAL CHANNEL. FUNCTIONAL- CHANNEL. CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch D") R NA 1.-2. 3-

b. Reactor Vessel Water Level -

Low. Level 3 Transmitter: NA( NA. R(*) 1. 2. 3 w Trip Logic: D. Q Q 1. 2. 3 l u

w c. Reactor Vessel Water Level -

m A Low. Level 1 Transmitter: ' NA( ' NA R(*' 1. 2. 3 Trip Logic: D Q Q 1. 2. 3 1

d. ADS Timer NA R R 1. 2. 3

e. Core Spray Pump Discharge Pressure - High NA Q Q 1. 2. 3' i k 3 f. RHR (LPCI MODE) Pump Discharge

& Pressure - High NA 0 -Q ~1. 2. 3 1

<v A g. Bus Power Monitor NA R NA 1. 2. 3 5

4

- - . _ . . -, .. . _ . , , w . - . . . - - - -..,,..-r-. ...,-_% ,,-,m--,- ., - - . - . . - - . . . . _ . . , .. - - - , .

? ,

i E I 5

kn TABLE 4.3.3-1 (Continued)

EMERGENCY CG. COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS C

5* CHANNEL OPERATIONAL

" CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION U S_URYEILLANCE REQUIRED

5. LOSS OF POWER

a. 4.16 kv Emergency Bus NA NA R 1. 2, 3, 4(*. 5(*

Undervoltage (Loss of Voltage) w b. 4.16 kv Emergency Bus NA H R 1, 2. 3, 4(*, 5(*

2 Undervoltage (Degraded a Voltage)

N ii 8

N l Ei

^

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 exem)ted from the quarterly channel calibration. l (c) The ADS Inhibit Switcles shall be maintained in the Automatic position.

(d) Required when ESF equipment is required to be OPERABLE.

1 r I

TABLE 3.3.4-1 (Continued) i CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTES ,

(a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed

! for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains control rod withdrawal block capability. .

l (b) This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher. ,

(c) This function is bypassed when the associated IRM channels are on range 8 or higher. ,

(d) A total of 6 IRM instruments must be OPERABLE.

(e) This function is bypassed when the IRM channels are on range 1.

(f) When (1) THERMAL POWER is greater than or equal to'30% of RATED THERMAL POWER and less than 90% of RATED THERMAL POWER and MCPR is less than 1.70. or (2) 'mERMAL POWER is greater than or equal to 90% of RATED THERMAL POWER and MCPR is less than 1.40.

(g) With any control rod withdrawn. Not ap per Specification 3.9.10.1 or 3.9.10.2.plicable to control rods removed (h) This signal is contained in the Channel A logic only.

I i

BRUNSWICK - UNIT 2 3/4 3-49 Amendment No.

E C

TABLE 4.3.4-1 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

R CHANNEL OPERATIONAL'

. CHANNEL FUNCTIONAL . CHANNEL CONDITIONS IN WHICH g TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED U 1. APRM N a. Upscale (Flow Biased) NA R(6'( 1 l

b. Inoperative NA S/Ul30 (" NA 1, 2. 5

c. Downscale NA S/U('(' .Q NA 1- l

d. Upscale (Fixed) NA S/U c) Q S/U(*"'I .0 """ R( 2. S

2. R00 B_0CK MONITOR

a. 1)pscale NA S/U( .Q R( 1(* l

b. Inoperative NA S/U(') .0 4 NA,' 1(*'

c. Downscale NA S/U( .Q R 1 I

$ 3. SOURCE RANGE MONITORS

(*

w a. Mtector not full in NA S/U(*) NA 2. 5 7, b. Upscale NA S/Ul.(* ,

(* NA 2. 5

- c. Inoperative NA S/U(*, .

(*

NA 2. 5

d. Downscale NA S/U*) . NA 2. 5

4. INTERMEDIATE RANGE MONITORS

a. Detector not full in NA S[g('"') .W(* NA 2 NA W NA ~5

b. Upscale NA S/U( .W(* NA 2 NA W NA 5

c. Inoperative NA S/U(*) .W(* NA 2 NA W NA 5

e d. -Downscale- NA S/U(*) .W(* NA 2 8 NA W NA 5 a 5. SCRAM DISCHARGE VOLUME B

?-i- a. Water Level - High NA Q R 1. 2, 5*'

.E

~

TABLE 4.3.5.5-1 CONTROL ROOM EMERGENCY VENTILATION SYSTEM i INSTRUiENTATION SURVEILLANCE REOUIREMENTS CHANNEL 1 CHANNEL FUNCTIONAL 1 CHANNEL-FUNCTION CHECK TEST CALIBRATION

1. CHLORINE ISOLATION:

a. Local NA' M A.

Detection Trip System

b. Remote NA M A Detection Trip .

System ;

2. RADIATION PROTECTION:

Control Building D 0- R I Air Intake

3. CONTROL ROOM ENVELOPE SM0KE PROTECTION:

a. Zone 4 NA 6 months (a)

b. Zone 5 NA 6 months (a)

(a) See Surveillance Requirement 4.7.2.d.2 l

l l

i i

BRUNSWICK - UNIT 2 3/4 3-64c Amendment No.

i I

INSTRUMENTATION ,

3/4.3.6 RECIRCULATION PUMP TRIP (RPT) ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP St A INSTRUMENTATION !

LIMITING CONDITION FOR OPERATION ;

3.3.6.1 The AWS-RPT system instrumentation channels shown in Table 3.3.6.1-1 1 !

shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.1-2. !

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION ,

a. With an ATWS-RPT system instrumentation trip setpoint less l conservative than the value shown in the Allowable Values column of :

Table 3.3.6.1-2, declare the instrument 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 less than required by the Minimum ;

OPERABLE Channels Per Trip System requirement. ,

t Verify that a sufficient number of channels remain OPERABLE or ;

1.

are in the tri) ped condition to maintain ATWS-RPT trip capability j for both Trip runctions within one hour, and ,

i

2. Restore the inoperable channel (s) to OPERABLE status or place the ;

i inoperable channel (s) in the tripped condition within 14 days. l i c. With trip capability for one ATMS-RPT Trip Function not maintained.

l restore trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . j d.

With restore trikrkapabilitYity p capabi for one Trip Function within one hour.for both ATWS-R j Otherwise, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

l BRUNSWICK - UNIT 2 3/4 3-88 Amendment No.

l

TABLE 3.3.6.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION-

' MINIMUM OPERABLECHANNE(y TRIP FUNCTION PER TRIP SYSTEM

1. Reactor Vessel Water Level -- Low. Level 2 2

2. Reactor Vessel Pressure - High 2 When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains ATWS-RPT capability.

BRUNSWICK - UNIT 2 3/4 3-90 Amendment No.

t i

TABLE 4.3.6.1-1

(

. ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS -

CHANNEL . !

CHANNEL FUNCTIONAL -CHANNEL - l TRIP FUNCTION CHECK TEST CALIBRATION

1. Reactor Vessel Water Level - .

Low. Level 2 i Transmitter: NA(') NA R(b) i Trip Logic: D 0 0 I i

2. Reactor Vessel Pressure - High !

Transmitter: NA(*) NA' R(b) I !

Trip Logic: D Q Q l l l -l l

I I

i

-I i

l i i i

i i

t (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 from the quarterly channel calibration. I BRUNSWICK - UNIT 2 3/4 3-92 Amendment No.

l

,--,1 .- -

--m. , ,__- y a , , _ _ - ,_----,n. - . -- ry r, .-n., .--

i l

INSTRUMENTATION END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.2 The end-of-cycle recirculation pump trip (E0C-RPT) system

instrumentation channels shown in Table 3.3.6.2-1 shall be OPERABLE with their l trip setpoints set consistent with the values shown in the Trip Set]oint i column of Table 3.3.6.2-2 and with the END-OF-CYCLE RECIRCULATION PJMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.6.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or l

equal to 30% of RATED THERMAL POWER and the MCPR limits obtained from the COLR l for use with Specification 3.2.2.1 require E0C-RPT.* !

ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values Column of Table 3.3.6.2-2. declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . l l c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

1. If the operable channels consist of one turbine control valve channel and one turbine stop valve channel, place both j inoperable channels in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . I

2. If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip .

system operable. ;

d. With one trip system inoperable, restore the inoperable trip systen; to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or take the ACTION required by Specification 3.2.2.1.

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or take the ACTION required by Specification 3.2.2.1.

The provisions of Specification 3.0.4 are not applicable.

BRUNSWICK - UNIT 2 3/4 3-93 Amendment No.

TABLE 3.3.6.2-1 l i

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMUM !

OPERABLE CHANNELS TRIP FUNCTION PER TRIP SYSTEM * !

1. Turbine Stop Valve - Closure 2* l

2. Turbine Control Valve - Fast Closure 2* !

I l

1 l

l l

i

, i l !

i l

l 1

l

When a channel is placed in an inoperable status solely for performance-L of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains E0C-RPT capability.

i-

These functions are by)assed when turbine first stage ]ressure is eqtiivalent to THERMAL 30WER less than 30% of RATED THERMAL POWER.

BRUNSWICK - UNIT 2 3/4 3-95~ Amendment No.

-TABLE 4.3.6.2.1-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS ,

CHANNEL.

FUNCTIONAL - CHANNEL l TRIP FUNCTION- TEST CALIBRATION

1. Turbine Stop Valve - Closure 0(9 R I i

2. Turbine Control Valve - Fast Closure <

- Q( R I-P

(

i l

l l

l l- 1

i (a) Including trip system logic testing.

I BRUNSWICK - UNIT 2 3/4 3-98 ' Amendment No.

INSTRUMENTATTON 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7 The reactor core isolativo cooling (RCIC) system actuation instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with their I 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:

l

a. With a RCIC system actuation instrumentation channel trip setpoint les.c conservative than the value shown in the Allowable Values column cf 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. i l

With one or more RCIC system actuation instrumentation channels b.

inoperable, take the ACTION required by Table 3.3.7-1. ]

SURVEILLANCE REQUIREMENTS .

1 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 CALIBPATION operations at the frequencies shown in l Table 4.3.7.1-1. l l

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

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BRUNSWICK - UNIT 2 3/4 3-99 Amendment No.

M TABLE 3.3.7-1 '

n REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION

!E A

y MINIMUM OPERABLE CHANNELS FUNCTIONAL UNIT PER TRIP SYSTEM ( ACTION

1. Reactor Vessel Water level - Low Level 2 2 50

2. Reactor Vessel Water Level - High 2(b' 51

3. Condensate Storage Tank Water Level - Low (* 2(*' 52 o -

E Y

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[

o (a) When a channel is placed in an ino)erable status solely for performance of required Surveillances, i entry into associated ACTIONS may ]e delayed as follows:

(1) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Unit 2.

(2) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Units 1 and 3. provided the Functional Unit maintains RCIC actuation capability.

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

(c) One trip 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 SYSTEM .

1 i

~ ACTUATION INSTRUMENTATION ACTIONS l I ACTION 50 - With the number of OPERABLE channels less than required by the ,

l Minimum OPERABLE Channels per Trip System requirement: ;

a. For one-trip system, ) lace the ino ;

that trip system in tic tripped c)perable channel ndition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (s) and/or. I or declare the RCIC system inope'able.

b. For both trip systems, declare the RCIC system inoperatle. i ACTION 51 - With the number of OPERABLE channels one less than requireo by i the Minimum OPERABLE Channels'per Trip System requirement, restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare the RCIC system inoperable.

ACTION 52 - With the number of OPERABLE channels less than required by the !

Minimum OPERABLE Channels per Tri) System requirement, place at-least one inoperable channel in tie trip)ed condition within 24

hours or declare the RCIC system inopera)le. ;

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4 E

p; TABLE 4.3.7.1-1 m i

' REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

3 CHANNEL CHANNEL FUNCTIONAL CHANNEL y

FUNCTIONAL' UNIT CHECK TEST CALIBRATION

1. Reactor Vessel Water Level - Low, Level 2 Transmitter: NA") NA 'R*

. Trip Logic: D Q. Q l

2. Reactor Vessel Water Level - High Transmitter: NA"' NA R*

Trip Logic: D Q Q l g

3. Condensate Storage Tank Level - Low NA Q l h Q. ,

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

(b) Transmitters are exempted from the' quarterly channel-calibration. .

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l l 3/4.3 INSTRUMENTATION l l

BASES l

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 1

The reactor protection system automatically initiates a reactor scram to:

a. Preserve the integrity of the fuel cladding.

l b. Preserve the integrity of the reactor coolant system.

l c. Minimize the energy which must be adsorbed following a loss-of-coolant accident, and prevent inadvertent criticality.

! This specification )rovides the limiting conditions for operation i necessary to preserve t1e ability of the system to perform its intended function even during periods when instrument channels may be out of service because of maintenance. When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests.

i Specified surveillance intervals and allowed out-of-service times were ;

established based on the reliability analyses documented in GE reports i NEDC-30851P-A " Technical Specification Improvement Analyses for BWR Reactor i Protection System." March 1988 and MDE-81-0485. Rev.1. " Technical Specification Imarovement Analysis for the Reactor Protection System for Brunswick Steam Electric Plant. Units 1 and 2." August 1994, as modified by BWROG-92102. Letter from C. L. Tully (BWROG) to B. K. Grimes (NRC). "BWR Owners' Group (BWROG) Topical Reports on Technical Specification Improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844 and NEDC-30851P)." November 4, 1992.

The reactor protection system is made up of two independent trip systems.

There are usually four channels to monitor each parameter with two in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram. The system meets the intent of IEEE-279 for nuclear power plant protection systems. ;

The measurement of response time at the specified frequencies provides j assurance that the )rotective, isolation, and emergency core cooling functions ;

associated with eac1 channel are completed within the time limit assumed in !

the accident analysis. No credit was taken for those channels with response times indicated as not applicable. 1 Res onse time may be demonstrated by any series of sequential, overlappi g or tota channel test measurements, provided such tests demonstrate the tota channel response time as defined. Sensor response time _ verification may be demonstrated by either 1) inplace, onsite, or offsite test measurements, or 2) utilizing replacement sensors with certified response times.

The bases for the trip settings of the reactor protection system are discussed in the bases for Specification 2.2.

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

1

INSTRUMENTATION BASES 1

3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION l This s l to mitigathecification ensures the effectiveness of the instrumentation usedthe conse l isolation of the reactor systems. When necessary, one channel ma l inoperable for brief intervals to conduct required surveillance. Somey be of the trip settings have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety. The setpoints of other instrumentation where only the high or low end of the i setting has a direct bearing on the safety. are established at a level away l from the normal operating range to prevent inadvertent actuation of the )

systems involved Specified surveillance intervals and allowed out-of-service times were established based on reliability analyses documented in GE reports -

NEDC-30851P-A. Supplement 2. " Technical S]ecification Improvement Analysis for i BWR Isolation Instrumentation Common to R)S and ECCS Instrumentation." March 1989 and NEDC-31677P-A. " Technical Specification Improvement Analysis for BWR ,

Isolation Actuation Instrumentation. July 1990, as modified by 0G90-579-32A. I Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE). !

" Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Analysis." June 25, 1990 and supplemented

, by GE letter report GENE-A31-00001-02 " Assessment of Brunswick Nuclear Plant l Isolation Actuation Instrumentation Against NEDC-31677P-A Bounding Analyses."

! August 1994.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control. This specification provides the tri) point settings that will ensure effectiveness of the systems to provide t1e design protection. Although the instruments are listed by system, in some cases the same instrument is used to send the start signal to several systems at the same time. The out-of-service times for the instruments are consistent with the requirements of the specifications in Section 3/4.5.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports 4 NEDC-30936P-A Parts 1 and 2. "BWR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation l

Instrumentation)." December 1988 and RE-011. Rev.1. " Technical Specification 1 Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant. Units 1 & 2." August 1994 as modified by 0G90-319-320. letter from W. P. Sullivan and J. F. Klapproth i (GE) to Millard L. Wohl (NRC). " Clarification of Technical Specification Changes Given in ECCS Actuation Instrumentation Analysis." March 22. 1990.

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

INSTRUMENTATION-BASES l l

3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION I The control rod block functions are provided consistent with the j requirements of the specifications in Section 3/4.1.4. Rod Program Controls 4 and Section 3/4.2. Power Distribution Limits. The trip logic is arranged so l that a trip in any one of the inputs will result in a rod block.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report i NEDC-30851P-A Supplement 1. " Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation." October 1988. ,

3/4.3.5 MONITORING INSTRUMENTATION 1 3/4.3.5.1 SEISMIC MONITORING INSTRUMENTATION f The OPERABILITY of the seismic monitorin instrumention ensures that sufficient capability is available to prompt y determine the magnitude of a ,

seismic event and evaluate the response of those features important to safety This capability is required to permit comparison of,the measured !

response to that used in the design basis for the facility.

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

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INSTRUMENTATION BASES 3/4.3.5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

Surveillances (Continued) i instrumentation continues to operate properly between each CHANNEL CALIBRATION. The CHANNEL CHECK frequency is consistent with that performed for other radiation monitors with isolation functions.

The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the radiation actuation instrumentation. The quarterly frequency of the CHANNEL FUNCTIONAL TEST was established based on Reference 7 and is consistent with that performed for other I radiation monitors with isolation functions. :

The CHANNEL CALIBRATION verifies the channel responds to the measured )arameter ;

within the necessary range and accuracy. CHANNE_ CALIBRATION leaves tie channel 1 adjusted to ensure consistency with the system assumptions (Reference 5). The i frequency of the calibration is consistent with the frequency of calibration of ;

other radiation monitors with isolation functions. ;

)

Chlorine Protection l The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the chlorine isolation instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the sensor when the sensor is replaced. The test verifies the calibration of the existing sensor prior to removal and performs an installation calibration of the i new sensor, including a complete channel calibration with the new sensor installed.

to verify the channel res)onds to the measured )arameter within the necessary range and accuracy. The CHANNE_ CALIBRATION leaves tie channel adjusted to ensure consistency with the system assumptions (Reference 6).

The chlorine detectors use an amperometric sensor consisting of a platinum cathode and silver anode joined by an electrolytic salt bridge, all enclosed in a permeable membrane. This design eliminates the majority of the maintenance required on previous detectors. The detectors have been in service at other facilities and have provided reliable service. The annual replacement and calibration are based on a manufacturer recommendation. The adequacy of the replacement interval has been confirmed through discussions with other utilities.

Smoke Protection The CHANNEL FUNCTIONAL TEST for the Smoke Protection instrumentation is consistent with the testing performed in accordance with the existing Fire Detection Instrumentation requirements. CHANNEL CALIBRATION is performed in accordance with the requirements of the CREVS specification (4.7.2).

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

fNSTRUMENTATf0N BASES 3/4.3.5.5 CONTROL Room EMERGENCY VENTILATION SYSTEM (Continued)

References

1. 10 CFR 50. Appendix A. General Design Criterion 19. Control Room.

{

, 2. Regulatory Guide 1.95. Revision 1. Protection of Nuclear Power Plant Control ,

Room Operators Against an Accidental Chlorine Release. l

3. Updated FSAR. Brunswick Steam Electric Plant. Units 1 & 2.

4. NUS-3697. Revision 2.' February 1983. Control Room Habitability Analysis. !

5. CP&L Calculation 01534A-248. Control Room Radiation Monitor Setpoint Evaluation. I

6. BNP Design Basis Document (DBD)-37. Control Building Heating. Ventilation..and Air Conditioning System.

I 7. GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and' ;

Allowed-Out-of-Service Times for Selected Instrumentation Technical -

Specifications." December 1992.

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

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INSTRUMENTATION BASES i

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION (Continued) i The initial CHANNEL CALIBRATION for the instruments associated with footnote (b) to Table 4.3.5.9-1 shall be performed using National Bureau of i Standards traceable sources which will verify that the detector operates l properly over its intended energy range and measurement range. For !

instruments which were operational prior to this specification being i implemented, previously established calibration procedures may be substituted for this requirement. Subsequent CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that the detector is still o)erationa'1. but the sources need not span the full ranges used in the initial CiANNEL CALIBRATION.

3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides 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 costulated event falls-within an envelope of study events given in General Electric Company Topical Report NED0-10349, dated March. 1971. l The end-of-cycle recirculation pump trip (E0C-RPT) system is a part of the Reactor Protection System and is a safety supplement to the reactor trip. The i purpose of the E0C-RPT is to recover the loss of thermal margin which occurs !

at the end-of-cycle. The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add !

negative scram reactivity. Each EOC-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core ,

during two of the most limiting pressurization events. The two events for !

which the E0C-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

A fast closure sensor from each of two turbine control valves provides input to one E0C-RPT system; a fast closure sensor from each of the other two turbine control valves provides input to the second E0C-RPT system. l Similarly, a position switch for each of two turbine stop valves )rovides input to one EOC-RPT system; a position switch for each of the otler two turbine stop valves provides input to the other EOC-RPT system. For each E0C-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 EOC-RPT system and trip both recirculation pumps.

Each E0C-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 THERMAL POWER are annunciated in the control room.

Specified surveillance intervals and allowed out-of-service time were i established based on the reliability analyses documented in GE report GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications."

December 1992.

BRUNSWICK - UNIT 2 B 3/4 3-6 Amendment No.

INSTRUMENTATION BASES 3/4.3.7 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 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.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A, " Bases for Changes to Surveillance Test Intervals and !

Allowed Out-of-Service Times for Selected Instrumentation Technical l Specifications." December 1992.

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

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ML20081H548

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