Text

Proposed Tech Specs Relocating Footnote from Item 1.c.1 of Table 3.3.2-1 to Item 1.c.1 of Table 4.3.2-1 to Ensure That Required Surveillance Testing of Mechanical Vacuum Pumps Identified
	ML20137M023
Person / Time
Site:	Brunswick
Issue date:	11/25/1985
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20137M017	List: ML20137M012; ML20137M023;
References
	NLS-85-177, NUDOCS 8512030584
	Download: ML20137M023 (21)
	v • d • e

,

ENCLOSURE 1 TO NLS-85-177 PROPOSED TECliNICAL SPECIFICATION PAGES BRUNSWICK-1 MECilANICAL VACUUM PUMPS (85 TSB 15) 0512030584 851125 PDR ADOCK 05000324 p

P Dif (1512 mar /cce, 2

BRUNSWICK-1

SUMMARY

LIST OF REVISIONS PAGE NO.

DESCRIPTION OF CHANGE 3/4 3-11 Deleted footnote (d) from item 1.c.l.

3/4 3-12 Change footnote (e) to (d) and footnote (f) to (e).

3/4 3-13 Change footnote (g) to (f).

3/4 3-14 Change footnote (h) to (g).

3/4 3-15 Change footnote (h) to (g).

-3/4'3-16 Deleted footnote (d); re-letter remaining notes.

3/4 3-25 Add footnote (d) to item 1.c.l channel calibration.

3/4 3-29b Delete footnotes from bottom of page.

3/4 3-29c New page listing footnotes deleted from 3/4 3-29b plus add footnote (d)

" Testing shall verify that the mechanical vacuum pump trips and the mechanical vacuum pump line valve closes."

. m w r ::c.

)

es h

TABLE 3.3.2-1 (BSEP-1-62)

E g

ISOLATION ACTUATION INSTRUMENTATION 7:

8 VALVE CROUPS MINIMUM NUMBER APPLICABLE c:

OPERATED BY OPERABLE CHANNELS OPERATIONAL h

TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

Low, Level 1 2,6,7,8 2

1,2,3 20 (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, 3 2

1,2,3 20 (B21-LT-NO24A-1,B-1, and B21-LT-NO25A-1,B-1)

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

U b.

Drywell Pressure - High 2,6,7 2

1,2,3 20 y

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

[

(C71-PTM-N002A-1,B-1,C-1,D-1) c.

Main Steam Line l

1.

Radiation - High 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) y 3.

Flow - High 1

2/line 1

22 (B21-PDT-4006A,B,C,D; g

B21-PDT stO7A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D)

(B21-PDTM-NOO6A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-NOO8A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)

m e.

a, TAELE 3.3.2-1 (Continued)

(BSEP-1-62) c h

ISOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE Z

OPERATED BY OPERABLE CHANNELS OPERATIONAL U

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION PRIMARY CONTAINMENT ISOLATION (Continued) d.

Main Steam Line Tunnel i

Temperature - High 1

2(d) 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) 1, 2 * )

21 I

t3 e.

Condenser Vacuum - Low 1

2 (B21-PT-N056A,B,C,D) 8' y

(B21-PTM-N056A-1,B-1,C-1,D-1)

C f.

Turbine Building Area l

Temperature - High 1

4(d) 1, 2, 3 21 (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)

I, Q.

R E

F.

__J

os TABLE 3.3.2-1 (Continued)

(BSEP-1-62)'

E UI ISOLATION ACTUATION INSTRUMENTATION 5

O VALVE GROUPS MINIMUM NUMBER APPLICABLE I

OPERATED BY OPERABLE CHANNELS OPERATIONAL g

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

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

2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High 6

1 1, 2, 3, 5, and*

23 (D12-RM-N010A,B) b.

Drywell Pressure - High 2,6,7 2

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

(C71-PTM-N002A-1,B-1,C-1,D-1) c.

Reactor Vessel Water Level -

Low, Level 2 1, 3 2

1,2,3 23 t)

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

[,

(B21-LTM-N024A-1,B-1 and B21-LTM-NO25A-1,B-1)

')

3.

REACTOR WATER CLEAh'JP SYSTEM ISOLATION a.

A Flow - High 3

1 1,2,3 24 (C31-dFS-N603-1A,lB) b.

Area Temperature - High 3

2 1,2,3 24 (C31-TS-N600A,B,C,D,E,F) c.

Area Ventilation A Temp. - High 3

2 1,2,3 24 (C31-TS-N602A,B,C,D,E,F)

If) d.

SLCS Initiation 3

NA 1, 2, 3 24 g

(C41A-SI) k e.

Reactor Vessel Water Level -

Low, Level 2 1, 3 2

1,2,3 24 2

.o (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:

g TABLE 3.3.2-1 (Continued)

(BSEP-1-62) g ISOLATION ACTUATION INSTRUMENTATION

??

pq VALVE CROUPS MINIMUM NUMBER APPLICABLE M

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

PER TRIP SYSTEM (b)(c) CONDITION ACTION Ey 4.

LORE STANDBY COOLING SYSTEMS ISOLATION a.

liigh Pressure Coolant Injection System Isolation 1.

IIPCI Steam Line Flow - liigh 4

1 1,2,3 25 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-N004-2; E41-PDTS-N005-2) 2.

IIPCI Steam Line liigh Flow ki Time Delay Relay NA 1

1,2,3 25 (E41-TDR-K33; y

E41-TDR-K43)

E 3.

IIPCI Steam Supply Pressure - Lou 4

2 1,2,3 25 (E41-PSL-N001A,B,C,D) 4.

IIPCI Steam Line Tunnel Temperature - liigh 4

2 1,2,3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; g

E41-TS-3488; o

El E41-TS-3489) l 5.

Bus Power Monitor NA(8}

1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) m 6.

IIPCI Turbine Exhaust Diaphragm Pressure - Iligh 4

2 1,2,3 25 (E41-PSil-NO12A, B,C,D)

l E

TABLE 3.3.2-1 (BSEP-1-62)

ISOLATION ACTUATION INSTRUMENTATION M

VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL h

TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION s

5.

Bus Power Monitor NA (8) 1/ bus 1, 2, 3 26 l

(E51-K42 and E51-K43) 6.

RCIC Turbine Exhaust Diaphragm Pressure - High 5

2 1,2,3 25 (E51-PS-NO12A,B,C,D) 7.

RCIC Steam Line Ambient Temp -

liigh 5

1 1,2,3 25 (E51-TS-N603A,B) y, 8.

RCIC Steam Line Area A Temp - !!igh 5 1

1,2,3 25 (E51-dTS-N604A,B) d

[

9.

RCIC Equipment Room Ambient Temp - High 5

1 1,2,3 25 v'

(E51-TS-N602A,B) 10.

RCIC Equipment Room A Temp - Ifigh 5 1

1,2,3 25 (E51-dTS-N601A,B) 5.

SHUTDOWN COOLINC SYSTEM ISOLATION a.

Reactor Vessel Water Level -

Low, Level 1 2,6,7,8 2

1,2,3 27 p

g (B21-LT-NOl7A-1,B-1,C-1,D-1) g, (B21-LTM-NO17A-1,B-1,C-1,D-1) a b.. Reactor Steam Dome Pressure-7, 8 1

1,2,3 27 High 8:

(B32-PS-N018A,B)

r i.

(BSEP-1-62)

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the'following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21' - Be in at least START-UP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in-at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least START-UP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - Establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hour.

ACTION 24 - Isolate the reactor water cleanup system.

ACTION 25 - Close the affected system isolation valves and declare the affected system inoperable.

ACTION 26 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 - Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

NOTES When handling irradiated fuel in the secondary containment.

(a)

See Specification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve group.

(b)

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

(c)

With only one channel per 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, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

(d)

A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.

_(e)

With reactor steam pressure > 500 psig.

(f)

Closes only RWCU outlet isolation valve.

(g)

Alarm only.

-BRUNSWICK - UNIT 1 3/4 3-16

~

Amendment No.

.~

E TABLE 4.3.2-1 (BSEP-1-62)

O ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH e

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK

-TEST CALIBRATION SURVEILLANCE REQUIRED

-i 1.

PRIMARY CONTAINMENT ISOLATION

~

a.

Reactor Vessel Water Level -

1.

Low, Level 1 (B21-LT-NOl7A-1,B-1,C-1,D-1)

NA(a)

NA R(b) g, 2, 3 (B21-LTM-NO17A-1,B-1,C-1,D-1)

D M

M 1, 2, 3 2.

Low, Level 2 (B21-LT-NO24A-1,B-1 and t'

B21-LT-NO25A-1,B-1)

NA(a)

NA R(b) 1 2, 3 x-(B21-LTM-NO24A-1,B-1 and u

B21-LTM-NO25A-1,B-1)

D H

M 1, 2, 3 b.

Drywell Pressure - High (C71-PT-N002A,B,C,D)

NA(a)

NA R

1, 2, 3 ID)

(C71-PTM-N002A-1,B-1,C-1,D-1)

D M

M 1,2,3 c.

Main Steam Line Id) 1.

Radiation - High D

W R

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

Pressure - Low (B21-PT-NO15A,B,C,D)

NA(a)

NA R(b) y (B21-PTM-NO15A-1,B-1,C-1,D-1)

D M

M 1

F 3.

Flow - High y

(B21-PDT-NOO6A,B,C,D; NA(a)

NA R(b) 1 I

B21-PDT-NOO7A,B,C,D; y

B21-PDT-NOO8A,B,C,D; B21-PDT-NOO9A,B,C,D) z

?

(B21-PDTM-NOO6A-1,B-1,C-1,D-1; D

M M

1 B21-PDTM-NOO7A-1,B-1,C-1,D-1; B21-PDTM-NOO8A-1,B-1,C-1,D-1; B21-PDTM-NOO9A-1,B-1,C-1,D-1)

TABLE 4.3.2-1 (Continued)

(BSEP-1-62) m E

E!

ISOLATION ACTUATION INSTRUMENTATION SURVLILLANCE REQUIREMENTS S

S CHANNEL OPERATIONAL e

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED z

U 5.

SHUTDGUN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water Level -

Low, Level 1

( B21-LT-N017 A-1,B-1,C-1,D-1 )

NA(a)

NA R(b) 1 2, 3

( B21-LTM-NOl7 A-1, B-1, C-1, D-1 )

D M

M 1, 2, 3 b.

Reactor Steam Dome Pressure -

IC)

High NA S/U

,M R

1, 2, 3 (B32-PS-NOl8A,B)

R

.~

M=

a i

8n

(BSEP-1-62) l

[

TABLE 4.3.2-1 (Continued) f ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES When handling leradiated fuel in the secondary containment.

When reactor steam pressure > 500 psig.

(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.

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

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

f r

I m

i t

BRUNSWICK - UNIT 1 3/4 3-29c Amendment No.

l

ENCLOSURE 2 TO NLS-85-177 PROPOSED TECilNICAL SPECIFICATION PAGES BRUNSWICK-2 MECilANICAL VACUUM PUMPS (85 TSB 15)

(1512 MAT /ccc )

J

i BRUNSWICK-2

SUMMARY

LIST OF REVISIONS PAGE NO.

DESCRIPTION OF CHANGE 3/4 3-11 Delete footnote (d) from item 1.c.l.

3/4 3-12 Change footnote (e) to (d) and footnote (f) to (e).

3/4 3-13' Change footnote (g) to (f).

3/4 3-14 Change footnote (h) to (g).

3/4 3-15 Change footnote (h) to (g).

3/4 3-16 Delete footnote (d); re-letter remaining notes.

3/4 3-25 Add footnote (d) to item 1.c.1 channel calibration.

3/4 3-29c Add footnote (d)" Testing shall verify that the mechanical vacuum pump trips and the mechanical vacuum pump line valve closes."

Relocated footnotes "'" and "#."

risi;mtec..

(BSEP-2-57) e E

TABLE 3.3.2-1 si U

ISOLATION ACTUATION INSTRUMENTATION R*

VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL E!

TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION U

w 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

Low, Level 1 2,6,7,8 2

1,2,3 20 (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, 3 2

1,2,3 20 (B21-LT-N024 A-1, B-1, and B21-LT-N025A-1,B-1) w 30 (B21-LTM-N024A-1,B-1, and i'

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

Z b.

Drywell Pressure - High 2,6,7 2

1,2,3 20 (C72-PT-N002A,B,C,D)

(C72-PTM-N002A-1,B-1,C-1,D-1) c.

Main Steam Line l

1.

Radiation - High 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) j[

(B21-PTM-N015A-1,B-1,C-1,D-1) h'[

3.

Flow - High 1

2/line 1

22 g

(B21-PDT-N006A,B,C,D; 5

B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; gy 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)

(BSEP-2-57)

TABLE 3.3.2-1 (Continued) 5y ISOLATION ACTUATION INSTRUMENTATION R*

VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CIIANNELS OPERATIONAL E

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION U

PRIMARY CONTAINMENT ISOLATION (Continued) w 4.

Flow - liigh 1

2 2, 3 21 (B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N008C-2; B21-PDTS-N009D-2) d.

Main Steam Line Tunnel Temperature - Iligh 1

2(d) 1, 2, 3 21 l

w 30 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; w

J.

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

Condenser Vacuum - Low 1

2 1, 2 * )

21 l

I (B21-PT-N056A,B,C,D)

(B21-PTM-N056A-1,B-1,C-1,D-1) f.

Turbine Building Area Temperature - liigh 1

4(d) 1, 2, 3 21 l

(B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; y

B21-TS-3227A,B,C,D; y

B21-TS-3228A,B,C,D; y

B21-TS-3229A,B,C,D; y

B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)

(BSEP-2-57)

E TABLE 3.3.2-1 (Continued)

E

[c ISOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE CPERATED BY OPERABLE CHANNELS OPERATIONAL E

TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION U

w 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - liigh 6

1 1,2,3,5, 23 (D12-RM-N010A,B) and* 23 b.

Drywell Pressure - High 2,6,7 2

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

(C72-PTM-N002A-1,B-1,C-1,D-1) w c.

Reactor Vessel Water Level -

3 Low, Level 2 1, 3 2

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

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

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - !!igh 3

1 1,2,3 24 (C31-dFS-N603-1A,lB) b.

Area Temperature - liigh 3

2 1,2,3 24 (C31-TS-N600A,B,C,D,E,F)

.I.

Area Ventilation A Temp. - liigh 3

2 1, 2, 3 24 c.

E (C31-TS-N602A,B,C,D,E,F)

If) d.

SLCS Initiation 3

NA 1,2,3 24 l

2:

e.

Reactor Vessel Water Level -

Low, Level 2 (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)

e.

(BSEP-2-57)

E TABLE 3.3.2-1 (Continued)

E

[c ISOLATION ACTUATION INSTRUhluTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL E

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION U

w 4.

CORE STANDBY COOLING SYSTEMS ISOLATION a.

liigh Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High 4

1 1,2,3 25 (E41-PDT-N004; E41-PDT-N005) 2.

IIPCI Steam Line liigh Flow R

Time Delay Relay NA 1

1,2,3 25 (E41-TDR-K33; Y

E41-TDR-K43) 3.

IIPCI Steam Supply Pressure - Low 4

2 1, 2, 3 25 (E41-PSL-N001A,B,C,D) 4.

HPCI Steam Line Tunnel Temperature - liigh 4

2 1,2,3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; g

E41-TS-3488; E.

E41-TS-3489)

IS) 1/ bus 1, 2, 3 26 5.

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

e

?

6.

HPCI Turbine Exhaust Diaphragm Pressure - High 4

2 1,2,3 25 (E41-PS!!-N012A,B,C,D)

i l

e.

l l

(BSEP-2-57) l l

9

~

I TABLE 3.3.2-1 (Continued) o, E

5 ISOLATION ACTUATION INSTRUMENTATION 5

Q VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL c

TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION z

I8I 1/ bus 1, 2, 3 26 l

5.

Bus Power Monitor NA (E51-K42 and E51-K43) 6.

RCIC Turbine Exhaust Diaphragm l

Pressure - High 5

2 1, 2, 3 25 (E51-PS-N012A,B,C,D) 7.

RCIC Steam Line Ambient Temp. -

~

i l

High 5

1 1,2,3 25 l

(E51-TS-N603A,B) 8.

RCIC Steam Line Area a Temp. -

Ei High 5

1 1, 2, 3 25 (E51-dTS-N604A,B) wl-9.

RCIC Equipment Room Ambient Temp. - High 5

1 1,2,3 25 10.

RCIC Equipment Room A Temp. - High 5 1

1, 2, 3 25 l

(E51-dTS-N601A,B) 5.

SHUTDOWN COOLING SYSTEM ISOLATION l

a.

Reactor Vessel Water Level -

Low, Level 1 2,6,7,8 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) g b.

Reactor Steam Dome Pressure - High 7, 8 1

1, 2, 3 27 g

(B32-PS-N018A,B)

W 8n

.O L

O*

(BSEP-2-57)

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - Estabilrh SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hot.r.

ACTION 24 - Isolate the reactor water cleanup system.

ACTION 25 - Close the affected system isolation valves and declare the affected system inoperable.

ACTION 26 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 - Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

NOTES When handling irradiated fuel in the secondary containment.

a.

See Specification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve group.

b.

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

c.

With only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function co occur.

In these cases, the inoperabic channet shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

d.

A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

e.

With reactor steam pressure > $00 psig.

f.

Closes only RWCU outlet isolation valve.

l i

3 Alarm only.

l l

BRUNSWICK - UNIT 2 3/4 3-16 Amendment No.

l l

(BSEP-2-57)

D*.

E TABLE 4.3.2-1 E

E ISOLATION ACTUATION INSTRIMENTATION SIRVEILLANCE REQUIREMENTS M

CHANNEL OPERATIONAL E

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH Q

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED u

1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

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

NA(a)

NA R(b) g, 2, 3

' (B21-LTM-NOl7A-1,B-1,C-1,D-1)

D M

M 1, 2, 3 2.

Low, Level 2 (B21-LT-NO24A-1,B-1 and B21-LT-NO25A-1,B-1)

NA(a)

NA R(b) 1, 2, 3 (B21-LTM-NO24A-1,B-1 and

{

B21-LTM-NO25A-1,B-1)

D M

M 1, 2, 3 b.

Dryvell Pressure - High NA ")

NA R(b) 1, 2, 3 I

(C72-PT-N002A,B,C,D)

(C72-PTM-N002A-1,B-1,C-1,D-1)

D M

h 1, 2, 3 c.

Main Steam Line

'l i

1.

Radiation - High

_D W

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

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

NA(a)

NA R(b) y (B21-PTM-NO15A-1,B-1,C-1,D-1)

D M

M 1

y 3.

Flow - High NA ")

NA R(b) y I

5

-(B21-PDT-NOO6A,B,C,D; E.

B21-PDT-NOO7A,B,C,D; B21-PDT-NOOSA,B,C,D; T,

B21-PDT-NOO9A,B,C,D)

E (B21-PDTM-N006A-1,8-1,C-1,D-1;

.D M

M 1

B21-PDTM-N007A-1,5-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-NOO9A-1,B-1,C-1,D-1)

7_

(BSEP-2-57)

TABLE 4.3.2-1 (continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES When handling irradiated fuel in the secondary containment.

When reactor steam pressure > 500 psig.

(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.

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

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

l r

l l

4 i

l l

BRUNSWICK - UNIT 2 3/4 3-29c Amendment No.

l

.

ML20137M023

Text

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