ML20024F716

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Revised Proposed Tech Specs Re NUREG-0737 Items Identified in Generic Ltr 83-02
ML20024F716
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/06/1983
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20024F218 List:
References
RTR-NUREG-0737, RTR-NUREG-737 GL-83-02, GL-83-2, NUDOCS 8309090605
Download: ML20024F716 (10)
v • d • e


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TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

l.

PRIMARY CONTAINMENT ISOLATION _

a. Reactor Vessel Water Level -
1. Low, Level i

<13 (B21-LT-N017A-1.B-l.C-1,D-1)

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

2. Low, Level 2 <l .0 *

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

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

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

b. Drywell Pressure - High ,'

~<13 (C71-PT-N002A,B,C.D)

(C71-PTri-N002 A-1,B-1, C-1, D-1 )

c. Main Steam Line <l .0 *
1. Radiation - High(b) -

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

2. Pressure - Low -

<!3

( B21-PT-N015 A,B .C.D)

( B21-PTM-N015 A-1. B-1. C-1, D-1 )

3. Flow - High <0.5* l (B21-PDT-NQ06A.B,C.D-B21-PDT-NOO7A,B,C,D:

B21-PDT-N008 A,B .C,D B21-PDT-N009A,B C.D)

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

B21-PDTM-N007A-1,B-1,C-1,D B21-PDTM-N008 A-1,B-1, C-1, D-1 :

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

d. Main Steam Line Tunnel Temperature - High <l3

( B21-TS-N010 A,B ,C,D:

B21-TS-N011A,B,C,D B21-TS-N012A,B,C,D:

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

e. Condenser Vacuum - Low 11 3 (B21-PT-N056A,B,C D)

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

BRUNSWTCr - UNTT I 3/4 3-22 Amendment No 8309090605 830906 PDR ADOCK 05000324 (P . - . . . 18@ #

. 1

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~

. TABLE 3.3.2-3 (Continued)

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

PRIMARY CONTAINMENT ISOLATION (Continued)

~f. Turbine Building Area Temperature - High NA (B21-T Sr-3225A, B ,C ,D; B21-TS-3226A ,B ,C ,D; B21-T &-32 2 7A,B ,C ,D; B21-T S-3 228A ,B ,C ,D ;

B21-TS-322 9A,B ,C ,D; B21-T S- 3230A , B ,C ,D ;

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

2. SECONDARY CONTAINMENT ISOLATION
a. Reactor Building Exhaust Radiation .High(b) 113 (D12-R!t-N01 OA, B)
b. Drywell Pressure - High 113 (C71-PT-N002A,B ,C ,D)

(071-P TM-N002A- 1, B- 1,0- 1, D- 1)

c. Reactor' Vessel Water Invel - Iow, Invel 2 11.0*

(B21-LT-N024A-1,B-1 and l B21-LT-NO2 5 A- 1, B-1 )

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

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

5

3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - High -

<13 (G31-dF S-N603-1A ,18)

b. Area Temperature - High 113 (G31-T S-N600A,B , C ,D,E ,?)
c. Area Ventilation Temperature AT - High 113 (G 31-T S-N602A ,B ,C,D ,E ,F)
d. SLCS Initiation NA l (C41A-S1)

{

i e. Reactor Vessel Watet Level - Low, Level 2 -

<1.0*

(B21-LT-NO24 A-1,B-1 and B21-LT-N025 A-1,9-1)

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

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

,1 TABLE 3.3.2-3 (Continued)

ISOLATION SYSTE!! INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

4. _ CORE STANDBY C00LINC SYSTEMS ISOLATION
a. High Pressure Coolant Injection System Isolation
1. HPCI Steam Line Flow - High 13(a) < t < 17(a)

(E41-PDT-N004; E41-PDT-N005 )

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

2.- HPCI Steam Supply Pressure - Low <13 (E41-PSL-N001 A, B ,C , D)

3. HPCI Steam Line Tunnel Temperature - High j:13 (E41-T S-3314; E41-T S-3315; E41-T S-3316 ;

E41-TS-3317; E41-TS-3318 ;

E41-T S-3354;

. E41-T S-3488 ;

E41-TS-3489)

4. Bus Power Monitor .

NA (E41-K55 and E41-K56)

5. HPCI Turbkne Exhaust Diaphragm Pressure - Righ NA (E41-PSil-N012A,B ,C , D)
6. HPCI Steam Line Ambient Temperature - High NA s551srS-N603C ,D)
7. HPCI 5 team Line Area NA (E51-drS-N604C , D)
8. Baergency Area Cooler Temperature - Iligh NA (E41-T S-60 2A,' B)
b. Reactor Core Isolation Cooling System Isolation
1. RCIC Steam Line Flow - High 13(a) < t < 17(a)

"~ ~~

(E51-PDT-N017; E51-PDT-N018 ) -

(E51-PDTS-N017-2;

, E51-PDT S-N018-2 )

2. RCIC Steam Supply Pressure - Low NA (E51-P S-N019A,B ,C , D)

BRUNSWICK - UNIT 1 3/4 3-24 Anendment No. _ _,

s' s

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# '

',

  • s.'
3. RCIC -3:eam Line Tunnel Temp - liigh NA l (651-TS-3319 ;

E51-TS-3320; s ., .E51-T S- 3321; E51-TS-3322 ;

E51-Ts-3323; E51-TS-3355 ;

E51-TS-3487)

4. Bus Power Monitor NA (E51-K42 and E51-K43)
5. RCIC Turbine Exhaust Diaphragm . NA

- Pressure - High .

. '(E51-P S-N012A , B ,C ,D)

RCIC Steam Line Ambient Temperature - High

'6 . NA (E51-T S-N603A, B) t

7. RCIC Steam Line Area A Temp - High NA

- '/ ~ (E51-dTS-N604A,5) *

~

s

0. Bnergency Area Cooler Temperature - High NA (E51-T S-N602A, B) 1 h

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

5. SHUTDOWN C00LINC SYSTEM ISOLATION
a. Reactor Vessel Water Level - Low, Level 1 NA (B21-LT-N017 A- 1, B- 1, C- 1. D- 1 )

(B21-LTM-N017A- 1, &- 1,0- 1,D- 1)

b. Reactor Steam Dome Pressure - High NA (B3 2-P S-N018A , B)

J f

1 9

BRUNSITICK - UNIT l'. 3/4 3-24a Amendment No. ,

~k TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUffENTATION RESPONSE TI!4E s s NOTES

  • Isolatio actuation instrinentntion response time only.
  1. Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and Table 3.6.5-1 for valves in each_ valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

(a) The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME. Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.

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

1 y

k a

J 5

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

4

- TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

. 1. PRI!!ARY CONTAINifENT ISOLATION

'a. Reactor Vessel Water Level -

1. Tew, Level 1 -<13 (B21-LT-N017 A- 1, B- 1, 0- 1,D- 1 )

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

2. Tow, Invel 2 11.0*

(B21-LT-N024A-1,B-1 and l B21-LT-N02 5 A- 1, D- 1)

(B21-LTM-N024A-1,B-1 and B21-LTti-NO2 5 A- 1, B- 1)

b. Drywell Pressure - High 113 (C72-P S-N002A,B ,C ,D) ,~
c. Main Steam Line -<1.0*
1. Radiation - High(b) '

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

2. Pressure - Low ~"<13 (B21-PT-N015A,B ,C ,D)

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

3. Flow - High 10.5* l (B21-PDT-N006A ,B ,C ,D; B21-PDT-N007A,B ,C ,D; B21-PDF-N008 A ,B ,C ,D; B21-PDT-N009A,B ,C ,D)

(B21-PDTM-N 006A- 1, B- 1, C- 1,D- 1 ;

B21-PDTM-N007A- 1, B- 1, C- 1,D-1 ;

B21-PDTM-N008 A- 1, B- 1,0- 1,D- 1 ;

B21-PDTif-N009 A- 1, B- 1, C- 1, D- 1 )

4. Flow - High 10.5*

(B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N0080-2 ;

B21-PDTS-N009D-2)

d. Main Steam Line Tunnel Temperature - High <13 (B21-T S-N010A,B ,C ,D; B21-T S-N011 A ,B ,C ,D; B21-T S-N012A,B ,C ,D ;

o B21-T S-N013A ,B ,C ,D)

e. Condenser Vacuum - Low -<13 (B21-P S-N05 6A,B ,C ,D)

BRUNSWICK-UNIT 2 3/4 3-22 Amen.iment No.

1 l

TABLE 3.3.2-3 (Continued)

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

.f. 'liarbine Building Area Temperature - High NA (B21-T S-3225A ,B ,C ,D; B21-T S-322 6A,B ,C ,D; B21-T S-3227A ,B ,C ,D; B21-T S-322 8A,B ,C ,D; B21-TS-3229 A ,B ,C ,D;

~

B21-T S-323 0A,B ,C ,D;

, B21-TS-3231 A,B ,C ,D ;

B21-T S-323 2A,B ,C ,D)

2. SECONDdRY CONTAINMENT ISOLATION
a. Reactor Building Exhaust Radiation - High(b) <t 3 l (D12-RM-N010A,B)
b. Drywell Pressure - High 113 (C72-P S-N00 2A,B ,C ,D)
c. Reactor Vessel Water Level - Low, Level 2 <1.0* l (B21-LT-N024A-1,&-1 and B21-LT-N025A- 1, B- 1)

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

3. REACTOR WATER CLEAFUP SYSTEM ISOLATION Y- ~
a. A Flow - High -

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

b. Area Temperature - High (1.3 (G31 -T S-N600A,B ,C ,D,E ,F)
c. Area Ventilation Temperature AT - High 113 (G 31-T S-N602A ,B ,C ,D ,E ,F)
d. SLCS Initiation NA (C41 A-S1)
e. Reactor Vessel Water Level - Low, Level 2 ~

<1.0* l (B21-LT-N024 A-1,8-1 and B21-LT-N025 A-1, B-1)

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

~

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

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

1 o "

1 <

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TItiE TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

4. . CORE STANDBY COOLING SYSTEtiS ISOLATION
a. High Pressure Coelant Injection System Isolation
1. HPCI Steam Line Flow - High (E41-dPIS-N004 and 13(a)<t<17(a)l E41-dPIS-N005)
2. HPCI Steam Supply Pressure - Low 113 (E41-PSL-N001 A,B ,C ,D) 3 .- HPCI Steam Line Tunnel Temperature - High <13 (E41-TS-3314 ;

E41-TS-3315; E41-TS-3316 ; ' .~

E41-TS-3317; E41-T S-3318 ;

E41-TS-3354; E41-TS-3488 ;

E41-TS-3489)

4. Bus Power Monitor NA (E41-K55 and E41-K56)
5. HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N012A,B ,C , D)
6. HPCI Stedi Line Ambient Temperature - High NA (E51-Td-N603C ,D) .
7. HPCI Stea's Line Area NA (E51-drS-N604C ,D)
8. Emergency Area Cooler Temperature - High NA (E41-TS-602A , B)
b. Reactor Core Isolation Cooling System Isolation
1. RCIC Steam Line Flow - High 13(a)<g<g7(a)l (E51-dPIS-N017 and E51-dPIS-N018 )
2. RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D)
3. RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319 ;

E51-TS-3320; E51-T S-3321 ;

E51-TS-3322; E51-T S-3323 ;

E51-T S-3355; E51-TS-3487 )

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

i .

8 TABLE 3.3.2-3 (Continued)

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

. 4. Bus Power 11onitor NA (E51-K42 and E51-K43)

5. RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-P S-N012A,B ,C ,D)
6. RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A, B)
7. RCIC Steam Line Area A Temp - High NA (E51-dT S-N604A ,B)
8. Emergency Area Cooler Temperature - High NA (E51 -T S-N602A, B) ,
9. RCIC Equipment Room A Temp - High NA (E51-dTS-N601 A ,B)
5. SHUTDOWN C00LINC SYSTEM ISOLATION
a. Reactor Vessel Water Level - Low, Level 1 NA

( B21-LT-N017 A- 1, B- 1,0- 1, D- 1 )

(B21-LTM-N017A- 1, B- 1,0- 1,D- 1)

b. Reactor Steam Dome Pressure - High NA (B32-PS-N018A ,B)

.k?

I t

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

I  ;

' :~

F r

J

. TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME NOTES

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

(a) The isolation system instrumentation response time shall be ocasured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME. Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.

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

=

' r-O BRUNSWICK - UNIT 2 3/4 3-24B Amendment No. j

. i

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