Text

Proposed Tech Specs Increasing Instrument Surveillance Tests Intervals & Allowable out-of-svc Times
	ML20076L732
Person / Time
Site:	Brunswick
Issue date:	10/28/1994
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML19312B539	List: BSEP-94-0413, Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times; ML20076L732;
References
	NUDOCS 9411040159
	Download: ML20076L732 (118)
	v • d • e

_

3/43 !NSTRUwENTAT:3N 3/432 RE A: TOR PRO *EC":3N Sv5TEw INSTRUwENT ATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1 1 shall be OPERABLE. Set points and interlocks are_ given I in Table 2.2.1 1.

APPLICABILITY: As shown in Table 3.3.1 1.

ACTION: pggRy ) [

. re uirements for the minimum number of OPERABLE c S not~

satisf system, place the inoper nnel(s) and/or trip system in the tr1ppeu c -d' n* w' one hour.

b. With the requirements e minimum number o BLE channels not satisfied f . rip systems, place at least one t e ' stem ** i n the ed condition within one hour and take the ACTION req by '

able 3.3.1 1.

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

SURVEILLANCE REQUIREMENTS , 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL j CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1 1.

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

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function' shall be demonstrated to be within its limit at least once per 18 I months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function, yrn. SERT' 2A

erable channel need not be placed in the tripped condition whe this wou e the Trip Function to occur. In these cases s inoperable channe be restored to OPERAB . within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Ta - 6 a Trip Function shall be taken.

operable in one trip system u 'he other.

" If more channels '

place system with more inoperable channels in the trip '

< ition, exceot when this would cauce the Trio Function to occur.

' Neutron detectors are exempt from response time testing. I BRUNSWICK UNIT 1 3/4 3 1 Amendment No. 171 9411040159 941028 PDR ADOCK 05000324 P PDR

Insert 1A Daae 3/4 3-1

a. With one channel less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.1-1 in one or more Functional Units, place the inoperable channel and/or that trip system in *he tripped condition

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

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

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

to maintain trip capability in the Functional Unit, and

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

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

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

Insert 2A, pane 3/4 3-1 An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall be taken.

This ACTION applies to that trip system with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION can be applied to either trip system.

a l

l l

l

V. %.

TABLE 3.3.1-1 m

E REACTOR PROTECTION SYSTEM INSTRUMENTATION y ~

" HINIMUM NUMBER APPLICABLE M OPERABLE CHANNELS OPERATIONAL l 8 PER 1 RIP SYSTEH (a) ACTION CONDITIONS

-@ FUNCTIONAL UNIT "n Intermediate Range Monitors:

y

1. l g

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

a. 2 3, 4 1

3 2, 5

b. Inoperative 3, 4 2 2 l

2. Average Power Range Monitor & h er e N S W Sims\1t 3 z* a. Neutron Flux - High, 15%

2, 5(b) 2 2 4

b. Flow Biased ..::trer % : - High 1 2 4-Y Fixed Neutron Flux - High 120% 1 2 .5 N c. 1, 2, 5 4

d. Inoperative 1 2

(c) NA

e. Downscale 1,.2, 5 I. LPRM 6

1, 2(d) 2 1

3. Reactor Vessel Steam Dome Pressure - liigh 2 6 level 1 1, 2 _l-

4. Reactor Vessel Water Level - Low, 4 4 1

5. Main Steam Isolation Valve - Closure 7 1, 2(d) 2

6. Main Steam Line Radiation - liigh h

a

's c

O

_ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ . _ _ . , _ _ _ _ __ ___.________ _ ______ _ ____ _ z___m _ _ _

_ # _ ---w ._ _ - _ + .- . - - , -- .. -

fp i

TABLE 3.3.1-1 (Continued) ll

si REACTOR PROTECTION SYSTEM INSTRUMENTATION 5

E MINIMUM NUMBER

' APPLICABLE OPERATIONAL OPERABLE CHANNELS gj PER TRIP SYSTEM (a) ACTION COliDITIONS y FUNCTIONAL UNIT 1, 2 I* ) 2 6

7. Dryvell Pressure - High 5

1, 2, S II) 2

8. Scram Discharge Volume Water Level - High 8-

9. Turbine stop Valve - Closure I I8I 4 I

10. Turbine Control Valve Fast Closure, 8 I IE} 2 Control Oil Pressure - Lou 9

U 1,2,3,4,5 1

11. Reactor Mode Switch in Shutdown Position 10 ,

Y 1,2,3,4,5 1 u 12. Manual Scram i, z, 3,'i, 5 2.

10 X

13. AubaGc Scrax Conhtors ,

e u

B n

O t

_, nw- -,,=, m & v= -w -ew -e- e - .-~a-- -

= . " * - .e + + -ee = .-= - - - * - - - -

r TABLE 3.3.1-1_(Continued) i REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 10 - In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

the Shutdown position within one hour. ,

In OPERATIONAL CONDITION 5, suspead all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert ,

all insertable control rods within one hour.

I I.N6ERT 3A NOTES (a) may be placed in an inoperable status for u e or

'{bt+eanal required surveillance wid. car olacjn? ^^ .. .e ,ys tem in the tripped condition provided one opt.tunaE u. M in the same trip '

j (syste p = .. oring that parameter.

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

and shutdown margin

} demonstrations.

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

(d) These functions are not required to be OPERABLE when the reactor l l

pressure vessel head is unbolted or removed.

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

INTEGRITY is not required. ,

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

(g) These functions are bypassed when THERMAL POWER is less than 301.of RATED THERMAL POWER.

I I

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

l i

1 3/4 3-5 Amendment No. 130 BRUNSWICK - UNIT 1

Insett 3A. Dane 3/4 3-5 When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability.

i

U g, TABLE 4.3.1-1 lii y REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CilANNEL OPERATIONAL

CONDITIONS IN WHICil CilANNEL FUNCTIONAL CilANNEL

' CALIBRATION (a) SURVEILLANCE REQUIRED l CHECK TEST E FUNCTIONAL UNIT -

n r 1. Intermediate Range Monitors:

l D S/U(b)(c) g(d) R 2

a. Neutron Flux - liigh R 3, 4, 5 D W W Id) NA 2,3,4,5 NA

b. Inoperative

2. Average Power Range Monitor:

( )(m) , g(d) Q 2 t' a. Neutron Flux - lingh 15% S 8

"g S

b 9 5 I simlated Them3( B">F S/U(b) ,g k y(e)(f),q g [

Flou-Biased ":::.... % 5 liigh S b.

S/U(b) g ? Q g(e) ,q g K

c. Fixed Neutron Flux - Nigh, 120% S ,

NA

") HA 1, 2, 5 K.

d. Inoperative h-

e. Downscale NA kQ NA 1 D NA (g) 1, 2, 5

f. LPRM

3. Reactor Vessel Steam Dome Pressure - liigh N A(k) R(I) 1,~2 g NA 1, 2 .

!j Transmitter: D hl h Q' y Trip Logic:

E Reactor Vessel Water Level - Lou, Level 1

" 4. N A( k) HA R II) 1, 2 1, 2 y

Transmitter:

Trip Logic:

D MQ %Q K~

t: .

W

" TABLE 4.3.1-1 (Continued)

o E

y REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CilANNEL OPERATIONAL

" CllANNEL CONDITIONS IN WilICil

' CllANNEL FUNCTIONAL TEST CALIBRATION (a) SURVEILLANCE REQUIRED CilECK E FUNCTIONAL UNIT NA -M* Q R(h) g 7

, 5. Main Steam Line Isolation Valve - Closure R(N 1, 2 -

6. Main Steam Line Radiation - Nigh S k)g

7. Dryvell Pressure - liigh NA(k) NA R II) 1, 2 Transmitter:

Trip Logic: D Mk Wk 1, 2 [.

R 1, 2, 5 NA Q

8. Scram Discharge Volume Water Level - liigh R(h) 3(o): K t

9. Turbine Stop Valve - Closure NA ---M7 Q Y 10. Turbine Control Valve Fast Closure, II I m R NA -- M-3. Q Control Oil Pressure - Low NA 1, 2, 3, 4 5 HA R ,

11. Reactor Mode Switch in Shutdown Position 5-NA 1, 2, 3, 4 NA Q

12. Manual Scram N Nb I l 2, j3f Vf N 7 \

\3, AutoMitic. Scr3h b>nk46IOfi NA 5 i a

9' s,,

O 6

g m- g g y ,--- y , ,w- - - - , -w,- <m e , eor - n mw - , e

TABLE 4.3.1-1 (Continued 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REOUTREMENTS NOTES (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

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

(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perfom the required surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2, if not performed within the previous 7 days. l (e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25%

of RATED THERMAL POWER.

(f)

This calibration shall consist of the adjustment of the APRM flow biased to conform to a calibrated flow signal.

' (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.

(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.

quarterly (1) Transmitters are exempted from the 32Dthif~ channel calibration.

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

(n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.

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

) THERMAL POWER.

3/4 3-9 Amendment No. 162 BRUNSUICK - UNIT 1

l NS'R'ME NT ATION 3/43? ISOLATION ACTUATION !NSTRUMENTAT10N LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.21 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2 2. 1 APPLICABILITY: As shown in Table 3.3.2 1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value sh;wn in the Allowable Values column of Table 3.3.2 2. declare the channel inoperable =d p'rc -

-the d epc eble chamne' da the t-4pa^d :;nditie;*tTntil the channel is N restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. INSERT IB the requirements for the minimum number of OPERABLE channel not sa r one trip system. place the inoper ie (s) and/or that trip sy he tripped co . within one hour.

~

c. With the requirements f minimum nui PERABLE channels not satisfied trip systems, place at leas c

system **

in th ed condition within one hour and take the ACTION re able 3.3.2 1.

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

SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL ,

CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL l CONDITIONS and at the frequencies shown in Table 4.3.2 1.

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

[*

f this woul able cnannel need not be placed in the tripped condition where a Trip Function to occur. In these cases the

)

inoperable channel sha ored to OPERABLE status e hours or the ACTION required by Table 3.3. -

taken.

that T ' nction shall be [l If more channels are in n one trip system in the other, place the tr' with more inoperable channels in t oed !

con . except when this would cause the Trip Function to occ BRUNSWICK UNIT 1 3/4 3-10 Amendment No. 171 l

Insert 1B, pane 3/4 3-10

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

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

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

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

within:

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

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

1 l

l I

l l

4 INSTRU"ENTA~0N ,

==

l SURVEILLAN:E REQUIREMENTS.(Continued)-

._ I l 4.3.2.3 The ISOLATION be demonstrated SYSTEM RESPONSE to be within its limit at least once per I h test are tested TIME.of

)M(

18 months.,,,

a shall include at least one logic train such that both at all chain logic h total at least once per 36 months and one channel per function suc channels are tested at least' once every N times 18 months where number of redundant channels in a spec 1fic isolationtr2Ih5 function.

t t

i

' Radiation monitors are exempt from response time testing.

i l

t i

Amendment No. 171 3/4 3 11 BRUNSWICK UNIT 1

r 4 "'ASLE 3.3.J '. (Cent:nuie>

SOLATION ACTUATION I NSTRLHENTATI ON NOTES

When handlar.e trradiated tuel in the secondary caiit a i nmen t (a) See Speci t i cat i on J.o .3.1. Table 3.o.3-1 tor valves in each valve group. -

ENSEL'T 2.B (b) fd ::- - ev oe piacco a i, an 2nuperause status tor 2 .. 3 for required survesitana . '+t M t ne trip system in the t ri pped con eas W ERABLE channel in it he e- ., s ys t em i s mon t t oring that pa ramet er .

(c)DckIfd1 -

one enannet per trip system, an inoperable cnannel n-not be place ' ripped condition where this wou e the Tri p Function to occur. . cases ' . erable channel shall be re s t o r ed t o A""" " .. Lm s ta t u s UTiii . '

knurs or the ACTION y .2-1 !or that Trip Function sha h .

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

(e) With reactor steam pressure > 500 psig.

(t) Closes only RWCU outlet isolation valve.

(g) Alarm only.

(h) Isolates containment purge and vent valves.

(i) Does not i sol at e Ell-F015 A,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 iisted in Table 3.6.5.2-1. ,

s 1 Amendment No. 149 BRUNSWICK - UNIT 1 3/4 3-17a

W

Insert 28, pane 3/4 3-17a When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed as follows:

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

(b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions, provided the Trip Function maintains isolation actuation capability.

1 1

I l

1 l

t bor' we ,

TABLE 4.3.2-1 E

g ISOLATION ACTUATION INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS tn CHANNEL OPERATIONAL.

i FUNCTIONAL CilANNEL- CONDITIONS IN WHICil CilANNEL Q CilECK TEST CAllBRATION SURVEILLANCE REQUIRED

, TRIP FUNCTION E 1. PRIMARY CONTAINHENT ISOLATION y

a. Reactor Vessel Water Level -

~

1. Low, Level I R(b) g, 7, 3 Transmitter: N A( a ) NA b

Trip Logic: D H-PQ % I , 2, 3

2. Low, Level 3 II'I 1, 2, 3 Transmitter: NA(a) NA R 1 rip Logic: D Sq MQ 1, ' 2 , 1- .K

b. Drywell Pressure - liigh R(b) 1, 2, 3 NA(a) NA Transmitter:

%Q N.

Trip Logic: D hQ 1, 2, 3 w Main Steam Line

%Q

c. R(d) 1, 2. 3 .

N 1. Radiation - High D w

,', 2. Pressure - Low R(b) g w Transmitter: NA(a) NA l uk Trip Logic: D %Q hq

3. Flow - lii gh R IDI. 1 NA(a) NA Transmitter:

Trip Logic: D gg 1 k

d. Main Steam Line Tunnel Temperature - liigh NA % R 1, 2, 3

[

Condenser Vacuum - Lou "I e.

Transmitter: NA(a) NA R(b) 1, 2(I'I N Trip Logic: D % h 1, 2 E f. Turbine Building Area Temperature - High NA % R 1, 2, 3 lk R 1, 2, 3 Main Stack Radiation - liigh NA Q g.

h. Reactor Building Exhaust I Radiation - High D kR R 1, 2, 3

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

. - --~ . . __, _ _ _ _ _ _ -_ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _

l l g W **

! E i !e y TABLE 4.3.2-1 (Continued) i ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

5 CIMNNEL OPERATIONAL i

' " CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH-TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Buildin Exhaust

, Radiation - H gh D h R 1.2.3.5 and'" N

b. Drywell Pressure - High Transmitter: NA(*) NA Rm 1. 2, 3 Trip logic: D

-bg %Q 1. 2. 3 X

c. Reactor Vessel Water Level -

Y Law. Level 2 N

Transmitter: NA(') NA R)ib

1. 2. 3 gi Trip Logic: 0 bQ bp 1. 2. 3

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

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

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

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

d. SLCS Initiation NA R NA 1. 2

& e. Reactor Vessel Water Level -

g Low. Level 2 N

=> Transmitter: N A' ' ' NA R 1. 2. 3 v

[

O Trip Logic: D y hQ 1. 2, 3 ^

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

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

,- % w- s. . ---ms, is---.- ,,wa % .c.. e im w

(, ,

E

~

5 r,

TABLE 4.3.2-1-(Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS b

-i CllANilEL -

.- OPERATIONAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICil

- TRIP FUNCTION CHECK TEST CALIBRATION -SURVEILLANCE REQUIRED.

4. CORE STANDBY COOLING SYSTEMS ISOLATION

a. liigh Pressure Coolant Injection-System Isolation

1. IIPCI Steam Line Flow liigh Transmitter: NA NA R'" 1. 2. 3 Trip logic: D MQ h Q. 1. 2. 3 X w 2. IiPCI Steam Line High Flow 3;: Time Delay Relay NA R R 1. 2. 3 5 3. IIPCI Steam Supply Pressure - Low NA WQ R 1. 2. 3 K w

4. }{PCI Steam Line Tunnel Temperature - High NA SA R 1. 2. 3 -l S. Bus Power Honitor NA R NA 1.2.3-

6. HPCI Turbine Exhaust Diaphragm Pressure - liigh NA

%)Q Q 1. 2. 3_ ~1

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

@ 8. IIPCI Steam Line Area 8- A Temperature - liigh NA SA R 1. 2. 3

9. HPCI Equipment Area g Temperature - liigh .NA SA R 1. 2. 3 s 10.

g Drhell Pressure - liigh ansmitter: NA NA R(" 1. 2.-3 Trip Logic: D hg % 1. 2. 3 N

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

v v y TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION . SURVEILLANCE REQUIREHENTS R CHANNEL OPERATI0tML CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WilICll TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g

A 4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

b. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam Line Flow - High tb Transmitter: NA(') NA R> 1. 2. 3 Trip Logic: D -ft9k --&-p Q 1. 2. 3 X

2. RCIC Steam Line Flow - liigh Time Delay Relay NA R R 1. 2. 3 RCIC Steam Supply Pressure - Low NA Q 1. 2. 3 X

3. --tt9 Q S 4. RCIC Steam Line Tunnel y Temperature liigh NA SA R 1. 2. 3 l

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

6. RCIC Turbine Exhaust Diaphragm Pressure - liigh NA Pq R 1. 2. 3 X.

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

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

a.

Po 10. RCIC Equipment Room R 1, 2. 3 l A Temperature - liigh NA SA R

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

! $ 12. DrhellPressure-liigh N A' ' ' NA R>tb 1, 2. 3 y

ansmitter: 1. 2. 3 Trip Logic: D h %yQ

( .

c uss . %&

"' TABLE 4.3.2-1 (Continued) as E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE-REQUIREMENTS

'C ' . .

n CilANNEL OPERATIONAL E

CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WillCil 8

TEST CALI BRATION SURVEILLANCE REQUIRED h.

CilECK

@ TRIP FUNCTION H

~ 5. S5!UTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Level - I Low,. Level 1 NA R(b) 1 2, 3 NA(a)

Transmitter:

Trip Logic: D b (. b 1, 2, 3 [

1, 2, 3 M-

b. Reactor Steam Dome Pressure - liigh- NA /UIChh R R

x>

M i

4 8

a,,

0-6 e __ **

-__.______-__-__a___ _ _ _ ____ __.____m_ _ _ _ _ _ __________.++.e.*-_______.P_u.m -_ _m_m___m.__-_m_m ________.__m_ - - _ _ _ _ _

__-________2. -- _ _ _ _ _ _ _ . - _ _ _ _ _ _ . _ _ _ - - . _ _ _ _ _ _

TABLE !. 3.J-1 (Centinuco)

ISOLATION ACTUATION INSTRUMENTAT'OIT SURVEll. LANCE REQUI REMENTS NOTES l

(a) The transmit ter channel cneck is satistied by the trip unit channel check. A separate t ransmitt er eneck is not required.

(b) Transmitters are exempted trom the annel calibration.

( c ) h __n o t pertormed witbin the previous 31 d

~

$[h (d)Testinkshali veriiy t hat the mechanical vacuum pump t ri ps and the mechanical vacuum pump line valve closes.

l

{

(e) When reactor steam pressure > 500 psig.

l (t') When handling i rradiat ed fuel in the secondary containment. l

)

BRUNSWICK - UNIT 1 3/4 3-32 Amendment No. 149

INS ~RUMENTAT!DN 3/4 3 3 EufRGENTY 70RE C00' : N3 Sv5TEw ATTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION !

3.3.3 The Emergency Core Cooling System (ECCS)-actuation instrumentation chahrie,5 I shown in Table 3.3.31 shall be OPERABLE with their trip setpoints set consistent with the values shown in the_ Trip Setpoint column of Table I I

3.3.3 2.

APPLICABILITY: As shown in Table 3.3.31.

4 ACTION:

a. With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3 2. declare the channel inoperable ead phce the "

"act:r;bic ch:m:1 " th: tripp;d conditichtil' the channel is K

restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

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

take the ACTION required by Table 3.3.31.

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

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated

} OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION. and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.31.

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

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

BRUNSWICK UNIT 1 3/4 3-33 Amendment No. 171 r

4 L ,,

E y '

y TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

MINIMUM fiUM!!E O APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP.S M M" 4% %

CONDITIONS ACTION 'l )

FUNCTtotJ

l. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level - Low, level 3 # 4- 1,2,3,4,5 30 7

b. Reactor Steam Dome Pressure - Low (Injection Permissive) / 1,2,3,4,5 g30 I-

c. Drywell Pressure - High EY 1, 2, 3 30 7 w

g d. Time Delay Relay 1/pumf 1,2,3,4,5 31 /

e. Bus Power Monitor" 1/ bus 1,2,3,4,5 32

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Drywell Pressure - High E4 1, 2, 3 30 [

b. Reactor Vessel Water Level - Low, Level 3 EY 1, 2, 3, 4", 5" 30 '/

c. Reactor Vessel Shroud Level (Drywell Spray Permissive) 1[ Valve 1, 2, 3, 4", 5" 31 7-g

d. Reactor Steam Dome Pressure . Low (Injection Permissive) h RHR Pump Start and LPCI Injection Valve Actuation I, 2, 3, 4", 5". g30 M g 1.

' " 2. Recirculation Loop Pump Discharge Valve Actuation Y 1, 2, 3, 4", 5" J T' 9 0 Y

e. R!iR Pump Start -- Time Delay Relay 1[pumf 1, 2, 3, .

4", 5" 31 [

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

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

Y w 4

TABLE 3.3.3-1 (Continued)

E E EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

HINIMUM it APPLICABLE OPERATIONAL

' OPERABLE CHANNEL.S)CONDITIONS PER TRIP.cycycula ACTION

,s

@ TRIP FUNCTION

.- FuNCTICH a

~ 3. 111C11 PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level - Low, Level 2 #Y 1, 2, 3 30 2" Y 1,2,3 30

b. Drywell Pressure - High 2

ICI 1,2,3 Il

c. Condensate Storage Tank Level - Low 2 ICI 1, 2, 3 13

d. Suppression Chamber Water Level - liigh 1, 2, 3 ~ 32 1/ bus

e. Bus Power Honitor(d)

Y

$ 4. AUTOMATIC DEPRESSURIZATION SYSTEM 16

/b 1, 2, 3

a. ADS Inhibit Switch

~Y 1,2,3 ff36 Reactor Vessel Water Level - Low, Level 3 b.

1 1,2,3 E3b Reactor Vessel Water Level - Low, Level 1 c.

e2 1, 2, 3 MM

d. ADS Timer M 3b 4" h 1, 2, 3 Core Spray Pump Discharge Pressure - liigh (Permissive) e.

2/ pump 1, 2, 3 Jf3b f.

RilR (LPCI HODE) Pump Discharge Pressure - liigh (Permissive) 1, 2, 3 32 1/ bus N g. Bus Power Monitor (d) 5

_ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ , - . ~ . .-

insert 3C, pane 3/4 3-38 When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function or the redundant Trip Function maintains ECCS actuation capability.

l l

, \

TABLE 3.3.3-1 (Continued)

EMERCENCY. CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION ch ACTIONS /~y p l ACTION 30

- With the number of OPERABLE channels ess than required by the X ;

Minimum'PERABLE Channels per Tri -Sy m.-'* requi rement :

O 2

n' r one trze system, Pl ace at least =e inoper INSEPJ 1C a.

in the p=d condition wit r declare the y associated ECCS inopera

b. For .rtp systems, declare the associated ioperable.

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

Minimum OPERABLE Channels per Trip fys d requirement, declare K the associated ECCS inoperable. g*

With the number of OPERABLE channels less than required by the ACTION 32 -

Minimum OPERABLE Channels per Trip M requirement, verify k bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the associated ECCS inoperable.

ACTION 33 - WiththenumberofOPERABLEchannels[lessthanrequiredbythe Minimum OPERABLE Channels per Trip h eeererequirement, place at K least one inoperable cha el in the tripped condition within one X

hour or declare the ystem inoperable. ,

PC.T ACTION 34 -

With the number of OPERABLE channels less than the Total Number of Channels declare the associated emergency diesel generator ,

inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

I ACTION 35 -

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

re- ki L, 7 AbTIOF3^ -

With the number of OPERABLE channels less than restore Rntmum G70L*.S'S channel s ner IctyTtT6ction requirement ,

the inoperab tir:it!1~To OPERABLE status . ~. 9 4 n 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or e associated ECCS inoperable.

INSERT 2c ,

I

/ .

3/4 3-37 Amendment No. 130 BRUNSWICK - UNIT 1 1 k

i l

TABLE 3.3.3-1-(Continued) .

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION NOTES g TNSEET K fe (a)fR theenal may be placed in an inoperable status for up to two hnure required surveitiance .;t50"+ niaci o +': ;..p system in the tripped ,

I condition, provided =+ bert-TFs OP:.<Apu. unanus'. '- +ha same trip system j lie :.';uiing the affected parameter. >

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

-(c) Provides signal to HPCI pump suction valves only.

(d) Alarm only.

(e). Required when ESF equipment is required to be OPERABLE.- g?-

( a one-time basis,-prior to start-up from the outage that began on Apr ,1992, the Minimum Number OPERABLE Channels per Trip S for-one reac r team dome pressure - low (injection permissiv ip function

{' may be reduce , r no longer than 7 days, from two (2 annels to one '

(1) channel withou s laring the associated ECCS perable in accordance

' n for Unit I and two with ACTION 31. This wi tedoneononeocc the following actions shall occasions for Unit 2. During7h se period :

be implemented .

(1) The inoperable channel she be place the condition that will

) satisfy the logic for-allowing injection b associated ECCS with the reactor steam-dome pressure below 410 psig i sig.

(2) Both c an6els in .the other trip system shall be maintaine PERABLE.

I (3) he reactor vessel head vent shall be maintained in the open position. _

i l

r

.) i i

BRUNSWICK - UNIT 1 3/4 3-38 Amendment No. 160 .

.i

-, . l L w. , ,

.s .g V TABLE 4.3.3-1 E

E EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUI E

OPERATIONAL A CHANNEL M CHANNEL CONDITIONS IN WHICH CHANNEL FUNCTIONAL

' CALIBRATION SURVEILLANCE REQUIRED ~ l'-

CHECK TEST E TRIP FUNCTION N

c 1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level -

Low, Level 3 R(b) 1,2,3,4,5 NAI *) NA 1,2,3,4,5 X Transmitter %Q Trip Logic: D hQ

b. Reactor Steam Dome Pressure - Low NA R Ib) 1,2,3,4,5 NA(a) 1,2,3,4,5 X Transmitter: g w Trip Logic: D %Q w Drywell Pressure - High R(b) g , 7, 3 h

c.

Transmitter: NA(a)

D NA hQ gg 1, 2 ,3 X Trip Logic:

R 1,2,3,4,5 l-NA R

d. Time Delay Relay R NA 1,2,3,4,5 l NA

e. Bus Power Nonitor

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM Drywell Pressure " High R(b) 1 2, 3

a. NA(a) NA Wk %

Transmitter:

Trip Logic: D Wk 1, 2, 3

& Reactor Vessel Water Level -

b. d) d)

Low, Level 3 1, 2, 3, 4(Id),5 5(Id) [

NA(a) NA R(b)

E Transmitter:

Trip Logic: D Mk > k 1, 2, 3, 4 Reactor Vessel Shroud Level

R(b) 1, 2, 3, 4((d)d), 5(d)

c. NA(a) NA ,5(d);{

Transmitter:

Trip Logic:

D @k % 1, 2, 3, 4 1 1

> z

E A kL 1

US TABLE 4.3.3-1 (Continued) we E ENERCENCY CORE COOLING SYSTEN ACTUATION INSTRUNENTATION SURVEILLANCE RE

. 6 CHANNEL OPERATIONAL n

M CHANNEL . CONDITIONS IN WHICil CHANNEL FUNCTIONAL 8

TEST CALIBRATION ' SURVEILLANCE REQUIRED l CHECK

@' TRIP FUNCTION

1 LDW PRESSURE COOLANT INJECTION NODE OF RHR SYSTEN (Continued) y i'4 R(b) g, y, 3, 4(d) - $(d)

NA(a)

d. Reactor Steam Dome Pressure - Low RHR Pump Start and LPCI 1, 2, 3, 4(d) , $(d) .

1.

Injection Valve Actuation D bQ h 1, 2, 3, 4(d) , $(d) /

2. Recirculation Loop Pump Discharge Valve Actuation D bQ Mk 1, 2, 3, 4(d) $(d)

~

w R R NA N e. RHR Pump Start - Time Delay Relay !

NA 1, 2,.3, 4(d) $(d)

NA R

f. Bus Power Monitor

3. HICH PRESSURE COOLANT INJECTION SYSTEN.

a. Reactor Vessel Water Level -

i l Low, Level 2 NA R(b) g,y,3- '

NA(a)

' Transmitter:

Trip Logic: D -tt? k Mk .

1, 2, 3 Drywell Pressure - High R(b): 1, 2, 3 l

g b.

Transmitter:

Trip Logic:

NA(a)

D NA P,"8' k Qk I , 2, 3

, j 1, 2, 3 .X n

c. Condensate Storage Tank Level - Low NA -M7 k Q

' h.

r - M-9 Q

.1, 2, 3 %

d. Suppression Chamber Water Level - liigh NA NA 1, 2, 3 NA R .

e. Bus Power Monitor-

-_ .. . . - - . _ __ _ _ _ . . _ . _ _ . . _ _ - . . _ _, , ~ . . , _ . . - ~ -

TABLE 4.3.3-1 (Continued)

"so

'E y EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS MX CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WillCH -

CllECK TEST CALIBRATION SURVEILLANCE REQUIRED l E TRIP FUNCTION

4. AUTOMATIC DEPRESSURIZATION SYSTEM D IC) R NA 1, 2, 3

a. ADS Inhibit Switch

b. Reactor Vessel Water Level -

Low, Level 3 R(b) 1, 2, 3 NA(a) NA Transmitter:

Trip Logic D Wk -tt-f> k 1, 2, 3 /

R' c. Reactor Vessel Water Level -

Low, Level 1 NA R(b) g , 7, 3 NA(a)

Transmitter: D Mk --t+-ap 1, 2, 3 X "h Trip Logic R R 1,2,3 -

NA

d. ADS Timer i

e. Core Spray Pump Discharge le 2. 3 .l Pressure - High NA -t+? k Q 1 .

f. RHR (LPCI MODE) Pump Discharge 1, 2, 3 NA -tty Q Pressure - High R NA 1, 2, 3 NA

g. Bus Power Monitor I

it

?

W 8 .

_m_ _ _ __ _ __.__ _ _ _______.___.___._ _ __________ _______m_m _ _ _ _ _ . _ _ __ _ _ _ _ _ _ __ . _ _ _ _ _ _ . _ _ . _ . . _ __, - ___

\,,' .

TABLE 4.3.3-1 (Continued) y E EHERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEN

y OPERATIONAL q E CilANNEL M CONDITIONS IN WHICH FUNCTIONAL CllANNEL CilANNEL 8

TEST CALIBRATION SURVEILLANCE REQUIRED l CllECK

@ TRIP FUNCTION G

5. LOSS OF POWER NA R 1, 2, 3, 4(d),,S Id) 4.16 kv Emergency Bus NA a.

Undervoltage (Loss of Voltage)

H R 1, 2, 3,.4(d) , 5(d) 4.16 kv Emergency Bus NA b.

' Undervoltage (Degraded Voltage) kl n

Y

?

N E

17 e

n 5

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

A separate transmitter check is not required. qhyihele vs[

[ y channel calibration.y

' C) (b) Transmitters are exempted from the jashall be maintained in the Automatic position.

(c) The ADS Inhibit Switches (d) Required when ESF equipment is required to be OPERABLE.

n-- 3 l

L l

1 TABLE 3.3.4-1 (Cent:nued) l CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION l

1RSERT ID noreg W

(a) The minimum u m,u . F ",DADLE w CHANNELS may be reduced hv ~

-I M

hours in one of the *-in e++ s m .. > ;m x im enance and/or testine oxcept-Qo p "',o g in, rlmc,;,n. -

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

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

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

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

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

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

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

l BRUNSWICK - UNIT 1 3/4 3-49 Amendment No. 147

)

1 I

Insert 1D. page 3/4 3-49 ,

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

maintains control rod block capability.

i l

1 l

l 1

l l

1 l

1 I

i l

w.

TABLE 4.3.4-1 g

E m CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION SURVEILIANCE REOUIREMENTS 63 OPERATIONAL k CHANNEL CHANNEL CONDITIONS IN WHICH

CHANNEL F11NCTIONAL CHELK TEST CALIBRATION SURVEILIANCE REQUIRED g TRIP F11NCTION E Y Upscale (Flow Biased) NA S/U R( }(*}- 1

,Q NA 1, 2, 5

b. Inoperative NA S/U 4 E 1-

c. Downscale NA S/U

,Q

)g)Ng,)

R 2, 5

d. Upscale (Fixed) NA S/U

2. ROD BIDCK MONITOR R(,) 1(g). y

a. _ Upscale NA S/U(c) M 7 1 NA ,Q Ng*}

b. Inoperative NA S/U(

S/U gk R 1(E} M

c. Downscale N

3. SOURCE RANGE MONITORS I ,W( } NA 2, 5-Y a. Detector not full in NA S/U

,W NA 2, 5 U b. Upscale NA. S/U Inoperative NA S/U ,W(d) ^ '

c. 2, 5 NA S/U ,W NA

d. Downscale

4. INTERMEDIATE RANGE MONITORS *

,W 'NA 2

a. Detector not full in NA Sg(* NA 5 NA W

b. Upscale NA S/U( } ,W(d) NA 2 W NA 5 NA I ,W( NA 2

$ c. Inoperative NA S/U(

W NA 5 f NA S/U("}' ,W( NA 2

d. Downscale NA W NA 5 NA E

5. SCRAM DISCHARGE VOLUME m R 1, 2, 5

" Water Level - High NA Q

- a.

l TABLE 4.3.5.5-1 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ,

INSTRUMENTATION SURVEILLANCE RE0VIREMENTS CHANNEL ,

CHANNEL FUNCTIONAL CHANNEL I FUNCTION CHECK TEST CALIBRATION CHLORINE ISOLATION:

, 1. Local Detection NA M A i

Trip System

2. Remote Detection NA M A l Trip System RADIATION PROTECTION:

l. Control Building D Mk R Air intake r

CONTROL ROOM ENVELOPE SM0KE PROTECTION:

1. Zone 4 NA 6 months (a)

2. Zone 5 NA 6 months (a) a 3 .

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

l i

I 1

BRUNSWICK - UNIT 1 3/4 3-64c Amendment No. 161 -j J

- _ _ _ _ _ _ _ _ - - _ - - _ - _ _ ._ =___ - _ _ _ _ - _ ._ __ ._ _ .__

i f

INSTRUMENTATION 3/4.3.6 AIVS RECIRCULATION PUMP TRIP (RPT) SYSTEM INSTRUMENTATION

_k _ d LIMITING CONDITION FOR OPERATION 3.3.6.1 The ATWS-RPT system instrumentationh H r ';

_ -?shown consistent in k Table 3.3.6.1-1 shall be OPERABLE with their trip setpoints set with the values'shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

less a.

Wigh an ATWS-RPT system instrumentation trip setpointcohnerva Table 3.3.6.1-2, declare the instrument channel inoperable until the channel is restored to OPERABLE status with its trip setpoint l

1 k N k adjusted consistent with the Trip Setpoint value.

With the number of OPERABLE channels one less than required for onebyorthe bot Minimur. OPERABLE Channels per Trip System requirement ir systems, place the inoperable channel (s) in the tripped co ition within one hour.

uired by

c. With th total number of OPERABLE channels less than 3 as for one the Minimu OPERABLE Channels per Trip System requireme l

trip system a :

1. If the inopera channels consist of one actor vessel water level channel and e reactor vessel p* ssure channel, place both inoperable chan s in the tri ed condition within one hour.

If the inoperable channels e e two reactor vessel water

2. pressure channels, declare level channels or two r ctor ves the trip system ino able.

d. With one trip syst inoperable, restore the inop able trip system to OPERABLE st a within 14 days or be in at least ARTUP within the next 8 rs.

least one trip stem

e. With th trip systems inoperable, restore at least STARTUP wi

n PERABLE status within one hour or be in at the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.6.1.1 Each AIVS-RPT system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, CHANNEL CALIBRATION operations at the' frequencies shown in Table 4.3.6.1.1-1.

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

) of the trip system.

3/4 3-88 Amendment No. 130 BRUNSWICK - UNIT 1

1 l

l l

I Insert 1E, pane 3/4 3-88 l

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

1. Verify that a sufficient number of channels remain OPERABLE or are in the tripped )

condition to maintain ATWS-RPT trip capability for both Trip Functions within one hour, and

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

c. With trip capability for one ATWS-RPT Trip Function not maintained, restore trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d. With trip capability for both ATWS-RPT Trip Functions not maintained, restore trip capability for ene Trip Function within one hour.

Otherwise, be in at least STARTUP within the next six hours.

TABLE 3.3.6.1-1 ,

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION CH4NNELS$[

MINIMUM PERABLE TR

^"""^*

o"w )

SYSTE f "r ._

TRIP FUNCTION 2

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

2. Reactor Vessel Pressure - High b

l m'[-*": S. .y w -2 7 tours for (a) k ,7sram may be placed in an inocernh1.

k- ach=* ef4 p myse== in OPrRABir. j (require @ w gTtrviced e :

l J

3/4 3-89 Amendment No.130 BRUNSWICK - UNIT 1

insert 2E, pane 3/4 3-89 (Unit in and 3/4 3-90 (Unit 2]

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

maintains ATWS-RPT capability.

l

TABLE 4.3.6.1-1 AWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SUR -

CHANNEL FUNCTIONAL CHANNEL CHANNEL

- TEST CALIBRATION l CHECK _

' TRIP FUNCTION

1. Reactor Vessel Water Level - )

Low, Level 2 NA R Transmitter:

Trip Logic:

NA D Mk g -

2. Reactor Vessel Pressure - High NA R(b)

NA(a)

Transmitter D y $

Trip Logic:

9 h

i 4

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

) %%3v"bfk9 (b) Transmitters are exempted f rom the menu"r channel calibration.

3/4 3-91 Amendment No. 130 BRUNSWICK - UNIT 1 .

~ ,

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

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

APPLICABILITY:

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

ACTION:

a. With a RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.7-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With one or reore RCIC system actuation instrumentation channels .

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

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

l 4.3.7.2 LOGIC SYSTEM FUNCTIONAL TEST 3 and simulated automatic operation of j all channels shall be performed at least once per 18 months. .

l l

1 e

i 3/4 3-92 Amendment No. 1 30 f BRUNSWICK - UNIT 1

v s as TABLE 3.3.7-1 28 E -

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION h

HINIMUM O

, OPERABLECitANNEgI ACTION PER TRIP SYSTEM h FUNCTIONAL UNIT a 2 50

" 1. Reactor Vessel Water Level - Low, Level 2 '

$g 2(b)

2. Reactor Vessel Water Level - High y(c) 52

3. Condensate Storage Tank Water Level - Low (d) v Y

N

's INSERT IC7 f for "a ta : ;. . , fu, sequired surveillance without l-Y E (a)(Achannetmaybeplacedinaninoperablestatusd mv. M v'ided at least unu ;;he, nPERABLE channel in the j placing the trip issystem in tha r%

monitori c hat parameter. -

Q C - :. W atem (b) One trip system with two-out-of-two logic.

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

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

~

f l

1 Insert 1G, page 3/4 3-93 (Unit il and 3/4 3-100 (Unit 21 f i

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

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

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

l I

f l

l 1

I

TABLE 3.3.7-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION t

l ACTIONS With the number of OPERABLE channels.less than required by the '

ACTION 50 -

Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system place the inoperable channel (s) and/or hours )(, -

that trip system in the tripped condition within 2-or declare the RCIC system inoperable.

For both trip systems, declare the RCIC system inoperable.

][NSEf(( 2,(5 b.

ACTION 51N- J;7With tne um. 'ver af OPrnAB_LE channels less than re uirdeclare

.squar;rrar .

er ye s ... '

l Minimum OPERABLE Channel ra e.

Lthe RCI h e--

ACTION $2 -

With the number of OPERABLE channels less than requiredplace by theat Minimum OPERABLE Channels per Trip System requireme hourSor declare the RCIC system inoperable. yg A '

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3/4 3-94 Amendment No.130

I

' BRUNSWICK - UNIT 1 ;

Insert 2G, paae 3/4 3-94 (Unit 1) and 3/4 3-101 (Unit 2)

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

& w TABLE 4.3.7.1 $

E y REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL M

CHANNEL FUNCTIONAL CHANNEL s

CHECK TEST CALIBRATION

@ FUNCTIONAL UNIT ,

1 Reactor Vessel Water Level - Low, Level 2

~

1. NA R( }

Transmitter:

Trip Logic:

NA D Mk Mk k

2. Reactor Vessel Water Level - High NAI ") NA R(b)

Transmitter:

Trip Logic: D Mk #7 g

3. Condensate Storage Tank Level - Low NA Mk Q en Y

N U -

E n

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

[ is not required..

o parterly (b) Transmitters are exempted from the % channel calibration.

+

I i

BASES FOR I SECTIONS 3.0 AND-4.0

. LIMITING CONDITIONS FOR OPERATIONS

.)

AND SURVEILLANCE 5tEQUIREtiENTS 1

l I

.)- q

.. i l

l RETYPED TECH. SPECS.

Updated Thru. Amend. 53 !

- -_- _ _ . _ _ _ . . _.__.f

NOTE

} The Summary statements contained in this section provide the bases for the specifications in Sections 3.0 and 4.0 and are not considered a part of these technical specifi-cations as provided in 10 CFR 50.36.

i j

)

RETYPED TECH. SPECS.

Updated Thru. Amend. 53 )

3/4.3 I NSTR UMENTATION HASES _

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

a. Preserve the integrity of the fuel cladding.

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

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

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

The reactor protection system is made up of two independent trip systems. There are usually four channels to monitor each parameter, with two in each trip system. The outputs of the channels in a trip system are combined in a logic so that_either channel will trip that trip system. The tripping of both trip systems will produce a reactnr scram. The system meets ,

the intent of IEEE-279 for nuclear power plant protection systems. The bases f or the trip settings of the RPS are discussed in the bases for Specification

} 2.2.

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

i Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements, provided such tests

' demonstrate the total channel response time as defined. Sensor response time d verification may be demonstrated by either; 1) inplace, onsite or offsite test j measurements, or 2) utilizing replacement sensors with certified response times. y o

The Bases f or the trip setpoint is given in the Bases for Section 2. .

')

1

~^- ,

IMSERT Iff

)

BRUNSWICK - UNIT 1 B 3/4 3-1 RETYPED TECH. SPECS.

Updated Thru. Amend. 53

insert 1H. Daae B 3/4 3-1 Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30851P-A, " Technical Specification Improvement Analyses for BWR Reactor Protection System," March 1988 and MDE-81-0485, Rev.1,

" Technical Specification Improvement Analysis for the Reactor Protection System for Brunswick' Steam Electric Plant, Units 1 and 2", August 1994, as modified by BWROG-92102, Letter from C. L.

Tully (BWROG) to B. K. Grimes (NRC), "BWR Owners' Group (BWROG) Topical Reports on Technical Specification improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844 and NEDC-30851P)," November 4,1992.

l 1

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INSTRLNENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRLMENTATION This specification ensures tue effectiveness of the instrumentation used to mitigate the consequences of accidents by prescrising the trip settings for isolation of the reactor systems. When necessary, one channel may be inoperable for brief intervals to. conduct required surveillance. Some of the trip settings have tolerances explicitly stated where both the high and low values are critical and may have a substantial ef fect on safety. The setpoints of other instrumentation, where only the high or low end of the setting has a direct bearing on_.the safety, are established.at a level away f rom the normal operating range to prevent inadvertent actuation of the systems involved.

3/ 4. 3. 3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRuiENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control. This specification provides the trip point settings that will ensure ef fectiveness of the. systems to provide the design protection. Although the instruments are listed by system, in some cases the -

same instrument is used to send the start signal to several systems at the s ame t ime. The out-of-service times f or the instruments are consistent with

) 7 the requirements of the specifications in Section 3/4.5.

.X N -

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

-7 @ sEET WD K

3/4.3.5 MONITORING INSTRUMENTATION 3/4.3.5.1 SEISMIC MONITORING INSTRUKENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those f eatures important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the f acility.

BRUNSWICK - UNIT 1 B 3/4 3-2 RETYPED TECH. SPECS. ,

Updated Thru. Amend. 5

insert 2H, paae B 3/4 3-2 Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30851P-A, Supplement 2, " Technical Specification improvement Analysis for BWR isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989 and NEDC-31677P-A, " Technical Specification improvement Analysis for BWR isolation Actuation Instrumentation," July 1990, as modified by OG90-579-32A, Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE), "Implernentation Enhancements to Technical Specification Changes Given in isolation Actuation Instrumentation Analysis," June 25, 1990 and supplemented by GE letter report GENE-A31-00001-02, " Assessment of Brunswick Nuclear Plant Isolation Actuation Instrumentation Against NEDC-31677P-A Bounding Analyses," August 1994.

Insert 3H, pane B 3/4 3-2 Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30936P-A, Parts 1 and 2, "BWR Owners' Group Technical Specification improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," December 1988 and RE-011, Rev.1, " Technical Specification improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant, Units 1 & 2," August 1994, as modified by 0G90-319-32D, letter from W. P. Sullivan and J. F. Klapproth (GE) to Millard L. Wohl (NRC), " Clarification of Technical Specification Changes Given in ECCS Actuation Instrumentation Analysis", March 22,1990.

Insert 4H, pane B 3/4 3-2 Specified surveillance intervals and allowed out-of-savice times were established based on the reliability analyses documented in GE report NEDC-30851P-A, Supplement 1, " Technical Specification improvement Analysis for BWR Control Rod Block Instrumentation," October 1988.

r

i INSTRUMENTATION BASES 3/4.3,5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

Surveillances (Continued) instrumentation continues to operate properly between each CHANNEL CALIBRATION. The CHANNEL CHECK frequency is consistent with that performed for other radiation monitors with isolation functions. pr-t, erg The CHANNEL FUNCTIONAL TEST is performed on each required chann to ensure that the pntire channel'will perform the intended function. ' e Control Building HVAC DBD (Reference 6) defines the specific act pio'to be satisfied by the radiation actuation instrumentation. The -enthb frequency of the X CHANNEL FUNCTIONAL TEST is consistent that par 4armadfarJar ram a %

monitors with isolation functions, t0as estabkslief laged og Re[erence 7 and The CHANNEL CALIBRATION verifies the channe responds to t e measure parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 5). The frequency of the calibration is consistent with the frequency of calibration of other radiation monitors with isolation functions.

Chlorine Protection .

The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control

.) Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the chlorine isolation instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

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

assumptions (Reference 6).

The chlorine detectors use an amperometric sensor consisting of a platinum cathode and silver anode joined by an electrolytic salt bridge, all enclosed in a permeable membrane. This design eliminates the majority of the 1 maintenance required on previous detectors. The detectors have been in l service at other facilities and have provided reliable service. The annual :

replacement and calibration are based on a manufacturer recommendation. The i adequacy of the replacement interval has been confirmed through discussions with other utilities. J Smoke Protection

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

BRUNSWICK - UNIT 1 B 3/4 3-3d Amendment No. 161 .

l I

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

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

2. Regulatory Guide 1.95, Revision 1 Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release.

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

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

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

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

GENE-770-06-1-A " Bases gr chan3cs to Swveillauce. Test r/" ~

Intervals aJ 40 ed Cat-of-Gervhe.Thcs for 6hled:ed lastruaJath Techical QeciRcations/' Decomber 1902,

) '

1 BRUNSWICK - UNIT 1 B 3/4 3-3e Amendment No. 161

i INSTRIMENTATION BASES 3/4.3.6 AIWS RECIRCULATION PIMP TRIP ACTUATION INSTRIMENTATION The AIWS recirculation pump trip system has been added at the suggestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a '

failure to scram during an anticipated transient. The response of the plant ,

to this postulated event falls within the envelope of study events1971.

given in General Electric Company Topical Report NEDO-10349, dated March, s 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ,

The reactor core isolation cooling system actuation instrumentation is ;

provided to initiate actions to assure adequate core cooling in_the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel"without providing actuation of any of the emergency core cooling equipment.

^m X m SSEtT6H ,

CNSERT5H .

s

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,A B 3/4 3-6 Amendment No. 68 BRUNSECK - UNIT 1

insert SH, pace B 3/4 3-6 Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-1-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," December 1992.

Insert 6H. pane B 3/4 3-6 (Unit 1) and B 3/4 3-7 (Unit 2)

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A,

Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected instrumentation Technical Specifications," December 1992.

ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT INCREASED INSTRUMENT SURVEILLANCE TEST INTERVALS AND ALLOWABLE OUT-OF-SERVICE TIMES MARKED-UP TECIINICAL SPECIFICATIONS PAGES - UNIT 2 The following pages have been revised and an 'X' has been placed in the margin to indicate where changes occur.

Technical Specifications 3/43-1,2,3,5,7,8,9 (RPS Instrumentation) 3/4 3-10,11,17a, 27 through 32 (Isolation Actuation Instrumentation) 3/4 3-33 through 35,37,38,43 (ECCS Actuation Instrumentation) through 46 3/4 3-49, 51 (Control Rod Withdrawal Block Instrumentation) 3/4 3-64c (Control Room Emergency Ventilation Innrumentation) 3/4 3-88, 90, 92 (ATWS-RPT Instrumentation) 3/4 3-93, 95, 98 (EOC-RPT Instrumentation) 3/4 3-94, 100, 101, 103 (RCIC Actuation Instrumentation) llases B 3/4 3-1 B 3/4 3-2 B 3/4 3-3d B 3/4 3-3e B 3/4 3-6 B 3/4 3-7 i

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E5-1 a

3/5'3 INS RUMEGATION 4

' 3 /4. 3' 2 ' RE ACTOR PROTECTION SYSTEM- INSTRUMEG ATION LIMITING CONDITION FOR OPERATION .

3.3.1 As a minimum, the reactor protection system instrumentation channels -

shown in Table 3.3 1 1 shall be'0PERABLE. Set points and interlocks are given I in Table 2.2.1 1.

APPLICABILITY: As shown in Table 3.3.1 1.

ACTION: M 6 Egg $ "

[a.-4 Lith the requirements for the minimum number of OPERAbLt cnannels not I satistleo im una trin (vstem. place the inoperable channel (s) rip . ~

system in the tripped'conditT6 F W ne hour.

b With the requirements for the min' er of OPE els not satisfied for both tr' s place at least one trip system .

the tri na lon within one hour and take the ACTION required by

-Taote .3.1 1. _

c. The provisions of Specification 3.0.3 are not applicable in OPERATIONAL -

CONDITION 5. -

SURVEILLANCE REQUIREMENTS U.1.1 Each reactor protection system instrumentation channel shall be !

demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL i CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL

CONDITIONS and at the frequencies shown in Table 4.3.1 1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of +

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

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function' shall be demonstrated to be within its limit at least once per 18 i !

nonths. Each test shall include at least one logic train such that both logic :

trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip '

function.

[NWW Y eraDie channet neeo not. De placed in the tripped conditio where t 1 ause the Trip Function to occur. In tha ses, the inoperable chann e restored to OPE atus within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by a or that Trip Function shall be taken.

- If more channels perable in one trip system tha + e other. ,

placa p system with more inoperable channels in the tri dition. exront wh~, W r unold cause the Trin Fun-tinn tn nrcur i Neutron detectors are exempt from response time testing. I 1

x BRUNSWICK UNIT 2 3/4 3 1 Amendment No. 202 !

insert 1 A, pane 3/4 3-1

a. With one channel less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.1-1 in one or more Functional Units, place the inoperable channel and/or that trip system in the tripped condition

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

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

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

to maintain trip capability in the Functional Unit, and

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

3. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip system to an OPERABLE status or place them in the tripped conditiont Otherwise, take the ACTION required by Table 3.3.1-1 for the Functional Unit.

Insert 2A, pane 3/4 3-1 An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall be taken.

This ACTION applies to that trip system with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION can be applied to either trip system.

'v .w g TABLE 3.3.1-1

.E -

p REACTOR PROTECTION SYSTEM INSTRUMENTATION RX APPLICABLE.

MINIMUM NUMBER O8 OPERATIONAL OPERABLE CHANNELS

@ FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a) ACTION l M

y 1. Intermediate Range Monitors:

I

a. Neutron Flux - High 2, 5(b) 3 l 3, 4 2 2

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

2. Average Power Range Monitor t' Simulated Thernal Power- l

a. Neutron Flux - High, 151 2, 5(b) 2 3 Y b. Flow Biased " :.;- "'1 High 1 2 4 X -.

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

d. Inoperative 1, 2, 5 2 5

e. Downscale 1 2 4

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

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

- l

4. Reactor Vessel Water Level - Lou, Level 1 1, 2 2 6 1

5. Main Steam Isolation Valve - Closure 1 4 4 1, 2(d) 2 7 I

, 6. Main Steam Line Radiation - High o

M,,

o Mo v e - - 3 m +, m em%+- w- r _> __

Q ._,

4 E TABLE 3.3.1-1 (Continued)

E E REACTOR PROTECTION SYSTEM INSTRUMENTATION "n

APPLICABLE MINIMUM NUMBER

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

% 1,- 2I' 3 2 6 u 7. Dryvell Pressure - High

8. Scram Discharge Volume Water Level - High 1, 2, 5(f) 2 5-1(E} 4 8

9. Turbine Stop Valve - Closure

10. Turbine Control Valve Fast Closure, Control Oil Pressure - Low II8} 2 8 1,2,3,4,5 1 9 w 11. Reactor Mode Switch'in Shutdown Position 5 I,2,3,4,5 1 10 w 12. Manual Scram 0

l3. Ado >at;e seram Codactors 1, 2, 3 , 4, F 2- 10 X 4

3 +

t 3,

i f w +

i :

.t i

_ _ _ _ - _ _ _ _ _ - _ _ _ _ . _ - _ - . . _ _ - , . . - - . . - . . ~ - , , . . . . . . - -- - . . _ . . - _ . _ .._ -- _______- _ - - _ -.

TABLE 3.3.1-1 (Continued)

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

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

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

It4 SERT 34 NOTES (a)"A 1 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 surv _ a without placing the trio av=M- i M ed ondition, provided at least,gtn- erm6ai in the same trip system s moniene k e m. parameter. 7d (b) The " shorting links" shall be removed from the RPS circuitry prior to and l during the time any control rod is withdrawn

and during shutdown margin demonstrations.

1 (c) An APRM channel is inoperable if there are less than 2 LPRM inputs per l 1evel or less than eleven LPRM inputs to an APRM channel.

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

l (e) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTECRITY is not required.

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

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

Not required for control rods removed per Specificat, ion 3.9.10.1 or 3.9.10.2.

)

3/4 3-5 Amendment No.160 BRUNSWICK - UNIT 2 C

Insert 3A. pane 3/4 3-5 When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability.

a i

v s y TABLE 4.3.1-1 Si y REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS EX CllANNEL OPERATIONAL O' CilANNEL FUNCTIONAL

@ FUNCTIONAL UNIT CHECK TEST CHANNEL p

CALIBRATION a)

CONDITIONS IN WHICll SURVEILLANCE REQUIRED l 4

9 1. Intermediate Range Monitors:

a. Neutron Flux - High D S/U(b)(c), g(d) R 2 !

D W R 3, 4, 5 -

b. Inoperative NA W(d) NA 2,3,4,5

2. Average Power Range Monitor:

I Z a. Neutron Flux - High 15% S Sg(}b)(m), g(d) Q 2 l 6IMt4l3ted IbOTPQf hW6g S W Q 5

b. Flow-Biased . :M -: "1 [ - High S S/U(b) ,pQ g(e)(f),q g y

c. Fixed Neutron Flux - High, 120% S S/U(b) ,gQ g(e) ,q g y.

d. Inoperative NA "I NA 1, 2, 5 X l e. Downscale NA hQ NA 1. N'

f. LPRM D NA (g) 1, 2, 5 g 3. Reactor Vessel Steam Dome Pressure - liigh

@ Transmitter NA(k) NA R II) 1, 2 l

Trip Logic: D

-+t'fk -ttP Q 1, 2 K

" 4. Reactor Vessel Water Level - Low, Level 1 y Transmitter: NA(k) NA R II) 1, 2 I Trip Logic: D p Q WQ 1, 2 K s i 1

L______________ ____________________________ _ _ - _ . . - -

.s

..v w i TABLE 4.3.1-1 (Continued) g E REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS p

E CilANNEL OPERATIONAL M

s CHANNEL FUNCTIONAL CHANNEL' CONDITIONS IN WillCil CilECK TEST CALIBRATIOH(a) S1fRVEILLANCE REQUIRED

@ FUNCTIONAL UNIT

5. Main Steam Line Isolation Valve - Closure NA Wk R(b) 1 [

6. Main Steam Line Radiation - High S

) R IN 1, 2 K

7. Drywell Pressure - High R II) 1, 2 Transmitter: NA(k) NA Trip Logic D -M-yh W 1, 2 K R 1, 2, 5

8. Scram Discharge Volume Water Level - High NA Q

% R(h) g(o)

9. Turbine Stop Valve - Closure NA

-+Hf Q 9 10. Turbine Control Valve Fast Closure, Control Oil Pressure - Low NA --M-y k R I IOI K NA 1, 2, 3, 4, 5

~

NA R

11. Reactor Mode Switch in Shutdown Position NA NA 1,2,3,4,5 Q

. . 12. Manual Scram 4

13. A tmati Scrw Cadactors NA W NA t, 2, f y, f [

I D

E.

O

TABLE 4.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRtHENTATION SURVEILIANCE REOUIREMENTS NOTES (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

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

(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2, if not performed within the previous 7 days. l (e) This calibration shall consist of the adjustment of the APRM readout to confo rm to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER greater than or equal to 25% of RATED THERMAL POWER. ,

(f)

This calibration shall consist of the adjustment of the APRM flow-biased ca*- .

to conform to a calibrated flow signal.

Whhe.

(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.

(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 transmitter check is not required .

{4 Aft 8P y (1) Transmitters are exempted from the,gn>HTTf clannel calibration.

(m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to 3 withdrawal of control rods for the purpose of brin 51ng the reactor to :

criticality.

(n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.

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

BRUNSWICK - UNIT 2 3/4 3-9 Amendment No. 193 l l

I

l

}NS7 U9 NTAT*0N 3/432 ?S0'.ATION CTUATION INSMUWENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.21 .

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

APPLICABILITY: As shown in Table 3.3.21.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint- l

]ess conservative than the value shown in the Allowable Values kolumn of Table 3.3.2 2. declare the channel inperable -end p!:cd V the Nperabic ch:rT1 m us tripped cond4tWntil the channel is &

restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. (( j; l

h . h uirements for the minimum number system, placeof OPERABLE the inoperabl channele (s) not satisfied'T6ru +

and/or that trip system in the d gondi - nin one hour.

c. With the requirements for . inimum number of 0 -

annels not satisfied for rip systems, place at least one trip in the t condition within one hour and take the ACTION require e 3.3.2 1.

d. The provisions of Specification 3.0.3 are not applicable in ;

) OPERATIONAL CONDITION 5.

I i

SURVEILLANCE REQUIREMENTS {

4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL 1 CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL }

CONDITIONS and at the frequencies shown in Table 4.3.21. j l

4 4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

[* An inoperable cnannel need not be placed in theIntripped condition where these cases, the this would cause the Trip Function to occur.

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.

- If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.

BRUNSWICK UNIT 2 3/4 3 10 Amendment No. 202

-_-__ _______o

t insert 18, pano 3/4 3-10

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

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

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

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

within:

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

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

N57 UWENTATION SURVEIL 3 NCE REQUIREMENTS ' Cont nued)

L4.3.2.-3 The ISOLATION SYSTEM RESPONSE TIME of each 1 solation function' shall I

'be demonstrated to. be within its limit at least once per 18 months Each test 1 shall-include at least one log 1C train such that both logictfEii?t! dire tested at least once per 36 months and one channel per function such hat all

[ ',

channels are tested at least once every N times 18 months, ere N is the !

total number of redundant channels in a specific isolation function.

' 8rd[h,s l

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i

Radiation monitors are exempt from response time testing.

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. BRUNSWICK UNIT 2 3/4 3 11 Amendnent No. 202 l

l D l l

c Ip . TABLE 3. 3. 2- 1 ( 4Ea t i nuca )

. I SOLATION ACTUATION INSTRUMENTATION NOTES

When handling irradiated fuel in the secondary cont'ainment.

(a) See S pec i t i ca t i on 3.o . 3.1. Ta bl e 3.o.3-1 lar salves in each valve group.

- INSERT 2B (b) b r' mv he placed in an inoperable status f or up t s ' ' . .vi 7 required surveillance without r..:!-'*hr *-_ , my em in the tripped

- ume trip condition provided e ' . . .e other OPERAul.E chani.u.

Sp e t hat paramet er .

(c) h70t- 7 . enannet per .r.p system. an t r. ope ra bl e enannes need np ne placed in the trappuu - . inn where this w<'u!' .as ine I ri p Function to occur. In tnese . . - . >l e channel shall be Of r e s t o re d t o OPE "' .a us wit hin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or t he Av. v.. 4 ed by '

Jabi t ... 2 ter that Trin Funct ion shall be taken.

(d) A channel is OPERABLE it J ot 4 instruments in that channel are OPERABLE.

(e) With reactor steam pressure > $00 psig.

-}

( t' ) Closes only RWCU outlet isolation valve.

(g) Alarm only.

(h) Isolates containment purge and vent valves.

(i) Does not isolate Ell-F015A.U.

(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 listed i n Tabl e 3.o. 5. 2- 1.

BRUNSWICK - UNIT 2 3/4 3-17a Amendment No. 179 G

insert 2B, pane 3/4 3-17a When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed as follows:

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

(b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions, provided the Trip Function maintains isolation actuation capability.

l e

v TABLE 4.3.2-1 E

E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE OPERATIONAL REQ jg CllANNEL CONDITIONS IN WillCll CifANNEL CllANNEL FUNCTIONAL SURVEILLANCE REQUIRED TEST CALIBRATION C, CilECK _

TRIP FUNCTION E

U l. PRIMARY CONTAINMENT ISOLATION 3, 2, 3 w

a. Reactor Vessel Water Level -

Low, Level 1 NA R(b) 1, 2 , 3 N 1.

Transmitter:

NA(a )

D -#-Pk -t&9k Trip Logic:

1, 2, 3 Low, Level 3 NA R(b) 1, 2, 3 1 2.

Transmitter:

NA(a)

D Mk #Pk Trip Logic 1, 2, 3 R(b) %

b. Drywell Pressure - High Transmitter:

NA(a)

,D Mk NA MQ 1, 2, 3 Trip Logic: E R Id) 1, 2, 3 u

N c. Main Steam Line Radiation - liigh D Mk u 1. g u

Pressure - Low NA R(b) [

NA(a) -+t"P k 1

" 2.

Transmitter:

Trip Logic:

D Mk Flow - High NA R(b) 1 X 3.

Transmitter:

NA(a)

D -4t-P k -tt"P k X Trip Logic:

D Mk 4k 2, 3

4. Flow - liigh R

1, 2, ) N

d. Main Steam Line Tunnel NA -tt-Pk Temperature - liigh R(b) 1, 2 II*)) ,A t NA M 1, 2

to E

e. Condenser Vacuum - Low Transmitter:

NA(a)

D Mk Trip Logic: 1, 2, 3 l X f, R f.

Turbine Building Area NA -- +t 8ll> k Temperature - liigh R 1, 2, 3 f NA Q g.

Main Stack Radiation - liigh

- 1, 2, 3 R

0 h. Reactor Building Exhaust D --+t :)

Radiation - fligh

L. .d E

5 k TABLE 4.3.2-1 (Continued)

F' ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS H

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

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High D

-M*Q R 1,2,3,5, and'" [

b. Dr ell Pressure - High ransmitter: NA NA R'6' 1, 2, 3 G.)

Trip Logic: D

--#3PQ -

WQ 1,2,3 I 2 c. Reactor Vessel Water Level -

w Low, level 2 Transmitter: NA NA R 1, 2, 3 R3 m Trip Logic: D --+HP (Q -ft* @ 1,2,3 N

3. REACTOR WATER CLEANUP SYSTEH ISOLATION

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

b. Area Temperature - High NA SA R 1,2,3

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

d. SLCS Initiation NA R NA 1, 2

@ e. Reactor Vessel Water Level -

R Low, Level 2 g Transmitter: NA NA R'6' 1, 2, 3 co Trip Logic: D --4HPk --&Pk 1, 2, 3

f. A Flow - High - Time Delay NA SA R *

.1, 2, 3

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

v b s

TABLE 4.3.2-1 (Continued) x

. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-i CHANNEL CHANNEL FUNCTIONAL CHANNEL-OPERATIONAL CONDITIONS IN WHICH m TRIP FUNCTICH CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION

a. High Pressure Coolant Injection System Isolation

1. HPCI Steam Line Flow - High Transmitter: NA NA R'6' 1, 2, 3 w 2.

Trip Logic:

HPCI Steam Line Flow - High D

-4t'#Q 'tt9Q 1,2,3

[-

E Time Delay Relay NA R R 1,2,3 5

w

3. HPCI Steam Supply Pressure - Low NA' WR R 1,2,3 V r

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

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

6. HPCI Turbine Exhaust Diaphragm Pressure - High HPCI Steam Line Ambient NA

--tHP Q Q 1,2,3 K

7.

Temperature - High NA SA R 1,2,3 g

8. HPCI Steam Line Area

,e a Temperature - High NA SA R 1,2,3 A 9. HPCI Equipment Area g Temperature - High NA SA R = 1,2,3

-,_, 10. Drywell Pressure - High

$ Transmitter: NA' NA R' 1, 2, 3 Trip Logic: D

@Q -4HPq 1, 2, 3 K

a -

TABLE 4.3.2-1 (Continued.1 b ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

r CHANNEL OPERATIONAL M CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 7 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g

4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

[ b. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam Line Flow - High Transmitter: NA NA R* 1,2,3 Trip Logic: D -tHPQ MQ 1,2,3 K

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

3. RCIC Steam Supply Pressure - Low 1,2,3 t' 4. RCIC Steam Line Tunnel NA --tt-]!> Q Q K

Temperature - High NA SA R 1,2,3

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

6. RCIC Turbine Exhaust Diaphragm Pressure - High 7.

NA --MiPQ R 1,2,3

[

RCIC Steam Line Ambient Temperature - High NA SA R 1,2,3 l

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

k g

10. RCIC Equipment Room A Temperature - High NA SA 1, 2, 3 R

l E 11. RCIC Steam Line Tunnel Tempera- -

ture - High Time Delay Relay NA SA R 1,2,3 l

$ 12. Drywell Pressure - High Transmitter: NA NA R* 1,2,3 Trip Logic: -M-jPQ D

--H-P Q 1,2,3

[

b v V g TABLE 4.3.2-1 (Continued)

E g ISOLATION ACTUATION INSTRtMENTATION SURVEILLANCE REQUIREMENTS s

E

CHANNEL OPERATIONAL

') e CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION ~ SURVEILLANCE REQUIRED f..

H y 5. SHtTTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Level -

Low, Level 1 Transmitter NAI *) NA R(b) 1, 2, 3 Trip Logic D Mk Wk 1, 2, 3 [

b. Reactor Steam Dome Pressure - High NA S/UIC ,Q R 1, 2, 3 w

2 a

n

-O

~

w - - - e -

)' , . TABLE 4.3.2-1 (dEstinued)

, ISOLATION ACTUATION INSTRUMENTATIOR SURVEILLANCE REQUIREMENTS NOTES I -

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

(b) Transmitters are exempted from the s h channel calibration. hk (c)(It not performed within the previous 31 days.] hak2 (d) Testing shall verify that the mechanical vacuum pump trips and the mechanical vacuum pump line valve closes.

(e) When reactor steam pressure > 500 psig.

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

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BRUNSWICK - UNIT 2 3/4 3-32 Amendment No. 379 O I 1

1

TNSTRUMENTATION-3/4.3.3 EMERGENCY CORE C0F_ING SYSTEM ACTUATION INSTRUMENTATION

~

, LIMITING CONDITION FOR OPERATION

-)

3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation ch2hnel5 shown in Table 3.3.31 shall be OPERABLE with their trip setpoints set consistent with the ' values shown .in the Trip Setpoint column of Table 3.3.3 2. I APPLICABILITY: As shown in Table 3.3.31.

ACTION: .

a. Wtth an ECCS actuation instrumentation channel trip setpoint less co'nservative than the value shown in the Allowable Values column of Table 3.3.3-2. declare the channel inoperable eM alece the %g=bic 4

-c%"xl ir thc t.-ipped m..di1Mtil the channel"is restored to - .

OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

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

take the ACTION required by Table 3.3.31.

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

SURVEILLANCE REQUIREMENTS

'j 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.31.

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

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

)

BRUNSWICK - UNIT 2 3/4 3-33 Amendment No. 202

.J y; E

x N TABLE 3.3.3-1 P

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

~ MINIMUM L LER

% APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP.3Y999CL n

CONDITIONS ACTION (

F W cT10N

1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level - Low, Level 3 #f 1,2,3,4,5- 30 (

b. Reactor Steam Dome Pressure - Low (Injection Permissive) 1,2,3,4,5 g30 l {

1 c. Drywell Pressure - High g*f 1,2,3 30 K

d. Time Delay Relay 1/ pump 1,2,3,4,5 31 (

e. Bus Power Monitor" 1/ bus 1,2,3,4,5 32

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Drywell Pressure - High 2'Y 1, 2, 3 30 K

b. Reactor Vessel Water Level - Low, Level 3 /Y 1, 2, 3, 4", 5" 30 K k c. Reactor Vessel Shroud Level (Drywell Spray Permissive) 1[ Valve 1, 2, 3, 4", 5" 31 (

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

S 1. RHR Pump Start and LPCI Injection Valve Actuation 1, 2, 3, 4", 5" 30 g)(30 K 4", 5"

2. Recirculation Loop Pump Discharge Valve Actuation 1, 2, 3,

(

e. RHR Pump Start - Time Delay Relay 1[purng 1, 2, 3, 4", 5" 31 K

f. Bus Power Monitor" 1/ bus 1, 2, 3, 4", 5" 32

_ _ _ _ _ . _ _ _ _ .____.____m_.. - _ . _ _ _ _ _ _ _ - _ _ _ _ _ _ - . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ - _

~

os t

_l G

v g TABLE 3.3.3-1 (Continued)

E .

y EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM ..J..o m APPLICABLE N OPERABLE CHANN OPERATIONAL PER TRIP ' " ' ~ "

CONDITIONS ACTION TRIP FUNCTION FUNCTION

3. HICH PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level - Low, Level 2 #Y 1,2,3 30 N

b. Drywell Pressure - High EN 1,2,3 30 X

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

2 e 1/ bus 1, 2, 3 32

e. Bus Power Monitor (d) 0 4. -AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch # 2. 1,2,3 36 X

b. Reactor Vessel Water Level - Low, Level 3 E 4 1,2,3

/$ k

c. Reactor Vessel Water IAvel - Low, Level 1 # 2,, 1, 2, 3 . )dI j(p K

d. ADS Timer #A 1,2,3 X36 K

e. Core Spray Pump Discharge Prosaure - High (Permissive) #Y 1,2,3 X% K g

f. RHR (LPCI HODE) Pump Discharge Pressure - High (Permissive) 2/ pump 1,2,3 X% )(,,

Bus-Power Monitor Id) 1/ bus. 1,2,3 32 N g.

5 p 1

._ - -- - - . .. . . =

l l

- TABLE 3.3.3-1 (Continued)

EMERCENCY. CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTIONS l j

. ACTION 30 - With the number of OPERABLE channels lessjthan required by the Minimum OPERABLE Channels per Trip W requirement: X_ l l

INSERT jC 5 For one trip-system, place at least o rable) l chan tripped condit" in one hour or i

( ,

' /

m declare the assoc o'erable.

i

b. For b p systems, declare the associate S y ]

perable. ,

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

the Minimum OPERABLE Channels per Trip requirement, K l ff l

declare the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip :;n._" requirement, verify bus power availability at least >nce er 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or

[ l declare the associated ECCS inoperable g ACTION 33 - WiththenumberofOPERABLEchannelsless[tha ~ required by

[. ] the Minimum OPERM LE Channels per Trip ,. d equirement, K place at least one inoperable channel in the ipped' condition withis one hour or declare the system %'

inoperable. .

ACTION 34 - With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1'or 3.8.1.2, as appropriate.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in j the tripped' condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then ;

continue until performance of the next required CHANNEL l FUNCTIONAL TEST.

ACit" % -

With the number of OPERABLE channels less ^-g..-wy y

" rD A R LE _C ' = n a ' _ em trip Function l

the Minun requiremen e t se aavym LM 4=nnel to OPERABLE je _ within 8 houre er declare the associatsu C ' '

inoperable. -

INsser zc l

\

1 l

.I l BRUNSWICK - UNIT 2 3/4 3-37 Amendment No. 160 1

1 Lnsert 10, pano 3/4 3-37

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or are placed in the tripped condition to maintain automatic ECCS actuation capability for the Trip Function, and

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place all inoperable channels that do not cause the Trip Function to occur in the tripped condition.

Otherwise, declare the associated ECCS inoperable.

l Insert 2C, paae 3/4 3-37 ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to maintain actuation capability of either ADS Trip System A or ADS Trip System B and restore the inoperable channels to OPERABLE ctatus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare ADS inoperable.

Insert 1C. pane 3/4 3-37

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or are placed in the tripped condition to niaintain automatic ECCS actuation capability for the Trip Function, and

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place all inoperable channels that do not cause the Trip Function to occur in the tripped condition.

Otherwise, declare the associated ECCS inoperable. j i

insert 2C, page 3/4 3-37 ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to maintain actuation capability of either ADS Trip System A or ADS Trip System B and restore the inoperable channels to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare ADS inoperable.

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TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

'y f1NSED 3C,_

NOTES (a)"A cnanne ...;, 5 placed in an inoperable

, status fnr !; t: t = h a.., iv Q l required surveillance witnuuc 2 ':

.n o system in the tripped T condition, prov u-f ieast one OPERABLE channel in one g uring the affected narameter.

om..s.

trQem J !

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

(c) Provides signal to HPCI pump suction valves only.

(d) Alarm only.

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

a one-time basis, prior to start-up from the outage that began on Apr 1992, the Minimum Number OPERABLE Channels per Trip System for one reac eam dome pressure - low (injection permissive) trip fun 1 may-be reduced, o longer than 7 days, from two (2) channels ne (1) channel without ce ng the associated ECCS inoperable accordance with ACTION 31. This will e on one occasion for U and two occasions for Unit 2. During the riods, the f ing actions shall >

be implemented:

(1) The inoperable channel shall aced in condition that will

) satisfy the logic for al ng injection by t ssociated ECCS with .

the reactor steam d pressure below 410 psig sig. I (2) Both chan in the othe*r trip system shall be maintaine RABLE.

(3) reactor vessel head vent shall be maintained in the open.

position.

i f

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BRUNSWiv., UNIT 2 3/4 3-38 Amendment No. 191 I

insert 3C, pane 3/4 3-38 When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function or the redundant Trip Function maintains ECCS actuation capability.

\ .

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v v v g TABLE 4.3.3-1 E

y EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

M -

CHANNEL OPERATIONAL G8 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

@ TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED l U

u 1. CORE SPRAY SYSTEN

a. Reactor Vessel Water Level -

Low, Level 3 Transmitter: 'NA(a) NA R(b) 1,2,3,4,5 Trip Logic D

-th>Q - t&p Q 1,2,3,4,5 K

b. Reactor Steam Dome Pressure - Low Transmitters NAI *) NA R(b) 1,2,3,4,5 t'

v Trip Logic D MQ _ Mk 1,2,3,4,5 K Y c. Drywell Pressure'- High

$ Transmitter: NAI *) NA R(b) 1, 2, 3 Trip Logic D -tt:P Q !> 1, 2, 3 N

d. Time EMlay Relay NA R R 1,2,3,4,5

e. Bus Power Nonitor NA R - NA 1,2,3,4,5

2. LOW PRESSURE COOLANT INJECTION NODE OF RHR SYSTEN

a. Drywell Pressure - High

{o Transmitter:

Trip Logic NA(a)

D NA

-tH> Q Wk R(b) 1, 2, 3 1, 2, 3 a b. Reactor Vessel Water Level -

" Low, Level 3

Transmitter: NA(a) NA R(b) 1, 2, 3, 4(d)

Trip Logic: D -th> hk ,

, Id) ,[

1, 2, 3, 4(d), S5(d)

c. Reactor Vessel Shroud Level g Transmitter: NA NA R 1, 2, 3, 4 5 Trip Logic: D --ttP % 1, 2, 3, 4(d), $(d)

s G J g TABLE 4.3.3-1 (Continued)

E y EMERCENCY CORE COOLING SYSTEM ACHIATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

M CHANNEL OPERATIONAL

8 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN u!!ICH

@ TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANr5 REQUIRED l 4

y IDW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEN (Continued)

d. Reactor' Steam Dome Pressure - Low NA(*I NA R(b) 1, 2, 3, 4(d),S Id)

1. RHR Pump Start and LPCI MQ 1, 2, 3, 4 Id) ,S Id) '

Injection Valve Actuation D

$Q k

2. Recirculation Loop Pump Discharge Valve Actuation D @Q --ttdP 1, 2, 3, 4 Id) ,S Id) N w

e. RHR Pump Start - Time Delay Relay NA

R R 1, 2, 3, 4(d) ,S Id)

f. Bus Power Nonitor NA R NA 1, 2, 3, 4(d),S Id) l 3. HICH PRESSURE COOLANT INJECTION SYSTEN

a. Reactor Vessel Nater Level -

Low, Level 2 Transmitter NAI *} NA R(b) 1, 2, 3

! Trip Logict D -etPk MQ 1, 2, 3 K

b. Drywell Pressure - High g Transmitter NAI ") NA R(b) 1, 2, 3' Trip Logict D Mk -4td> 1, 2, 3 K

y n

c. Condensate Storage Tank Level - Low NA Mk Q 1,2,3 K

y d. Suppression Chamber Water Level - High NA

$Q Q 1, 2, 3 K

g e. Bus Power Monitor NA R NA 1, 2, 3 l

l l

l

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

r.

~

., g _

g TABLE 4.3.3-1 (Continued)

E y

EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREMENTS E

M

'? CHANNEL OPERATIONAL 8

CHANNEL FUNCTIONAL CHANNEL

TRIP FUNCTION CONDITIONS IN WHICH Q CHECK TEST CALIBRATION SURVEILLANCE REQUIRED l n

g 4. AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch D(C} R NA 1,.2, 3'

b. Reactor Vessel Water Level -

Low, Level 3 Transmitter NAI *} NA R(bj 1,2,3 Trip Logic D --46pQ -9PPk 1, 2, 3 R*

c. Reactor Vessel Water Level -

Low, Level I w Transmitter: NAI ") NA R(b) 1, 2, 3 h Trip Logict D Mk Q

1,2,3 K

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

L

e. Core Spray Pump Discharge Pressure - High NA P Q 1,2,3 K

f. RHR (LPCI NODE) Pump Discharge Pressure - High NA Tk Q 1,2,3 K

g g. Bus Power Monitor NA R NA .1, 2, 3 O

- . ~ . . . ... - ,

-f:

s :

TABLE 4.3.3-1 (Continued)

E E EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SUR y OPERATIONAL '

CHANNEL '

CHANNEL CONDITIONS IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE REQUIRED- l. ,

CALIBRATION 8

CHECK _

TEST i

> TRIP FUNCTION 1

g u 5. IDSS OF POWER R. ' 1, 2 3 3, 4(d) 5(d)

MA NA

. a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)

R 1,2,3,4 Id) 5(d) ,

MA N i

b. 4.16 kw Emergency Bus i Undervoltage (Degraded Voltage) ,

E.

s Y

re .

Y The transmitter. channel check is satisfied by thequay trip {cr/[ unit ~channel check.

(a)

A separate transmitter check is not required.annel calibration.

g .

o (b) Transmitters are esempted from theThe ADS Inhibit Switches shall be maintained in the Auto (c) is required to be OPERABLE.

(d) Required when ESF equipment .

_ ,.z.. a. 2___..L_.,_m. .a-- ..aa___..__-m_m.-_-__ _______-m u__ b e-- -- e __ _ F' s_

w 4*s9-v-"- .we..'4 e -+ec+- eu*r.-- "t e. e-g

W4 s- %

I

-- TABLE 3.3.4-1 (Continued)

~

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION Nbb NOTES f

(a The minimum num er of OPERABLE C b one for up to Y l

]h, hours in one of the

~

s or maintenance and/or ces gf i or function.

(forRo 1 (b) This function is bypassed if detector is reading >100 cps or the IRH )

channels are on range 3 or higher. .

l

)

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

(d) A total of 6 IRM instruments must be OPERABLE. I (e) This function is bypassed when the IRH channels are on range 1. 1 (f) When (1) THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER and less than 90% of RATED THERMAL POWER and MCPR is less than 1.70, or (2) THERMAL POWER is greater than or equal to 90% of RATED THERMAL POWER and MCPR is less than 1.40.

(g) With any control rod withdrawn. Not applicable to control rods removed

.}

per Specification 3.9.10.1 or 3.9.10.2.

J i

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

BRUNSWICK - UNIT 2 3/4 3-49 Amendment No. 168 C

insert 1D, pane 3/4 3-49 When a channel is placed in a inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains control rod block capability. )

1 1

I j

l 1

I l

I i

l l

1 i

1 l

l l

1

t J w -

as TABLE 4.3.4-1 il CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION SURVEILIANCE REOUIREMENTS g

s q M CHANNEL OPERATIONAL

. CHANNEL FUNCTIONAL CHANNEL' CONDITIONS IN WHICH CHECK _ TEST CALIBRATION SURVEILLANCE REQUIRED g TRIP FUNCTION

1 ~

" )(*}

Upscale (Flow Biased) NA S/U " R l g) 1,2,5

b. NA NA-Inoperative S/U ,) ,

1 hwnscale NA SW(,)

c.

d. Upscale (Fixed) NA S/U ,Q(g)(g) Ng R ,) 2, 5 -

l

2. ROD BIDCK MONITOR NA R(*} 1((E

a. Upscale S/U(I*}Mk 4 b. Inoperative NA S/U(#} g,Q Ng*

R 1(E}

1 E} ,

c. Downscale NA .

S/U

3. SOURCE RANCE MONITORS NA S/U(# ) ,W I) NA 2, 5 '

Y a. Detector not full in 2, 5 i NA ,W NA

$ b. Upscale S/U

,W d

NA 2, 5

c. Inoperative NA S/U NA ,W NA 2,.5

d. Downscale S/U

4. INTERMEDIATE RANGE MONITORS NA 2

a. Detector not full in NA Sg("}k'} ,W(d) NA 5 NA W

,W I} 2 1 NA 'S/U("} NA 4 b. Upscale -

NA V NA 5 k ,W NA 2 E c. Inoperative NA S/U("

NA V NA 5 NA S/U( ,W( NA 2.

d. Downscale

.,5 NA W NA E

5. SCRAN DISCHARGE VOLUNE

.U

" R_ 1, 2, 5( }

~

a. Water Level - High NA Q

TABLE 4.3.5.5-1 CONTROL ROOM EMERGENCY VENTILATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL FUNCTION CHECK TEST CALIBRATION CHLORINE ISOLATION:

1. Local Detection NA M A Trip System

2. Remote Detection NA M A Trip System RADIATION PROTECTION: -

1. Control Room Air Intake D

WQ R CONTROL ROOM ENVELOPE SM0KE PROTECTION: ,

1. Zone 4 NA 6 months (a)

2. Zone 5 NA 6 months (a) h (a) See Surveillance Requirement 4.7.2.d.2 l

l l

.)

BRUNSWICK - UNIT 2 3/4 3-64c Amendment No. 192 !

, INSTRUMENTATION

)

3/4.3.6 RECIRCULATION PUMP TRIP (RPT) ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION <

LIMITING CONDITION FOR OPERATION l '

3.3.6.1 The ATWS-RPT system instrumentation *

- -- " - N hown in Table 3.3.6.1-1 shall be OPERABLE with their trip setpoints set consisteht k

with the values shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a. With an ATWS-RPT system instrumentation trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6.1-2, declare the instrument channel inoperable until the channel is restored to OPERABLE status with its trip setpoint INSERT qE adjusted consistent with the T 1, Set,oint watue.

~ With the number of OPERABLE channels one less than required by the I inimum OPERABLE Channels per Trip System requirement for one or hi j r '

t systems, place the inoperable channel (s) in the tripped within one hour.

condt

/

c. With the tota umber of OPERABLE channels less than s required by the Minimum OPE E Chan,nels per Trip System requ' nt for one i trip system and:

1. If the inoperable cha is consist one reactor vessel water level channel and one re tor y el pressure channel, place both inoperable channels in tripped condition within one hour.

2. If the inoperable els include t reactor vessel water level channels two reactor vessel p sure channels, declare the trip sy a inoperable.

l

d. With one tr* system inoperable, restore the inopera trip system l to OP status within 14 days or be in at least ST P within the n 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

e. th both trip systems inoperable, restore at least one trip sy a to OPERABLE status within one hour or be in at least STARTUP withs the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . *

)

BRUNSWICK - UNIT 2 3/4 3-88 Amendment No. 160

Insert 1E, page 3/4 3-88

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

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

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

c. With trip capability for one ATWS-RPT Trip Function not maintained, restore trip capability ,

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l

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

Otherwise, be in at least STARTUP within the next six hours.

l 1

i

) TABLE 3.3.6.1-1 ,

AIVS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 4NN(45 N MINIM T PERABLETgP)

TRIP FUNCTION SYSTEM . 27. 0 7:r_"2"' 7"""

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

2. Reactor Vessel Pressure - High 2 i

\

l l

l FidSEP.T W '

r (8) ke trTp'T7::- ==v be olaced in an inoperable status for un en ' ha"-- 3 for required surveillance nravid " --- ,os v s .. . .

--4a system is ,

.! OPERABfL - l l

- -- i BRUNSWICK - UNIT 2 3/4 3-90 Amendment No. 160

insert 2E. Daae 3/4 3-89 (Unit il and 3/4 3-90 (Unit 2)

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

1 1

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

1. Reactor Vessel Water Level -

o. Low, Level 2 Transmitter: NA(a) NA R ID)

Trip Logic: D WQ WQ

2. Reactor Vessel Pressure - High Transmitter:

Trip Logic:

NA(a)

D

/kk R ID)

(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 channel calibration.

BRUNSWICK - UNIT 2 3/4 3-92 Amendment No.160

f l

i INSTRUMENTATION ;

END-OF-CYCLE' RECIRCULATION' PUMP TRIP SYSTEM INSTRUMENTATION LIMITINC CONDITION FOR OPERATION 3.3.6.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels'shown in Table 3.3.6.2-1 shall be'0PERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint '.

column of Table 3.3.6.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.6.2-3.

APPLICABILITY: OPERATIONAL' CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.* ;

ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the A11ovable Values Column of Table 3.3.6.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels one less than required by che

- Minimum OPERABLE Channels per Trip System requirement for one or.both

< trip systems, place the inoperable channel (s) in the tripped

-N i} condition within :- " - 12. hcnes, -

c. With the number of OPERABLE' channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one ,

trip system and:

1. If the operable channels consist of one turbine control, valve i channel and one. turbine stop valve channel, place both '

inoperable channels in the tripped condition within cr: E ;.-/2 % .)

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

system operable. l

d. With one trip system inoperable, restore the inoperable trip system j to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or take the ACTION required by i Specification 3.2.3.

e. With both trip systems inoperable, restore at least one trip system !

to OPERABLE status within one hour or take the ACTION required by l Specification 3.2.3. *

]

During the current cycle operation, the end-of-cycle recirculation pump trip (EOC-RPT) system will be inoperable (manually bypassed); therefore, Specification 3.3.6.2 above does not apply. The provisions of

..) Specification 3.0.4 are not applicable.

BRUNSWICK - UNIT 2 3/4 3-93 Amendment No. 160 )

TABLE 3.3.6.2-1 ,

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMUM

~ OPERABLE CFANN PERTRIPSYSTEMg 1 TRIP FUNCTION 2(b) l

1. Turbine Stop Valve - Closure ,

l 2(b)

2. Turbir9 Control Valve - Fast Closure i

- NSERT IF

(*) * -

r up to hours j f

A trip system may

for required surveil .teo L OP (b) These functions are bypassed when turbine first stage pressure is

} equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER. .

3/4 3-95 Amendment No. 160 BRUNSWICK - UNIT 2 0

insert 1F, paae 3/4 3-95 (Unit 2 only)

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

l i

[) TABLE 4.3.6.2.1-1 l END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION TEST CALIBRATION

~

1. Turbine Stop Valve - Closure R [

2. Turbine Control Valve - Fast Closure ) R r

1 i

1 4

i (a) Including trip system logic testing.

BRUNSWICK UNIT 2 3/4 3-98 Amendment No.160

(

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

1 i

4

' -l INSTRUMENTATION ,

[ . 1 y l

-1 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION-LIMITING CONDITION FOR OPERATION !

3.3.7 The reactor core isolation cooling (RCIC) system actuation Ms/r !

instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with 4beip4 trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.7-2. . .

e-APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome

\ pressure greater than 113 psig.- l ACTION: 'i With a RCIC system actuation instrumentation channel trip setpoint j a

less conservative than the value shown in the Allowable Values column of Table 3.3.7-2, declare the channel inoperable until the channel is 1 restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value..

1

b. With one or more RCIC' system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.7-1. l

,, i SURVEILLANCE REQUIREMENTS

() '

4.3.7.1 Each RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL i

l 1

FUNCTIONAL TEST and CEANNEL CALIBRATION operations at the frequencies shown in j Table 4.3.7.1-1.

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

1 l

i l

1 s

i .

] -

i 3/4 3-99 Amendment No. 160 BRUNSWICK - UNIT 2

.J w. Q ^i E TABLE 3.3.7-1 E

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.

-h R

' MINIMUM E OPERABLECHANNELg*) '

PER TRIP SYSTEM ACTION U FUNCTIONAL UNIT u 2 50

1. Reactor Vessel Water Level - Low, Level 2 2(b) $g

2. Reactor Vessel Water Level - High Condensate Storage Tank Water Level - Low (d) 2 ICI 52 3.

t.c Y

E o

j. INSpr M S

" red surveillance without _

f (a) A channe may e y ace the placing the tri rapped condition provided at le.ast one other m LR-- t* E 1 (b) One trip system with two-out-of-two logic.

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

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

insert 1G. Daae 3/4 3-93 (Unit 1) and 3/4 3-100 (Unit 2)

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

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

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

I I

i i I

TABLE 3.3.7-1 (Continued)

]

REACTOR CORE ISOLATION COOLING SYSTEM j l

ACTUATION INSTRUMENTATION ACTIONS i

ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. ror one trip system, place the inoperable channel (s) Jnd/or that trip system in the tripped condition within MourS %

or declare the RCIC system inoperable. 2Y j 1

INSERT 2G b. ror both trip systems, dectare the RCIC system inoperabte.

ACTION 51 siG ... "- nf OPERABLE channeln 1--- O__:. .y..... uy wue ,

Minimum OPERABLP. W A Ep oy.6 - .:-" -=ent, declare _,

2 Lthe ne m ;__ _ znoperable. l ACTION 52 - With the number of OPERABLE channels less than required by the j Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within M 2Y [

hourJoe declare the RCIC system inoperable.

.) p K \

l i

l l

4 l

t' l

l

. i i

BRUNSWICK - UNIT 2 3/4 3-101 Amendment No. 160 l

Insert 2G, pane 3/4 3-94 (Unit 1) and 3/4 3-101 (Unit 2)

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

a' -Q -Q]

$ TABLE 4.3.7.1-1 E

y REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

M CHANNEL 8

CHANNEL FUNCTIONAL CHANNEL g FUNCTIONAL UNIT CHECK TEST CALIBRATION G

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

Trip Logict D

--MP Q --43> k

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

Trip Logict D ;;

@Q

3. Condensate Storage Tank Level - Low NA :: 7 Q s

Y o

w o

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

(b) Transmitters are exempted from the A hannel calibration.

N i______________________________________________________ _ . _ _ _ _ _ _ _ . _ _ _ _ _____ __ _ _ _ _ _ _ . _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___________

-s

P wpe <

BASES FOR SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION ,

AND

'. ') SURVEILLANCE REQUIREMENTS l

I

)

i j

1 l

l l

l i

1

)

RETYPED TECH. SPECS. '

Updated Thru. Amend. 78.

i i

) :

P l

l NOTE The Summary statements contained in this section provide the bases for the specifications in Sections 3.0 and 4.0

(-. and are not considered a part of these~ technical specifi-cations as provided in 10 CFR 50.36.

l'

.)

?

1 4

6

..)

RETYPED TECH. SPECS. 3 Updated Thru. Amend. 78 C

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

a.

Preserve the integrity of the fuel cladding.

b.

Preserve the integrity of the reactor coolant system. ,

c.

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

This specification provides the limiting conditions for operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because of maintenance.

When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests.

The systems. reactor protection system is made up of two independent trip in each tripThere are usually four channels to monitor each parameter with two system.

The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The ,

tripping of both trip systems will produce a reactor scram. The system meets C the intent of TREE-279 for nuclear power plant protection systems. The bases 2 2.the trip settings of the RPS are discussed in the bases for Specification for The measurement assurance that of response time at the specified frequencies provides the protective, isolation, and emergency core cooling functions associated with the accident analysis. each channel are completed within the time limit assumed in times indicated as not applicable.No credit was taken for those channels with response Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements, provided such tests

demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) inplace, onsite, or offsite test ,

i measurementa; times. or 2) utilizing replacement sensors with certified response

"""Thr " * ? ! C fws 6ac 66Ay W p f7! Sie "iV0r #" ^" ***00 fs,s idiva. 2.0 ^

NSERT W w

)

JLRUNSWICK - UNIT 2 B 3/4 3-1 RETYPED TECH. SPECS.

Updated Thru. Amend 78 L

I insert 1H, pane B 3/4 3-1 i

Specified surveillance intervals and allowed out-of-service times were established based on the )'

reliability analyses documented in GE reports NEDC-30851P-A, " Technical Specification improvement Analyses for BWR Reactor Protection System," March 1988 and MDE-81-0485, Rev.1,

" Technical Specification Improvement Analysis for the Reactor Protection System for Brunswick Steam Electric Plant, Units 1 and 2', August 1994, as modified by BWROG-92102, Letter from C. L.

Tully (BWROG) to B. K. Grimes (NRC), "BWR Owners' Group (BWROG) Topical Reports on Technical Specification Improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844 and NEDC-30851P)," November 4,1992.

i t

-INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures t:.s ef fectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the trip settings for isolation of the reactor systems. When necessary, one channel may be inoperable for brief intervals to conduct required surveillance. Some of-the trip settings have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety. The setpoints of other instrumentation where only the high or low end of the setting has a direct bearing on the safety, are established at a level away from the normal operating range to prevent inadvertent actuation of the syste_ms inv ived. ,

-[ 3 ..

uu.mNCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control. This specification provides the trip point settings that will ensure effectiveness of the systems to provide the design .

protection. Although the instruments are listed by system, in some cases the same instrument is used to send the start signal to several systems at the same time. The out-of-service times for the instruments are consistent with

",) the requirminents of the specifications in Section 3/4.5.

W@MM39 3/4.3.4 ~ CON L ROD WITHDRAWAL BLOCK INSTRUMENTATION N

The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Rod Program Controls and Section 3/4.2, Power Distribution Limits. The trip logic is arranged so that a trip in,any one of the inputs will result in a rod block.

3/4.3.5 MUNITORING INSTRUMENTATION 3/4.3.5.1 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seir:mic monitoring instrumention ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility.

}

BRUNSWICK - UNIT 2 B 3/4 3-2 RETYPED TECH. SPECS.

Updated Thru. Amend. 78

.p

Insert 2H, pane B 3/4 3-2 Specified surveillance intervals and allowed out-of-service times were established based on the

-reliability analyses documented in GE reports NEDC-30851P-A, Supplement 2, " Technical Specification Improvement Analysis for BWR lsolation instrumentation Common to RPS and ECCS Instrumentation," March 1989 and NEDC-31677P-A " Technical Specification improvement Analysis

~for BWR isolation Actuation instrumentation," July 1990, as modified by OG90-579-32A, Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE), " Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Analysis," June 25, 1990 and supplemented by GE letter report GENE-A31-00001-02, " Assessment of Brunswick Nuclear Plant Isolation Actuation instrumentation Against NEDC-31677P-A Bounding Analyses," August 1994.

Insert 3H. page B 3/4 3-2 Specified surveillatwe intervals and allowed out-of-service times were established based on the

. reliability analyses documented in GE reports NEDC-30936P-A, Parts 1 and 2, "BWR Owners' Group Technical Specification improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," December 1988 and RE-011, Rev.1, " Technical Specification improvement

. Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant Units 1 & 2," August 1994, as modified by OG90-319-32D, letter from W. P. Sullivan and J. F. Klapproth (GE) to Millard L. Wohl (NRC), " Clarification of Technical Specification Changes Given in ECCS Actuation instrumentation Analysis", March 22,1990.

Insert 4H. page B 3/4 3-2 Specified. surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report NEDC-30851P-A, Supplement 1, " Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," October 1988.

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

Surveillances (Continued) instrumentation continues to operate properly between each CHANNEL CALIBRATION. The CHANNEL CHECK frequency is consistent with that oorfnrmd for other radiation monitors with isolation functions. f The CHANNEL FUNCTIONAL TEST is performed on each required cha Jnneli ensure that the entire channel will perform the intended function. TfFe Control Building HVAC DBD (Reference 6) defines the specific act g to be satisfied

."'.,o requency of the by the radiation actuation instrumentation. The CHANNEL FUNCTIONAL TESTois consistent wit that performed for other rad _iatinn [g monitors with isolation functions. gg g] y [}f '

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

Chlorine Protection .

The CHANNEL FUNCTIONAL TEST is performed cn each required channel to ensure that the entire channel will perform the intended function. The Control

) Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the chlorine isolation instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the sensor when the sensor is replaced. The test verifies the ,

calibration of the existing sensor prior to removal and performs an installation calibration of the new sensor, including a complete channel calibration with the new sensor installed, to verify the channel responds to the measured parameter within the necessary range and accuracy. The CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 6).

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

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

BRUNSWICK - UNIT 2 B 3/4 3-3d Amendment No. 192

i INSTRUMENTATION BASES

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3/4.3.5.5 CONTROL Room EMERGENCY VENTILATION SYSTEM (Continued)

References

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

2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release. ,

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

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

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

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

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7, 4eue-7w 1- A,

Baus for cmjes te feveillace Test Intenals anJ AllewL Out-,f-service has for Wtej -

Imt%extatiot Taknial Speci&ati ns," f)eceder 1992.

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i BRUNSWICK - UNIT 2 B 3/4 3-3e Amendment No. 192

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i INSTRQ4ENTATION i i

BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRG4ENTAT The initial CHANNEL CALIBRATION for the instruments associated with footnote (b) to Table 4.3.5.9-1 shall be performed using National Bureau of Standards traceable sources which will verify that the detector operates properly over its intended energy range and measurement. range. For instruments which were operational prior to this specification being ,

implemented, previously established calibration procedures may be substitut for.this requirement. e d

Subsequent CRANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that thk detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.

3/4.3.6 .

RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.

The response of the plant to this postulated event f alls within an envelope of study events given in General Electric Company Topical Report NEDO-10349, dated March,1971.

The end-of-cycle. recirculation pump trip (E00-RPT) system is a part of the

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Y Reactor Protection. System and is a safety supplement to the reactor The trip.

purpose of the E00-RPT is to recover the loss of thermal margin which occurs at the end of-cycle.

The physical phenomenon involved is that the void

.] reactivity feedback due to a pressurization transient can add positive reactivity to the reactivity.

negative scram reactor system at a faster rate than the control rods add Each E00-RPT system trips both recirculation during two of the most limiting pressurization events. pumps, reducing c The two events for which the EOC-RPT protective feature will function are closure of the turbine stop valves and f ast closure of the turbine control valves.

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

Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch for each of the other two EOC-RPTstop turbine valves provides input to the other EOC-RPT system. For each system, logic for closure of the turbine stop valves.the sensor relay contacts are arra will actuate the EOC-RPT system and trip both recirculation pumps.The operation of Each EOC-RPT controlled.

administratively system may be manually bypassed by use of a keysvitch which is bypass at < 30% of RATED THERMAL POWER are annunciated in the -

INSERT Sit

) BRUNSWICK - UNIT 2 B 3/4 3-6 Amendment No. gg i

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insert SH. pano B 3/4 3-6 Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-1-A, " Bases for Changes to Surveillance Test intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," December 1992.

Insert 6H. pane B 3/4 3-6 (Unit 1) and B 3/4 3-7 (Unit 2)

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected instrumentation Technical Specifications," December 1992.

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INSTR! MENTATION _

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'- BASES 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation'from its primary heat sink and the loss of feedwater flow to .

the reactor vessel without providing actuation of any of the emergency core-cooling equipment.

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s BRUNSWICK - UNIT 2 B 3/4 3-7 Amendment No. 94 x-

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