ML20065K969

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Proposed Tech Specs,Reflecting Relocation of Response Time Tables to UFSAR
ML20065K969
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/14/1994
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20065K933 List:
References
NUDOCS 9404200206
Download: ML20065K969 (23)
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Text

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ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT RESPONSE TIME TABLE RELOCATION MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1

.)

E4-1 9404200206 940414 PDR ADDcK 05000324 P PDR-

s 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentaticn channels shown in Table 3.3.1-1 shall be OPERABLE,wi L l1 AGUE i T".CTI" """

prengyce m; = m - p ;;7 n m,t,1 1, ' ' Set points and interlocks are given in Table 2.2.1-1.

APPLICARILITY: As shown in Table 3.3.1-1.

ACTION: y 1

a. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or trip system in the tripped condition
  • within one hour.
b. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one trip system ** in  ;

the tripped condition within one hour and take the ACTION required by Table 3.3.1-1. i

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 CilANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of 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 e 'r ". 1 m -3.3. & shall be demonstrated to be within its limit at least once per 18 mon t h s .-d2Each 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 et least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 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, excent when this would cause the Trip Function to occur.

M Nid h Mhecbr$ OJL exemf[rwnresp8aMAcYtSh.

f BRUNSW1CK - UNIT 1 3/43-1 Amendment No. ' 78 l

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1 i 1

. h tgrs - Rc a u w ro Uponm F5AK TABLE 3.3.1-2, REACTOR PROTECTION SYSTEM RESPONSE TIMES RESPONSE TI E (Second j FUNCTIONAL NIT

\

1. Intermedi Range Monitors
a. Neutron flux - High("} NA
b. Inoperativ NA I
2. Average Power Ran, Monitor (8)
a. Neutron Flux - igh, 15% -

3 0.09

b. Flow-Biased Neutr n Flux - High NA
c. Neutron Flux - High, 120% $ 0.09
d. Inoperative NA
c. Downscale NA
f. LPRM NA

\

3. Reactor Vessel Steam Dome Pressur - High $ 0.55
4. Reactor Vessel Water Level - Low, Level 1 $ 1.05
5. Main Steam Line Isolation Valve - Clo re $ 0.06
6. Main Steam Line Radiation - High NA
7. Drywell Pressure - High NA
8. Scram Discharge Volume Water L' el - High NA
9. Turbine Stop Valve - Closure 1 0.06
10. Turbine Control Valve Fast losure, 3 0.08 Control Oil Pressure - .ow
11. Reactor Mode Switch in utdown Position NA
12. Manual Scram NA (a) eutron detectors are exempt from respanse time testing. Response time shall be measured from detector output or from the input of the-first electronic component in the channel.

BRUNSWICK - UNIT 1 3/4 3-6 Amendment No.130

\

_l IriSTRUMENTATI,0N 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent _with the values shown in the Trip Setpoint column of Table 3.3.2-2,and 1;L ISCLATION Si3TCH

-4EPPC!!"E T:hr .: ;H - ' n tam c 2a.M APPLICABILITY: As shown in Table 3.3.2-1.

ACTION: <

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

b. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition
  • within one hour.
c. With the requirements for the minimum number of OPERABLE channels not f satisfied for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 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 CONDITIONS and at the frequencies shown in Table 4.J 2-1. j 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.

i I

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or' l the ACTION required by Table 3.3.2-1 for that Trip Function shall be I taken.
    • If more channels are inoperable in one trip system than in the other, place the trip system with taore inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.

BRUNSWICK - UNIT 1 .3/4 3-10 Amendment No. 130 [

. 1 INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)

  1. N 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function sha+** ,

. * " - 2.2.2 3 shall be demonstrated to be within its limit at least once I per 18 months. Each test shall include at least one logic train such that both logic chains 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 ,

isolation function.

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BRUNSWICK - UNIT 1 3/4 3-11 Amendment No. 130 l i

( [E a tATES 7D LAff A TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TR FUNCTION RESPONSE TIME (Secon f M

1. P HARY CONTAINHENT ISOLATION
a. Reactor Vessel Water Level - l

. Low Level 1 s ,

1

2. Low, Level 3 1. (d) ,

s13p0 l

b. Drywe 1 Pressure High 513
c. Main St m Line
1. Radia ion High(b) ' (d) 51.p0 1 s13 4 I
2. Pressure Low s13 High (d)
3. Flow 50.p0 513
d. Main Steam Line Tun el Temperature - 'gh s13
e. Condenser Vacuum Lo s13
f. Turbine Building Area Te eratur -

High NA l

b

g. Main Stack Radiation High ) s 1.0(d) j
h. Reactor Building Exhaust R i ion Hightb) NA
2. SECONDARY CONTAINMENT ISOLATI N
a. Reactor Building Exh t Radiation Higb(b) s13 l
b. Drywell Pressure - igh s13
c. Reactor Vessel ater Level Low, Level s13
3. BEACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - h NA )
b. Area Te,perature - High NA
c. . Area entilation A Temperature High NA
d. S S Initiation NA
e. eactor Vessel Water Level - Low, Level 2 s f a Flow - High - Time Delay NA
g. Piping Outside RWCU Rooms Area Temperature High NA l 1

BRUNSWICK - UNIT 1 3/4 3 23 Amendment No. 166 r 1

& N6LD6Ai TABLE 3.3.2 3 (Continued).

7 ISOLATION SYSTEH INSTRUMENTATION RESPONSE TIME P FUNCTION RESPONSE TIME (Seco ds9'*)

4. E STANDBY COOLING SYSTEMS ISOLATION
a. (ghPressureCoolantInjectionSystemIsolation ,
1. PCI Steam Line Flow High s13(c)
2. H I Steam Line Flow High Time Delay Relay NA
3. HPCI team Supply Pressure Low s13
4. HPCI St m Line Tunnel Temperature, High / NA l
5. Bus Power nitor NA
6. HPCI Turbine haust Diaphragm Pressury High NA
7. HPCI Steam Line bient Temperature High NA
8. HPCI Steam Line Are ATemperatur/-High NA
9. HPCI Equipment Area Te ratur ' High NA
10. Drywell Pressure - High NA
b. Reactor Core Isolation Coolin S tem Isolation
1. RCIC Steam Line Flow - igh 5 13(C)
2. RCIC Steam Line Flo High Time D ay Relay NA
3. RCIC Steam Suppl Pressure Low NA .
4. RCIC Steam Li Tunnel Temperature High NA
5. Bus Power nitor NA
6. RCIC Tur ine Exhaust Diaphragm Pressure High NA
7. RCIC team Line Ambient Temperature High NA
8. RC C Steam Line Area A Temperature High 1A
9. RCIC Equipment Room Ambient Temperature High NA
6. RCIC Equipment Room A Temperature High NA
11. RCIC Steam Line Tunnel Temperature High NA Time Delay Relay
12. Drywell Pressure High NA BRUNSWICK UNIT 1 3/4 3 24 Amendment No. 166

l t l l

1 TABLE 3.3.2-3 (Conti .

. , en ISblATION SYSTEM INSTI . NTATION RESPONSE TIME l

TRIP FUNCTION ' RESPONSE TIME (Secot.ds)(a)(e)l

$. Sif UTDOWN COOLIN.'; S :H ISOLATI

a. React essel Water Level - Low, Lev 1 NA
b. eactor Steam Dome Pressure - liigh NA f

i Ghk' DOO 0 Y bb f

+

l l

1 3 .t .

I BRUNSWICK - UNIT 1 3/4 3-25 Amendment No. 149

I l

a TABLE 3.3.2-3 (Continued) I ISOLATION SYS' TEE INSTRUMENTATION RESPONSE TIMP l

NOTES (a) The isolation stem instrumentation respon-> time shall be measured and recorded as a pa of the ISOLATION SYST RESPONSE TIME. Isolation system instrumenta 'on response time s cified includes any delay for diesel generator sta ting assumed in he accident analysis.

(b) Radiation monitors are e empt fr m response time testing. Response time shall be measured from detset output or the input of the first electronic component in the hannel.

l (c) includes time delay add d by the time delay relay.

(d) Isolation actuatio instrumentation 'sponse time for MSIVs only. No diesel generator elays assumed.

(e) Isolation sy em instrumentation response t' e specified f or the Trip Function a unting each valve group / damper sh- I be added to the isolatir time f or valves in each valve group sh n in Table 3.6.3-1 and secon ry containment isolation dampers shown in T- le 3.6.5.2-1 to obt' n ISOLATION SYSTEM RESPONSE TIME for each valve, amper. -!

(f) Isolation system instrumentation response time for associ ed valves l except MSIVs.

I 1

3GLGTG- fet.otArew Tb UFSAd i

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l BRUNSWICK - UNIT 1 3/4 3-26 Amendment No. 149 I

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

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INSTRUMENTATION 3/4.3.3 EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation shown in Table 3.3.3-l' shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2, sa.t r"=Ci CUiiE hm m m mruton i niE a = aim,o . ;, T"l u An s . s - s .

APPLICABILITY: As shown in Table 3.3.3-1.

s 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 and place the inoperable channel in the tripped condition until 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 Tabic 3.3.3-1.
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 4.3.3-1.

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at 1 cast 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 ' - *:51 3. 3. 3 3~

shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that ..

all channels are tested at least once every N times 18 months, where N is the l total' number of redundant channels in a specific ECCS function.

J BRUNSWICK - UNIT 1 3/4 3-33 Amendment No. 130 4

e . -1 r...- . , - , -

I

. I TABLE 3.3.3-3 EMERCENCY CORE COOLING SYSTEM RESPpN MES

,./

ECCS RESPONSE TIME (Seconds)

1. CORE SPRAY SYSTEM / < 27
2. LPCI MODE of RHR Sy 40
3. HICH PRESSU ' COOLANT INJECTION SYST < 30
4. AUTOM C DEPRESSURIZATION SYSTEM f NA

/ . . , . . -

5 OSS'0F POWER N DELGTG- IlGlocATen 70 idFSAg .

'5

?

BRUNSWICK - UNIT 1 3/4 3-42 Amendment No. 130 l ,

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

4 ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50-324 I OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT RESPONSE TIME TABLE RELOCATION .

l MARKED UP TECHNICAL SPECIFICATION PAGES - UNIT 2 I

't 1

I E5-1

l 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITINC 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 mu mLACIGR GuiTCIIu i Si'CTE"

' r 20::Su T UiG u aim m, in Tobim 3.3.1-2. Set points and interlocks are given in Tabic 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION: y

a. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or trip system in the tripped condition
  • within one hour.
b. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 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 perf ormance of the CliANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the f requencies 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 af * * 2.3.!-? shall be demonstrated to be within its limit at least once per 18 months.Tb 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. ,

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.
    • If more channels are inoperable in one trip system than in the other, niace the trip system with more inoperable channels in the tripped bondition, except when this would cause the Trip Function to occur.

N N t,utron citft CbrJ dtfL t/SA(( rom P 5 f*4 0 b yds D -

BRUNSWICK - UNIT 2 3/43-1 Amendment No. 105

fe f(tbCbTED N S5 TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES RESPON " TIME FUNCTIONAL UN (S onds)

1. Intermediate

\ geMonity

a. Neutron F1 - liigh
b. Inoperative A
2. Average Power Range onitor(a)
a. Neutron Flux - Ht h, 15% $ 0.09
b. Flow-Biased Neutror Flux - High ,,

~

NA

c. Neutron Flux - High, 120% $ 0.09
d. Inoperative NA
e. Downscale NA
f. LPRM / NA
3. Reactor Vessel Steam Dome Pressu e - High - 1 0.55
4. Reactor Vessel Water Level - Low, level 3 1.05
5. Main Steam Line Isolation Valve - Cl dre ~< 0.06

/

6. Main Steam Line Radiation - liigh / NA
7. Drywell Pressure - liigh NA
8. Scram Discharge Volume Water 7Le el - High NA
9. Turbine Stop Valve - Closure . 1 0.06 l
10. Turbine Control Valve Fast losure, ~< 0.08 Control Oil Pressure - w
11. Reactor Mode Switch in mtdown Position NA ,
12. Manual Scram NA  !

l l

(8 eutron detectors are exempt from response' time testing. Response time shall be measured from detector output or from the input of the first electronic component in the channel, l

l BRUNSWICK - UNIT 2 3/4 3-6 Amendment No.160 ,

l

. .- -~ ..-- . .. . - . - - - . ~. -- - - . . - - . -

INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values

  • shown in the Trip Setpoint column of Table 3.3.2-2.aad ith ICOLAT:CN CYCT"i RE W " '"T o m i m ., u m ToLim 1.3.' 3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values ~ ]

column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition
  • within one hour,
c. With the requirements for the minimum number of OPERABLE channels .;

not satisfied for both trip systems, place at least one trip system **

in the tripped condition within one hour and take the ACTION required by Table 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. 'l l

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

  • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION 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, M ace 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. 160

r .

INdTRUMENTATION l SURVEfLLANCE REQUIREMENTS (Continued) 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function ebn w l> NJ o 1 1 *1 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that both logic chains 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 isolation function.

N.

A .hbhn ytt on 'Ib r ,) UQ rn [nm itsfax be b5 0.06 K ,

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&g BRUNSWICK -~ UNIT 2 3/4 3-11 Amendment No.160

f. - f(lbCh'W h TABLE 3.3.2-3 ISOLATION SYSTEH INSTRUMENTATION RESPONSE TIME TRIP F ION RESPONSE TIME ( Seconds a)(ed
1. PRIM CONTAINHENT ISOCATION

} ,

a. Rea tor Vessel Water Level -
1. ow, Level 1 $13 (d)
2. Lo . Level 3 $1

< f)

b. Drywell P ssure - liigh _13
c. Main Steam L'ne
1. Radiation - Higb(b) <

< g, (d) 113 l 2.

Pressure - Lo .

$13

3. Flow - High <0.

$13g(d)

~

II l

4 Flow ~ lii gh <0. d) 313 (f) l

d. Main Steam Line Tunnel Temp ature - igh $13
e. Condenser Vacuum - Low <13
f. Turbine Building Area Temperatu - High NA
g. Main Stack Radiation - Higb(b \ -<1.0(d)
h. Reactor Building Exhaust R diation - Hlgh(b) NA l
2. SECONDARY CONTAINMENT ISOLATJ N 1
a. Reactor Building Exh st Radiation - High l $13
b. Drywell Pressure High <!3 i
c. Reactor Vessel ater Level - Low, Level 2 113 l
3. REACTOR WATER CL UP SYSTEH ISOLATION
a. 6 Flow - ligh (45 ICI l
b. Area emperature - High 3
c. Ar.a Ventilation a Temperature - High $13 l
d. SLCS Initiation NA y . Reactor Vessel Water Level - Low, Level 2 113 j s

l i

f. A Flow - High - Time Delay Relay NA l BRUNSWICK - UNtt 2 3/4 3-23 Amendment No. 179

, g h@ h

<@ L 6 % ' TABL_E 3.3.2- 41 Continued) ,

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

~

4 TRIPFhCTION RESPONSE TIME (Secon s)(8 8)

4. COR STANDBY COOLING SYSTEMS ISOLATION
a. ligh Pressure Coolant Injection System isolation

' C)

l. HPCI Steam Line Flow - High 11 l
2. PCI Steam Line Flow - High Time Delay Relay A l
3. HP I Steam Supply Pressure - Low ,

113 4 HPCI Steam Line Tunnel Temperature - High $13

$. Bus Po er Monitor NA

6. HPCI Tur ine Exhaust Diaphragm . Pressure - igh NA
7. HPCI Steam ine Ambient Tempe ra ture - High NA
8. HPCI Steam Li e Area o Temperature - ligh NA l
9. IIPCI Equipment rea Temperature - nigh NA l
10. Drywell Pressure High / NA l
b. Reactor Core Isolation oling S tem Isolation
1. RCIC Steam Line Flow - ligd 113(c) l

/

2. RCIC Steam Line Flow - th h Time Delay Relay NA l

/

3. RCIC Steam Supply Pressure Low NA 4 RCIC Steam Line Tun /nel Tempera ure - High NA 'l

/

5. Bus Power Monit r NA ,
6. RCIC Turbine Exhaust Diaphram Press e - High NA
7. RCICSteam/LineAmbient Temperature - igh NA
8. RCIC St m Line Area o Temperature - liig 'HA l
9. RCIC uipment Room Ambient Temperature - H h NA l
10. RCI Equipment Room o Temperature - High NA l-
11. IC Steam Line Tunnel Temperature - High NA Time Delay Relay 12 Drywell Pressure - High A i

i BRUNSWICK - UNIT 2 3/4 3-24 Amendment No. 179  !

l l

1

f . .

l

'TARLE 3.3.2-3-(Continued)

ISOLATION SYSTEM INSTRUMEJGATION RESPONSE TIME TRIP FUNCTION RESPONSE TIMC (Seconds)(a)(e

5. SiluTDOWN COOLING S} TIM ObOU l
a. Reacto - essel Water Level - Low, L'd 1 NA
b. eact or Steam Dome Pressure - liigh NA i

l JGLETE- lEEloco p IdfSAM J

i d

d BRUNSWICK - UNIT 2 3/4 3-25 Amendment No. 179

-,v. - -- -,

. TABLE 3.3.2-3 (Cont.inued) -

ISOLATION SYSTEM -INSTRUMENTATION RESPONSE TIME NOTES

/

)

l l

measured.and- j (a) The isolation syste instrumentationresponsetimeshal[l, recorded as a part of e ISOLATION SYSTEM RESPONSE TJM isolation i system instrumentation r (ponse time specified inel,udes any delay for t dieselgeneratorstartinghsumedintheacciden/ analysis.

(b) Radiat ion monitors are exempt s'm o

l responsevtime testing. Response time shall be measured from detector put e 'y/the input of the first l electronic component in the channe (c) Includes time delay added by they ime d Qay relay.

/ N (d) Isolation actuation instru ntation responsh ime for MSIVs-only. No diesel generator delays ssumed.

(e) Isolation system i trumentation response time spec t '

  • ed f or t he Tri p Function actuati each valve group / damper shall be ad u{ to the isolation tim- tor v'alves in each valve group shown in tam 3.6.3-1 and secondary ntainment isolationdampersshowninTable3.6.(5.-lto .

obtain I LATION SYSTEM RESPONSE TIME for each valve /dauper.

(f) Is ation system instrumentation response time f or associated valve xcept MSIVs.

s D 6LETGT - 0LbCMED T3 0f5NE,  !

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BRUNSWICK - UNIT 2 3/4 3-26 Amendment No. 179

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INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2. w.d ith "" RCChoY CGRE CGGLII;0 OYSTCH RCOPC::CC '""r a; no c. ..

";H -5.a.a-a.

APPLICABILITY: As shown in Table 3.3 3-1.

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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 and place the inoperabic channel in the tripped condition until 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 3.3.3-1.
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 Tabic 4.3.3-1.

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

4.3.3.3 The ECCS RESPONSE TIME of each ECCS function sha... . Tablo 2.3.J- 1 shall be demonstrated to be within the limit at least once per 18 months.

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

l BRUNSWICK - UNIT 2 3/4 3-33 Amendment No. 160 l

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TABLE 3.3.3-3 ,

EMERCENCY CORE COOLING SYSTEM RESJ ES

/

/

/

ECCS RESPONSE TIME (Seconds)

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1. CORE SPRAY SYSTE j/ $ 27
2. LPCI MODE of RilRJYS < 40

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3.

HN'N IIICil PRESSpR[ COOLANT INJECTION ~ SYSTEM $ 30

4. AUTO 'IC DEPRESSURIZATIOl# SYSTEM ^g NA
5. OSS OF POWER NA LW ATEO P Nf$$f l

BRUNSWICK - UNIT 2 3/4 3-42 Amendment No. 160 l

A ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 & 50 324 OPERATING LICENSES DPR-71 & DPR 62 REQUEST FOR LICENSE AMENDMENT RESPONSE TIME TABLE RELOCATION LIST OF REGULATOR.Y COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light Company in this document. Any other actions discussed in the submittal represent intendeo or planned actions by Carolina Power & Light Company. .They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.

Committed Commitment date or outage

1. Relocate Response Timo Tables that are being removed from Amend.13  !

Technical Specifications by TSC 94TSB02 into the Updated FSAR in Amendment 13 to the UFSAR.

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