ML20058C346

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Proposed Tech Specs Clarifying Isolation Sys Instrumentation Requirements
ML20058C346
Person / Time
Site: Brunswick  
Issue date: 10/24/1990
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20058C337 List:
References
NUDOCS 9011010175
Download: ML20058C346 (56)
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Text

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J ENCL 4SURE 1 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & $0 324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT PRIMARY CONTAINMENT IS01ATION SYSTEM (NRC TAC NOS. 67991 AND 67992) i TECHNICAL SPECIFICATIOi4 PAGES - UNIT 1 9011010175 901024 PDR ADOCK 05000324' P

PNU(

4 C

INDEX i

BASES SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) l 3/4.4.4 CllEMISTRY........................................~...-B 3/4 4-2

[

3/4.4.5 C P EC I F I C A CT I V I TY................................... B 3 / 4 4 -2 i

3/4.4.6 PR ES SURE/ TEM PERATURE LIMITS......................... B 3 /4 4-3 l

3/4.4.7 MAIN STE AM LI NE. lSOLATION VALVES.................... B 3 /4 4-7 '

s 3/4.4.8 STRU CTUR AL I NT EC RI TY................................ B 3 / 4 4 - 7 l

t.

l 3/4.5 EMERCENCY CORE C00LINC SYSTEM 1/4.5.1 111C11 PRESSURE COOLANT INJECTION SYSTEH.............. B 3 /4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)............. B 3/4 5-1 3/4.5.3 LOW PRESSURE COOLI NG SYSTEMS........................ B 3 /4 5-2 3/4.5.4 SUPPRESSION P00L.................................... B 3/? 5-4 t

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY C0NTA!NMENT.................................

B 3/4 6-1 3/4.6.2 DEPRESSURI ZATION AND COOLI NG SYSTEMS................ B 13 /4 6-3 3/4.6.3 PRIMARY CONTAI NMENT ISOLATION VALVES................ B 3 /4 6-4 3/4.6.4 VACUUM REllEF....................................... B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT............................... B 3/4 6-5 3/4.6.6 CONTAI NMENT ATHOSPflERE CONTR0L...................... B 3 /4 6-6 l

r 3/4.7 PLANT SYSTEMS 3/4.7.1-SERVICE WATER SYSTEMS.~..............................

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM............

B 3/4 7-la i

i BRUNSWICK - UNIT 1 XI Amendment No.

f 1

s DEFINITIONS OPERABLE - OPERABILITY (Continued) i Implicit in this definition shall be the assumption ~ that all necessary attendant inst rumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to - perform it a function (s) are also capable of performing their related support function (s).

{

OPERATIONAL CONDITION An OPERATIONAL CONDITION shall be any one inclusive combination' of. mode switch position and average reactor coolant temperature as indicated in Table 1.2..

~

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure toe fundamental' nuclee > characteristics of the reactor core and related instrumentation and.

I are 1) described in Section 14 of the Updated FSAR,,2) authoriced under the '

provisions of 10 CFR $0.59, or 3) otherwise approved ty the Commission.-

PRESSURE BOUNDARY LEAKAGE PRESSURE BOUNDARY LEAKACE shall be leakage through'a non-isolatable f ault in a' reactor coolant system component body, pipe wall, or vessel wall.

(

PRIMARY CONTAINMENT INTECRITY t

t PRIMARY CONTAINHENT INTECRITY chall exist whent a.

All penet rations required to be closed during accident' conditions are eithert i

1.

Capable of being closed by an OPERABLE containment automatic isolation valve system, or i

2.

Closed by at least one manual valve, blind 1 flange, or deactivated i

automatic valve secured'in its closed positiore, except as provided in Table 3.6.3-1 of Specification 3.6.3.1.

l b.

All equipment hatches are' closed and sealed.

c.

Each containment air lock is OPERABLE pursuant to Specification 3.6.1.3.

d.

'The containment leakage rates are within the limits of Specification 3.6.1.2.

The sealing mechanism associated'with each penetration (e.g., welds, e.

bellows or 0-rings) is OPERABLE.

BRUNSWICK - UNIT.1-1-5 Amendment: No.

a.

TABLE 3.3.2-1 5

E ISOLATION ACTUATION INSTRUMENTATION E

E VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL

. TRIP FUNCTION SICNA1.(a )

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

E i

O 1.

P8tIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

Low, Level 1 2, 6 2

1,'2, 3 20 8

2 1, 2, 3 27 2.

Low, Level 3 1-2 1, 2, 3 20 Drywell Pressure - High 2, 6' 2

1,2,3 20 l

b..

c.

Main Steam Lire w'

1.

Radiation - High 1

2 1, 2, 3 21 5

2.

Presrure -' Low II5) 2 1-22 l

w 3.

Flo# - High II5}'

2/line

' I 22 l.-

d.

Main Steam Line Tunnel

~ Temperature - High 1(5}~

2(d) 1, 2, 3 21

-l e.

Condenser Vacuum - Low II5) 2 1, 2 * )

21 l

I f.

Turbine Building Area l

Temperature'- High II5) 4(d) 1, 2, 3 21 g.

Main Stack Radiation - High (h) 1 1,-2, 3

28 R

E h.

Reactor Building Exhaust

-R Radiation - High 6-1

. 1, 2, 3 20 E

z.

, - +.,,.

_,...---........,,r.

~.

._..~.y....

......,_,..___.m.

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

e

=

TABLE 3.3.2-1 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION l

"c -

n" VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SICNAL(a)

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

G 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust a.

Radiation - High (1) 1 1, 2, 3. 5, and* 23 6

1 1,2,3 20 b.

Drywell Pressure - High (1) 2 1,2,3 23 2, 6 2

1,2,3 20 c.'

Reactor Vessel Water Level -

Low, Level 2 (1) 2 1, 2, 3 -

23 3

2 1, 2,. 3.'

24-

.w N

w

. 3..

REACTOR WATER CLEANUP SYSTEM ISOLATION

.L w

a.

A Flow - High 3

~1 1,-2, 3-23-b.

Area Temperature - High 3-2 1, 2, 3 24-c.

Area Ventilation A. Temperature - High 3

2 1, 2, 3 24 l-II) d.

SLCS Initiation 3

NA 1, 2, 3

- 24 e.-

Reactor Vessel Water Level -

Low, Level 2 3

2 1, 2, 3 24-R l

E f.

A Flow - High -~ Time Delay Relay NA 1-1, 2, 3 24

. 2 E

F.

,n

--nr.

,,.,--senwrs-

--N,n.,,.re-,.

c.,,.-...n.-

c w..

.,e-e e

,n--r x-

-+-

,w w,.,

-m.~

~..,

,mn, a.,wA. e -e n-

~,e~..

-e

o TABLE 3.3.2-1 (Continued)

,:=

E ISOLATION ACTUATIDF INSTRUMENTATION E

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

PER TRIP SYSTEM (b)(c) CONDITION ACTIO4 E$

4.

CORE STANDBY COOLING SYTTEMS ISOLATION a.

High Pressure Coolant Injection System Isclation 1.

HPCI Steam Line Flow - High 4'

I 1, 2, 3 25 2.

HPCI Steam Line Flow - High Time Delay Relay NA 1

1, 2, 3 25~

3.

HPCI Steam Supply Pressure - Low 4

2 1, 2,. 3 25 7(k) 1 1, 2, 3 25 l

ws b:

4.

HPCI Steam Line Tunnel w

Temperature - High~

4 2

1,2,3 25 IE) 1/tyus 1, 2, 3 26 5.

' Bus Power Monitor NA 6.

HPCI Tur'bine Exhaust Diaphragm Pressure - High 4

2 1,.2, 3

25 7.

. HPCI Steam Line Ambient Temperature - High 4-1-

1, 2, -3 25 8.

HPCI Steam'Line Area l

a Temperature - High'

'4-1 LI, 2,-3 25' l

R R

9..

HPCI" Equipment Area Temperature'- High 4..

1 1, 2, 3 25 o

rv.

z.

110.

Drywell Pressure - High 7(k) 3

- g, 2, 3

-25~

l o-

+2.

,e...

-nei s, *r ev.

w--r's..

=, -,

-,--e.r--wsrt=.-

s.w e

=- e ree--

  • wwe

-m-.

+-s-w

' w -e c

+

w-e' -v e-+am-s e-,w--.

-m-r~-*-m---e

~.

  • -mv

.-.=.-eem

TABLE 3.3.2-1 (Continued)

E

. Q ISOLATION ACTUATION INSTRUMENTATION VALVE CRGUPS MINIMUM NUMBER APPLICABLE

- Q OPERATED BY OPERABLE CHANNELS OPERATIONAL

. TRIP FUNCTION SICNAL(a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION

- E 4.

CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

.A b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow -'High 5

I 1, 2,.3 25 2.

RCIC Steam Line Flow - High Time Delay Relay NA I

1, 2, 3 25 3.

RCIC Steam Supply Pressure - Low 5

2 1, 2, 3 25' 9(k) 1

~1,

2. 3, 25 l

4.

- RCIC Steam Line. Tunnel Temperature - High 5

2 1, 2. 3

. 25 w

IE}

1/ bus 1, 2, 3 26 w -

5.

Bus Pawer Monitor NA

1 4

v' 6.

RCIC Turbine Exhaust Diaphragm Pressure - High 5

2 I,.2, 3 25 7.

RCIC Steam Line Ambient -

Temperature - High 5

1 1, 2,. 3 25-4 8.

RCIC Steam Line Area a Temperature - High 5

l' I, 2, 3 25 9.

kCIC Equipmer.t Room Ambient Temperature - High 5

1-1, 2, 3 25~

y 10.

RCIC. Equipment Room a Temperature - High 5

li 1, 2, 3_

25 l

a' 2

11.. RCIC Steam Line Tunnel E :.

Temperature - High Time Delay Relay NA, 1

1, 2, 3 25

- 12.. Drywell Pressure

.High-9(k) 1 1, 2, 3 25 9

W v-,

-g e.,-,.

e.,g-

,e w.w

..,w.+#

-,-w

,m.

g

-e+,<e-w,,,-,

5.+

.,se n

new,n

,,e-... -.,,

,ve w-

.-+- -.,.,

eoc

4-~

t TABLE 3.3.2-1 (Continued) m.

1 C-E ISOLATION ACTUATION INSTRUMENTATION

. cec

-o VALVE CROUPS MINIMUM NUMBER APPLICABLE n

OPERATED BY

- OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION' SIGNAL (a )

PER TRIP SYSTEM (b)(c) CONDITION-ACTION..

cz Y-

' 5.

SHUTDOWN COOLING SYSTEM ISOLATION a.

Reactor Vessel kater. Level -

2; 6 2

1,2,3

' 20.

Low, Level. I 8

2 1,2,3

'27-II) 1

-1,.2, 3

27 l.'

b.i Reactor Steam Dome Pressure - High 8

~

N b~

ba 8

e*

1

- k.

~

=

0.-

Ig a,

e E

- ts

~

d asr -

r

-. u v.

I r.

a z

.ww

.+-e e-w--+s<

  • 1-rw

=ir*

e a

- -e--mr+w w - a-c+ v r -we.*+er

-w4 e

em-v-

-w c =- w e a-~ e -e -rewm-+

.wv.-w e

ww-+

ww,, w w,a w+

'w.+--ev e-w ww+s.

.se r ve

~4 eir is w+-ras-e+-==

.4

.=

TABLE 3.3.2-l'(Continued)

IS01.ATION ACTUATION INSTRUMENTATION NOTES When handling irradiated fuel in the secondary containment (a)

See Specification 3.6.3.1, Table 3.6.3-1 for valvea in each valve.

group.

(b)

A channel may: be placed in an' inoperable status = for. up to 2-hours-for required surveillance without. placing the t rip' 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 inoperableLchannel shall be restored to OPERABLE status within: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.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.

(h)

Isolates containment purge and vent valves.

(i)

Does not isolate Ell-F0l$A,B.

(j)

Does not isolate B32-F019 or B32-F020.

(k)

Valve isolation depends upon low steam su' ply pressure coincident p

with high drywell pressure.

(1)

Secondary containment -isolation dampers' as -li sted; in Table 3.6.5.2-1.

BRUNSWICK - UNIT 1 3/4 3-17a

- Amendment No.

k

.g i

E TABLE 3.3.2-2 E!

E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E

ALLOWABLE

-TRIP FUNCTION TRIP SETPOINT VALUE E!

~i 1.

PRIMARY CONTAINMEtdT ISOLATION

~

-a."

Reactor Vessel Water Level -

3 + 162.5 inches (a)

+ 162.5 inches *I I

1.

Low, Level 1 2.

Low, Level 3~

3 + 2.5 inches (a) 3'+ 2.5 inches *)

I

. b.

Drywell Pressure ~- High-1 2 psig.

$ 2 psig c.

Main Steam Line 1.

Radiation - High

$ 3 x full power 5 3.5 x full power w

IC ICI' 25' background background 2.

Pressure - Low 3 825 psig

- 3 825 psig j 3.

Flow - High i 140% of rated flow

. $ 140% of rated flow d'

? Main Steam Line. Tunnel Temperature - High 5 200*F

$ 200*F e.

Condenser Vacuum - Low 2[7 inches Hg vacuum 3 7 inches Hg vacuum--

f.

Turbine Building Area Temperature - High.

5 200*F'

- < 200*F l-

'g.

. Main Stack Radiation - High (b)

' (b) 5-h.

Reactor' Building Exhaust' Radiation - High

$ 11 mr/hr

$ 11 mr/hr l

I a:

3

..O :

g

-L.--

..l~.,-

,45s

--m...-w.r.

--i.r...

~,- --., _ _

...m'.

r U. ms..-

4,

,E..<,,,

vm.'.n..',.,,,-.n.-.,

.-w-.m.,h,-y..

+

~

l.,

[-

'E TABLE 3.3.2-2 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS o*

. ALLOWABLE

-TRIP FUNCTION TRIP SETPOINT VALUE "G

- 3.

2. - SECONDARY CONTAINMENT ISOLATION..

a.

Reactor' Building Exhaust Radiation - High 3 11 mr/hr

$ 11 mr/hr

~

~

b.

Drywel1 Pressure - High

$ 2 psig

$ 2 psig 3 + 112' inches (a)

>;+ 112 inches (a)

Reactor. Vessel' Water Level,- Low, Level ?

,c.

3..

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

la Flow -:High 5 53 gal / min 3 53 gal / min

~b.. Area Temperature - High.

$ 150*F

$ IS0*F w

~

I

_ 50*F'

- lI c.

Area Ventilation a Temperature - High

< $0*F

d. 'SLCS Initiation

.NA NA:

Reactor Vessel Water Level - Low,.

3 + 112-inches *}

>}+112 inches (a)

_e.

Level:2'-

I

.f.. A Flow - High?- Time. Delay Relay

$ 43 Seconds

$ 45 seconds-l 1

.k'

.=.;

O

.: l -

=

_ O.;

a,,

2.w -.. - - ;..

a-

.. a-

. -. a _, a..

-4 g

TABLE 3.3.2-2 (Continued)

Ep ISOLATION ACTUATION INSTRUMENTATION SETPOINTS x

ALLOWABLE a

TRIP FUNCTION TRIP SETPOINT VALUE q

4.

CORE STANDBY COOLING SYSTEMS ISOLATION

~

a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High f 300~. of1 rated flow

< 300% of~ rated flow-2.

-HPCI Steam Line Flow..- High l-Time Delay Relay 3 < t < 7 seconds

-3<t < 12 seconds 3.

HPCI Steam Supply Pressure - Low.

'>~100 psig

> 100 psig 4..

HPCI Steam Line Tunnel Temperature - High 200*F

< 200*F

~

7' 5.

Bus Power Monitor NA' NA

'E HPCI Turbine Exhaust. Diaphragm:

o.

6.

Pressure - High i< 10 psig,

.'$-10 psig

< 200*F

< 200*F-l; 7.

HPCI Steam'Line Ambient Temperature - High

.50*F

.< 50*F j,

8.'

HPCI Steam'Line Area 6. Temperature.- High.

9.

HPCI Equipment Area Temperature High~

-.< 175*F

. <-175'F l

~

10.- Drywell Pressure - High

-< 2 prig

< 2 psig.

l R.

a R.

E F-

a-g TABLE 3.3.2-2 (Continued)

E

_p ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

-nx ALLOWABLE e

TRIP FUNCTION TRIP SETPOINT VALUE E

'4.-

CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

~

b.-

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High

$ 300% of rated flow

$ 300% of rated flow 2.

RCIC Steam Line Flow - High g

Time Delay Relay 3 $ t $ 7 seconds 3$t < 12 seconds

.l 3.

. RCIC Steam Supply Pressure - Lov.

> 50 psig

> 50 psig 4.

lRCIC Steam'Line Tunnel Temperature - High

$ 175'F

$ 175'F

.l 5

5.

Bus Power Monitor NA-NA de 6.

RCIC Turbine Exhaust Diaphragm

~ Pressure -'High

$ 10 psig

< 10 psig 7.

RCIC Steam Line Ambient' Temperature - High

$~200*F

< 200*F l

18.

RCIC Steam Line-Area A. Temperature - High

< 50*F

- < 50*F.

l'

.9.

RCIC Equipment Room Ambient

' Temperature High-

$ 175'F'

$ 175'F l

10.- RCIC Equipment-Room

.g

-o Temperature - High 5 50*F

$ 50*F[

l

.y

g 11.- RCIC Steam Line Tunnel-Temperature - High g'

Time Delay Relay-

< 30 minutes

< 30 minutes zo

-12.

Drywell Pressure.- High

_ < 2 psig.

1 2 psig

--=u

=

=

=

.-..__._._...~;_.a.

. o.,

i TABLE 3.3.2-3 t

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME-TRIP FUNCTION R_rSPONSE TIME (Seconds)(a)(e)'[ f 1..

PRfMARY CONTAINMEhr ISOLATION a.

Reactor Vessel Water Level -

1.

Low, Level =1

$13

- < 1.'g( d ) -

. l' l

2. ~ Low, Level'3 213 I) i b.

Drywell Pressure - High -

$13 1.

Radiation -'High(b) c.

Main. Steam Line

<l.0(d) '

l.

. j 3 13( f).

2.

Pressure - Low

$13-f

<0.g(d) 3.

Flow - iligh

_513 I I' l

d.

Main St eam Line Tunnel. Temperature - High :'

$13 e.

Condenser Vacuum - Low

<l3 f.

Turbine Building Area Temperature - High.

1 I

NA' Main Stack Radiation - liigb(b)-

.$~1.0(d) g.

h.

Reactor Building Exhaust Radiation - HighID)

'NA' l

2.

SECONDARY CONTAINMENT ISOLATION ReactorBuildingExhaustRadiation-'High{b)

.333

.]

a.

a

.b.

Drywell Pressure ' High

$ 13..

c.

Reactor Vessel Water Level - Low, Level 2 '

.313; l.

j

.3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High

$45(c P l'

b.

Area. Temperature - liigh 313 i;

c.

Area Ventilation A Temperature - High 513 j.

I d.-

SLCS Initlation NA e.

Reactor Vessel Water Level - Low, Level 2-

$13 l.

1 1.

A Flow - High:- Time Delay Relay.

NA'

- l 1

3/4 3-23 Amendment No..

l BRUNSWICK - UNIT 1 l-m.

+,

av

+

-6 1

i 1

TABLE 3.3.2-3 (Continued)

~!

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME RESPONSE TIME' (Seconds)(a)[

TRIP FUNCTION

-i 4

CORE STANDBY COOLING SYSTEMS ISOLATION f

a.

liigh Pressure Coolant injection System Isolation 1

1.

11P01 Steam Line Flow. High.

$13(c)

-ll 2.

IIPC1 St sam Line Flow - High Time Delav 'Stelay NA

'l 3.

IIPCI Steam' Supply Pressure - Low -

513 1

4.

HPCI St eam Line ' Tunnel Temperat ure - High

'$13 j

t 5.

Bus Power Monitor NAl

[

6.

HPCI Turbine Exhaust Diaphragm Pressure - High.

NA l

7.

IIPCI Stecm' Line Ambient Tempe rature '- lligh NA' t

8.

HPCI Steam Line Area n'Temperat ure '- liigh NA l.

'f

9.. llPCI Equipment-Area Temperature - liigh

'NA' l

l 10.

Drywell Pressure - High' NA l

-[

b.

Reactor Core Isolation Cooling; System isolation' i

1.

RCIC Steam Line Flow - High 313(c)

l. j 2.

RCIC St eam Line Flow - liigh Time : Delay Relay" NA 3.

RCIC Steam Supply Pressure - Low NA-4 RCIC Steam Line Tunnel Temperature - liigh NA-l-

5.

Bus. Power Monitor >

'NA ti 6.

RCIC Turbine Exhaust Diaphram Pressure - High'

NA.

i 7.

RCIC Steam Line Ambient Temperature lligh NA; j

B.

RCIC Steam Line Area 4' Temperature - High NA l

r 9.

RCIC Equipment Room Ambient Temperature - High

. N A1 l

{

10. RCIC EquipmenL Room A Temperature.- High NA l.

11.

RCIC Steam Line Tunnel Temperature

.lligh N A' Time Delay. Relay J

r

12. Drywell Pressure - liigh NA-1';

l a

BRUNSWICK - UNIT 1-

.3/4 3-24

" Amendment' No..

r 1I s-

[

s,

c

.g i

e 1

s

-g-

7. l,. -

J 1.

j

.r I

  1. f' g

9

.c y g

+

i f.

'I o

e

f. _

TABLE 3.3.2-3 (con'tinued)1 2

1 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME.

TRIP FUNCTION RESPONSb ThME (SEcondN)(a N.

1 5.

Sil'UT!s0WN 'C00LINC' SYSTEM ISOLAT10N x

-r

, Reactor Vessel; Nater Level T I.owfLevel~1-N A.1 M

a.

b..

React or ' Steam Do' sl Pressure lligli

, NA' m

4 e

n d

.,jf 3-t.p -

i j

^

d %'-l

(

j; a

-+:

+

F 1

l po-

+

c r

,3("

..%.I f

1 1

l l

t

7. i '

l c.j 1

i f

4 i

4 l

~

I BRUNSWICK - UNIT.1, 3/4[3-25 LAmendment No.-

y-l 7

J z;*g m

1

-; g_

f !.$

! 8'i-s e

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME NOTES (a)

The isolation system instrumentation response time shall be measured and-recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.

Isolation system instrumentation response time specified includes any delay for diesel generator starting assumed in the accident analysis.

(b)

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

(c )

includes time delay added by the time delay relay.

(d)

Isolat ion actuation inst rumentat ion response time f or MSIVs only.

No diesel generator delays assumed.

(e)

Isolation system instrumentation response time specified for the Trip function actuating each valve group / damper shall be added to the isolat ion time for valves in each valve group shown in Table 3.6.3-1 and secondary containment isolation dampers shown in Table 3.6.5.2-l'to obtain IS0l.ATION SYSTEM Resp 0NSE TIME for each valve / damper.

(i )

Isolation system instrumentation response time for associated valves except MSIVs.

i BRUNSWICK - UNIT 1 3/4 3-26 Amendment No.

I

E TABLE 4.3.2-1 E

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRD%g S

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHAA C CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED' U

l.

PRIMARY CONTAINMENT ISOLA"" ION a.

Reactor Vessel Water Level -

1.

Low, Level 1 Transmitter:

NA(a)

NA R(b)

I, 2, 3 -

Trip Logic:

D M

M 1,. 2, 3 2.

Low, Level 3 Transmitter:

NA(a)

NA R(b) 1 2, 3 Trip Logic:

D M

M 1, 2, 3-b.

Drywell Pressure - High-Transmitter:

NA(a)

NA R(b)

- y, 7. 3 Trip-Logic:

.: D M

M' 1, 2,. 3 s

c.

Main Steam Line Id) y 1.

Radiation - High P

W R

I, 2, 3 w"

2.

-Pressure - Low Transmitter:

NA(a)

NA R(b) 3 Trip Logic:

D M

M

.1 3..

Flow - High Transmitter:

NA(a)

NA

' rih) z I

Trip Logic:

D M

M 1

d.

Main Steam Line Tunnel Temperature - High NA

'M R

1, 2, 3 e.

Condenser Vacuum - Low g

g I, 2g Transmitter:

NA NA R

g i 1, 2 *)

I Trip Logic:

D_

M-M o.

f.

Turbine. Building Area

?,

' Temperature - High NA M

R 1, ' 2, 3 l

z

,o g.

Main-Stack Radiation - High NA Q

R 1, 2, 3 h.

Reactor Building Exhaust l...

Radiation - High D

M R

.1, 2,- 3

,. =

5 TABLE 4.3.2-1 (Continued)

E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAF, CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 3

2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust I f '.

Radiation - High D

M R

1,2,3,5, and b.

~ Drywell Pressure - High R,)

1, 2, 3 p

Transmitter:

NA(a)

NA Trip Logic D

M M

1, 2, 3 c.

Reactor Vessel Water Level -

Low, Level 2 Transmitter:

'NA(a)

NA

.R(b) 1, 2, 3 Trip Logic:

D M

M 1, ' 2, 3 u

- 5 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION w

E a.

A Flow - High D

M R

1, 2, 3 ce b.

Area Temperature - High NA M

R 1, 2, 3 c.

Area Ventilation a Temperature - High NA M

R 1, 2, 3 l

d.

SLCS Initiation NA R.

NA 1, 2, 3 e.

Reactor Vessel Water Level -

Low, Level-2 Transmitter:

NA(a)

NA R(b)

I, 2, 3

' Trip Logic:

D M

M 1, 2, 3 y

f.

A Flow - High - Time Delay Relay we M

R 1, 2, 3 l

i 8

m

_._...<.,-.=e-m:...m

~-m-_

=o..m-- -.

,m

__m;~,_.

5 TABLE 4.3.2-1 (Continued)

E 2

Idu1ATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.5 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH' E

TRIP 7 UNCTION CHECK TEST CALI BRATION SURVEILLANCE REQUIRED U

4.

CORE STANDBY COOLINC SY3TEMS ISOLATION a.

High Pressure Coolant Injection System' Isolation 1.

HPCI Steam Line Flow - High Transmitter:

NA(a)

NA R(b) 1, 2,. 3 Trip Logic:

D M

M.

I, 2, 3 2.-

HPCI Steam Line Flow - High-Time Dalay Relay NA R

R 1, 2, 3 3.

HPCI Steam Supply Pressure - Low NA-M R

1, 2, 3 v

d>

4.

HPCI Steam Line Tunnel Temperature - High NA M

Q-1, 2, ' 3 5.

-Bus Power Monitor-NA R

NA 1, 2, 3 6.

HPCI Turbine Exhaust Diaphragm' Pressure - High' NA M

Q 1,'2 13' 7.-

HPCI Stear Line Ambient-

~

Temperature - High NA M

R-1, 2,'3

~l; 8.

HPCI Steam Line Area a_ Temperature - High NA M

R 1, 2, 3 j.

E 2

9.

HPCI Equipment Area il Temperature - High NA M.

-Q 1, 2, l' l

z 10.

Drywell Pressure - High a)-

ID}'

Transmitter:

NA NA R

1, 2, 3 Trip Logic:

D M

M 1, 2, 3

.._2_.

5 TABLE 4.3.2-1 (Continued)

E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS O

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

" TRIP FUNCTION CHECK TEST

' CALIBRATION SURVEILLANCE REQUIRED Ei '

4. - CORE STANDBY COOLING SYSTEMS ISOLATION (Continued) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High Transmitter:

NA(a)

NA R(b) 1, 2, 3 Trip Logic:

D

'M M

1, 2, 3 -

2.

RCIC Steam Line Flow - High Time' Delay Relay NA R

R I, 2, 3 3.

RCIC Steam Supply Pressure - Low NA M

Q 1,. 2,- 3 ti 4.

RCIC Steam Line Tunnel

~, 2,. 3 l

Temperature - High ~

NA M

R~

1 1

5.

Bus Power Monitor NA R

NA-

1. 7 3 o

6.

RCIC Turbine Exhaust Diaphragm Pressure - High-NA M

R 1, 2, 3 7.

RCIC Steam Line-Ambient Temperature - High NA M

'R

1. 2, 3 l-8.

RCIC Steam Line Area:

1, 2,-3

-l A Temperature -lHigh-

.NA M

R 9.

RCIC Equipment Room Ambient-Temperature - High NA' M

Q L1,.2, 3 l.

10.

RCIC Equipment Room-g a Temperature - High NA M

Q 1, 2, 3

.l e

E.

11.. RCIC Steam Line Tunnel Temperature '- High Time Delay, Relay NA M

R 1, 2, - 3 12.

Drywell Pressure - High inansmitter:

NA(a)

NA R(b) 1, 2, 3 l

Trip Logic:

D M

M 1,.2, 3

l

v

8

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TABLEL-4;3.2 l6(Continued)3

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ISOLATION ACTUATION INSTRUMENTATION = SURVEILLANCE REQUIREMENTS r- ]

"u m

NOTES 5 (a) The transmit ter' channel ' check 'is satisfiedi by thelriplunii channel

- check. - A separate t ransmitter check,is not. required..

' 1 (b), Transmitters 'are-exempted f rom the.mohthly: charineV cal'ibration. :

4 j;j

- (c) It. not pertormed within the prev.ious 31 days.

r

-(d )., Test ing shall, veri fy L.t hat ; the mechanical f-' vacuum 1. pump t ri pal and the.4

,t

+

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[

j,I

- (e) When - reactor steam pressure > $00; psig.

.]

~

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BRUNSWICK - UNIT 1 3/4 6-14T

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~4 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOHATIC ISOLATION DAMPERS LIMITINC CONDITION FOR OPERATION 3.6.5.2 The secondary containment-automat ic isolat' ion dampers "shown in Table 3.6.5.2-1 shall be OPERABLE.

Al ijLI CAB I LITY t - OPERATIONAL CONDITIONS 1, 2, 3, 5, and *.

l l

ACTION:

With one or more of the secondary containment isolation dampers specified in Table 3.6.5.2-1 inoperable, operat' ion may continue and the provisions of.

Specification 3.0.4 are not applicable, provided that at least one isolation damper is maintained OPERABLE in each af fected penetration that is ~open, andi

~

~

a.

The inoperable damper is restored to OPERABLE status,within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or b.

The affected penetration is isolated by use of'a closed damper within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or c.-

SECONDARY CONTAINMENT LINTECRITY is demonst rat ed. wit hin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the damper is restored. to OPERABLE status within 7 days.

Otherwise, in OPERATIONAL CONDITIONS 1, 2, or 3, be in'at le as t - Il0T l

SliUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SilVTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise, in OPERATIONAL CONDITION $ or *, suspend irradiated-fuel-l handling in the secondary contairment, CORE ALTERATIONS, or activities that could reduce the SilVTDOWN MARCIN.

The provisions oi Specification 3.0.3 are not applicable.

t

BRUNSWICK - UNIT 1 3/4 6-22 Amendment No.

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4 CONTAINMENT SYSTEMS BASES 3/4.6.3 PRIHARY CONTAINMENT ISOLATION VALVES (Continued)'

A list of automatic closing primary containment isolation valves and theirc

(

associated closure times shall be available at the' plant in accordance with' i

Sect ion 50.71(c) c.f 10 CFR Part 50.

The addition and deletion of primary containment isolation valves shall be made in accordance with Section 50.59 of 10 CPR Part 50.

3/4.b.4 VACUUM RELIEF Vacuum relief breakers are provided to equalize.the pressure between the drywell and suppression-pool and the suppression pool and reactor. building.

This system will maintain the structural ~ integrity of the containment under; conditions of large' differential pressures; The vacuum breakers between the drywell and the_suppressio'n pool must not be inoperable in'the open position since this would allow bypassing of'the suppression pool in case of an accident. There are an adequate number.of 1

valves to provide some. redundancy so that operation may continue with.no more'

)

than 2 vacuum breakers inoperable and' secured in the closed position.

Each set of vacu'um relief valves between the suppression chamber and reactor building provides 100% relief, Which may.by required in the unlikely event-that negative pressures develop in the primary containment'. =

The Nitrogen Backup System provides backup motive power for these' suppression pool-reactor building vacuum breakers on a loss of instrument' air ~. -The normal non-interruptible instrument air system for these vacuum breakers is designed as a Seismic Class I system supplied by air compressors powered from the.

j The Nitrogen Syst' m serves as a backup to that air system emergency buses.

e and thus the loss of the Nit rogen System, or portions thereof,Edoes not make.

the vacuum breakers inoperable. The design allows for the out of service times in Actions b and c.

The Nitrogen Backup System is added to the Suppression Pool-Reactor Building Vacuum Breaker specification _to satisfy NRC concerns relative to 10 CFR 50.44(c)(3) as-addressed in the. Brunswick Safety Evaluation Report dated October 30, 1986 concerning Generic Letter 84-09.

pressuriaation to 1130~psig assures sufficient system capacity to provide 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation with design valve actuation and-system leakage.

3/4.6.5 SECONDARY CONTAINMENT i

4 Secondary containment is designed to minimize any ground level release of radioactive material which may result from an accident. The reactor building provides secondary containment during normal operation when the' drywell is sealed and in service. When the reactor.is shut down, or during refueling, the drywell may be open and the reactor building t! an becomes the primary containment.

t s

BRUNSWICK - UNIT.1 B 3/4 6-5 Amendment No.

s e

-i 4

?

CONTAINMENT SYSTEMS BASES (Continued) 3/4.6.5 SEC014DARY CONTAINMENT (Continued)

Establishing and maintaining a vacuum in the building with the standby gas treatment system, once per 18 months, along with the surveillance'of.the valves, is' adequate to ensure that t here' ar; no violations of. the integrity of the secondary containment.

i A list of secondary centainment automatic isolation-dampers shall be'available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.

The addition and deletion of: secondary containment aucomatic' isolation dampers shall be made in accordance with Section 50.59 of 10 CFR Part 50.

3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL t

The OPERABILITY of the rontainment iodine filter trains ensures that sufficient iodine removal capability will-be available.in the event of a LOCA. The reduction in containment iodine inventory reduces the resulti'g n

site boundary radiation doses associated with containment. leakage. The operation of this system and resultant io' ine removal capacity -are consistent d

with the assumptions used in the LOCA analyses.

The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this' equipment will be available to maintain the hydrogen concentration within containment below its-flammable limit during post-LOCA conditions. The containment inerting system is capable of controlling the expected. hydrogen generation associated with 'l) zirconium-water reactions, 2) radiolytic decomposition of water, and. 3) corrosion of metals within containment. The hydrogen control system is consistent'with the recommendations of Regulatory Culde 1.7, " Cont rol' of Combustible Cas Concentrtions in Containment Following a LOCA."

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

l

.,l '

1 ENCIDSURE 2 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1. AND 2 NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR-71 & DPR 62-REQUEST FOR LICENSE AMENDMENT PRIMARY CONTAINMENT IS01ATION SYSTEM i

(NRC TAC Nos, 67991 AND 67992)

TECHNICAL SPECIFICATION PAGES '- ' UNIT 2.

l

'l i

d'

.i INDEX

-+

BASES SECTION

.P.A.C E.

3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CHEMISTRY............................................ B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY.................................... B 3/4 4-2 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.......................... B 3/4 4-3 3/4.4.7 MAI N STEAM LI NE I SOLATI ON VALVE S..................... B 3 /4 4-7 l

3/4.4.8 S TR UCTU RA L. I NTECR I T Y................................. B 3 /4 4 ~ 7 3/4.5 EMERCENCY CORE C00LINC SYSTEM 3/4.5.1 HICH PRESSURE COOLANT INJECTION SYSTEM............... B 3 /4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)....'..........~B 3/4'5-1 3/4.5.3 LOW PRESSURE COOLING SYSTEMS......................... B 3/4.5-2 3/4.5.4 SUPPRESSION P00L..................................... B 3/4.5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 P R I MA RY CONTA I N ME NT.................................. B 3 / 4 6 - 1 3/4.6.2 DEPRESSUR IZ ATION AND COOLING SYSTEMS................. B -3 /4 6-3 3/4.6.3 PRIMARY CONTAINMENT I SOLATION VALVES................. B 3 /4 6-4 3/4.6.4 V AC UU M R E L I EF........................................ B 3 / 4 6 - 5 I

3/4.6.5 SECONDARY CONTAINMENT................................ B 3/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHERE CONTR0L....................... B 3/4 6-6 l

3/4.7 PLANT SYSTEMS 3/4.7.1 S ERVI CE W AT ER S YSTEMS................................ B 3 /4 7-1 3/4.7.2 CONTROL ROOM EMERCENCY FI LTRATION SYSTEM............. B' 3 /4 la 5

i i

BRUNSWICK - UNIT 2 XI Amendment No.

i

i i

?

DEFINITIONS i

0FFSITE DOSE CALCU' ATION MANUAL (ODCH)

The OFFSITE DOSE CALCULATIONAL. MANUAL (ODCH) is a manual' which contains the current methodology and parameters to be'used to calculate offsite doses resulting from the. release of radioactive gaseous and liquid effluents; the methodology to calculate gaseous and. liquid ef fluent monitoring.

instrumentation alarm / trip setpoints; and, the requirement s of the environmental radiological monitoring program.-

OPERABLE - OPERABILITY A system, subsystem, train,. component, or device shall. be OPERABLE or have OPERABILITY when it is capable of 'perf orming its-specified f unction (s).

Implicit in this definition shall be the assumption that. all necessary; attendant instrumentatioa, controls,' normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capaale of performing their-related support function (s).

OPERATIONAL CONDITION i

An OPERATIONAL CONDITION shall be any one inclusive combination of mode switch I

position and average reactor coolant temperatureins indicated in Table 1.2.

PilYSICS TESTS PilYSICS TESTS shall be those tests performed to measure the fundamental-nuclear characteristics of_the reactor core and.related instrumentation and are 1) described in Sect-ion 14 of the Updated FSAR, 2) aut horized under the a

provisions ~of 10 CFR 50.59, or 3) otherwise approved by thtI Commission.

PRESSURE BOUNDARY LEAKAGE t

l PRESSURE BOUNDARY LEAKACE shall be leakage through a non-isolable f ault in a reactor coolant system component 1 body, pipe wall, or vessel wall.

PRIMARY CONTATNMENT INTECRITY.

i PRIMARY CONTAINMENT INTECRITY shall exist whent l

a.

All penetrations required'to be closed during-accident conditions l

cre either 1.

Capable of being closed by an OPERABLE containment. automatic isolation valve system, or 2.

Closed by at.least one. manual-valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided ~

in Table 3.6.3-1 of Specification 3.6.3.1.

l i

BRUNSWICK - UNIT 2

!-5 Amendment No s

1

C5 -

55 TABLE 3.3.2-1 Si

'E ISOLATION ACTUATION INSTRUMENTATION 5

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

TRIP FUb'CTION SICNAL(a)

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

u 1.

PRIMARY CONT _AINMENT ISOLATION A

a.

Reactor Vessel Water Level -

1.

7.ow, Level 1 2, 6 2

1,2,3 20 8

2

'1, 2, 3 27 2.

Low, Level 3 1

2-1, 2, 3 20 b.

Drywell Pressure - High 2, 6 2

1,2,3 2 0. -

l w

c.

Main Steam Line E

1.

Radiation --High 1

2 1,2,3 21 2.

Pressure - Low

.lf5) 2 1

22

.l w

3.

Flow - High II5) 2/line 1

22 l

4.

Flow - High II5) 2 2, 3 21

'l d.

Main Steam Line Tunnel Temperature - High I I5) 2(d)

'1, 2, 3 21 l

I3)

I e.

Condenser Vacuum - Low I

2 1, 2 *-

21 l.

f.

Turbine Building Area Temperature - Hign II5}

IC}

.E 21

-l 4

1, 2, 3 2

g.

Main Stack Radiation - High:

(h)1 1

1,2,3 28

?

z h.

Reactor, Building Exhaust 6

1 1,2,3 20 l.

Radiation - High

q TABLE 3.3.2-1 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION is*

VALVE CROUPS MINIMUM NUMBER

' APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL E

TRIP FUNCTION SIGNAL (a)

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

vo 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust (1) 1 1,2,3,5, 23 l

Radiation - High and

  • 6 1

1, 2, 3 20 l~

b.

Drywell Pressure - High (1) 2 1, 2,.3 23 2, 6-2 1,2,3 20 Reactor' Vessel Water-Level'-

(1) 2 1,2,3 23 c.

Low, Level 2 3

2 1, 2, 3

'24 w

it w

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION L

A Flow - High 3

1

.1, 2, 3 24 a.

b.

Area Temperature - High 3

2 1,2,3 24 c.

Area Ventilation A Temperature - High 3

2 1,2,3 24 l

II) d.

SLCS Initiation.

3 NA 1, 2, 3 24-e.

Reactor Vessel Water Level -

Low, Level 2 3

2 1,'2,.3 24-f.

A' Flow - High - Time Delay Relay NA 1

1,2,3 24 l

E.

!.g

.E

-.c

+ ' -

.E TABLE 3.3.2-1 (Continued)

E E

ISOLATION ACTUATION-INSTRUMENTATION F;

VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATEP BY OPERABLE CHANNELS OPERATIONAL E

TRIP FUNCTION SIGNAL (a)

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

ha 4.

CORE STANDBY COOLING SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High 4

1 1,2,3 25 2.

HPCI Steam Line Flow - High Time Delay Relay NA 1

1,-2, 3

25

'l 3.

HPCI Steam Supply Pressure - Low 4) 2 1, 2, 3 25 us

'7 1

1,2,3 25 l,

us 4.

HPCI Steam Line Tunnel f

Temperature - High 4

2 1,2,3 25 IK)'

1/ bus 1, 2, 3 26 5.

Bus Power Monitor NA 6.

HPCI Turbine Exhaust Diaphragm Pressure - High.

4 2

1,2,3 25 7.

HPCI Steam Line Ambient Temperature - High 4

1 1,2,3 25 8.

HPCI Steam,Line' Area A Temperature - High 4

1 1,2,3 25 l

E 9.

HPCI Equipment Area Temperature - High 4

.1 1,2,3 25~

l c

10.

Drywell Pressure - High 7(k) 1 1, 2, 3 25 l

e

t 55 TABLE 3.3.2-1 (Continued)

Ey ISOLATION ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL (a)

PER TRIF SYSTEM (b)(c) CONDITION ACTION z

Q 4.

CORE STANDEY COOLING SYSTEMS ISOLATION (Continued) w b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High 5

1-1,2,3 25 2.

RCIC Steam Line Flow - High Time Delay Relay NA 1

1, 2, 13 25

.l 3.

RCIC Steam Supply Pressure - Lou 9[()

2 1,2,3 25

'l 1, 2, 3 25 l

4..

RCIC Steam-Line Tunnel t',

Temperature - High 5

2 1, 2, 3 25 5.

Bus Power Monitor NA IB)'

1/ bus 1, 2, 3 26 6.

RCIC Turbine Exhaust Diaphragm Pressure - High 5

2 1, 2, 3-25 7.

RCIC Steam Line Ambient l

Temperature - High 5

1.

1, 2, 3 25 1

8.

RCIC Steam Line Area A. Temperature - High 5

1_

1, 2, 3 25 9.

RCIC Equipment Room Ambient Temperature - High 5

1 I, 2, 3 2:5 y

10. _RCIC Equipment Room a Temperature - High 5

1 1,2,3 25 a

c.

2~

11.

RCIC Steam Line Tunnel NA.

1 1,2,3-25 E

LTemperature - High

' Time Delay Relay z.

12.. Drywell Pressure - High 9(k) 1 1,2,3 25

.~.

2.

6:

~

t l

E' TABLE 3.3.2-l'(Continued).

E

- E

. ISOLATION ACTUATION INSTRUMENTATION

.-n

' MINIMUM NUMBER

~

VALVE CROUPS 12PLICABLE -

OPERATED BY OPERABLE CHANNELS OPERATIONAL

E

TRIP FUNCTION SIGNAL (a)'

PER TRIP' SYSTEM (b)(c) CONDITION' ACTION l A

w 5.

SHUTDOWN COOLINC: SYSTEM ISOLATION a.

Reactor. Vessel) Water Level -

2, 6 2

- 1,=2, 20.'

Low, Level I 8

2

. I';-2,~3

- 27.

8 I}

El 1,:2, 3:

27.;

1 I

b.

Reactor-Steam Dome Pressure.High m

1 -

- u 0

' W

~

..O'

..m..

W

^v e-+-

w

,I 4

r A

9

'~

_ e

~

e

~

"g "2

s rv

+

,,l o.

...u.

e r

m 4

e.

._.-e,.m.,..,

3,_...

m

,,w,,.. _ _...,....,,_.....m_

s

_.4.4._.,-.,..,,.e.v.,_...

i..L..#..,..,m

-.m.7..'

,,, 1..q J,,, _. _.2;. ;,

.e_,,s.-.,._~..s4,_,

. _ c ',:~.

1

~

TABLE' 3.3.2-1 (Continued )

ISOLATION ACTUATION INSTRUMENTATION NOTES WSen handling irradiated fuel in the secondary containment.

(a)

See Speci fication 3.6.3.1, Table 3.6.3-1 for' ~ valves in each valve-group.

(h)

A channel may be placed in an inoperable ' status f or up' to-2 hours -f or-required surveillance without placing the trip. system in the tripped '

condition provided at least one other OPERABLE channeliin the same trip' z

system is monitoring that parameter.

(c)

With only one' channel per t rip: system, an inoperable channel need.notf 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the. ACTION requir'ed' by

. Table 3.3.2-1 for that Trip Function shall be taken.

~

(d)

A channel is OPERABLE if 2 of 4' instruments in that1 channel-are OPERABLE.

(e)

With reactor steam pressure > $00 psig.

(f)

Closes only RWCU outlet isolation valve.

(g)

Alarm only.

(h)

Isolates containment purge and vent valves.

(i)

Does not isolate Ell-F015A,B.

(j)

Does not isolate B32-F019 or B32-F020..

(k)

Valve isolation depends upon low steam supply -pressure coincident with:'-

high drywell pressure.

(1)

Secondary containment -isolation dampers as listediin Table 3.6.5.2-1.

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

.e.

5 TABLE 3.3.2-2 E

E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS R*

ALLOWABLE TRIP FUNCTION-TRIP SETPOINT-VALUE E

'Q l.

PRIMARY CONTAINMENT ISOLATION m

a.

Reactor Vessel Water Level -

1.

Low. Level 1

~> + 162.5 inches (a)

~> + 162.5. inches (a) 2.

Low, Level 3

> + 2.5 inches (a)

> + 2.5 inches (a)

. l b.

Drywell Pressure - High-1 2 psig 1 2 psig c.

Main Steam Line 1.

Radiation - High 53x fullpgwer 53.5x'fu{l y power-background background w

N u

2.

Pressure - Low

> 825 psig L

_ > 825 psig 3.

Flow - High 5 140% of rated: flow

$ 140% of rated flow 4.

Flow - HigL

$_40% of rated' flow

$'40% of ratedfflow-d.

Main Steam Line Tunnel 1 Temperature - High 5 2.v'F

$ 200*F e.

Condenser Vacuum - Low

> 7-inches Hg vacuum

> 7 inches Hg vacuum f.

Turbine Building Area. Temperature - High.

$ 200*F

$ 200*F

[

g.

Main Stack Radiation - High (b)

(b)

E.

h.

Reactor Building Exhaust Radiation - High

'$ 11 mr/hr 5 11 mr/hr l.

R

.E r

' ' ' ~

~

~ " " '

~~

wr**'

rw, *

~ =

r-a

=m,--.'

. a E

TABLE 3.3.2-2 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5*

ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE e

Ci 2.

SECONDARY CONTAINMENT ISOLATION w

a.

Reactor Building Exhaust Radiation High 5 11 mr/hr

$ 11 mr/hr b.

Drywell Pressure - High

$ 2 psig 5 2 psig c.

Reactor Vessel Wat er Level - Low, Level 2 3 + 112 inches (a)

>1+ 112 inches (a)'

3.

REACTOR WATER CLEANUP SYSTEM" ISOLATION a.

A Flow - High

$ 53 gal / min 1: 53 gal / min b.

Area Temperature - High

_$ 150*F i 150*F' -

c.

Area Ventilation A Temperature - High 5 50*F

$ 50*F'~

-l' d.

SLCS Initiation NA NA

.112 inches (a)~

> + ll2. inches (a) e.

Reactor Vessel Water Level'- Low, Level 2

>+

f.

A Flow - High - Time Delay Relay'

$ 45 seconds.

< 45 seconds

-l E

a i

e n

- ~ <

v-

--y'n e"--

e - ~ -

1, s

ww.

vs..--

e E

TABLE 3.3.2-2 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E-ALLDWABLE TRIP FUNCTION TRIP SETPOINT VALUE E

U 4.

CORE STANDBY COOLING SYSTEMS ISOLATION u

a.

High Pressure Coolant Injection Syster Isolation 1.

HPCI Steam Line Flow - High 5 300% of rated flow

$ 3001 of rated flow 2..

HPCI Steam Line Flow - High Time Delay Relay.

3 $ t $ 7 seconds 3 $ t i 12 seconds

-l 3.-

HPCI Steam Supply Pressure - Low

> 100 psig

> 100 psig 4.

HPCI Steam Line Tunnel Temperature - liigh 5 200*F

$ 200*F-u 5.

Bus Power Monitor NA NA d

6.

HPCI Turbine Exhaust Diaphragm Pressure - High.

$ 10 psig-

$ 10 psig 7.

HPCI' Steam Line Ambient Temperature - High

$ 200*F

$'200*F

.l 8.

HPCI Steam Line Area a Temperature.- High

$ 50*F

$'50*F 9.

'HPCI Equipment Area Temperature High'

$ 175'F

$ 175*F ll

10..DrywellTPressure --High

$ 2 pr.ig

$ 2 psig l-E a

E

.?.

=

E TABLE 3.3.2-2 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5

f' ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE E

Q 4.

CORE STANDBY COOLING SYSTEMS ISOLATION (Continued) w b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High 5 3001 of rated flow

$ 300% of rated. flow-2.

RCIC Steam Line Flow

.High Time Delay Relay-3 $~t $ 7 seconds 3$t 5 12' seconds l'

3.

RCIC Steam Supply Pressure - Low 3'50 psig 2 50 psig w

4.-

RCIC Steam Line Tunnel Temperature - High 5 175*F

< 175*F

~

v 5.

Bus Power Monitor NA NA v

O 6.

.RCIC Turbine Exhaust Diaphragm Pressure - High

.5 10'psig'

$L10 psig 7.

RCIC Steam Line. Ambient Temperature - High' 5 200'F

$ 200*F l.

8.

RCIC Steam Line Area A Temperature - High' 5 50*F '

$ 50*F l

9.

RCIC Equipment Room Ambient Temperature - High 5 175'F.

5 175'F

'l 10.

RCIC Equipment Room 2

a Temperature - High 5 50*F

.$ 50*F1

.l c.

2 11.- RCIC Steam Line Tunnal Temperature'- High 5 30 minutes 5 30 minutes E

Time Delay, Relay' 12.

Drywell-Pressure - High

< 2 psig

'$ 2 psig

~.

, _.,.. _. ~.... ~.

,en TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME -

TRIP FUNCTION-RESPONSE ' TlHE (Second s )(a )(e) l '.

PRIMARY CONTAINMENT' ISOLATION a.

Reactor Vessel Water Level --

1.

Low, Level 1

<13-

< 1. (d)'

2.. Low, i.evel 3 713gII b.

Drywell Pressure - liigh-

$13 c.

Main Steam Line l.

Radiation - High(b)

(g, (d)

I)

I

_13 2.

Pressure - Low

<13

<0. Id) 3.

Flow - liigh 313gI).

}

'<0. (d) 4.

Flow - High

-313gI) y; d.

- Main Steam Line Tunnel Ten.perature - liigh'

$13 c.

Condenser Vacuum - I.ow

$13 p

f.-

Turbine Building Area Temperature - High NA

[

g.

Main Stack Radiation liigb(b)

<l.0(d)'

t

)

h.

Reactor Building Exhaust Radiation High

. N A' l'

2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b) g3 a.

b.

Drywell Pressure - High

<13-1

~

l c.

Reactor Vessel Water Level - Low, Level 2

$13 l

3.

REACTOR WATER CLEANUP SYSTEM IS0lATION a.

A Flow - High

<45(C) b.

Area Temperature - High

<13 c.

Area Ventilation 6 Temperature - High

$13 li d.

SLCS Initiation NA Reactor Vessel Water Level - Low, Level 2

<13 4

e.

f.

A Flow - liigh - Time Delay Relay NA BRUNSWICK - UNIT 2 3/4 3-23 Amendment No.

.~

s TABLE 3.3.2-3 ' (Cont inued)

ISOLATION SYSTEM 11NSTRUMENTAT10N' RESPONSE TIME' IRESPONSE' TIME (Seconds)(a)(e) hj TRIP FUNCTION

,a 4.

CORE STANDBY COOLING SYSTEMS ISOLATION.

1

-a.

liigh Pressure Coolant Injection System Isolat' ion?

+

7

1. 'llPCIESt'eam'Line Flow - liigh:

' < 13 f C ) -

)

f 2.

110C1 Steam Line Flow'--liigh Time-Delay. Relay-ENA.

l.

3.

.llPCI Steam Supply Pressure - Low 513-9

-?

4.-

IIPCI Steam Line TunnelL Temperature = - II,igh 513:

l'

.5.

Bus Power Monitor NA~

[

C

~

'l

-LIP'l Turbine Exhaust Diaphragm 1 Pressure.- liigh NA' 6.

,7. illPCI ~ Steam Line Ambient Temperature - liigh?

NA 9:

8.1 IIPCI Steam Line Area a-Temperatur,e lligh INA l

~

9.

!!PCI Equi pment Area Temperature -- High t.

JhA -:

.l.

10.

Dryweli Pressure)- liight NA l

k b.

Reactor Core' Isolation Cooling System.! solation' -

Ja 1.

RCIC Steam. Line Flow - liigh

,$13(c)'

_l

-l 2.

RCIC Steam Line Flow -'liigh Time Delay 1 Relay NA lJ 3.

RCIC Steam Supply Pressure - Low

-NA O

4.

RCIC Steam Line Tunnel Temperature - liigh4 NA;

~l 5.

Bus Power Monitor-

NA-I 6.

RCIC Turbine Exhaust Diaphram1 Pressure '- liigh J NA-7.

RCIC Steam Line Ambient. Temperature - High

<NA 8.

RCIC' Steam Line Area.6 Temperature

lligh

-NA

-l 9.

RCIC Equipment Room Ambient Temperature - liigh '

NA

[l.

10.

RCIC Equipment Room a Temperature-- liigh NA

~l y

11' RCIC Steam Line Tunnel Temperature - liigh NA Time Delay Ralay.

12.

Drywell Pressure - liigh NA-l f

1 i'i BRUNSWICK - UNIT 2 3/4 3-24 Amendment No.

f I

+

(

i.._

s-e_

'-.-_--1

~. p 3'.<,-.

3 q,

t

.g_;,

..y.-

. - - i 4

. 30 r,-

,,._y e.

i 4_ % 3

i

~b-r N

'A f

,3 Y

9.

_q :

d.?

Y N

+

. p i

r

.8 i

hk

~.

. ; n-n r

,.:y ;;

. h.

1

-. TABLE 3'.3.2-3. (Cont inued)-.

l iq

' I SOLATION : SYSTEM J INSTRUMENTAT10Nl RESPONSE TIME <

(

.. ~;

- TRIPNUNCTION-.

t iRESPONSETIME'(Seconds)(")S*I[-.. b G

5.:, SilVTDOWN -C00LINC SYSTEM ISOLATIONJ 11 w

1 s.-

n

~...

s

- a.-

. React or. Ves seixWater.? Level _ -1 Low; t.evel. li NA.

,i s.

.x

,bb l Reactor Ste'am Dome"ressiire -; High

' nan yr-n 1

.J

+.

y l;

. f.

t

[

t

' y '.

a

5

't!-

li, i

i

!g 1

o u

~l

> g :.

?;

e 3

r s

Q r

~

a-1 4

y

.g.

w,

, j',' t 3

i[

. q_

-s m.

y at +

s

._ v.

3 3

t e

a_

Ui.

g

~

e i

.l.-

1

c :.

a

+

4 e,

,E s

?

3 J.

,e.:

9' v

j

-5

, i li-r

'.1 1J k

4

i e

h

~

y-1 m:.

BRUNSWICK --UNIT 2'

'3/4 3 25

' AmeNdmentfNo.

[!

^

g.

,,4

= n

- )

?_;

)

l

L e _

.M'.

.I TABLE'3.3;2-3L(Continued)-

ISOLATION SYSTEM' INSTRUMENTATION RESPONSE TIME F

NOTES'

-(a)~

The isolation system instrumentation res~ponse time shalltbe measured'and-

~

recorded as a1part of the,lSOLATION SYSTEM' RESPONSE lTlHE. -isolation-system instrumentation response time L specifiedl includes.any1delayEfor1 diese1' generator' starting! assumed infthe accident analysis.:

i (b)

Radiation. monitors are ' exempt. f rom response time-t e' sting. ; Response t time:

shall be measured f rom-detector ; output crithe l input of thel:first--

electronic.componentiin the' channel.

0 (c) includes : time-delay added by the 't ime delaygrelayi (d)

Isolation actuation instrumentation response' time [for:MSIVs only.

No, diesel generator delays-assumed.

(e)

Isolation system instrumentation response < time >specified;forfthe: Trip.

<l Function actuating eachLvalve group / damper-shall be:added: Locthe].

j isolation time f or valves /in each valve group:shown in Table 3.6.3-1 and-

-secondary containment 7 isolation; dampers,shownLin, Table 3.6.5.2-1 to obtain ISOLATION' SYSTEM kESPONSE TIME ' for 'each v'al ve/dampe'r;.

j i

q (f)

Isolation system instrumentation response time for associated' valves

)l j

except HSIVs.

}

d s

4

-. )

-i

\\

f s

'i BRUNSWICK - UNIT 2 3/4 3-26 Amendmai.t he

.l

i

l e-5 TABLE 4.3.2-I E

E ISOLATION ACTUATION ' INSTRUMENTATION SURVEILLANCE REQUIREMENTS isn CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL' CONDITIONS IN WHICH e

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Ei 1.

PRIMARY CONTAINMENT ISOLATION r.

a.

Reactor Vessel Water Level -

1.

Low, Level 1 Transmitter:

NA(a)

NA R(b) y, y 3 Trip Logic:

D M

M 1,2,3 2.

Low, Level 3 Transmitter:

NA(a)

NA R(b) 1, 2, 3 Trip Logic D

M M

1, 2, 3 b.

Drywell Pressure - High Transmitter:

NA(a)

NA R(b) 1 2, 3 Trip Logic:-

D M

M 1, 2, 3 c.

Main Steam Line IE) y 1.

Radiation - High D

W R

1, 2, 3 m

2..

Pressure - Low Transmitter:-

NA(a)

NA R(b) 3 Trip Logic:

D M

M 1

3.

Flow - High Transmitter:

NA(a)

NA l-(A}-

Trip Logic:

D M

M 1

4.

' Flow - High D

M

M 2,. 3 d.

Main Steam Line Tunnel Temperature-- High-NA M

R 1, 2, 3 s

e.

Condenser Vacuum - Low D-Transmitter:

NA(a)

NA

'R(b) y,2(e)

IE) l Trip Logic:

D M

'M 1, 2 e

f.

Turbine Building Area z

,o Temperature - High NA M

R 1, 2, 3 l

g.

Main Stack Radiation - High NA Q

R 1, 2, 3 h.

Reactor Building Exhaust l'

Radiation - High D

H R.

1, 2, 3

=

+

o E

TABLE 4.3.2-1 (Continued)-

.E-E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E

G

-TRIP FUNCTION CHECK TEST CALIBRATION SURVEILIAHI REQUIRED u

2.

SECONDARY CONTAINMENT ISOLATION a..

Reactor Building Exhaust III l

Radiation - High D

M R

I 2,3,5, and b.

Drywell Pressure High -

Transmitter:

NA(a)

NA R(b)

I, 2, 3 Trip Logic:

D M

M I, 2, 3 c.

Meactor Vessel Water Level -

w Lov, Level 2 S

Transmitter:

NA(a) -

NA R(b) 3, y 3_

Trip Logic:

D M

M I, 2, 3 w

u" 3.

REACTOR WATER CLEANU/ SYSTEM ISOLATION a.

8 Flow - High D

M R

I, 2, 3 b.

, Area Temperature - High NA M

R 1, 2, 3 c.

Area Ventilation a Temperature - High NA M

R I, 2, 3 l

d.

SLCS Initiation NA 9

NA I, 2, 3

.e.

Reactor Vessel Water Level -

5 Low, Level 2 5.

Transmitter:

NA(a).

NA R(b)

I, 2, 3 5

Trip Logic:

D

-M M

I, 2, 3 3

m f.

a' Flow - High - Time Delay Relay NA M

R-1, 2, 3.

l

R-E TABLE. 3.2-1 (Continued)

E E

ISOIATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Es CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED G

u 4

CORE STANDBY COOLING SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High Transmitter:

NA(a)

NA R(b) 1 2, 3 Trip Logic:-

D M

M 1, 2, 3 2.

HPCI Steam Line Flow - High Time Delay Relay NA R-R

1. 2, 3

.l b

3.

HPCI Steam Supply Pressure - Low NA M

R 1, 2, 3 u

4 4

HPCI Steam Line Tunnel Terperature - High NA M

.Q 1, 2, 3 5.

Bus. Power Monitor NA R

NA I, 2, 3 6.

HPCI Turbine Exhaust s

Diaphragm Pressure - High NA M

Q 1, 2, 3 7.

HPCI Steam Line Ambient Temperature - High NA M

R 1, 2, 3 l

8.

HPCI Steae Line Area

-5 a Temperature - High NA.

M R

1, 2, 3 l.

a 2-9.

HPCI Equipment Area E

Temperature - High NA M

Q~

1, 2, 3

.j z

7 10.

Drywell Pressure - High

~

Transmitter:

NA(a)-

NA R(b).

I, 2, 3

-Trip Logic:

D M

M 1, 2, 3

l-

-e-l I

l.

E TABLE 4.3.2-1 (continued)

E i

y If,OLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

~

E CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHA!NIEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 3

4.

CORE STANDBY COOLING SYSTEMS ISOLATION (Continued) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High Transmitter:

NA(a)

'NA R(b) 1, 2, 3 Trip Logic:

D

-M M

1, 2, 3 2.

RCIC~ Steam Line Flow - High Time Delay Relay NA R

R 1, 2, 3 l

3.

'RCIC Steam Supply Pressure - Lov NA M-Q 1, 2, 3 t'

4 RCIC Steam Line Tunnel Temperature - High N f.

M R

1, 2, 3.

l.

S.

Bus Power Monitor llA R

NA

' 1, 2, 3 o

6.

RCIC Turbine Exhaust Diaphragm Pressure - High NA M

R 1,

2,- 3 7.

RCIC Steam Line Ambient-l Temperature - High NA M

R 1, 2, 3 5

8.

RCIC Steam Line Area l

a Temperature - High NA; M

R.

1, 2, 3 e-9.

RCIC Equipment Room Ambient l~

Temperature - High' NA M

Q.

I, 2, 3

.I f

10.. RCIC Equipment Room

' L.

a Temperature - High NA M

.Q 1,

2,- 3 n

5.

?,.

11.

RCIC Steam Line Tunnel Tempera-I l

ture - High Time Delay Relay NA M

R 1, 2, 3 l

12.

Dryvell Pressure - High-Transmitter:

NA(a)

NA R(b) 1, 2, 3 Trip Logic:

D M

M-

.1, 2, ' 3 l

. ~..

.,.2

_u-

t a

l I

TABLE 4.3.2-1 (Cont inued)

ISOLATION ACTUATION IWSTRUMEWTAT10W SURVEILLANCE REQtilREMENTS NOTES (a) The transit ter channel check is satisfied by the t rip unit' channel check. A ssparate t ransmitter check is not required.

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

(c) If not perf ormed within the previous 31 days. -

(d) Testing shall verify that the mechanical vacuum pump trips'and the.

I mechanical vacuum pump line valve closes.

(e) When reactor _ steam pressure 3 500 psig..

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

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

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' Pk! MARY COWTAINMENT 180LAttoll vat.'VES L

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Table 3.6.3-1:has been-deleted.-

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. Heter to ' Plants Procedure RCl*02.6.

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I Pages. 3/4' 6-lb through' 3/4 6-5 7. have' been deleted.'

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i l6 (Next page is 3/4 6-18)'

g, iBRUNSWICK;- UNIT:2?

' 3/4 b-14' AniendEn't Noil:

~

4

e.

i i

CONTAINMENT SYSTEMS I

SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS LIMITINC CONDITION FOR OPERATION 3.6.$.2 The secondary containment automatic isolation dampers.nown in' f

Table 3.6.5.2-1 shall be OPERABLE.

AP,PLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, $, and *.

l t

ACTION:

[

With one or more of the secondary containment isolation. dampers specified'in Table 3.6.$.2-1 inoperable, operatiois may continue and the. provisions of-.

[

Specification 3.0.4 arc not applicable, provided that at least ione isolation

'i damper is naintained' 0PERABLE.in, eac6 af fected penetration that is open,' and t '

{

t The inoperable damper is restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, a.

or b.

The af f ected penetration is isolated by use of a closed damper within' 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or Li c.

SECONDARY CONTAINMENT INTECRITY is demonstrated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and

(

the damper is restored to OPERABLE status within 7 ilays.

-j Otherwise, in OPERATIONAL CONDITION 1, 2, or 3,- be In at l ea s t. il0T l

S* *lTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ~and in COLD SilUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise, in OPERATIONAL CONDITION $ or *,' suspend irradiated fuei.

l handling in the secondary containment, CORE ALTERATIONS, or activities that could reduce the SilUTDOWN MARCIN.

The provisions'of Specification 3.0.3 are not applicable.

t d

J

  • When irradiated fuel is being handled in the secondary ~ containment.

h i

BRUNSWICK - UNIT'2 3/4 6-22 uAmendment No.

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TA' B LE ' 3.6. 5. 2' -1"

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q SECONDARY CONTAIWMENT AUTOMATIC ISOLATION ' DAMPERS-a.

5

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n 4

j.

Table :3.6.5.2-1 has been. del et ed.

.,r

. Refer to Plant Procedure'RC1-02.6.

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.t BRUNSWICK'-. UNIT'2!

3/4 6-24 Amendment i No. :

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+

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s-

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t

=:

O i

CONTAINMENT SYSTEMS

]

BASES li4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES (Continued)-

i A list of automatic closing primary containment isolation valves and their associated closure times shall be available at the plant in accordance with Section 50.71(c) of.10 CPR part 50. The addition and deletion of primary containment isolation valves shall be made'in accordance with Section 50.59 of 10 CFR part 50.

3/4.6.4 VACUUM RELIEF 1

Vacuum relief breakers are provided to equalize the pressure ~ between the' drywell and suppression pool and the suppression pool and reactor. building,-

This system will maintain the structural integrity of the containment under conditions of large differential pressures.

The vacuum breakers between the drywell and the suppression pool must not be inoperable in the open position since this would allow bypassing of the suppression pool in case of an accident. There are an adequate number of valves to provide some redundancy so that cperation may continue with no more than 2 vacuum breakers inoperable and secured in the closed ' position.

t Each set of vacuum relief valves between the suppression chamber and react or -

building provides 100% rellel, which may be required in the unlikely event that negative press 6 res develop in the primary containment.

The Nitrogen Backup System provides backup motive power f or these ' suppression pool-reactor building vacuum breakers on a loss of instrument air..The normal y

non-interruptible inst rument air system for these vacuum breakers is designed t

as a Seismic Class 1 system supplied by air compressors powered from the

{

emergency buses.

The Nitregen System serves as a backup to the air system and thus the loss of the Nit rogen System, or portions thereo!, does not make the vacuum breakers inoperable. This design allows for the out of-service times in Actions b and c.

The Nitrogen Backup System is added to the Suppression pool-Reactor Building Vacuum Breaker specification to satisf y NRC concerns relative to 10 CFR 50.44(c)(3) as addressed in the Brunswick Safety Evaluation Report dated October 30, 1986 concerning Ceneric Letter 84-09.

pressurization to 1130 psig assures suf ficient system capacity to provide 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation with design valve actuation and system leakage.

3/4.6.5 SECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level release of radioactive material which may result from an accident. The reactor building provides secondary containment during normal operation when the drywell is sealed and in service. When the reactor is shut down or.during refueling the drywell may be open and the reactor building then becomes the primary containment.

AUNSWICK - UNIT 2 B 3/4 6-5L Amendment No.

i 4

. 3

o

+

e CONTAlWMENT SYSTEMS BASES (Continued) 3/4.6.5 SECONDARY CONTAlWMENT (Continued) l Establishing and maintaining a vacuum in the building with the standby gas treatment system, once per 18 months, along with the surveillance of the valves, is adequate to ensure that there are no violations of the integrity of

.}

the secondary containment.

. A list of secondary containment automatic isolation dampers 'shall be available f

at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The addition and deletion of secondary containment automatic isolation dampers shall be made in accordance.with Section 50.59 of 10 CFR Part ~50.

l 3/4.6.6 CONTAINMENT ATMOSPilERE CONTROL The OPERABILITY of the containment lodine' filter trains ensures that i

sufficient iodine removal capability will be available in the event of. a IDCA. ' The reduction of containment iodine inventory reduces.the resulting i

site. boundary radiat ion doses associated with containment leakage.' The operation of this system and resultant lodine removal capacity are consistent with the assumptions used in the LOCA analyses.

The OPERABILITY of the equipment and systems required for the detection and con:rol of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. The containment inerting system is capable of controlling the expected hydrogen generation associated'with'l) zirconium-water reactions, 2) radiolytic decomposition of water, and 3) corrosion of metals within containment. The hydrogen control system is consistent'with the T

recommendations of Regulatory Culde 1.7, '_' Control of Combustible Cas -

Concentrations in Containment Following a LOCA."

l

[

1 t

l -.

l BRUNSWICK - UNIT 2 B 3/4 6-6 Amendment No.

o 4

l i

ENCIDSURE 3 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT PRIMARY CONTAINMENT IS01ATION SYSTEM (NRC TAC NOS. 67991 AND 67992)

INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications (Appendix A to Operating Licenses DPR 71 and DPR 62) would be incorporated as follows:

UNIT 1 Remove Page Insert Page XI XI 15 15 3/4 3 12 3/4 3-12 3/4 3-13 3/4 3 13 3/4 3 14 3/4 3 14 3/4 3 15 3/4 3 15 3/4 3 16 3/4 3 16 3/4 3 17a 3/4 3 17a 3/4 3 18 3/4 3 18 3/4 3 19 3/4 3 19 3/4 3 20 3/4 3 20 3/4 3 21 3/4 3 21 3/4 3 23 3/4 3 23 3/4 3-24 3/4 3 24 3/4 3 25 3/4 3 25 3/4 3-26 3/4 3 26 3/4 3 27 3/4 3 27 3/4 3 28 3/4 3 28 3/4 3-29 3/4 3 29 3/4 3 30 3/4 3 30 3/4 3-32 3/4 3 32-3/4 6 14 3/4 6 14 3/4 6 15 l

3/4 6 16 3/4 6-17 3

3/4 6 22 3/4 6 22 3/4 6-24 3/4 6-24 i

B 3/4 6 5 B 3/4 6-5 B 3/4 6-6 B 3/4 6 6 i

E3 1

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UNIT.2 l

Remove Page Inmart Pame i

XI XI l

15 15 l

3/4 3 12 3/4 3 12

+

3/4 3 13.

3/4 3 13-1 3/4 3 14 3/4 3 14

{

3/4.3 15 3/4 3 15 3/4 3 1G

.3/4 3 16 l

3/4-3 17a 3/4-3 17a 3/4 3 18.

3/4 3 18 3/4 3 19 3/4 3 19 l

3/4 3 20 3/4 3 20 l

3/4 3 21 3/4 3 21-3/4 3 23 3/4 3 23 3/4 3 24 3/4 3 24 3/4 3 25' 3/4 3 25 3/4 3 26 3/4 3 26 3/4 3 27 3/4 3 27 3/4 3 28 3/4.3 28.

l 3/4 3 29 3/4 3 29 l

3/4-3 30 3/4 3 30 3/4 3 32 3/4 3 32-3/4 6 14 3/4 6 14 3/4 6 15

]

3/4 6 16 3/4 6 17 3/4 6 22 3/4 6 22 j

3/4 6 24 3/4 6 24 B 3/4 6 5 B 3/4 6 5 l

B 3/4 6 6 B 3/4 6 6 1

1 E3 2

.

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