ML20028A314

Intermediate Range Monitors H

1, 2 2

6 Low, Level 1 4

1 O

(B21-LT-N017A-1,B-1,C-1,D-1)

U

( B 21-LTtt-N017 A-1, B-1, C-1,D-1 )

5.

Main Steam Isolation Valve - Closure 1

4 4

54 (B21-F022A,B,C,D and

?

B21-F028A,B,C,D) 6.

Main Steam Line Radiation - liigh 1, 2(d) 2 7

(D12-RM-K603A,B,C,D)

I, i

i TABLE 3.3.1-1 (Continued) g 5

i y

REACTOR PROTECTION SYSTEM INSTRUMENTATION M

M I

APPLICABLE MINIMUM NUMBER 5

OPERATIONAL OPERABLE CllANNELS G

FUNCTIONAL UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)

ACTION j

7. Drywell Pressure - liigh 1, 2(*)

2 6

l (C71-PS-N002A,B,C,D)

8. Scram Discharge Volume Water level -

liigh 1, 2, 5(b) 2 5

(C 11-LSil-No 13A,B,C,D)

9. Turbine Stop Valve - Closure 1(8) 4 8

(EHC-SVOS-lX,2X,3X,4X)

M

10. Turbine Control Valve Fast Closure',

u Control Oil Pressure - Low 1(E) 2 8

b (EllC-PSL-1756,1757,1758,1759)

11. Reactor !! ode Switch in Shutdown ;'osition 1,2,3,4,5~

1 9

(C71A-51) j

12. Mdii'tal scram--

1 1,2,3,4,5 I

10 l

(C71-A-S3A,B) e' n

Vi g

n

^

.O..

7 m

e6

%Q.

4

's, s

I'

~

f

r.

s n

1, y

3 ~.

l

/

' ~,

C a

^

TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES 9

RESPONSE TIME FUNCTIONAL UNIT' AND INSTRUMENT NUMBER 8

5

~

(Seconds) g p;

1.

(C 51-IRM-K601 A, B,C, D, E, F,G,H) :

w a.

Neutron Flux - High*

NA b.

Inoperative NA

~2. ' Average Power R$nge Monitor

1 r

(C51-APRM-CH. A,B,C,D,S F):

I a.

Neutron Flux - High, 15%

< 0.09 b.

Flow-Biased Neutron Flux - High NA R2 c.

Neutron Flux - Iligh, 120%

< 0.09

,c.

d.

Inoperative NA u,

i*

e.

Downscale NA f.

LPRM NA 3.

Reactor Vessel Steam Dome Pressure - High

< 0.55 (B21-PT-N023A,B,C,D)

(B21-PTM-N023A-1,B-1,C-1,D-1) 4.

Reactor Vessel Water Level - Low, Level 1 j(l.05 (B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1)

Ny 5.

Main Steam Line Isolation Valve-Closure g-(B21-F022A,B,C,D and j(0.06 y

B21-F028A,B,C,D) e J

6.

Main Steam Line Radiation - High NA

)

(D12-RM-K603A,B,C,D) 1 1

s a

)

l

i i

I g

TABLE 3.3.1-2 (Continued)

E!

v) fi REACTOR PROTECTION SYSTEM RESPONSE TIMES

--6 O

RESPONSE TIME I

FUNCTIONAL UNIT AND INSTRUMENT NUMBER (Seconds) 5 7.

Drywell Pressure - liigh NA (C71-PS-N002A,B,C,D) 8.

Scrain Discharge Volume Water Level - High NA (C l l-LS!!-N013A,B,C, D) i 9.

Turbine Stop Valve - Closure

( EaC-S VOS-I X,2 X,3 X,4 X)

--< 0.06 i

I

10. Turbine control Valve Fast Closure,

< 0.08

-l Control Oil Pressure - Low ga (EllC-PS L-1756,1757,1758,1759) s~

y

11. Reactor !! ode Switch in Shutdown Position NA p

(C71A-SI)

12. Manual Scram NA (C71 A-S 3A,B)

thutron detectors are exempt from response time testing. Response time shall be measured from detector output or from the input of the first electronic component in the channel.

N 9

g-Bn U

9 e

i!

E TABLE 4.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

i QIANNEL OPERATIONAL FUNCTIONAL UNIT QIANNEL FUNCTIONAL QIANNEL CONDITIONS IN WHIQ1 AND INSTRUMEKr NUMBER CIECK TEST CALIBRATION (8)

SURVEILLANCE REQUIRED 4

1.

Intermediate Range donitors:

( C51-IRM-K601 A J. C,D, E, F,G.H) a.

Neutron Flux - High D

S/U(b)(c)

R 2

I!

l D

W 8

R 3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitors

( C51-APRM-CH. A, B, C,D, E, F) a.

Neutron Flux - liigh 15%

S S/U(b), g(d)

Q 2

y S

W Q

5 b.

Flow-Biased Neutron Flux - High S

S/U(b),y g(e)(f),q g

c.

Fixed Neutron Flux - High, 120%

S S/U(b),y y(e),q 3

d.

Inoperative NA W

NA 1, 2, 5 e.

Downscale NA W

NA 1

f.

LPRM D

NA (g) 1, 2, 5 -

3.

Reactor Vessel Steam Dome Pressure - High

)

( B21-PT-N023A, B, C,D)

NA NA R

1, 2 l

U

( B 21-PTM-NO23 A-1, B-1, C-1,D-1)

D M

M 1, 2 0"

E 4.

Low, Level 1 y

(B21-LT-N017A-1,B-1,C-1 D-1)

NA( ) NA R

1, 2 II)

(B21-LTM-N017A-1 B-1,C-1.D-1)

D M

M 1, 2 1

I i

as TABLE 4.3.1-1 (Continued) i n

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS en 5

O CHANNEL OPERATIONAL FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICil g

AND INSTRu1ENT NUHBER CHECK TEST CALIBRATION (a)

SURVEILLANCE REQUIRED El

5. Main Steam Line Isolation Valve -

NA M

R(h) y Closure (B21-F022A,B,C,D and B21-F028A,B,C,D)

6. Main Steam Line Radiation - High S

M( A)*

R'd )

1, 2 l

( D12-RM-K603 A, B,C, D)

7. Drywell Pressure - High NA M

Q 1, 2

( C71-PS-N002 A, B,C, D) u, l

30

8. Scram Discharge Volume Water Level - High NA Q

R 1, 2, 5 La os (C12-LS H-N013 A,B,C,D)

9. Turbine Stop Valve - Closure NA M

R(h) 1, (EllC-S VOS-1X,2X,3X,4X)

10. Turbine Control Valve Fast Closure, Control Oil Pressure -

Low NA M

R 1

(EHC-PSL-1756,1757,1758,1759)

11. Reactor Moda Switch in Shutdown NA R

NA 1,2,3,4,5

@i Position (C71 A-S I)

12. Manual Scram NA Q

NA 1,2,3,4,5 (C71 A-S 3 A,B)

E.

TABLE 4.3.1-1 (Continued) m

o REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5il

~

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

5 p;

(b) Uithin 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.

H H

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

(d) When changing f rom CONDITION 1 to 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 CONDITION 2.

t (e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when THERNAL POWER > 25% of RATED THERNAL POWER.

(f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a u,

];

calibrated flow signal.

us (g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.

(h) This calibration shall consist of a physical inspection and actuation of these position switches, k

(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 monthly channel calibration.

l B

n i

t

i*

~

o, TABLE 3.3.2-1

n ISOLATION ACTUATION INSTRUMENTATION N

Q VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION 1.

PRIMARY CONTAINMENT ISOLATION H

a.

1.

Low, Level 1 2,6,8 2

1, 2, 3 20 l

(B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1)

f 2.

Low, Level 2 1, 3 2

1, 2, 3 20 (B21-LT-N024A-1,B-1, and t

B21-LT-N025A-1,B-1)

(B21-LTM-N024A-1,B-1 and u,

1 3:

B21-LTM-N025A-1,B-1)

Il c,

d.

b.

Drywell Pressure - liigh 2, 6 2

1,2,3

'20 l

]

(C71-PS-N002A,B,C,D)

F' c.

Radiation - liigh (d) 1 2

1,2,3 21 (D12-RM-K603A,B,C,D) 2.

Pressure - Low 1

2 1

22 (B21-PT-N015A,B,C,D)

(B 21-PTM-N015A-1, B-1,C-1, D-1) 3.

Flow - liigh 1

2/line 1

22 (B21-PDT-N006A,B,C,D; y

B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D) y (B21-PDTM-N006A-1,B-1,C-1,D-1; B 21-PDTM-NOO7A-1, B-1,C-1, D-1 ;

B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1.C-1,D-1) s A

e

i os TABLE 3.3.2-1 (Continued)

o S

v2 ISOLATION ACTl!ATION IR3TRUMENTATION di "I

R VALVE GROUPS MINIMUM NUMBER AFPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL g

TRIP FUNCTION AND INSTRUMEKr NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION d.

Main Steam Line Tunnel Temperature - Iligh 1

2(*)

1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low 1

2 1, 2(f) 21 i'

(B21-PS-N056A,B,C,D) i f.

Turbine Building Area un Temperature - High 1

4(*)

1, 2, 3 21 l

3 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; un d.

B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust g

Radiation - Iligh 6

1 1, 2, 3, 5, and* 23 (D12-RM-N010A,B) o a

b.

Drywell Pressure - Iligh 2, 6 2

1, 2, 3 23 (C71-PS-N002A,B,C,D)

.if 9

m TABLE 3.3.2-1 (Continued) m ISOLATION ACTUATION INSTRUMENTATION 5

Q VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION N

c.

E' Low, Level 2 1, 3 2

1,2,3 23 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)

(B21-LTM-NO24A-1,B-1 and B21-LTM-N025A-1,B-1) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - liigh 3

1 1,2,3 24 R,3 (G31-dFS-N603-1A,lB)

I c-a b.

Area Temperature - liigh 3

2 1, 2, 3 24 a

1.

(G31-TS-N600A,B,G,D,E,F) i u

c.

Area Ventilation A Temp. - High 3

2 1,2,3 24 I

(G31-TS-N602A,B,C,D,E,F) d.

SLCS Initiation 3 (K)

NA 1, 2, 3 24 (C41 A-S I) e.

Low, Level 2 1, 3 2

1,2,3 24 (B21-LT-N024 A-1,B-1 and j

B21-LT-N025 A-1,B-1)

}

g (B21-LTM-N024 A-1,B-1 and y

B21-LTM-N025 A-1,B-1)

Nn

.O s

1

m TABLE 3.3.2-1 (Continued) m ISOLATION ACTUATION INSTRUMENTATION Q

VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION H

4.

CORE STANDBY COOLING SYSTEMS ISOLATION w

a.

Iligh Pressure Coolant Injection System Isolation l

1.

IIPCI Steam Line Flow - High 4

2 1,2,3 25 j

(E41-dPIS-N004 and E41-dPIS-N005) 2.

HPCI Steam Supply Pressure - Low 4

2 1, 2, 3 25 (E41-PSL-N001A,B,C,D) 3.

IIPCI Steam Line Tunnel Temperature - liigh 4

2 1,2,3 25 k[

(E41-TS-3314; E41-TS-3315; y

E41-TS-3316; Z

E41-TS-3317 ;

E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489)

\\

4.

Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) 5.

IIPCI Turbine Exhaust 1

l Diaphragm Pressure - liigh 4

2 1, 2, 3 25 N

(E41-PSil-N012A,B,C, D) g 6.

IIPCI Steam Line Ambient g-Temperature - liigh 4

2 1,2,3 25 y

(E51-TS-N603C, D) n 7.

HPCI Steam Line Area A Temp. -

g

.o liigh 4

2 1, 2, 3 25 (E51-dTS-N604C,D) 8.

Emergency Area Cooler

-Temperature - Iligh 4

2 1,2,3 25 u

(E41-TS-N602A,B)

~

1__ -

l E

E TABLE 3.3.2-1 (Continued)

E ISOLATION ACTUATION INSTRUMEffrATION H

R VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL 6

TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION N

s b.

Reactor Core Isolation Cooling Systern Isolation 1.

RCIC Steam Line Flow - liigh 5

2 1,2,3 25 (E51-dPIS-N017 and E51-dPIS-N018) 4 2.

RCIC Steam Supply Pressure - Low 5

2 1,2,3 25 (E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel Temperature

- liigh 5

2 1, 2, 3 25 (E51-TS-3319; i

E51-TS-3320; u

{

)

E51-TS-3321; u

E51-TS-3322;

.h E51-TS-3323; E

E51-TS-3355; E51-TS-3487) 4.

Bus Power Monitor NA (h) 1/ bus 1, 2, 3 26 (E51-K42 and E51-K43) 5.

RCIC Turbine Exhaust Diaphragia Pressure - High 5

2 1, 2, 3 25 (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temp -

g liigh 5

2 1, 2, 3 25 (E51-TS-N603A,B) mn i

7.

RCIC Steam Line Area A Temp - liigh 5

2 1,2,3 25

[]

(E51-dTS-N604A,B) n sc 8.

RCIC Equipment Room habient Temp - Iligh 5

2 1, 2, 3 25 (E51-TS-N602A.B) 9.

RCIC Equipment Room A Temp - liigh

'5 2

1, 2, 3 25

~

(E51-dTS-N601A,B) s

I TABLE 3.3.2-1 (Continued) as m

E ISOLATION ACTUATION INSTRUMENTATION v3 N

Q VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL g TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION 5.

SilUTDOWN COOLING SYSTEM ISOLATION a.

Low, Level 1 2,6,8 2

1, 2, 3 27 (B21-LT-N017A-1,B-1,C-1,D-1)

(821-LTM-N017A-1,B-1,C-1,D-1) j, b.

Reactor Steam Dome Pressure-8 1

1,2,3 27 l

liigh (B32-PS-N018A,B)

W i

u L/t t

4 i;

i 8

9 M

8n O

u s

'J

l i

TABLE 3.3.2-2 Ei i

y ISOLATION ACTUATION INSTRUtlENTATION SETPOINTS Mn ALLOWABLE

]

TRIP FUNCTION AND INSTRUMEMT NUMBER TRIP SETPOINT VALUE a

1.

PRIMARY CONTAINMENT ISOLATION g

a.

1.

Low, Level 1

> + 162.5 inches *

> + 162.5 inches

l (B21-LT!!-N017A-1,B-1,C-1,D-1)

~~

"~

2.

Low, Level 2

}; + 112 inches *

]L + 112 inches *

[

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) i

j b.

Drywell Pressure - liigh

< 2 psig

< 2 psig 3

(C71-PS-N002A,B,C,D) i c.

Main Steam Line i

Y' l.

Radiation - Iligh j( 3 x full power background j( 3.5 x full power O

(D12-RM-K603A,B,C,D) background 2.

Pressure - Low JL 825 psig

};825 psig (B21-PTM-N015A-1,B-1,C-1,D-1) 3.

Flow - liigh

< 140% of rated flow

< 140% of rated flow (B21-PDTit-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)

i

'f k

i 9

a g-En g

9 0

'I TABLE 3.3.2-2 (Continued) e,

n I

5 y,

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS Q

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 5;;

d.

Main Steam Line Tunnel d

Temperature - High

< 200*F

< 200*F F'

(B21-TS-N010A,B C,D; B21-TS-N0llA,B,C,D; B21-TS N012A,B,C D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low jL 7 inches Hg vacuum

];7 inches Hg vacuum

( B21-PS-N056 A, B, C, D) j f.

Turbine Building Area Temp - High

< 200*F

( B 21-TS-3225 A, B,C, D; id B 21-TS-3226 A,B, C,D ;

l B 21-TS-3227 A,B, C, D; y'

B21-TS-3228A,B,C,D; B 21-TS-3229 A, B,C, D; B21-TS-3230A,B,C,D;

'l B 21-TS-3231 A, B, C, D; B21-TS-3232A,B C,D) i 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - I.gh

< 11 ar/hr

< 11 mr/hr

( D12-RM-N010A,B) a-

l b.

Drywell Pressure - High j[ 2 psig j[ 2 psig

![

( C71-PS-N002 A, B,C, D) 3 i

o i

c.

y Low, Level 2 JL + 112 inches *

> + 112 inches

l if (B21-LTM-N024A-1,B-1 and n

!1 g

B21-LTM-N025A-1 B-1) e

r-_

t i

g TABLE 3.3.2-2 (Continued)

E!

u>

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS N

R ALLOWABLE TRIP FUNCTION AND INSTRUMERf BUMBER TRIP SETPOIRf VALUE c:

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION

a a.

A Flow - liigh

< 53 gal / min

"~< 53 gal / min (G31-dFS-N603-1A,lB)

"~

b.

Area Temperature - liigh

< 150*F

< 150*F (C31-TS-N600A,B,C,D,E,F)

~~

~"

c.

Area Ventilation Temperature A Temp - High

< 50*F

< 50*F (G31-TS-N602A,B C,D,E,F) d.

SLCS Initiation NA NA (C41A-SI) h e.

u Low, Level 2 JL + 112 inches *

]L + 112 inches

l j

d.

(B21-LTM-N024A-1,B-1 and j

B21-LTM-N025A-1,B-1)

.(

i 4

CORE STANDBY COOLING SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation l

1.

IIPCI Steam Line Flow - High

< 300% of rated flow

< 300% of cated flow (E41-dPIS-N004 and E41-dPIS-N005) 2.

HPCI Steam Supply Pressure - Low

]L100psig

> 100 psig_

(E41-PS L-N001 A, B,C, D) f 3.

IIPCI Steam Line Tunnel Temperature - liigh

< 200*F

< 200*F l

E.

(E41-TS-3314; E41-TS-3315; E

E41-TS-3316; z

E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) s e

i l

t Us TABLE 3.3.2-2 (Continued)

E I:

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5

!ll

~

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE U

4.

Bus Power Monitor NA NA 4

(E41-K55 and E41-K56) s 5.

HPCI Turbine Exhaust Diaphragm Pressure - High j( 10 psig

< 10 psig i '

(E41-PSH-N012A,B,C,D) 6.

HPCI Steam Line habient Temp - liigh

<2b0*F

< 200*F (E51-TS-N603C,D) i 7.

HPCI Steam Line Area A Temp - liigh j:_ 50*F j[50*F (E51-dTS-N604C,D) l ki 8.

Emergency Area Cooler Temp - High

-< 175*F

< 175'F (E41-TS-N602A,B)

I" S!

b.

Reactor Core Isolation Cooling System Isolation

)

1.

RCIC Steam Line Flow - High

< 300% of rated flow

< 300% of rated flow (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply Pressure - Low 2;50 psig

};50 psig

)

(E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel Temp - liigh

< 175'F

< 175'F (E51-TS-3319; i

E51-TS-3320; E51-TS-3321; I

Ei E51-TS-3322; E

E51-TS-3323; i !

0" E51-TS-3355; E51-TS-3487) n z

4 Bus Power Monitor NA NA I

P (E51-K42 and E51-K43) s 9

TABLE 3.3.2-2 (Continued) e.

o ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5

Q ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE

{

h 5.

RCIC Turbine Exhaust Diaphragm "i

Pressure - High j(10psig j( 10 psig j

(E51-PS-NO12A,B,C,D) i 6.

RCIC Steam Line Ambient Temp - Iligh

< 200*F*

< 200*F i

(E51-TS-N603A,B) i; ;

7.

RCIC Steam Line Area A Temp - liigh

< 50*F

< 50*F i ;

(E51-dTS-N604A,B) 8.

RCIC Equipment Room Ambient Temp - liigh

< 175'F j

(E51-TS-N602A,B)

~~< 175'F u

9.

RCIC Equipment Room A Temp - liigh

< 50*F 2:

(E51-dTS-N601A,B)

~~< 50*F

~~

[

5.

SilUTDOWN COOLING SYSTEM ISOLATION f

a.

Low, Level 1

> + 162.5 inches *

> + 162.5 inches

l (B21-LTM-N017A-1,B-1,C-1,D-1)

"~

b.

Reactor Steam Dome Pressure - liigh l

(B32-PS-N018A,B)

-< 140 psig

'~ 140 psig I

I N.I g

g-i 8

h

Vessel water levels refer to REFERENCE LEVEL ZERO.

e e

r

TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

-l TRIP FUNCTION AND INSTRUMENr NUMBER RESPONSE TIME (Seconds)# l 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Veasel Water Level -

1.

Low, Level 1

<13 l.

(B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1) 2.

Low, Level 2

<l.0**

l (B21-LT-N024A-1,B-1 and B21-LT-NC25A-1,B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) b.

Drywell Pressure - High

<13 (C71-PS-N002A,B,C,D) c.

Main Steam Line

<l.0**

1.

Radiation - Righ*

(D12-RM-K603A,B,C,D) 2.

Pressure - Low

<13 (B21-PT-N015 A,B,C,D)

(B21-PTM-N015A-1,B-1,C-1,D-1) 3.

Flow - High

<0.5**

(B21-PDT-N006 A,B,C,D ;

B21-PDT-N007 A,B,C,D; B21-PDT-N008 A,B,C,D ;

B21-PDT-N009A,B,C,D)

(B21-PDTM-N006 A-1, B-1, C-1,D-1 ;

- B21-PITIM-N007A-1,B-1,C-1,D-1; j

B21-PDTM-N008 A-1, B-1, C-1,D-1 ;

B21-PDTM-N009A-1,B-1,C-1,D-1) d.

Main Steam Line Tunnel Temperature - High 1

(B21-TS-N010A,B,C,D;

__13 B21-TS-N011A,B,C,D; i

B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low

<l3 (B21-PS-N056 A,B,C,D) 4 d

BRUNSWICK-UNIT 1 3/4 3-22 Amendment No.

-m % me -.,

w-.

4 o-4...

" ~ ~

* - ^~' ' ~ ' ' ~ ~ ' ' '

rv

-y-

.w

--.e--

3-m-

,3-y7 y----m.-

m,- + -,

7 t

'------N T-77-

l l

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l

TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# l f.

Turbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High*

~<13 a.

(D12-RM-N010A,B) b.

Drywell Pressure - High

<13 (C71-PS-N002A,B,C,D)

~

c.

Reactor Vessel Water Level - Low, Level 2

<l.0**

l (B21-LT-N024A-1,'B-1 and

~

B 21-LT-N025A-1, B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1 B-1) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High

<13 (G31-dFS-N603-1A,IB) b.

Area Temperature - High

<13 (G31-TS-N600A,B,C,D,E,F)

Area Ventilation Temperature AT - High

<l3 c.

(G31-TS-N602A,B,C,D,E,F)

~

d.

SLCS Initiation NA (C41A-S I)

Reactor Vessel Water Level - Low, Level 2

<1.0**

l e.

(B21-LT-N024 A-1,B-1 and

~

B21-LT-N025 A-1 B-1)

(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1) l r

l l

BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.

l t

l-

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# l 4.

CORE STANDBY COOLING SYSTEMS ISOLATION High Pressure Coolant Injection System Isolation l

a.

1.

HPCI Steam Line Flow - High (13 (E41-dPIS-N004 and E41-dPIS-N005) 2.

HPCI Steam Supply Pressure - Low

<13 (E41-PSL-N001A,B C D)

~~

3.

HPCI Steam Line Tunnel Temperature - High

<13 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-34897 4.

Bus Power Monitor NA (E41-K55 and E41-K56) 5.

HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PS H-N012A,B,C, D) 6.

HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D) 7.

HPCI Steam Line Area NA (E51-dTS-N604C,D) 8.

Energency Area Cooler Temperature - High NA (E41-TS-602A,B) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High NA (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; i

E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4 Bus Power Monitor NA (E51-K42 and E51-K43)

BRUNSWICK - UNIT 1 3/4 3-24 Amendment No.

~

i

- -- I

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEN INSTRUMENTATION RESPONSE TIME l

TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

l 5.

RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B) 7.

RCIC Steam Line Area A Temp - High NA (E51-dTS-N604A,B) 8.

Emergen.cy Area Cooler Temperature - High NA (E51-TS-N602A,B) 9.

RCIC Equipment Room A Temp'- High NA (E51-dTS-N601A,B) 5.

SHUTDOWN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water Level - Low, Level 1 NA l

(B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1) b.

Reactor Steam Dome Pressure - High NA (332-PS-N018A,B)

Radiation monitors are exempt from response time testing. Response time shall be measured f rom detector output or the input of the first electronic component in the channel.

- Isolation actuation instrumentation response time only.

Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

BRUNSWICK - UNIT 1 3/4 3-24a Amendment No.

TABLE 4.3.2-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS u>

Nn CilANNEL OPERATIONAL M

CllANNEL EUNCTIONAL CHANNEL CONDITIONS IN WilIQI 8

TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION SURVFILLANCE REQUIRED Ey 1.

PRIMARY Q)NTAINMENT ISOLATION H

a.

1.

Low, Level 1 (B21-LT-N017A-1,B-1,0-1,D-1)

NA(a)

NA R(b) 1, 2,, 3 (B21-LTM-N017A-1,B-1,0-1,D-1)

D M,

M 1, 2, 3 2.

Low, Level 2 l

(B21-LT-N024A-1,B-1 and

)

b)

B21-LT-N025A-1,B-1)

NA NA

~R 1, 2, 3 l

(B21-LTM-N024A-1,B-1 and

{

B21-LTM-N025A-1,B-1)

D M

M 1, 2, 3 b.

Drywell Pressure - liigh NA M

Q' 1, 2, 3 u3 h

( C71-PS-N002A, B, C,D) u c.

Radiation - liigh D

W R

1, 2, 3

( D12-RM-K603 A, B, C, D) 2.

Pressure - Low

( B21-PT-N015A, B, C,D)

NA(a)

NA R(b) 3 (B21-PTM-N015A-1,B-1,0-1,D-1)

D M

M 1

3.

Flow - IIIgh

( B21-P DT-N006 A, B, C, D; NA(a)

NA R(b) g B21-Pur-N007A,B,C,D; y

B21-P DT-N008 A, B, C,D; B21-PUT-N009A,B,C,D)

( B21-P DTM-N006 A-1, B-1,0-1, D-1 ;

D M

M i

B21-PDTM-N007A-1,B-1,0-1,D-1; a

B21-P DTM-N008 A-1, B-1, 0-1, D-1 ;

,o B21-PurM-N009A-1,B-1,0-1,D-1) 4

J g

TABLE 4.3.2-1 (0)ntinued) 5@

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS l-t QIANNEL OPERATIONAL i

QIANNEL FUNCTIONAL QlANNEL CONDITIONS IN WHIQi g

TRIP FUNCTION AND INSTRUMENT NUMBER OlECK TEST CALIBRATION SURVEILLANCE REQUIRED A"

d.

Main Steam Line Tunnel Temperature - liigh NA H

R 1, 2, 3 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C D; B21-TS-N012 A, B, C, D; B21-T S-N013A, B, C.D) e.

Condenser Vacuum - Low NA M

R 1, 2#

(B21-PS-N056A,B,C,D) f.

Turbine Building Area Temp-liigh NA M

R 1, 2, 3

( B21-T S-3225A, B, C, D; w3 B21-T S-3226A, B, C,D; B 21-T S-3227A, B, C, D; u

eh B21-T S-3228A, B, C,D; B 21-T S-3229 A, B, C, D; B21-T S-3230A, B, C,D ;

B21-TS-3231 A,B C,D; B21-T S-3232A, B, C,D) 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - liign D

H R,

1,2,3,5, and *

(D12-RM-N010A,B) 8 8n E.!

g TABLE 4.3.2-1 ( Continued)

F3 Lj ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4

9 QlANNEL OPERATIONAL CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WilIQI

,]

TRIP FUNCTION AND INSTRUMEMr NUMBER CHECK TESE CALIBRATION SURVEILLANCE REQUIRED s

b.

Drywell Pressure - High NA M

Q 1, 2, 3

( C71-P S-N002A, B, C,D) c.

Low, Level 2 (B21-LT-NGt4 A-1,B-1 and NA(a)

NA,,

R(b) 1, 2, 3 B21-LT-N025 A-1,B-1)

(B21-LTM-N024 A-1,B-1 and D

M M

1, 2, 3 B21-LTM-N025 A-1,B-1) u 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - liigh D

M R

1, 2, 3 Y

(C31-dFS-N603-1 A, l B) w 5,.

Area Temperature - liigh NA M

R 1, 2, 3

( G31-T S-N600 A, B, C, D, E,F) l c.

Area Ventilation A Temp - liigh NA M

R 1, 2, 3

( G31-T S-N602 A, B, C, D, E,F) d.

SLCS Initiation NA R

NA 1, 2, 3

( C41A-SI) e.

Low, Level 2

)

(B21-LT-N024 A-1,B-1 and NA NA R

1, 2, 3.

!i B21-LT-N025 A-1,B-1) m h.

(B21-LTM-N024 A-1, B-1 and D

M M

1, 2, 3 g

B21-LT!!-N025 A-1,B-1) n

.O e

TABLE 4.3.2-1 ( Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEtfrS r.n N

QLuiNEL OPERATIONAL 0

QlANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICH TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TESr CALIBRATION SURVEILLANCE REQUIRED GA 4.

CORE STANDBY COOLING SYSTEMS ISOLATION H

H a.

liigh Press'ure Coolant Injection System Isolation

'l 1.

IIPCI Steam Line Flow - High D

M Q

1, 2, 3 (E41-dPIS-N004 and E41-dPIS-N005) 2.

IIPCI Steam Supply Pressure -

Low NA M

R 1, 2, 3 (E41-PSL-N001A,B,C,D) 3.

IIPCI Steam Line Tunnel e,

3:

Temperature - High NA M

Q 1, 2, 3

( E41-T S-3314 ;

u, E41-TS-3315; E41-TS-3316; E41-IS-3317; E41-TS-3318; E48-TS-3354; E4 S-3388; E41.S-3489) 4.

Bus Power Monitor NA R

NA 1, 2, 3 (E41-K55 and E41-K56) 5.

IIPCI Torbine Exhaust g.

Diaphragm Pressure - IIIgh NA M

Q 1, 2, 3 (E41-PSil-N012A,B,C D) mu 6.

IIPCI Steam Line Ambient Temp - liigh NA M

R 1, 2, 3 (E51-TS-N603C.D) l 7.

IIPCI Steam Line Area a Temp - liigh NA M

R 1, 2, 3

( E51-dT S-N664C,D)

El TABLE 4.3.2-1 (Cantinued)

E E

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS AnM OIANNEL OPERATIONAL QIANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICil Q

TRIP FUNCTION AND INSTRUMENT NUMBER GIECK TESC CALIBRATION SURVEILLANCE REQUIRED 4

8.

Emergency Area Cooler r.

Temp - liigh NA M

Q 1, 2, 3 (E41-TS-N602A,B) b.

Reactor Core Isolation Cooling Oystem isolation 1.

RCIC Steam Line Flow - liigh NA H

Q 1, 2, 3 (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply ki Pressure - Low NA H

Q 1, 2, 3 (E51-PS-N019A,B,C,D) u da 3.

RCIC Steam Line Tunnel liigh Temperature NA M

R 1, 2, 3 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4.

Bus Power Monitor NA R

NA 1, 2, 3 (E51-K42 and E51-K43)

Nb 5.

RCIC Turbine Exhaust R.

Diaphragm Pressure - liigh NA M

R 1, 2, 3 8

( E51-PS-N012A, B, C, D)

E i.f I

TABLE 4.3.2-1 (Q)ntinued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Gfi QIANNEL OPERATIONAL Q

QIANNEL FUNCTIONAL QIANNEL CONDITIONS IN WlIIQI TRIP FUNCTION AND INSTRUMEKr NUMBER QIECK TEST CALIBRATION SURVEILLANCE REQUIRED 54 6.

RCIC Steam Line Ambient H

Temp - liigh NA M

R 1, 2, 3

( E51-TS-N603A,B) 7.

RCIC Steam Line Area A Temp - liigh NA M

R 1, 2, 3

( E51-dT S-N604A, B) 8.

RCIC Equipment Room Ambient Temp - liigh NA M

Q 1, 2, 3 (E51-TS-N602A,B) 9.

RCIC Equipment Room A M

Temp - liigh NA M

Q 1, 2, 3 (E51-dTS-N601A,B)

'i' y

5.

SilUTDOWN COOLING SYSTEM ISOLATION a.

1-LT NOl7A-1,B-1,0-1,D-1)

NA(a)

NA R(b) 2, 3

( B21-LTM-N017A-1, B-1, C-1,D-1)

D M

M 1, 2, 3 b.

Reactor Steam Dome Pressure -

liigh NA S/U(c),M R

1, 2, 3

( B32-PS-N018A, B)

When handling irradiated fuel in the secondary containment.

)

When any turbine stop valve is open.

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

S A separate transmitter check is not required.

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

(c) If not performed within the previous 31 days.

?

es TABLE 3. 3. 3-1 EMERGENCY Q)RE COOLING SYSTEM ACTUATION INSTRUMENTATION N

y:

MINIMUM NUMBER APPLICABLE '

i OPERABIE QIANNELS OPERATIONAL g

TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Water level - Low, Iavel 3 2

1.2,3,4,5 30 l

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

( B21-LT S-NO31 A-4, B-4, C-4, D-4) b.

Reactor St'eam Dome Pressure - Iow (Injection Permissive)"

2 1,2,3,4,5 31

( B21-PT-N021 A, B, C, D)

( B21-PT S-N021 A-2, B-2,0-2, D-2) c.

Drywell Pressure - liigh 2

1, 2, 3 30

( El l-PS-N0l l A, B, C, D) d.

Time Iblay Relay 1

1,2,3,4,5 31 ~

(E21-K16A,B) l u

U e.

Bus Power Monitor #

1/ bus 1,2,3,4,5 32 (E21-KlA,B) 2.

LPCI MODE OF RilR SYSTEM a.

Drywell Pressure - liigh 2

1,2,3 30

( E l l-PS-N011 A, B, C, D) b.

Reactor Vessel Water Iavel - low, Invel 3 2

1, 2, 3, 4*, 5*

30 l

( B21-LT-NO31 A, B, C, D)

(B21-LTS-NO31A-4,B-4,C-4,D-4)

Reactor Vessel Shroud level (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5*

31 c.

(B21-LT-NO36 and B21-LT-NO37)

(B21-LTM-NO36-1 and B21-LTM-NO37-1) d.

Reactor Steam Dome Pressure - low (Injection Permissive) x

( B21-PT-N021 A, B, C, D)

( B21-PTM-N021 A-1, B-1, C-1, D-1)

( B21-PT S-N021 A-2, B-2, C-2, D-2) 1.

RilR Pump Start and LPCI Injection Valve Actuation 2

1, 2, 3, 4*, 5*

31 2.

Recirculation loop Pump Discharge Valve Actuation 2

1, 2, 3, 4*, 5*

31 I

tan TABLE 3.3.3-1 (Continued)

E EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION y

i 7:

MINIMUM NUMBER APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMEIR NUMBER PER TRIP SYSTEM CONDITIONS ACTION l

5 J

s c.

RilR Pump Start - Time Delay Relay 1

1, 2, 3, 4*,

5*

31 (STR-1Al,2 and STR-181,2) f.

Bus Power Monitor #

1/ bus 1, 2, 3, 4*,

5*

32 (Ell-K106A,B) 3.

IIPCI SYSTEM a.

Reactor Vessel Water Level - Low, Level 2 2

1, 2, 3 30 (B21-LTrNO31 A,B,C, D)

(B21-LTS-NO31A-2,B-2,C-2,D-2) u b.

Drywell Pressure - liigh 2-1, 2, 3 30 6

(Ell-PS-N0llA,B,C,D) w c.

Condensate Storage Tank Level - Low 2**

~

1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.

Suppression Chaiaber Water Imvel - High "

2**

1, 2, 3 '

33 (E41-LSil-N015A,B) e.

Bus Power Monitor # 1 1/ bus 1, 2, 3 32

~

(E41-K55 and E41-K56) 4 ADS a.

Drywell Pressure - liigh, colucident'with.

2 1, 2, 3 30 (Ell-PS-N010A,B,C,D) b.

. Reactor vessel Water Imvel

-Lrm, Imvel'3 2

'1,, 2, 3 -

30 l

(B21-LT-NO31A,B',0. D)

.g (B21-LTS-NO31A-3,B-3,C-3,D-3)_

{

s s

.y s

Y

~

~,?

.~ -

4@

j g

1 9

~

4 w.

Se

-+%

~.

y N'

p:

v Y

,..e n

n

~ - " ' "

,~

4 u

TABLE'3.3.3-1 (Omtinued)

oG is EMERCENCY CORE COOLiLU SYSTEM ACTUATION INSTRUMENTATION g

t _

9 z

HINIMUM NUMBER APPLICABLE s

OPERABLE QIANNELS Ct'ERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM

, CONDITIONS ACTION e

c.

Reactor Vessel Water level - low, Iavel 1 1

1, 2, 3 1'

30 l

(B21-LT-N042A,B)

( B21-LTM-N042A-1, B-1) d.

ADS Timer 1

1,2,3 31

( B21-TDPU-K5A, B) e.

Core Spray Pump Discharge Pressure - liigh (Permissive) 2 1,2,3

~

31 (E21-PS-N008A,B and E21-PS-H009A,B) f.

RilR (LPCI MODE) Pump Discharge Pressure - liigh (Permissive) 2/ pump 1, 2, 3 31 (Ell-PS-N016A,B, C,D and El1-PS-N020A,B,C,D) u g.

Bus Power Monitor #

1/ bus 1, 2, 3 32 Y

(B21-RIA,B)

H m

APPLICABLE TOTAL NO.

OlANNELS MINIMUM QIANNELS OPERATIONAL FUNCTIONAL UNIT OF CHANNELS TO TFIP OPERABLE CONDITIONS ACTION 5.

IDSS OF POWER a.

4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5##

34 Undervoltage (loss of Voltage) g b.

4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5##

35 g

Undervoltage (Degraded g-Voltage)

$n y

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

- Provides signal to llPCI pump suction valves only.

Alarm only.

1. Required when ESP equipment is required to be OPERABLE.

I

ton TABLE 3.3.3-2 E

EHERCENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION SETPOINTS N

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE h.

U l.

CORE SPRAY SYSTEM e

a.

Reactor Vessel Water level - Low, Level 3

-> + 2.5 inches *

> + 2.5 inches

l (B21-LTS-NO31A-4,B-4,C-4,D-4)

~

b.

Reactor Steam Dome Pressure - Low 410 + 15 psig 410 + 15 psig (B21-PTS-N021A-2,B-2,C-2,D-2) c.

Drywell Pressure - Iligh

< 2 psig

< 2 psig (Ell-PS-N0llA,B,C,D) d.

Time Delay-Relay 14 < t <~ 16 secs 14 < t <~ 16 secs (E21-K16A,B)

-~

~

l N

Bus Power Monitor NA NA e.

y (E21-KIA,B)

Y 2.

LPCI MODE OF RilR SYSTEM a.

Drywell Pressure - Iligh

< 2 psig

< 2 psig (E11-PS-N011A,B,C,D) b.

Reactor Vessel Water Level - Low, Level 3

> + 2.5 inches *

> + 2.5 inches

l (B21-LTS-NO31A-4,B-4,C-4,D-4) c.

Reactor Vessel Shroud Level

> - 53 inches *

> - 53 inches

l (H21-LTH-NO36-1 and B21-LTM-NO37-1)

!i d.

Reactor Steam Doine Pressure - Low

$g 1.

RilR Pump Start and LCPI Valve g

Actuation 410 + 15 psig 410 + 15 psig (B21-PTS-N021A-2,B-2,C-2,0-2) n 2.

Recirculation Pump Discharge Valve Actuation 310

15 psig 310

15 psig (B21-PTM-N021A-1,B-1,C-1,D-1)

es TABLE 3.3.3-2 (Continued) ps 3

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS v3 0

ALLOWABLE e

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 64 c.

RilR Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 seconds d

(STR-1Al,2 and STR-181,2) f.

Bus Power Monitor NA NA (Ell-K106A,B) 3.

IIPCI SYSTEM a.

Reactor Vessel Water level - Low, Level 2

> + 112 inches *

}; + 112 inches

l (B21-LTS-NO31A-2,B-2,C-2,D-2) b.

Drywell Pressure - liigh

< 2 psig j( 2 psig (Ell-PS-N0llA,B,C,D) w c.

Condensate Storage Tank Level - Low Y

(E41-LS-N002; E41-LS-N003)

-~> 23 feet 4 inches

> 23 feet 4 inches l

~~

u" d.

Suppression Chamber Water Level - liigh

< -2 feet **

l (E41-LSil-N015A, B) e.

Bus Power Monitor NA NA (E41-K55 and E41-K56) 4.

ADS a.

Drywell Pressure-liigh

-< 2 psig

-< 2 psig (E11-PS-N010A,B,C,D) b.

Reactor Vessel Water level - Low, Level 3 Ei (B21-LTS-NO31A-3,B-3,C-3,D-3)

~~> + 2.5 inches *

> + 2.5 inches

l en l.

c.

Reactor Vessel Water Level - Low, Level 1

}; + 162.5 inches *

}; + 162.5 inches

l (B21-LTM-N042A-1,B-1) mo" d.

ADS Timer (B21-TDPU-K5A,B)

< 120 seconds

TABLE 3.3.3-2 (Continued)

,:o h

EMERGENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION SETPOINTS s

Q ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE c.

Core Spray Pump Discharge Pressure - liigh

> 100 psig

> 100 psig H

(E21-PS-N008A,B and H

E21-PS-N009A,B) f.

RilR (LPCI MODE) Pump Discharge Pressure - liigh

> 100 psig

> 100 psig (Ell-PS-N016A,B,C,D and El1-PS-N020A,B,C,D) g.

Bus Power ' Monitor NA NA (B21-KIA,B) 5.

LOSS OF POWER u

D a.

4.16 kv Faergency Bus Undervoltage a.

4.16 kv Basis - 2940 t 161 volts 2940 t 315 volts v

6 (less of Voltage)#

b.

120 v Basis - 84 i 4.6 volts 84 i 9 volts y

c.

< 10 sec. time delay

< 10 secs. time delay b.

4.16 kv Emergency Bus Undervoltage a.

4.16 kv Basis - 3727

9 volts 3727

21 volts (Degraded Voltage) b.

120 v Basis - 106.5 t 0.25 volts 106.5 t 0.60 volts c.

10 t 0.5 sec. time delay 10 t 1.0 sec. time delay lI a

8

This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result n

g in a trip.

Iower voltage conditions will result in decreased trip times.

Vessel water levels refer to REFERENCE LEVEL ZERO.

Suppression chamber water level zero is the torus centerline minus 1 inch.

g TABLE 4.3.3-1 5

EMERGENCY CORE 000 LING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS vs 4n7:

QlANNEL OPERATIONAL OfANNEL FUNCTIONAL QlANNEL CONDITIONS IN WHIQI g

TRIP FUNCTION AND INSTRUMENT NUMBER QiECK TEST CALIBRATION SURVEILLANCE REQUIRED A

1. CORE SPRAY SYSTEM a.

Low, Level 3

( B21-LT-NO31 A, B, C,D)

NA(*}

I NA R

1,2,3,4,5

( B21-LT S-NO31 A-4, B-4, C-4,D-4)

D H

M 1,2,3,4,5 b.

Reactor Steam Dome Pressure - Low a)

( B21-PT-NO21 A, B, C,D)

NA NA R(b) 1,2,3,4,5 l

( B21-PT S-N021 A-2, B-2, C-2,D-2)

D M

M 1,2,3,4,5 c.

Drywell Pressure - liigh NA M

Q 1, 2, 3 g

( E l l-PS-N0l l A, B, C, D) s~

d.

Time Delay Relay NA R

R 1,2,3,4,5 g

[,

(E21-K16A,B) l u

e.

Bus Power Monitor NA R

NA 1,2,3,4,5 (E21-KlA,B)

2. LPCI HODE OF RilR SYSTEM a.

Drywell Pressure - liigh NA M

Q 1, 2, 3

( El l-PS-N011 A, B, C, D) b.

Low, Level 3 (B21-LT-NO31A,B C.D)

NA NA R

1, 2, 3, 4*, 5*

( B21-LT S-NO 31 A-4, B-4, C-4, D-4)

D M

M 1, 2, 3, 4*, 5*

c.

Reactor Vessel Shroud level g

)

g (B21-LT-NO36 and B21-LT-NO37)

NA NA R

1, 2, 3, 4*, 5*

l g

(B21-LTM-NO36-1 and B21-LTM-NO37-1) D M

M 1, 2, 3, 4*, 5*

.U

E TABLE 4.3.3-1 (Continued)

E E3 EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS M

CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CRANNEL CONDITIONS IN WilICH E

TRIP FUNCTION AND INSTRUHENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED s

s d.

Reactor Steam Dome Pressure - Low NA(a)

NA R(b) 1, 2, 3, 4*, 5*

l (B21-PT-N021A,B,C,D) 1.

RilR Pump Start and LPCI Injection Valve Actuation D

M M

1, 2, 3, 4*,

54 (B21-PTS-N021A-2,B-2,C-2,D-2) 2.

Recirculation Loop Pump Discharge Valve Actuation D

M M

1, 2, 3, 4*,

5*

(B21-PTM-N021A-1,B-1,C-1,D-1)

RilR Pump Start - Time Delay Relay NA R

R 1, 2, 3, 4*,

5*

e.

Ri (STR-IAl.2 and STR-1BI,2) f.

Bus Power Monitor NA R

NA 1, 2, 3, 4*,

5*

(Ell-K106A,B)

3. IIPCI SYSTEM a.

Low, Level 2 (B21-LT-NO31A,B,C,D)

NA(a)

NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2)

D M

M 1, 2, 3 b.

Drywell Pressure - liigh NA M

Q 1, 2, 3 (Ell-PS-N0llA,B,C,D) c.

Condensate Storage Tank Level - Low NA H

Q 1, 2, 3 g.

(E41-LS-N002; E41-LS-H003) d.

Suppression Chamber Water Level - Iligh NA M

Q 1, 2, 3 (E41-LSit-N015A,B) u c.

Bus Power Monitor NA R

NA 1, 2, 3 (E41-K55 and E41-K56)

I

g TABLE 4.3.3-1 (Continued)

G IA E!!ERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS d

O CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICll g

TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED n

4. ADS a.

Drywell Pressure - liigh NA M

Q 1, 2, 3 (E l l-PS-N010A, B,C, D) b.

Low, Level 3 (B21-LT-NO31A,B,C,D)

NA(8)

NA R(D) 1, 2, 3

( B21-LTS-NO 31 A-3, B-3,C-3, D-3)

D M

M 1, 2, 3 c.

Low, Level 1 M

(B21-LT-N042A,B)

NA(a)

NA R(b) 1, 2, 3 (H21-LTM-N042A-1,B-1)

D M

M 1, 2, 3 b

d.

ADS Timer NA R

R 1, 2, 3 E

(B21-TDPU-K5A,B) e.

Core Spray Pump Discharge Pressure - liigh NA M

0 1, 2, 3 (E21-PS-N008A,B and E21-PS-N009A,B) f.

RilR (LPCI MODE) Pump Discharge Pressure - liigh NA M

Q 1, 2, 3 (EI1-PS-NO16A,B,C,D and E11-PS-N020A,B,C,D)

N re g.

Bus Power Monitor NA R

NA 1, 2, 3 h

(B21-KI A,B) 9n

.O

g TABLE 4.3.3-1 (Continued)

Sy EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS t

X CHANNEL OPERATIONAL i

CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH g

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED n

4. ADS a.

Drywell Pressure - High NA M

Q 1, 2, 3 (EIl-PS-N010A,B,C,D) b.

Low, Level 3 l

(B21-LT-NO31A,B,C,D)

NA(a)

NA R(b) 1, 2, 3 l

( B21-LTS-NO31 A-3, B-3,C-3, D-3)

D M

M 1, 2, 3 c.

Reactor Vessel Water Level 2

Low, Level 1

{

(B21-LT-N042A,B)

NA(a)

NA R(b)

I, 2, 3 (B21-LTM-N042A-1,B-1)

D M

M 1, 2, 3 h,

d.

ADS Timer NA R

R 1, 2, 3 (B21-TDPU-KSA,B) r.

e.

Core Spray Pump Discharge Pressure - liigh NA M

0 1, 2, 3 (E21-PS-N008A,B and E21-PS-N009A,B) f.

RilR (LPCI MODE) Pump Discharge Pressure - liigh NA M

Q 1, 2, 3 (El!-PS-N016A,B,C,D and E I l-PS-N020A, B,C, Di w

g.

Bus Power Monitor NA R

NA 1, 2, 3 h

(B21-KIA,B)

E,

$j TABLE 4.3.3-1 (02ntinued)

E$

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIJN SURVEILIANG REQUIREMENTS M

cs M

QlANNEL OPERATIONAL 8

CHANNEL FUNCTIONAL CHANNEL 00NDITIONS IN WNICH Q

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILIANCE REQUIRED U

5.

LOSS OF POWER g

a.

4.16 kv Emergency Bus NA NA R

1, 2, 3, 4*, 5*

Undervoltage (Loss of Voltage) b.

4.16 kv Emergency Bus S

M R

1, 2, 3, 4*, 5*

Undervoltage (Degraded Voltage)

R v-

Required when ESP equipment is required to be OPERABLE.

u L

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

83 A separate transmitter check is not required.

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

Si 2n

.O

TABLE 3.3.5. 3-1 POST-ACCIDENT MONITORING INSTRUMENTATION 4

MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.

Reactor Vessel Pressure 2

l (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.

l (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 3.

Suppression Chamber Water Level 2

l (CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3)

(CAC-LT-2602; CAC-LR-2602) l 4.

Suppression Chamber Water Temperature 2

l (CAC-TR-1258-14, 21;~

and C91-P602) 5.

Supp"2ssion Chamber Atmosphere Temperature 2

(CAC-TR-1258-17 thru 20; and C91-P602) 5.

Drywell Pressure 2

l (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.

Drywell Temperature 2

l (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.

Drywell Radiation 2

l (CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 9.

Drywell Ox" gen 2

(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) 10.

Drywell Hydrogen 2

l (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) 11.

Safety Relief Valve Position Indication:

1/ valve a.

Primary - Sonic (B21-FY-4157 thru 4167) b.

Secondary - Temp. (B21-TR-R614, points 1-11) i BRUNSWICK - UNIT 1 3/4 3-51 Amendment No.

es TABLE 4.3.5.3-1 m

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS S

CllANNEL CHANNEL INSTRUMEtTF AND INSTRUMENT NUMBER CHECK CALIBRATION N

1.

Reactor Vessel Pressure M

R l

H (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.

Reactor Vessel Water level M

R l

(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,8; B21-LT-NO37 ; and B21-LTM-NO37-1) 3.

Suppression Chamber Water level M

R l

(CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3; CAC-LT-2602; CAC-LR-2602) 4.

Suppression Chamber Water Temperature M

R l

(CAC-TR-1258-14, 21; and C91-P602) h 5.

Suppression Chamber Atmosphere Temperature M

R (CAC-TR-1258-17 thru 20; and C91-P602) yj 6.

Drywell Pressure M

R l

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.

Drywell Temperature M

R l

(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.

Drywell Radiation M

R l

(CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262; and CAC-AQH-1262-1,2,3) 9.

Drywell Oxygen Concentration M

R l

(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) k 10 Drywell Hydrogen Concentration M

R l

g, (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) i n

11.

Safety Relief Valve Position Indication a.

Primary - Sonic (B21-FY-4157 thru 4167)

M R

b.

Secondary - Temp. (B21-TR-R614, points 1-11)

M R

Ej TABLE 3.3.6.1-1

&W ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 4

)

O MINIMUM NUMBER OPERABLE TRIP 5

TRIP FUNCTION AND INSTRUMENT NUMBER SYSTEMS PER OPERATING PUMP m

H 1.

1 g

Low, Level 2 l

(821-LT-N024A-2,B-2 and B21-LT-N025A-2,B-2)

(821-LTM-N024A-2,B-2 and i

B21-LTM-N025A-2,B-2) 2.

Reactor Vessel Pressure - liigh 1

(B21-PS-N045A,B,C,D)

I k'.>

i I3 0

i b

a

. a n

O

'l

D8 TABLE 3.3.6.1-2 E

h ATUS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS m

O 8

TRIP ALLOWABLE G

TRIP FUNCTION AND INSTRUMEffr NUMBER SETPOINT VALUE 4

1.

Reactor Vessel, Water level -

> + 112 inches *

) + 112 inches

Low, Level 2 (B21-LTM-N024A-2,B-2; B21-LTM-N025A-2,B-2) 2.

Reactor Vessel Pressure - High

--<!!20'psig

~~<ll20.psig

( B 21-PS-N045A, B, C, D) e 5~

Y R

8 fr 8n

.O

Vessel water levels refer to REFERENCE LEVEL ZERO.

El TABLE 4.3.6.1-1 E

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS b

CIIANNEL CHANNEL FUNCTIONAL CHANNEL 8

TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION dy 1.

Intermediate Range Monitors:

Low, level 2 s

(B21-LT-N024A-2,B-2 and NA(a)

NA R(b) l B21-LT-N025A-2,B-2)

(B21-LT!!-N024A-2,B-2 and D

g g

B21-LTil-N025A-2,B-2) i 2.

Reactor Vessel Pressure - liigh NA M

R (B21-PS-N045A, B, C, D)

M e-Y 0

8n

.U (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 monthly channel calibration.

E TABLE 2.2.1-1 6

h REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS R

ALLOWABLE FUNCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUES 5

h 1.

Intermediate Range Monitor, Neutron Flux - liigli(I)

-< 120 divisions of full scale

< 120 divisions

( C51-IRM-K601 A, B, C, D, E, F, G,11)

- of full scale n

2.

Average Power Range Monitor (CSI-APRM-CH.A,B,C,D,E,F) a.

Neutron Flux - liigh, 15%(2)

& 35% of RATED THERMAL POWER 1 15% of RATED THERMAL POWER Flow Biased Neutron Flux - High(3)(4)

< (0.66 W + 54%)

b.

Y Fixed Neutron Flux - liigh(4) i 120% of RATED THERMAL POWER

< 120% of RATED c.

THERMAL POWER 3.

Reactor Vessel Steam Dome Pressure - High 1 1045 psig i 1045 psig (B21-PTM-N023A-1,B-1,C-1,D-1) 4.

Reactor Vessel Water Level - Iow, Level 1 J_ +162.5 inches *

> +162.5 inches *

(B21-LTM-N017A-1,B-1,C-1,D-1) 5.

Main Steam Line Isolation Valve - Closure (5)

< 10% closed

< 10% closed (B21-F022A,B,C,D; B21-F028 A, B, C, D) 6.

g Main Steam Line Radiation - High 1 3 x full power background 1 3.5 x full power (D12-RM-K603A,B,C,D) background m

S 7.

Drywell Pressure - liigh

< 2 psig f,

( C72-PS-N002 A, B, C, D)

-< 2 psig

~~

x 8.

Scram Discharge Volume Water Level - High i 109 gallons i 109 gallons'

( C l 2-LS il-N013 A, B, C, D)

(Cl 2-ISil-4516 A,B,C, D) l s

9

TA3LE 2.2.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS TABLE NOTATION

Vessel water levels refer to REFERENCE LEVEL ZERO.

l (1)

The Intermediate Range Monitor scram functions are automatically bypassed when the reactor mode switch is placed in the Run position and the Average Power Range Monitora are on scale.

(2) This Average Power Range Monitor scram function is a fixed point and is increased when the reactor modo switch is placed in the Run position.

(3) The Aversge Power Range Monitor scram' function is varied, Figure 2.2.1-1, as a function of recirculation loop flow (W). The trip setting of this function must be maintained in accordance with Specification 3.2.2.

(4)

The APRM flow-biased high neutron flux signal is fed through a time constant circuit of approximately 6 acconds. The APRM fixed high neutron flux signal does not incorporcte the time constant, but responds directly to instantaneous neutron flux.

(5)

The Main Steam Line Isolation Valve-Closure scram function is automatically bypassed when the reactor mode switch is in other than the Run position.

(6)

These scram functions are bypassed when THERMAL POWER is less than 30% of RATED THERMAL POWER.

l BRUNSWICK - UNIT 2 2-6 Amendment No.

}

TABLE 3.3.1-1 m

?

'd REACTOR PROTECTION SYSTEM INSTRUMENTATION n

Q APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CllANNELS FUNCTIONAL UNIT Arid INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)

ACTION N

1.

(C51-IRM-K601A,B,C,D,E,F,G H)

'4 a.

Neutron Flux - liigh 2, 5(b) 3 g

3, 4 2

2 b.

Inoperative 2, 5 3

1 3, 4 2

2 2.

Average Power Range Monitor (CSI-APRM-Cll.A,B,C,D,E,F) a.

Neutron Flux - liigh, 15%

2, 5(b) 2 3

g S

b.

Flow Biased Neutron Flux - High 1

2 4

[

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 I) 3.

Reactor Vessel Steam Dome Pressure - High 1, 2 2

6 (B21-PT-N023A,B,C,D)

( B 21-PTM-N023 A-1,B-1,C-1, D-1) 4.

Intermediate Range Monitors H

1, 2 2

6 Low, Level I k

( B 21-LT-N017 A-1,B-1,C-1,D-1) g (H21-LTM-N017A-1,B-1,C-1,D-1) u 5.

Main Steam Isolation Valve - Closure 1

4 4

(B21-F022A,B,C,D and m

g B21-F028A,B,C,D) 6.

Main Steam Line Radiation - liigh 1, 2(d) 2 7

( D 12-RM-K603A, B,C, D)

g TABLE 3. 3.1-2 9

pj REACTOR PROTECTION SYSTEM RESPONSE TIMES m

l O

RESPONSE TIME a

FUNCTIONAL UNIT AND INSTRUMENT NUMBER (Seconds) h 1.

(C51-IRM-K601A,B,C,D,E,F.C.H):

u a.

Neutron Flux - liigh*

NA b.

Inoperative NA 2.

Average Power Range Monitor

4 (CS I-APRM-CII. A, B, C, D, E, F) :

a.

Neutron Flux - High,15%

_C_ 0.09 b.

Flow-Biased Neutron Flux - High NA t;

c.

Neutron Flux - liigh, 120%

j[0.09 d.

Inoperative NA e

e.

Downscale NA f.

LPRM NA 3.

Reactor Vessel Steam Dome Pressure - Ingh j[ 0.55

( B21-PT-N023 A, B,C, D)

(B21-PTM-N023A-1,B-1,C-1,D-1) 4.

Reactor Vessel Water Level - Low, Level 1

< l.05 (B21-LT-N017A-1,B-1,C-1,D-1)

~~

( B 21-LTM-N017 A-1, B-1,C-1, D-1)

I g

5.

Main Steam Line Isolation Valve-Closure

< 0.06 g-(B21-F022 A,B,C,D and g

821-F028 A, B. C, D) n g

6.

Main Steam Line Radiation - lugh NA

( 012-RM-K603 A, B,C, D)

TABLE 3.3.1-2 (Continued) g A5 REACTOR PROTECTION SYSTEM RESPONSE TIMES M

b*

RESPONSE TIME I

FUNCTIONAL UNIT AND INSTRUMENT NUMBER (Seconds)

NA p

7.

Drywell Pressure - liigh (C72-PS-N002A,B,C D) s, NA 8.

Scram Discharge Volume Water Level - liigh (C12-LSil-N013 A, B,C,D)

(Cl2-LSil-4516 A,B,C,D) 9.

Turbine Stop Valve - Closure

--< 0.06

( EllC-S VOS-lX,2X,3X,4X)

10. Turbine Control Valve Fast Closure,

[0.08 id Control Oil Pressure - Low (EllC-PSL-1756,1757,1758,1759)

Y NA g'

11. Reactor Mode Switch in Shutdown Position (C72 AHS 1)

NA

12. Manual Scram (C72 A-33 A, B)

Neutron detectors are exempt from response time testing. Response time shall be measured from

~

detector cutput or from the input of the first electronic component in the channel.

9 M

g

a TABLE 4.3.1-1 M

M REACIOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS N

Q QlANNEL OPERATIONAL i

FUNCTIONAL UNIT QlANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQI g

AND INSTRUMENT NUMBER GIECK TEST CALIBRATION (*

SURVEILLANCE ItEQUIRED 4

H 1.

Intermediate Range Monitors:

( C51-IRM-K601A,B,C,D,E,F G,H) a.

Neutron Flux - liigh D

S/U(b)(c)

R 2

D W

i R

3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor:

( C51-APR M-Ql. A, B, C,D, E, F) a.

tkutron Flux - liigh 15%

S S/U(b), g(d)

Q 2

w S

W Q

5 b.

Flow-Biased Neutron Flux - High S

S/U(b),y g(e)(f),q g

c.

Fixed Neutron Flux - High, 120%

S S/U(b),y g(e),9 3

d.

Inoperative NA W

NA 1, 2, 5 c.

Downscale NA W

NA 1

f.

LPRM D

NA (g) 1, 2, 5 3.

Reactor Vessel Steam Dome Pressure - liigh g

( B21-PT-N023A, B, C,D)

NA NA R

1, 2

( B 21-PTM-N023A-1, B-1, C-1. D-1)

D H

H 1, 2 m

E.

M 4.

f, Low, Level I g

g (B21-LT-N017A-1,B-1,C-1 D-1)

NA NA R

1, 2

( B21-LTM-N017A-1, B-1, C-1,D-1)

D H

H 1, 2 O

=_

E TABLE 4.3.1-1 (Continued)

E{

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS n*

CllANNEL OPERATIONAL FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)

SURVEILLANCE REQUIRED

5. Main Steam Line Isolation Valve -

NA M

R(b) 1 Closure (B21-F022 A,B,C,D and B21-F028A,B,C,D)

II)'

Id)

6. Main Steam Line Radiation - High S

M R

1, 2

( D12-RM-K603 A, B, C, D)

7. Drywell Pressure - liigh NA M

Q 1, 2

( C72-PS-N002 A, B, C, D)

?

8. Scram Discharge Volume Water Y

Level - High NA Q

R 1, 2, 5 (Cl2-LSil-N013 A,B,C,D)

(Cl2-IS H-4516 A, B,C,D)

9. Turbine Stop Valve - Closure NA M

R(h) y (EllC-S VOS-lX,2X,3X,4X)

10. Turbine Control Valve Fast Closure, Control Oil Pressure -

Low NA M

R 1

( EllC-PS L-1756,1757,1758,1759)

'G a

11. Reactor Mode Switch in Shutdown NA R

NA 1,2,3,4,5 h

Position 3

(C72 A-S I)

12. Manual Scram NA Q

NA 1,2,3,4,5 (C72 A-S 3 A, B)

)

l I

e

os 28 E

TABLE 4.3.1-1 (Continued) h REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

I E

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

(b) Uithin 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 IRH 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) Uhen changing from CONDITION 1 to 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 CONDITION 2.

(c) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.

hh '(f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a calibrated flow signal.

a In (g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.

m (h) This calibration shall consist of a physical inspection and actuation of chase position switches.

(1) 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 a rr.nsmitter check is not required.

I g

(1) Trar.smitters are exempted from the monthly channel calibration.

8n L

m TABLE 3.3.2-1 w5 U;

ISOLATION ACTUATION INSTRUtfCNTATION N

Q VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION g

M 1.

PRIMARY CONTAINMENT ISOLATION a.

1.

Low, Level 1 2,6,8 2

1, 2, 3 20 (B21-LT-N017A-1,B-1,C-1,D-1) 4 (B21-LTM-N017A-1,B-1,C-1,D-1) 2.

Low, Level 2 1, 3 2

1,2,3 20 (B21-LT-N024A-1,B-1, and B21-LT-N025A-1,B-1)

(B21-LTli-N024A-1,B-1 and u

2:

B21-LTM-N025A-1,B-1) b.

Drywell Pressure - liigh 2, 6 2

1, 2, 3 20 l

F' (C72-PS-N002A,B C.D) 4 c.

Radiation - liigh (d) 1 2

1, 2, 3 21 (D12-RM-K603A,B,C,D) 2.

Pressure - Low 1

2 1

22 (B21-PT-N015A,B,C,D)

(B21-PTM-N015A-1,B-1,C-1,D-1) 3.

Flow - liigh 1

2/line 1

22 Bi (B21-PDT-N005A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-N008A,B C,D; B21-PDT-N009A,B,C,D) y

( B 21-PDTii-N006A-1, B-1,C-1, D-1 ;

B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1) 1

TABLE 3.3.2-1 (Continued)

E!

y ISOLATION ACTUATION INSTRUMENTATION M

M VALVE CROUPS MINIMUM NUMBER APPLICABLE 8

OPERATED BY OPERABLE CIIANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION N

4.

Flow - liigh 1

2 2, 3 21 y

(B21-PDTS-N006A-2; B21-PDTS-N0078-2; B21-PDTS-N008C-2; B21-PDTS-N009D-2) s d.

!!ain Steam Line Tunnel Temperature - liigh 1

2(*)

1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B C.D; u,

];

B21-TS-N013A,B,C,D) y2 c.

Condenser Vacuum - Low 1

2 1, 2(f) 21

[;

(821-PS-N056A,B,C,D) f.

Turbine Building Area Temperature - liigh 1

4(*}

1. 2, 3 21 (821-TS-322 5A, B,C, D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; y

B21-TS-3232A,B,C,D) k 2.

SECONDARY CONTAINMENT ISOLATION Dy a.

Reactor Building Exhaust Radiation - liigh 6

1 1, 2, 3, 5, and* 23

'64 (D12-RM-N010A,B) b.

Drywell Pressure - Iligh 2, 6 2

1, 2, 3 23 (C72-PS-N002A,B,C,D) l

a, TABLE 3.3.2-1 (Continued)

E M

ISOLATION ACTUATION INSTRUMENTATION N

Q VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL cs TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION N

H c.

Low, Level 2 1, 3 2

1,2,3 23 (B21-LT-N024A-1,B-1 and 821-LT-N025A-1,B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High 3

1 1,2,3 24 id (G31-dFS-N603-1A,lB) b.

Area Temperature - High 3

2 1, 2, 3 24 (G31-TS-N600A,B,C,D,E F) c.

Area Ventilation A Temp. - High 3

2 1,2,3 24

..:G31-TS-N602A, B,C, D,E, F) d.

SLCS Initiation 3 (8)

NA 1, 2, 3 24 (C41A-SI) e.

Reactor Vessel Water. Level -

Low, Level 2 1, 3 2

1,2,3

24 (821-LT-N024 A-1,B-1 and 821-LT-N025 A'-1,B-1) g (B21-LTM-N024 A-1,B-1 and g

B21-LTM-N025 A-1,B-1) 8n W

1 9

g TABLE 3.3.2-1 (Continued) 5

$j ISOLATION ACTUATION INSTRUMENTATION h

O VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL g

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c) CONDITION

_ ACTION 4[

4.

CORE STANDBY C00LINC SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High 4

2 1,2,3 25 (E41-dPIS-N004 and E41-dPIS-N005) 2.

HPCI Steam Supply Pressure - Low 4

2 1, 2, 3 25 (E41-PSL-N001A,B,C.D) 3.

HPCI Steam Line Tunnel Temperature - High 4

2 1, 2, 3 25 ki (E41-TS-3314; E41-TS-3315; Y

E41-TS-3316; 5'

E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 4.

Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) 5.

HPCI Turbine Exhaust Diaphraga Pressure - High 4

2 1, 2, 3 25 g

(E41-PSH-N012A,B.C,D) 6.

HPCI Steam Line Ambient Temperature - High 4

2 1, 2, 3 25 (E51-TS-N603C,D) n u

7.

HPCI Steam Line Area A Temp. -

High 4

2 1, 2, 3 25 (E52-dTS-N604C, D) 8.

Emergency Area Cooler Temperature - High 4

2 1, 2, 3 25 (E41-TS-N602A,B)

TABLE 3.3.2-1 (Continued)

!E ISOLATION ACTUATION INSTRUMENTATION 2

H VALVE CROUPS MINIMUM NUMBER APPLICABLE.

b OPERATED BY OPERABLE CHANNELS OPERATIONAL I

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c) CONDLTION ACTION Oy b.

Reactor Core Isolation Cooling System Isolation N

1.

RCIC Steam Line Flow - High 5

2 1,2,3 25 (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply Pressure - Low 5

2 1, 2, 3 25 (E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel Temperature

- Itigli 5

2 1, 2, 3 25 (E51-TS-3319; E51-TS-3320; E51-TS-3321; g

}

E51-TS-3322; E51-TS-3323; 9

4 E51-TS-3355; p

E51-TS-3487) 4.

Bus Power Monitor NA (h) 1/ bus 1, 2, 3 26 (E51-K42 and E51-K43) 5.

RCIC Turbine Exhaust Diaphragm Pressure - High 5

2 l',

2, 3 25 (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temp -

liigh 5

2 1,2,3 25 (E51-TS-N603A,B) is g

7.

RCIC Steam Line Area A Temp - High 5

2 1, 2, 3 25 g

(E51-dTS-N604A,B) h 8.

RCIC Equipment Room Ambient Temp - liigh 5

2 1, 2, 3 25

,o (E51-TS-N602A,B) 9.

RCIC Equipment Room A Temp - liigh 5

2 1,2,3 25 (E51-dTS-N601A,B)

6 j@

TABLE 3.3.2-1 (Continued)

E$

ISOLATION ACTUATION INSTRUMENTATION f4 b

VALVE GROUPS HINIMUM NUMBER APPLICABLE 8

OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION N

5.

SilUTDOWN COOLING SYSTEM ISOLATION n

a.

Low, Level 1 2,6,8 2

1, 2, 3 27 (B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1) b.

Reactor Steam Dome Pressure-8 1

1, 2, 3 27 l

High (B32-PS-N018A,B)

R C

4 ~

y g

~ -

R 8n.

s S-4*

b

.-m e

d

^

b; ', $;

s TABLE 3.3.2-2 E!

y ISOLATION ACTUATION INSTRUMENTATION SETPOINTS Rn ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE G

1.

PRIMARY CONTAINMENT ISOLATION p

a.

1.

Low, Level 1

-> + 162.5 inches *

> + 162.5 inclees*

(B21-LTM-N017A-1,B-1,C-1,D-1) 2.

Low, Level 2

> + 112 inches *

( B21-LTM-N024 A-1, B-1 and B21-LTM-N025A-1,B-1) b.

Drywell Pressure - liigh

< 2 psig i 2 psig

( C72-PS-N002 A, B,C, D) c.

Main Steam Line y

1.

Radiation - Iligh 1 3 x full power background

< 3.5 x full power C

( D12-RM-K603 A, B, C, D) background 2.

Pressure - low

> 825 psig

-> 825 psig (B21-PTM-N015A-1,B-1,C-1,D-1) l 3.

Flow - liigh

< 140% of rated flow

< 140% of rated flow (B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1) 4.

Flow - liigh

< 40% of rated flow

< 40% of rated flow g

( B21-PDTS-N006 A-2 ;

B21-PDTS-N0078-2 ;

Q-B21-PDTS-N008C-2; B21-PDTS-N009D-2)

L

.if

g TABLE 3.3.2-2 (Continued)

EW ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 04 b

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 5y d.

Main Steam Line Tunnel Temperature - liigh

< 200*F

< 200*F s,

( B 21-TS-N010 A, B,C, D; B21-TS-N0ll A,B,C,D; B21-TS N012 A,B,C,D; B 21-TS -N013 A, B,C, D) c.

Condenser Vacuum - Low

> 7 inches Hg vacuum

~~> 7 inches lig vacuum

~~

( B21-PS -N056 A, B, C, D) f.

Turbine Building Area Temp - liigh

"~< 200*F

< 200*F

( B21-TS-3225 A, B, C, D;

~~

t*

B21-TS-3226 A,B,C D; 8'

B21-TS -3227 A, B,C, D; y2 B21-TS -3228 A, B,C, D; B21-TS-3229 A, B,C, D; B21-TS -3230 A, B, C, D; B21-TS-3231 A, B,C, D; B 21-TS -3232 A, B, C, D) 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - 111gh

-< 11 mr/hr

< 11 mr/hr

( D12-RM-N010A, B)

~

g b.

Drywell Pressure - liigh j[2psig

C 2 psig g

( C72-PS-N002 A, B, C, D) h c.

g Low, Level 2

> + 112 inches *

(B21-LTM-N024 A-1,B-1 and

,o B21-LTM-N025 A-1, B-1)

I

m TABLE 3.3.2-2 (Continued) g ISOLATION ACTUATION IRSTRUMENTATION SETPOINTS 5

F:

ALLOWABLE I

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE Oy 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION 4J a.

A Flow - liigh j[ 53 gal / min

( 53 gal / min (C31-d FS -N603-1 A, lB) b.

Area Temperature - liigh

< 150*F

( G31-TS-N600A, B, C, D, E, F) c.

Area Ventilation Temperature A Temp - liigh'

~-< 50*F

< 50*F

( G31-TS-N602 A, B, C, D, E, F) d.

S LCS Initiation NA NA (C41 A-S I) 20 e.

Low, Level 2

> + 112 inches *

> + 112 inches

w b

(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1, B-1) 4.

CORE STANDBY COOLING SYSTEMS ISOLATION a.

liigh Pressure Coolant Injection System Isolation l

1.

IIPCI Steam Line Flow - High

< 300% of rated 510w

< 300% of rated flow (E41-dPIS-N004 and E41-dPLS-N005) 2.

IIPCI Steam Supply Pressure - Low

__ 100 psig

>_100 psig (E41-PS L-N001 A, B, C, D)

N g

3.

IIPCI Steam Line Tunnel Temperature - liigh

< 200*F

< 200*F g.

(E41-TS-3314 ;

ej E41-TS-3315; E41-TS-3316; n

g:

E41-TS-3317 ;

E41-TS-3318; E41-TS-3354 ;

E41-TS-3488; E41-TS-3489) t

e, TABLE 3.3.2-2 (continued) m5 C;

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS ny, ALLOWABLE i

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 4.

Bus Power Monitor NA NA H

(E41-K55 and E41-K56) tO 5.

HPCI Turbine Exhaust Diaphragm Pressure - liigh

{ 10 psig j( 10 psig

( E41-PSil-N012A,B,C, D) 6.

IIPCI Steam Line Ambient Temp - liigh

< 200*F

< 200*F (E51-TS-N603C,D) 7.

IIPCI Steam Line Area A Temp - liigh

-< 50*F

< 50*F (E51-dTS-N604C,D)

~

h 8.

Emergency Area Cooler Temp - liigh j[175'F j[175*F (E41-TS-N602A,B) w d

O b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High

-~< 300% of rated flow

< 300% of rated flow (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply Pressure - Low

> 50 psig

__ 50 psig (E51-PS-N019A,B,C, D) 3.

RCIC Steam Line Tunnel Temp - liigh

_< 175'F

< 175'F (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; j

E51-TS-3323; R.

E51-TS-3355; 2

E51-TS-3487) a" 4.

Bus Power Monitor NA NA y

(E51-K42 and E51-K43) 9 k

r-TABLE 3.3.2-2 (Continued)

U ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E

ALLOWABLE TRIP FUt1CTION AtJD INSTRUMENT NUMBER TRIP SETPOIfR VALUE E

5 RCIC Turbine Exhaust Diaphragm e4 Pressure - liigh

< 10 psig

< 10 psig (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temp - liigh

< 200*F

< 200*F (E51-TS-N603A,B) 7.

RCIC Steam Line Area A Temp - Iligh

<5b*F

< 50*F (E51-dTS-N604A,B) 8.

RCIC Equipment Room Ambient Temp - Iligh

~< 175*F

< 17 5 *F (E51-TS-N602A,B)

M 9.

RCIC Equipment Room A Temp - Iligh

< 50*F

< 50*F (E51-dTS-N601A,B)

O 5.

SitUTDotlN COOLING SYSTEM ISOLATION a.

Low, Level 1

> + 162.5 inches *

(H21-LTM-N017A-1,B-1,C-1,D-1)

~

b.

Reactor Steam Dome Pressure - liigh

< 140 psig

< 140 psig (B32-PS-N018A,B)

U

!1-a rv

$?

Vessel water levels refer to REFERENCE LEVEL ZERO.

TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l

TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSETIME(Seconds)#l 1.

PRIMARY CONTAINMENT ISOLATION a.

1.

Low, Level 1 fl3 (B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1) 2.

Low, Level 2

<1.0**

(B21-LT-N024A-1,B-1 and

"~

B21-LT-N025A-1,B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) b.

Drywell Pressure - High

<13 (C72-PS-N002A,B,C,D) c.

Main Steam Line

<1.0**

1.

Radiation - High*

~~

(D12-RM-K603.A,B,C, D) 2.

Pressure - Low

<13 (B21-PT-N015A,B,C,D)

~~

(B21-PTM-N015A-1,B-1,C-1,D-1) 3.

Flow - High

<0.5**

(B21-PDT-NOO6A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-N008A,3,C,D; l

B21-PDT-N009A,B,C,D)

(B21-PDTM-N006A-1,B-1,C-1, D-1 ;

B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1) 4.

Flow - High f,0.5**

(B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N008C-2; B21-PDTS-N0097-2) d.

Main Steam Line Tunnel Temperature - High fl3 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low

<l3 (B21-PS-N056A,B,C,D) 4 BRUNSWICK-UNIT 2 3/4 3-22 Amendment No.

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

{

TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSETIME(Seconds)#l f.

Turbine Building Area Temperature - Righ NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High*

413 a.

(D12-RM-N010A,B) b.

Drywell Pressure - High

<13 (C72-PS-N002A,B,C,D) c.

Reactor Vessel Water Level - Low, Level 2

<1.0**

(B21-LT-N024A-1,B-1 and

~~

B21-LT-N025A-1,B-1)

(B21-LIM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High

<13 (G31-dFS-N603-1A,1B)

"~

b.

Area Temperature - High

(13 (G31-TS-N600A,B,C,D,E,F) c.

Area Ventilation Temperature aT - Righ

<13 (G31-TS-N602A,B,C,D,E,F)

~~

d.

SLCS Initiation NA (C41A-S1)

Reactor Vessel Water Level - Low, Level 2

""<1.0**

e.

(B21-LT-N024 A-1,B-1 and B21-LT-N025 A-1,B-1)

(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1) l l

BRUNSWICK - UNIT 2 3/4 2-23 Amendment No.

l

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRU"ENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

l 4.

CORE STANDBY COOLING SYSTEMS ISOLATION High Pressure Coolant Injection System Isolation l

a.

1._

HPCI Steam Line Flow - High

< 13 (E41-dPIS-N004 and

~~

E41-dPIS-N005) 2.

HPCI Steam Supply Pressure - Low

{13 (E41-PSL-N001A,B,C,D) 3.

HPCI Steam Line Tunnel Temperature - High f13 (E41-TS-3314; E41-TS-3315 ;

E41-IS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 4.

Bus Power Monitor NA (E41-K55 and E41-K56) 5.

HPCI Turbine Exhaust Diaphragm Pressure - High-NA (E41-PSH-N012A,B,C,D) 6.

HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D) 7.

HPCI Steam Line Area NA (E51-dTS-N604C.D) 8.

Emergency Area Cooler Temperature - High NA (E41-TS-602A,B) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High NA (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4 Bus Power Monitor NA (E51-K42 and E51-K43)

BRUNSWICK - UNIT 2 3/4 3-24 Amendment No.

l 1

4 TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM -IETRUMENTATION RES PONSE TIME l

TRIP FUNCTION AND INSTRUMENT NUMBER -

RESPONSE TIME (Seconds)#

l 5.

RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B) 7.

RCIC Steam Line Area A Temp - High NA (E51-dTS-N604A,B) 8.

Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B) 9.

RCIC Equipment Room A Temp - High.

NA (E51-dTS-N601 A,B) 5.

SHUTDOWN COOLING SYSTEM-ISOLATION Reactor Vessel Water IAvel - 14w, Iavel 1 NA a.

(B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1 B-1,C-1,D-1) b.

Reactor Steam Dome Pressure - High NA (B32-PS-N018 A,B) 1 i

4 i

Radiation monitors are exempt from response time testing. Response time shall be measured from detector output or the input of the first electronic component in the channel.

- Isolation actuation instrumentation response time only.

2

Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

BRUNSWICK - UNIT 2 3/4 3-24A Amendment No.

m

---.m

.--w

,.-3.

_,__4

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

TABLE 4. 3. 2-1 ISOLATION ACTUATION INSTRUMEfffATION SURVEILLANCE REQUIREMENTS QlANNEL OPERATIONAL Q

QIANNEL FUNCTIONAL QIANNEL CONDITIONS IN WitIQi TRIP FUNCTION AND INSTRUMEfff NUMBER GIECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.

PRIt:ARY _ODNfAINMEfff ISOLATION a

o a.

1.

Low, Level 1

( 821 -LT-N017A-1, B-1, C-1, D-1)

NA NA R

1, 2, 3 (B21-LTM-N017A-1 B-1,C-1.D-1)

D M

M 1, 2, 3 2.

Low, Level 2

( B21-LT-N024A-1, B-1 and B21-LT-N025A-1,B-1)

NA(a)

NA R(b) 1, 2, 3 (B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1)

D H

H 1, 2, 3 6'

b.

Drywell Pressure - liigh NA M

Q 1, 2, 3 Y'

( C72-PS-N002A, B, C.D) w" c.

Radiation - liigh D

W R

1, 2, 3

( D12-RM-K603 A, B, C, D) 2.

Pressure - Low

( B21-PT-N015A, B, C,D)

NA(a)

NA R(b) 3 (B21-PTM-N015A-1,B-1,C-1,D-1)

D M

M 1

3.

Flow - liigh

( B21-P DT-N006 A, B, C,D; NA(")

NA R(b) 3 B21-Plyf-N007A,B,C D; p

B21-P DT-N008 A, B, C,D ;

2 B21-PDT-N009A,B,C,D)

( B21-PlyfM-N006 A-1, B-1, 0-1, D-1 ;

D H

M 1

B21-PDTM-N007A-1,B-1 C-1.D-1;

[*

B21-P DTM-N008A-1, B-1, C-1, D-1 ;

,o B21-PDTM-N009A-1,B-1.C-1,D-1)

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS a

n QlANNEL OPERATIONAL OIANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilIQI TRIP FUNCTION AND INSTRUME!Pr NUMBER OlECK TEST CALIBRATION SURVEILLANCE REQUIRED 5

4 4.

Flow - liigh D

M M

2, 3

( B21-PDTS-N006A-2 ;

ra B21-PDTS-N007B-2; B21-P DTS-N008 C-2 ;

B21-PDTS-N009D-2) d.

Main Steam Line Tunnel Temperature - liigh NA M

R 1, 2, 3

( B21 -T S-N010A, B, C, D; B21-T S-N0 l l A, B, C,D ;

B21-T S-N012 A, B, C, D; B21-T S-N013A, B, C,D) e.

Condenser Vacuum - Low NA M

R 1, 2#

Y (B21-PS-N056A,B,C,D) f.

Turbine Building Area Temp-liigh NA M

R 1, 2, 3

( B 21-T S-3225 A, B, C, D; B21-T S-3226A, B, C,D; B 21-T S-3227 A, B, C, D; B21-T S-3228A, B, C,D; B 21-T S-3229A, B, C, D; B21-TS-3230A,B,C D; B21-T S-3231 A, B, C, D; B21-T S-3232A, B, C,D) 2.

SECONDARY CONTAINMENE ISOLATION g

a.

Reactor Building Exhaust Radiation - liigh D

M R

1,2,3,5, and *

(D12-RM-N010A,B) n

.O

TABLE 4.3.2-1 (Qmtinued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c-N OlANNEL OPERKTIONAL O

QIANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilIQI TRIP FUNCTION AND INSTRUMENT NUMBER GlECK TEST CALIBRATION SURVEILLANCE REQUIRED 54 b.

Drywell Pressure - High NA M

Q 1, 2, 3

( C72-P S-N002A, B, C,D) c.

Lov, Level 2 (B21-LT-N024 A-1,B-1 and NA(")

NA R(b) 1, 2, 3 B21-LT-N025 A-1,B-1)

(B21-LTM-N024 A-1,B-1 and D

M M

1, 2, 3 B21-LTM-N025 A-1,B-1) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION M

a.

A Flow - liigh D

M R

1, 2, 3 (G31-d FS-N603-1 A,lB) u b

b.

Area Temperature - liigh NA M

R 1, 2, 3

( C31-T S-N600A, B, C.D. E, F) l c.

Area Ventilation A Temp - High NA M

R 1, 2, 3 (C31-TS-N602A,B,C,D E,F) d.

SLCS Initiation NA R

NA 1, 2, 3 (C41 A-SI) e.

Low, Level 2 (B21-LT-N024 A-1,B-1 and NA(a)

NA R(b) 1, 2, 3 B21-LT-N025 A-1,B-1)

N (B21-LTM-N024 A-1,B-1 and D

M M

1, 2, 3 m

h B21-LTM-N025 A-1,B-1)

$n

.b

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSIRUMENTATION SURVEILLANCE REQUIREMENTS G

S QIANNEL OPERATIONAL-9 CHANNEL FUNCTIONAL CRANNEL 00NDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED c

N 4.

Q)RE STANDBY COOLING SYSTEMS ISOLATION H

a.

liigh Pressure Coolant Injection System Isolation l

1.

IIPCI Steam Line Flow - High D

M Q

1, 2, 3 (E41-dPIS-N004 and E41-dPIS-N005) 2.

HPCI Steam Supply Pressure -

Low NA M

R 1, 2, 3 (E41-PSL-N001A,B,C,D) ca 3.

liPCI Steam Line Tunnel 2:

Temperature - High NA M

Q 1,. 2, 3

( E41-TS-3314; c2 da E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3388; E41-TS-3489) 4.

Bus Power Manitor NA R

NA 1, 2, 3 (E41-K55 and E41-K56) q J

5.

HPCI Turbine Exhaust p.

Diaphragm Pressure - High NA M

Q 1, 2, 3 d

( E41-PSll-N012A, B, C, D) 6.

IIPCI Steam Line Ambient Temp - liigh NA M

R 1, 2, 3

( E51-TS-N603C,D) u 7.

IIPCI Steam Line Area A Temp - liigh NA N

R 1, 2, 3 (E51-dTS-N604C D)

4 i

TABLE 4.3.2-1 (Continued)

E U

ISOLATION ACTUATION INSTRUMEKrATION SURVEILLANCE REQUIREMENTS CllANNEL OPERATIONAL t

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICil E

TRIP FUNCTION AND INSTRUMEMr NUMBER OIECK.

TEST CALIBRATION SURVEILLANCE REQUIRED G

w 8.

Emergency Area Cooler Temp - liigh NA M

Q 1, 2, 3 (E41-TS-N602A,B) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High NA M

Q 1, 2, 3 (E51-dPIS-N017 and E51-dPIS-N018) 2.

RCIC Steam Supply t'

Pressure - Low NA M

Q 1, 2, 3 (E51-PS-N019A,B,C,D) 3.

RCIC Steam Line Tunnel liigh Temperature NA M

R 1, 2, 3 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4.

Bus Power Monitor NA R

NA 1, 2, 3 (E51-K42 and E51-K43) f 5.

RCIC Turbine Exhaust l

g.

Diaphragm Pressure - liigh NA M

R 1, 2, 3 (E51-PS-N012A,B,C,D) m S

i.f

TABLE 4.3.2-1 (Q)ntinued)

E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

^QlANNEL OPERATIONAL H

b OIANNEL F11NCTIONAL QIANNEL CONDITIONS IN WilIQI 8

TRIP FUNCTION AND INSTRUMENT NUMBER GlECK TEST CALIBRATION SURVEILLANCE REQUIRED G

h 6.

RCIC Steam Line Ambient Temp - liigh NA M

R 1, 2, 3 g

( E51-TS-N603 A, B) 7.

RCIC Steam Line Area a Temp - Iligh NA M

R 1, 2, 3 (E51-dT S-N604A, B) 8.

RCIC Equipment Room Ambient Temp - liigh NA M

Q 1, 2, 3

( E51-TS-N602A, B) 9.

RCIC Equipment Ro im A uy Temp - Iligh NA M

Q 1, 2, 3 (E51-dTS-N601A,B) g 5.

SliUTDOWN C00LINC SYSTEM ISOLATION a.

Low, Imvel 1 (B21-LT-N017A-1,B-1,C-1,D-1)

NA(8)

NA R(b) 3, 2, 3

( B 21-LTM-N017A-1, B-1, C-1, D-1)

D M

M 1, 2, 3 b.

Reactor Steam Dome Pressure -

liigh NA S/U(c),M R

1, 2, 3 (B32-PS-N018A,B) fi g

When handling irradiated fuel in the secondary containment.

g-

When any turbine stop valve is open.

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

A separate transmitter check is not required.

l n

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

(c) If not performed within the previous 31 days.

TABLE 3.3.3-1 E

En EMERGENCY Q)RE Q)0 LING SYSTEM ACTUATION INSTRUMENTATION M

n 7:

HINIMUM NUMBER APPLICABLE OPERABLE QlANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER O

PER TRIP SYSTEM CONDITIONS ACT ION U

1.

Q)RE SPRAY SYSTEM Reactor Vessel Water level - Low, Level 3 2

1,2,3,4,5 30 a.

( B21-L.T-NO31 A, B, C, D)

( B21-LTS-NO31 A-4, B-4, C-4, D-4) b.

Reactor Steam Dome Pressure - Low (Injection Permissive) 2 1,2,3,4,5 31 (B21-PT-N021 A,B C,D)

( B21-PT S-N021 A-2, B-2, 0-2, D-2) c.

Drywell Pressure - liigh 2

1,2,3 30

( E l l-PS-N011 A, B, C, D)

Ei d.

Time Delay Relay 1

1,2,3,4,5 31

( E21-K16 A, B) l e.

Bus Power Honitorf 1/ bus 1,2,3,4,5 32 (E21-KIA,B) 2.

LPCI NODS OF RifR SYSTEM a.

Drywell Pressure - Iligh 2

1,2,3 30

( El l-PS-N0 l l A, B, C, D) b.

Reactor Vessel Water Level - Low, Level 3 2

1, 2, 3, 4*, 5*

30

( B21-Ur-NO 31 A, B, C, D)

( B21-LTS-NO31 A-4, B-4,0-4. D-4)

Reactor Vessel Shroud IAvel (Drywell Spray Permissive) 1 y

c.

h (B21-Ur-NO36 and B21-LT-N037) 1, 2, 3, 4*, 5*

31 y.

(B21-LTM-NO36-1 and B21-LTM-NO37-1) d.

Reactor Steam Dome Pressure - Low (Injection Permissive)

[,'

( B21-PT-N021 A, B, C, D)

( B21-PTM-N021 A-1, B-1,0-1, D-1)

( B21-PT S-N021 A-2, B-2, 0-2, D-2) 1.

RIIR Pump Start and LPCI Injection Valve Actuation 2

1, 2, 3, 4*, 5*

31 2.

Recirculation Loop Pump Discharge Valve Actuation 2

1, 2, 3, 4*, 5*

31

pl TABLE 3.3.3-1 (Continued)

E!

E3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION hnW MINIMUM NUMBER APPLICABLE 8

OPERABLE CHANNELS OPERATIONAL

[j TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION O

e.

RilR Pump Start - Time Delay Relay 1

1, 2, 3, 4*, 5*

31 y

(STR-2A1,2 and STR-281,2) f.

Bus Power Monitori 1/ bus 1, 2, 3, 4*, 5*

32 (Ell-K106A,B) 3.

IIPCI SYSTEM a.

Reactor Vessel Water Level - Low, Level 2 2

1, 2, 3 30 (H21-LT-NO31A,B,C,D) ti (B21-LTS-NO31A-2,B-2,C-2,D-2) b.

Drywell Pressure - High 2

1,2,3 30 d,

(Ell-PS-N0llA,B,C,D) w c.

Condensate Storage Tank Level - Low 2**

1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.

Suppression Chamber Water Level - High 2**

1, 2, 3 33 (E41-LSil-N015A,B) e.

Bus Power Monitor #

1/ bus 1, 2, 3 32 (E41-K55 and E41-K56) 4.

ADS g

a.

Drywell Pressure - liigh, coincideat with 2

1, 2, 3 30 g

(Ell-PS-N010A,B,C,D) h b.

Reactor Vessel Water Level - Low, Level 3 2

1, 2, 3 30 g

(B21-LT-NO31A,B,C,D)

(B21-LTS-NO31A-3,B-3,C-3,D-3) 4

TABLE 3.3.3-1 (Continued) g G

C; EMERCENCY CORE COOLINC SYSTEM ACTUATION INSTRUMENTATION n

Q MINIMUM NUMBER APPLICABLE OPERABLE CHANNELS OPERATIONAL g

TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION n

H c.

Reactor Vessel Water Level - Low, Level 1 1

1,2,3 30 (B21-LT-NO42A,B)

(B21-LTM-N042A-1,B-1) d.

ADS Timer 1

1, 2, 3 31 (B21-TDPU-K5A,B) e.

Core Spray Pump Discharge Pressure - Iligh (Permissive) 2 1, 2, 3 31 (E21-PS-N008A,B and E21-PS-N009A,B) f.

RIIR (LPCI MODE) Pump Discharge Pressure - liigh (Permissive) 2/ pump 1, 2, 3 31 (E11-PS-N016A,B,C,D and Ell-PS-N020A,B,C,D)

~

u, 3

Bus Power Monitor #

1/ bus 1, 2, 3 32 2:

(B21-KlA,B) u, d,

APPLICABLE

'g TOTAL NO.

CilANNELS MINIMUM CllANNELS OPERATIONAL FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE CONDITIONS ACTION 5.

LOSS OF POlIER a.

4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5##

34 Undervoltage (Loss of Voltage)

Ilndervoltage (Degraded 2/ bus 2/ bus 1,2,3,4##,5##

b.

4.16 kv Emergency Bus 3/ bus 35 Voltage)

B"

No t applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.

- Provides signal to llPCI pump suction valves only.

Alarm only.

1. Required when ESP equipment is required to be OPERABLE.

as TABLE 3.3.3-2 8

d D'ERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOIffrS 5

S ALLOWABLE e

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 54 1.

CORE SPRAY SYSTEM e-i u

a.

Reactor Vessel Water Imvel - Iow, Level 3

~> + 2.5 inches *

( B 21-LTS-NO31 A-4, B-4, C-4, D-4) b.

Reactor Steam Dome Pressure - Low 410 + 15 psig 410 + 15 psig

( B21-PTS-NO 21 A-2, B-2, C-2, D-2)

~

l c.

Drywell Pressure - High

< 2 psig i 2 psig (Ell-PS-N0ll A,B,C,D) d.

Time Delay-Relay 14 < t < 16 secs 14 < t < 16 secs (E21-K16 A,B)

~ ~

l M

e.

Bus Power tbnitor NA NA (E21-KIA,B)

Y Z

2.

LPCI HODE OF RHR SYSTEM a.

Drywell Pressure - High 1 2 psig i 2 psig

( E l l-PS-N0 l l A, B, C, D) b.

Reactor Vessel Water Level - low, Level 3

-> + 2.5 inches *

~~> + 2.5 inches *

( B21-LTS-NO31 A-4,B-4,C-4,D-4) c.

Reactor Vessel Shroud Level

-> - 53 inches *

~> - 53 inches *

(B21-LT!!-NO36-1 and B21-LTM-NO37-1) d.

Reactor Steam Dome Pressure - Low g

l 1.

RHR Pump Start and LCPI Valve

[i Actuation 410 + 15 psig

~

l

( B21-PTS-N021 A-2, B-2, C-2, D-2)'

~

410 + 15 psig

4 2.

Recirculation Pump Discharge Valve Actuation

'310 t 15 psig 310 t 15 psig (B21-PTM-N021A-1,B-1,C-1,D-1) l

o, TABLE 3.3.3-2 (Continued)

G EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

=

s Q

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE 9

b; e.

RHR Pump Start - Time Delay Relay 9<t < 11 seconds 9<t< 11 seccnds H

(STR-2Al,2 and STR-2BI,2) f.

Bus Power Monitor NA NA (E l l-K106A, B) 3.

IIPCI SYSTEM a.

Reactor Vessel Water Level - Low, Level 2

};+ 112 inches *

(B21-LTS-NO31 A-2, B-2, C-2, D-2) b.

Drywell Pressure - liigh

< 2 psig

< 2 psig (Ell-PS-N0llA,B,C,D) c.

Condensate Storage Tank Level - Low j; 23 feet 4 inches

};23 feet 4 inches l

(E41-LS-N002; E41-LS-N003)

U' d.

Suppression Chamber Water Level - Iligh

< -2 feet **

j( -2 feet **

l (E41-LSil-N015A,B) e.

Bus Power Monitor NA NA (E41-K55 and E41-K56) 4.

ADS a.

Drywell Pressure-liigh

< 2 psig

< 2 psig (Ell-PS-N010A,B,C,D) b.

Reactor Vessel Water Level - Low, Level 3 k

(821-LTS-NO31A-3,B-3,C-3,D-3)

""> + 2.5 inches *

> + 2.5 inches *

~~

m D

c.

Reactor Vessel Water lavel - Low, level 1

> + 162.5 inches

h

( B 21-LT!!-N04 2 A-1, B-1)

> + 162.5 inches

u" d.

ADS Timer

f (B21-TDPU-K5A,B)

< 120 seconds

< 120 seconds g

TABLE 3.3.3-2 (Continued)

N E!

EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E

R ALLOWABLE W

TRIP FilNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE l

E!

Core Spray Pump Discharge Pressure - liigh

}_100 psig 2 100 psig e.

y (E21-PS-N008A,B and E21-PS-N009A,B) o f.

RIIR (LPCI MODE) Pump Discharge Pressure - liigh

)_100 psig

> 100 psig (Ell-PS-N016A,B,C,D and Ell-PS-N020A,B,C,D) g.

Bus Power Monitor NA NA (B21-KIA,B)

E' 5.

LOSS OF POWER n

I' a.

4.16 kv Emergency Bus Undervoltage a.

4.16 kv Basis - 2940 t 161 volts 2940 t 315 volts M

(Loss of Voltage)G b.

120 v Basis - 84

4.6 volts 84 i 9 volts c.

j[ 10 sec. time delay j( 10 sec. time delay b.

4.16 kv Emergency Bus Undervoltage a.

4.16 kv Basis - 3727

9 volts 3727 t 21 volts (Degraded Voltage) b.

120 v Basis - 106.5 i 0.25 volts 106.5 i 0.60 volts 10 t 0.5 sec. time delay 10 t 1.0 sec. time delay c.

U B

ft 8"

This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result y

in a trip.

tower voltage conditions will result in decreased trip times.

Vessel water levels refer to REFERENCE LEVEL ZERO.

- Suppression chamber water level zero is the torus centerline minus 1 inch.

TABLE 4.3.3-1 ss EMERGENCY Q)RE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEffrS 4o M

QlANNEL OPERATIONAL I

QIANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQI g

TRIP FUNCTION AND INSTRUMENT NUMBER OIECK TEST CALIBRATION SURVEILLANCE REQUIRED U

1. CORE SPRAY SYSTEM g

a.

Reactor Vessel Water 14 vel -

Low, Level 3 I

NA ")

NA R(b) 1,2,3,4,5 (B21-LT-NO31 A, B C.D)

( B21-LTS-NO31 A-4, B-4, C-4, D-4)

D M

M 1,2,3,4,5 b.

Reactor Steam Dome Pressure - Low

( B21-PT-N021 A, B, C,D)

NA(a)

NA Id )

1,2,3,4,5 (B21-PTS-N021A-2,B-2,C-2,D-2)

D M

M 1,2,3,4,5 c.

Drywell Pressure - liigh NA M

Q 1, 2, 3

( El l-PS-N0l l A, B, C. D) d.

Time Delay Relay NA R

R 1,2,3,4,5 w

d, (E21-K16A,B) l 9

e.

Bus Power }bnitor NA R

NA 1,2,3,4,5 (E21-KIA,B)

2. LPCI MODE OF RilR SYSTEM a.

Drywell Pressure - liigh NA M

Q 1, 2, 3

( E l l-PS-N0 l l A, B, C, D) b.

Low, Level 3 (B21-LT-NO31A,B,C D)

NA(a)

NA R(b) 1, 2, 3, 4*, 5*

k

( B21-LTS-NO 31 A-4, B-4, C-4, D-4)

D M

M 1, 2, 3, 4*, 5*

S c.

Reactor Vessel Shroud Level h

(B21-LT-NO36 and B21-LT-NO37)

NA(d )

NA R(b) 1, 2, 3, 4*, 5*

(B21-LTM-N036-1 and B21-LTM-NO37-1) D M

M 1, 2, 3, 4*, 5*

n

.If

.. =

TABLE 4.3.3-1 (Continued) as m5 0;

EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

Q CllANNEL OPERATIONAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH g TRIP FUNCTION AND INSTRUMdMT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED d.

Reactor Steam Dome Pressure - Low NA(a)

NA R(b) 1, 2, 3, 4*, 5*

( B 21-PT-N021 A, B, C, D) l 1.

RilR Pump Start and LPCI Injection Valve Actuation D

M M

1, 2, 3, 4*,

5*

(B21-PTS-N021A-2,B-2,C-2,D-2)

I 2.

Recirculation Loop Pump Discharge Valve Actuation D

M M

1, 2, 3, 4*,

5*

( B21-PT!!-NO21 A-1, B-1, C-1, D-1) e.

RilR Pump Start - Time Delay Relay NA R

R 1, 2, 3, 4*,

5*

(STR-2Al 2 and u,

2:

STR-2B1,2) y' f.

Bus Power Monitor NA R

NA 1, 2, 3, 4*,

5*

g (Ell-K106A,B)

3. IIPCI SYSTEM a.

Low, Iavel 2 (B21-LT-NO31A,B,C,D)

NA(a)

NA R(b) 1, 2, 3 (821-LTS-NO31A-2,B-2,C-2,D-2)

-D M

M 1, 2, 3 b.

Drywell Pressure - liigh NA M

Q 1, 2, 3 (Ell-PS-N0llA,B,C,D) g c.

Condensate Storage Tank Icvel - Low NA M

Q 1, 2,'

3 (E41-LS-N002; E41-LS-N003) k d.

Suppression Chamber Water Level - liigh NA N

Q 1, 2, 3 3

(E41-LSil-N015A, B) y e.

Bus Power Monitor NA R

NA 1, 2, 3 (E41-K55 and E41-K56)

w TABLE 4.3.3-1 (Continued)

n h

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVF.ILLANCE REQUIREMENTS s:

h CilANNEL OPERATIONAL CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICH TRIP FUNCTION AND INSTRUMENT NUMBER CliECK TEST CALIBRATION SURVEILLANCE REQUIRED E

N

4. ADS a.

Drywell Pressure - liigh NA H

Q 1, 2, 3 (Ell-PS-N010A,B,C,D) b.

Reactor Vessel Water Level 2

I.ow, level 3 (821-LT-NO31A,B,C,D)

NA(a)

NA R(b) 1, 2, 3 (B21-LTS-NO31A-3,B-3,C-3,D-3)

D M

M 1, 2, 3 c.

Reactor Vessel Water Izvel -

Low, Level !

y (B21-LT-N042A,B)

NA(a)

NA R(b) 1, 2, 3

( B21-LTti-N04 2 A-1, B-1)

D M

M 1, 2, 3

[,

d.

ADS Timer NA R

R 1, 2, 3 g

(821-TDPU-K5A,B) e.

Core Spray Pump Discharge Pressure - liigh NA M

Q 1, 2, 3 (E21-PS-N008A,B and E21-PS-N009A,B) f.

RilR (LPCI MODE) Ptuap Discharge Pressure - liigh NA M

Q 1, 2, 3 (Ell-PS-N016A,B,C,D and E 11-PS-t!O20A, B,C, D) k g.

Bus Power Monitor NA R

NA

'1, 2, 3 g

(B21-KIA,B)

R R

E.

y TABLE 4.3.3-1 (Continued)

Ey EMERGENCY CORE (DOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILIANCE REQUIREMENTS M

M

, CilANNEL OPERATIONAL 8

CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil TRIP FUNCfION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED G

5.

IDSS OF POWER y

a.

4.16 kv Emergency Bus NA NA R

1, 2, 3, 4*, 5*

Undervoltage (Loss of Voltage) b.

4.16 kv Emergency Bus S

M R

1, 2, 3, 4*, 5*

Undervoltage (Degraded Voltage)

M s~

Yg

Required when ESF equipment is required to be OPERABLE.

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

A separate transmitter check is not required.

(b) Transmitters are exempted f rom the monthly channel calibration, y

B 3n

TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.

Reactor Vessel Pressure 2

l (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.

(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 3.

Suppression Chamber. Water Level 2

l (CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3)

(CAC-LT-2602; CAC-LR-2602) l 4.' Suppression Chamber Water Temperature 2

l (CAC-1R-1258-14, 214 and C91-P602) 5.

Suppression Chamber Atmosphere Temperature 2

(CAC-TR-1258-17 thru 20; and C91-P602) 6.

Drywell Pressure 2

l (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.

Drywell Temperature 2

l (CAC-TR-1258-1 thru 13, 22, 23, 24; l

and C91-P602) 8.

Drywell Radiation 2

l (CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 9.

Drywell Oxygen 2

l 4

(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) 10.

Dryvell Hydrogen 2

(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) 11.

Safety Relief Valve Position Indication:

1/ valve Primary - Sonic (821-FY-4157 thru 4167) a.

b.

Secondary - Temp. (B21-TR-R614, points 1-11)

BRUNSWICK - UNIT 2 3/4 3-51 Amendment No.

~ -

Si TABLE 4.3.5.3-1 S

El POST-ACCIDENT MONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS c4nM CHANNEL CilANNEL I

INSTRUllENT AND IdSTRUMENT NUMBER CHECK CALIBRATION 5

h 1.

Reactor Vessel Pressure M

R l

(B21-PI-ROO4A,B; C32-LPR-R608; and C32-PT-N005A,B) n, 2.

Reactor Vessel Water Level M

R (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and'B21-LTM-NO37-1) r 3.

Suppression Chamber Water 14 vel M

R l

(CAC-LT-2601; CAC-LY-2601-1; CAC-L1-2601-3; CAC-LT-2602; CAC-LR-2602) 4.

Suppression Chamber Water Temperature M

R l

(CAC-TR-1258-14, 21; and C91-P602) id 5.

Suppression Chamber Atmosphere Temperature M

R (CAC-TR-1258-17 thru 20; and C91-P602) u 6.

Drywell Pressure M

R l

b)

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.

Drywell Temperature M

R l

(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.

Drywell Radiation M

R j

(CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQll-1261-1,2,3; CAC-AR-1262; and CAC-AQti-1262-1,2,3) 9.

Drywell Oxygen Concentration

.M R

l (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) g 10.

Drywell liydrogen Concentration M

R (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) l h

11.

Safety Relief Valve Position Indication D

a.

Primary - Sonic (B21-FY-4157 thru 4167)

M R

b.

Secondary - Temp. (821-TR-R614, points 1-11)

M R

8

~

TABLE 3.3.6.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION M

7:

MINIMUM NUMBER OPERABLE TRIP TRIP FUNCTION AND INSTRUMENT NUMBER SYSTEMS PER OPERATING PUMP

1

),

l'

,o Low, Level 2 (B21-LT-N024A-2,B-2 and B21-LT-N025A-2,B-2)

(B21-LTM-N024A-2,B-2 and B21-LTM-N025A-2,B-2) 2.

Reactor Vessel ' Pressure - Ingh 1

(B21-PS-N045A,B,C,D)

D 4

'W

~~

r

=

~

s e

O w.

g 4(.

4 5

~

^

~

(

g x

v

~

s.F8' 4

4

'M

[

N

n v

4~

TABLE 3.3.6.1-2 en-

n Q

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOIffl3 en Nn M

TRIP ALLOWABLE I

TRIP FUNCTION AND INSTRUMENT NUMBER S ETPOIlfr VALUE E

p 1.

Reactor Vessel, Water level -

~

> + 112 inches

J_ + 112 inches

Low, Level 2 y

(B21-LTM-N024 A-2,B-2; B21rLTM-N025A-2,B-2)

~

2.

Reactor Vessel Pressure - High

-<t120 psig

-<1120 psig

( B 21-LS -N045 A, B,C. D)

M s.

Y

?

N 9

it a

rt E.

Vessel water levels refer to REFERENCE LEVEL ZERO.

f os TABLE 4.3.6.1-1

o huj ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o'-1 9

CHANNEL CilANNEL FUNCTIONAL CilANNEL TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION 5

P4 1.