ML20086U114
| ML20086U114 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/28/1984 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20086U103 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.15, TASK-TM 83TSB18, GL-83-02, GL-83-2, NLS-84-065, NLS-84-65, NUDOCS 8403070162 | |
| Download: ML20086U114 (31) | |
Text
..
ENCLOSURE 1 SERIAL:
NLS-84-065 BRUNSWICK STEAM ELECTRIC PLANT UNIT I PROPOSED TECHNICAL SPECIFICATION PAGES (CP&L' SERIAL NO. 83TSB18) l
.g,
p O
4
- P-PDR 7
c; 7
c (BSEP-l-18)
.E' TABLC 3.3.2-1 (Continued)
~
di
~
ISOLATION ACTUATION INSTRIMENTSTION
~R VAL 7E GROUPS-MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL ITRIP FUNCTION A:iD INSTRUMENT NL"BER-
' SIGNAL (a)
'PER TRIP SYSTEM (b)(c) CONDITION
' ACTION H
H l4.
CORE STANDBV COOLING. SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System' Isolation 1.
HPCI-Steam Line' Flow - High 4
1 1,2,3 25 (E41-PDT-N004; E41-PDT-N005)-
(E41-PDTS-N004-2; I
E41-PDTS-N005-2) 2.
IIPCI Steam Line High Flow t'.
Time Delay Relay NA 1
1,2,3 25
. (E41-TDR-K33; Y
E41-TDR-K43) 3.
IIPCI Steam Supply Pressure - Low 4-2 1,2,3 25 l
l (E41-PSL-N001A,B,C,D) l 4.
IIPCI Steam Line Tunnel Temperature - liigh 4
2 1,2,3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) n.
S 5.
Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 f,
(E41-K55 and E41-K56)
Y 6.
IIPCI Turbine Exhaust Diaphragm Pressure - High 4
2 1,2,3 25 (E41-PSil-N012 A, B, C, D)
.~
J kr
/.T@\\
t/
(BSEP-1-18)
+'
E.
p.
TABLE 3.3.2-1 (Continued)'
E!
g IbaLATION ACTUATION INSTRU4ENTATION
. r:
8
' VALVE CROUPS MINIMUM. NUMBER APPLICABLE g
OPERATED BY OPERABLE CIIANNELS OPERATIONAL q
TRIP FUNCTION AND INSTRQ1ENT NUMBER SIGNAL (s) '
PER TRIP SYSTEM (b)(c) CONDITION ACTION 7.
IIPCI Steam Line Ambient Temperature - liigh 4
1 1,2,3 25
( E51 -TS-N60 3C, D) 8.
IllC I St eam Li ne Ar ea A Te mp. -
Ili gh 4
1 1,2,3 25 (E51-dTS-N604C,D) e 1
9.
Emergency Area Cooler Temperature - liigh 4
1 1, 2,-3
-25
( E41 -TS-N602A, B) b.
Reactor Core Isolation Cooling System Isolation
[
1.
RCIC St eam Li ne Flow - Iligh 5
1 1,2,3 25
( E51 -PDT-N017 ;
E51-PDT-N018)
(E51-PDTS-N0 7-2; E51 -P DTS-N 018-2) 2.
RCJC Steam Line liigh Flow Ti me De lay Re lay NA 1
1,2,3 25
( E51 -TDR-K32 ;
E51-T DR-K 12) 3.
RCIC Steam Supply Pressure - Low 5
2 1,2,3 25 l,
g
( E51 -PS-N019A, B, C, D)
"g 4.
RCIC St eam Li ne Tunnel Temperature g
- liigh 3
2 1, 2, 3 25 g
(E51-TS-3319; E51-T S-3320 ;
,o E51-TS-3321; E51 -T S-3322 ;
E51-TS-3323; E51-TS-3 3 55; E51-TS-3487)
= - -
k k
(BSEP-1-18)-
-n
.tw
.E' TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION k
VALVE GROUPS' MINIMUM NUMBER APPLICABLE OPERATED BY.
' OPERABLE CHANNELS OPERATICNAL'
! TRIP FUNCTION AND INSTRUMENT NUMBER' SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION l
H 5.
Bus Power Monitor-NA (h) 1/ bus 1, 2, 3 26 (E51-K42 and-E51-K43) 6.. RCIC Turbine Exhaust Diaphragm Pressure - !!igh 5
2 1, 2, 3 25 (B51-PS-N012A,B,C,D) 1 7.
RCIC Steam Line Ambient Temp -
!!!gh 5
1
- 1. 2, 3 25 (E51-TS-N603A,B) 8.-
RCIC Steam Line Area A Temp - High 5
1-1, 2, 3
'25 l
t (E51-dTS-N604A,B)
I c.
l '
Temp - lilgh 5
- I 1, 2, 3 25 u
9.
RCIC. Equipment Room Ambient l
(E51-TS-N602A,B) 10.
RCIC Equipment Room 4 Temp - liigh 5
1 1,2,3 25 (E51-dTS-N601/.,3) 5.
SHUIDOWN COOLING SYSTEM ISOLATION a.
l Low, Level 1 2, 6, 7,-8 2
1, 2, 3 27 (B21-LT-N017A-1,B-1,C-1,D-1).
(B21-LTM-N017A-1,B-1,C-1,D-1) g b.
Reactor Steam Dome Pressure-7, 8 1
1, 2, 3 27 5
High E.
(B32-PS-N018A,B)
?
E
.I l
~
- 4..
_(BSEP-1-18)
- u E
TABLE 3.3.2-2 (Continued)
E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS N*
ALLOWABLE
- TRIP FUNCTION AND INSTRUMENT. NUMBER TRIP SETPOINT-VALUE
.- g U
3.
REACTOR' WATER CLEA:lUP SYSTEM ISOLATION'
~
w-
.a.,
A Flow
.lligh 1 53 gal / min 1 53 gal / min
- (G31 -d FS-N603-1 A, IB) b.
Area Temperature - High
< 150*F
< 150*F
.I (G31-TS-N600A,B,C,D,E,F) c.-
Area Ventilation Temperature A. Temp '- High
< 50*F
< 50*F l-(G31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation NA NA I
(C41A-SI) l
'h
-e.
' Low, Level 2
> + 112 inches *
> + 112 inches
- i (B21-LT!!-N024A-1, B-1 and 5
B21-LTM-N025A-1,B-1) 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - High
< 300% of rated flow
< 300% of rated flow (E41-PDTS-N004-2; E41-PDTS-N005-2) 1 2.
IIPCI Steam Line liigh Flow 1
Time Delay Relay 3 < t < 7 seconds 3 < t < 12 seconds l
f (E41-TDR-K33; g
E41-TDR-K43) l 3.
HPCI Steam Supply Pressure - Low
> 100 psig
> 100 psig l
(E4'l-PSL-N001A,B,C,D) l
- 7 (BSEP-1-18)-
'I
[
TABLE 3.3.2-2 (Continued) g g
ISOLATION ACTUATION INSTRIMENTATION SETPOINTS M
7:
ALLOWABLE I
TRIP FUNCTION AND INSTRINENT NUMBER TRIP SETPOINT VALUE Ey 4.
111C1 Steam Line Tunnel Temperature - High
. < 200* F :
. < 200* F l
(E41-TS-3314; g
- E41-T S-3 315 ;
E41-TS-3316 ;
E41-T S-3317 ;
[
E41 -TS-3318 ;
E41-T S-3354 ;
E41-TS-3438; l
E41-T S-3489) 5.
Bus Power Monitor NA NA' l
(E41-K55 and E41-K56) l g-6.
IIICI Turbine Exhaust Diaphragm l
Pressure - liigh
< 10 psig
<*10 psig I
y
( E41-PSil-N012A,B,C, D) 5 7.
111C1 Steam Line Ambient Temp - High
< 200* F
< 200*F l
(E51-TS-N603C,D) 8.
IIICI Steam Line Area A Temp - High
< 5 0* F
< 5 0* F l
l (E51 tits-N604C,D) 9.
Emergency Area Cooler Temp - liigh
< 175'F
< 175'F l
l
( E41 -TS-N602A, B) b.
Reactor Core Isolation Cooling System Isolation l
1.
RCIC Steam Line Flow - liigh
< 300% of rated flow
< 300% of rated flow 2
(E51-PDTS-N017-2; E
E51 -P DTS-N 018-2) ay 2.
RCIC Steam Line High Flow Time De lay Relay.
3<t < 7 seconds 3 < t < 12 seconds y
(E51-TDR-K32; E51-T DR-K 12) 3.
RCIC Steam Supply Pressure - Iow
)_50 psig J,50 psig l
( E51-PS-NO I 9A, B, C, D)
(BSEP-1-18)L Ef TABLE 3.3.2-2 (Continued)
E!g' ISOLATION ACTUATION INSTRG4ENTATION SETPOINTS l
o*
' ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TP.IP SETPOINT VALUE g;
[j 4..
RCIC Steam Line Tunnel Temp - High
< 175'F
< 175*F r.
(E51-TS-3319; E51ers-3320; E51-TS-3321 ;
E 51-T S-3322 ;
E51-TS-3323; E51-IS-3355;.
E51-TS-3487)-
l 5.
Bus Power Fbnitor NA NA (E51-X42 and E51-K43) c, 6.
RCIC Turbine Exhaust Diaphragm 2
Pressure - liigh j[ 10 psig
- < 10 psig
( E51 -PS-N012A, B, C D)
I!
- 7.
RCIC Steam Line Ambient Temp
- lligh
< 2 00* F
< 2 00* F l
( E51 -TS-N60 3A, B)
)
8.
RCIC Steam Line Area A Temp - High
< 5 0* F
< 50*F (E51 -dTS-N6 04A, B) l 9.
RCIC Equipnent Room hubient Temp - Iligh
< 175'F
< 175'F (E51-TS-N602A,B) 10.
RCIC Equipnent Room A Temp - Itigh
< 5 0* F
< 50* F (E51 -dTS-N60 LA, B) 5.
S!!UTDOWN COOLING SYSTEM ISOLATION a.
S' Low, Le vel 1
( B21 -LTM-N017A-1, B-1, C-1, D-1 )
~~> + 162.5 inches *
~~> + 162. 5 inches
- j n
y b.
Esactor St eam Dome Pressure - liigh
- ( 140 psig
- [ 140 psig
)
( B32-PS-NOl 8A, B) l
- Vessel water levels refer to REFERENCE LEVEL ZERO.
{:
(BSEP-1-18)
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRIMENTATION RESPONSE TIME
' TRIP FUNCTION 'AND INSTRINENT NINBER RESPONSE TIME (Seconds)#
- 1. ' PRIMARY CONTAINMENT ISOLA': ION a.
- 1. _ fow, Im vel 1
<13
' ( B21 -LT-N017A-1, B-1, C-1, D-1)
(B21-L TM-N 017A-1, B-1, C-1, D-1) 2.
Low, Ievel 2
<l.0*
(B21-L T-N O2 '.'. - 1, B-1 and B21-LT-N025A-1,3-1)
(B21-LTM-N024A-1, B-1 and
~
B21-LTM-N025A-1 B-1)
=b.
Drywell Pressure - liigh
<13 (C71-PT-N002A, B, C, D)
(C71-P TM-N 002A-1, B-1, C-1, D-1) c.
<1.02 1.
Radiation - High(b)
(D12-RM-K603A, B,C, D) 2.
Pressure - low
<13
( B21-PT-N01 SA,B, C,D)
. (B21-P' DEN 015A-1, B-l, C-1, D-l',
3.
Flow - High
<0.5*
(B21-P DT-N006A,B, C,D ;
-~
B21-PDT-N007A, B, C,D ;
B21-P DT-N 008A, B,C,D ;
B21-PDT-N009A,B, C,D)
~ (B21-P DTM-N006A-1, B-1, C-1,D-1 ;
B21-PDTM-N007A-1, B-1, C-1, D-1 ;
B21-P DTM-N 008A-1, B-1, C-1, D-1 ;
B21-PDTM-N009A-1, B-1, C-1, D-1 )
d.
Ma'in St eam Line Tunnel Temperature - liigh
<13 (B21-TS-N010A,B.C D; B21-T S-N011A, B,C,D ;
B21-TS-N012A, B,C,D ;
B21-T S-N013A, B, C,D) c.
Condenser Vacuin - Low
<13
( B21-PT-N05 6A, B, C, D)
(B 21-P TM-N 05 6A-1, B-1, C-1, D-1)
' BRUNSWICK - UNIT 1 3/4 3-22 Amendc:ent No.
r (BSEP-1-18)
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRLMENTATION RESPONSE TLME TRIP FUNCTION AND INSTRlNENT NINBER RESPONSE TIME (Seconds)#
~
PRIMARY CONTAINMENT ISOLATION (Continued) f.,
lhrbine Building Area' Temperature - High NA (B21-TS-322 5A,B, C,D ;
B21-T S-3 22a,B,C,D ;
B21-TS-322 7A', B, C,D ;
B21-T S-3 228A, B,C.D ;
B21-TS-3229A,B, C,D ;
B21-T S-3230A,B, C,D ;
B21-TS-3231A,B,C,D; B21-T S-3232A,B,C,D)
- 2.. SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b)-
_,13 l
a.
(D12-RM-N010A,B) b.
Drywell Pressure - High
-<13 (C71-PT-N002A,B,C, D)
(C71-P TM-N 002A-1, B-1, C-1, D-1)
- c. '
Reactor Vessel Water level - Low, Ievel 2
-<l.0*
(B214.T-N024-1, B-1 and B21-LT-N025A-1,B-1)
(B21-LTM-NO24-1, B-1 and B21-LTM-N025A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION
- a..
A Fl ow - Hi gh
-(13 (G 31-dF S-N603-1A,1B )
b.
. Area Temperature - High
-<l 3 (C31-TS-N600A,B C.D,E,F) c.
Area Ventilation Temperature E - Hi gh
-<13 (G 31-T S-N6 02A, B, C,D, E, F) d.-
SLCS Initiation NA
_(C41A-SI)~
e.
Reactor Vessel Water Level - Low, level 2
-<l.0*
(B21-LT-N024 A-1, B-1 and B21-LT-N02 5 A-1, B-1)
(B?l-LTM-NO24 A-1,B-1 and B21-L TM-N 02 5 A-1, B-1)
BRUNSWICK - UNIT 1 3/4 3-23 Anendment No.
-. -. ~
j; (BSEP-1-18) t TABLE 3.3.2-3 (Co ntinued)
ISOLATION SYSTEM INSTRLMENTATION RESPONSE TIME
. TRIP FUNCTION AND INSTRL'4ENT NtNBER RESPONSE TIME (Seconds) #
4.
CORE STANDBY C00LINC SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow - Hf gh
-<13(a)##
(E41-PDT-N004; E41-PDT-N005)
(E41-P DTS-N004-2 ;
E41-PDTS-N005-2)
-2.
HPCI Steam Line High Flow Time Delay Relay NA (E41-TDR-K33; E41-T DR-K43) 3.
HPCI St eam Supply Pressure - Iow
<13 l
(E41-PS L-N001A,B, C, D) 4.
HPCI Steam Line Tunnel Temperature - High
--<13 (E41-TS-3314 ;
E41-TS-3315; E41-TS-3316; E41-T S-3317; E41-TS-3318;-
E41-T S-3354 ;
E41-TS-3488; E41-T S-3489) 5.
Bus Power Monitor NA l
(E41-K55 and E41-K56) 6.
HPCI Turbine Exhaust Diaphragm Pressure - High NA l
(E41-PSH-N012A, B, C, D) l 7
HPCI St eam Line Ambient Temperature - High NA (E51-TS-N603C, D) 8.-
HPCI St eam Line Area NA (E51-dTS-N604C,D) 9.
Emergency Area Cooler Temperature - High NA (E41-TS-602A, B) b.
Reactor Co re Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High
<13(")###
(E51-PDT-N017; _
.E51-PDT-N018)
- (E51-P DTS-NO17-2 ;
E51-PDTS-N018-2) 4 BRUNSWICK. UNIT 1 3/4 3-24 Amendment No.
~.
(BSEP-1-18) e:
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER-RESPONSE TIME (Seconds)#
2.
RCIC Steam Line High Flow Time Delay Relay NA (E51-TDR-K32; E51-TDR-K12) l
- 3. 'RCIC Steam Supply Pressure - Low NA l
(E51-PS-N019A,B,C,D) l 4.
RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-332!;
E51-TS-3323; E51-TS-3355; E51-TS-3487)
~5.. Bus Power Monitor NA (E51-K42 and E51-K43) l 6.
RCIC Turbine Exhaust Diaphragm NA Pressure - High (E51-PS-N012A,B,C,D) l 7.
RCIC Steam Line Ambient Temperature - High NA
'(E51-TS-N603A,B) l 8.
RCIC Steam Line Area a Temp - High NA (E51-dTS-N604A,B) 9.
Emergency Area Cooler Temperature - High NA
'(E51-TS-N602A,B) 10.
RCIC Equipment Room A Temp - High-
'lA (E51-dTS-ho01A B) 5.
SHUTD0bM COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Level -. Low, Level 1 NA (B21-LT-N017A-1,B-1,C-1,D-1)
-(B21-LTM-N017A-1,B-1,C-1,D-1) b.
Reactor Steam Dome Pressure - Hfgh NA
'(B32-PS-N018A,B)
{
i
' BRUNSWICK - UNIT 1 3/4 3-24a Amendment No.
_m
_________________________________m
(BSEP-1-18) c
- N TABLE 3.3.2-3 (Continued) g-ISOLATION SYSTL'M INSTRUMENTATION RESPONSE TIME NOTES (a)
The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.
(b)
Radiation monitors are exempt from response time testing. Response time shall be taeasured from detector output or the input of the first electronic component in the c.hannel.
- - Isolation actuation instrumentation response time only.
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.
Includes time delay added by the time delay relay (E41-TDR-K33 and E41-TDR-K43).
'iff Includes time delay added by the time delay relay (E51-TDR-K32 and E51-TDR-K12).
e
's BRUNSWICK - UNIT I 3/4 3-24b Amendment No.
_____________________________J
t-C l
o-
.(BSEP-1-18)
,E g
TABLE 4.3.2-1 (Continued) l
. ISOLATION ' ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8
CilAN'4EL OPERATIONAL CHANNEL FUNCTIONAL
.CRANNEL CONDITIONS IN WHICH' Q
CliECK TEST CALIBRATION.
SURVEILLANCE REQUIRED y TRIP FUNCTION AND INSTRUMEN1" NUMBER
' <4. CORE STANDBY COOLING SYSTEMS ISOLATION L
a.
Iligh Pressure Coolant Injection System Isolation l
i 1.
filPCI Steam Line Flow - liigh 4
l; (E41-PDT-N004; NA(a)
NA R(b)
I, 2, 3 f
E41-PDT-N005)
(E41-PDTS-N004-2; D
M M
1, 2, 3 E41-PDTS-N005-2) l l
$(
2.
IIPCI Steam Line lil h Flow t
Time Delay Relay
.NA R
R 1, 2, 3 -
8' y
(E41-TDR-K33; gl E41-TDR-K43) 3.
IIPCI Steam Supply Pressure -
1.ow NA M
R 1, 2, 3 l
(E41-PSL-N001A,B,C,D) 4.
IIPCI Steam Line Tunnel Temperature - Iligh NA M
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; g.
E41-TS-3354; m
E.
E41-TS-3488; E41-TS-3489) n" 5.
Bus Power Monitor NA R
NA 1, 2, 3 f
(E41-K55 and E41-K56) 6.
HPCI Turbine Exhaust Diaphragm Pressure - High NA M
Q 1, 2, 3 l
(E41-PSil-N012A,B,C,D)
c; j
(BSEP-1--18) v j
TABLE
",.3.2-1 (Continued)
. Ej v>.
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
CHANNEL
' OPERATIONAL CHANNEL:
FUNCTIONAL' h.TRIPFUNCTIONAND'INSTRUMENTNUMBER
- CHANNEL-CONDITIONS IN WHICH CHECK
~ TEST
' CALIBRATION-SURVEILLANCE REQUIRED >
H H,
7.
HPCI Steam'Line Ambient Temp - liigh
'NA-
.M R
1,'2, 3
(E51-TS-N603C,D)-
8.-
HPCI Steam Line Area A -Temp - liigh NA' M-R 1,2,3 (E51-dTS-N604C,D) 9.
Emergency _ Area Cooler l-Temp - liigh NA M
Q 1, 2, 3 y -
(E41-TS-N6024,B)
D b..
- Reactor Core Isolation Cooling System Isolation.
N 1.
RCIC Steam Line Flow - High l
(551-PDT-N017; NA(a)
NA R(b) 1, 2, 3 l
E51-PDT-N018)-
(E51-PDTS-N017-2; D
M M
1, 2, 3 (E51-PDTS-N018-2) 2.
RCIC Steam Line liigh Flow q
Time Delay Relay NA R
R 1, 2, 3 (E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply y
Pressure - Low NA M
Q 1, 2, 3 (E51-PS-N019A,B,C,D) 0'
,a,
v (BSEP-1-18)
.s E.Q.'
TABLE.4.3.2-1'(Contiinued)~
ISOLATION' ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL'
-OPERATIONAL CHANNEL.
. FUNCTIONAL
. CHANNEL CONDITIONS IN WHICH.
E TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g<
s 4.
.RCIC Steam Line Tunnel l
High. Temperature-NA M
R 1,.2, 3
(E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487)
R 5.
Bus Power Monitor' NA R
NA
- 1. 2, 3 (E51-K42 and'E51-K43) w l
4 6.
RCIC Turbine Exhaust
.y Diaphragm Pressure - High NA M
R 1, 7., J (E51-PS-N012A,B,C,D) 7.
RCIC Steam Line Ambient Temp - Iligh
-NA
'M R
1, 2, 3 (E51-TS-N603A,B) 8.
RCIC Steam Line Area A Temp - liigh NA M
R 1, 2, 3 (E51-dTS-N604A,B) 9.
RCIC Equipment. Room Ambient Temp - liigla NA M
Q 1, 2, 3 i
(E51-TS-N602A,B) 9 g
10.
RCIC Equipment Room A l
Temp - Iligh NA M
Q 1, 2, 3 rt g
(E51-dTS-N601A,B)
.o*
-s
~
o (BSEP-1-18) -
- w.
- Ei -
TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL-CONDITIONS IN WHICH
'h TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
-e 5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Low, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(a)
NA R(b) 1, 2, 3 (B21-LTM-N017A-1,B-1,C-1,D-1)
D M ~
M 1, 2, 3 b.
Reactor Steam Dome Pressure -
liigh NA S/U(c),M R
1, 2, 3 (332-PS-N018A,B) u, D
Y M
u-
- When handling irradiated fuel in the secondary containment.
- When reactor steam pressure > 500 psig.
(a) The transmitter channel check is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
(c) If not performed within the previous 31 days.
-9 g.
9n
.o l
l -7 j, I-ENCLOSURE 2 SERIAL: NLS-84-065 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 PROPOSED TECHNICAL SPECIFICATION PAGES (CP&L SERIAL NO. 83TSB18) 6 hiiiii
1
~
(BSEP-2-18) en Ej TABLE 3.3.2 ' (Continued)
ISOLATION ACTUATION INSTRUMENTATION R
VALVE GROUPS MINIMUM NUMBER APPLICABLE e
OPERATED BY OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION H
4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection Systent Isolation 1.
IIPCI Steam Line Flow - liigh 4
1 1,2,3 25 j
(E41-dPIS-N004 and E41-dPIS-N005)
I 2.
IIPCI Steam Line liigh Flow Time Delay Relay NA 1
1,2,3 25 (E41-TDR-K33; E41-TDR-K43) 3.
IIPCI Steam Supply Pressure - Low 4 2
1,2,3 25 l
(E41-PSI-N001A,B,C,D) w 4.
IIPCI Steam Line Tunnel l
,L Temperature - liigh 4
2 1,2,3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E4 i -TS-3317 ;
E41-TS-1318; E41-TS-333?;
E41-TS-3488; E41-TS-3489) 5.
Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 l
g (E41-K55 and E41-K56) 6.
IIPCI Turbine Exhaust l
Diaphragm Pressure - liigh 4
2 1, 2, 3 25 (E41 PSil-N012A,B,C,D) z 7.
IIPCI Steam Line Ambient l
P Temperature - liigh 4
1 1,2,3 25 (E51-TS-N603C,D)
~
(BSEP-2-18) en g
TABLE 3.3.2-1 (Continued) vi ISOLATION ACTUATION INSTRUMENTATION O
VALVE GROUPS MINIMUM NUMBER APPLICABLE e
OPERATED BY OPERABLE CilANNELS OPERATIONAL z
TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION H
8.
IIPCI Steam Line Area A Temp. -
l lliph 4
, 2, 3 25 (E51-dTS-N604C,D) 9.
Emergency Area Cooler l
Temperature - liigh 4
I 1, 2, 3 25 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh 5
1 (E51-dPIS-N017 and E51-dPIS-N018) u 2.
RCIC Steam Line Iligh Flow Y
Time Delay Relay NA 1
1, 2, 3 25 Z
(E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply Pressure - Low 5
2 1' 2' 3 25 l
(E51-PS-N019A,B,C,D) 4.
RCIC Steam Line Tunnel Temperature l
- liigh 5
2 1, 2, 3 25 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; g
E51-TS-3323; g
E51-TS-3355; o-E51-TS-3487)
I 5.
Bus Power Monitor NA 1/ bus 1, 2, 3 26 l
(E51-K42 and E51-K43) go 6.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 5
2 1, 2, 3 25 (E51-PS-N012A,B,C,D)
-a u--m
-g
(BSEP-2-18) to TABLE 3.3.2-1 (Continued) l l
_ ISOLATION ACTUATION INSTRUMENTATION I
E VALVE CROUPS MINIMUM NUMBER APPLICABLE h
TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION OPERATED BY OPERABLE CHANNELS OPERATIONAL
\\
a 7.
RCIC Steam Line Ambient Temp -
liigh 5
1 1,2,3 25 (E51-TS-N603A,B) 8.
RCIC Steam Line Area A Temp - Iligh 5
1 1,2,3 25 l
(E51-dTS-N604A,B) 9.
RCIC Equipment Room Ambient l
Temp - liigh 5
1 1,2,3 25 (E51-TS-N602A,B)
R 10 RCIC Equipment Room A Temp - High 5
1 1,2,3 25 j
^
(E51-dTS-N601A,B)
Y C
5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Low, Level 1 2,6,7,8 2
1,2,3 27 (B21-LT-N017A-1,B-1,C-1,D-1)
( B 21-LTM-N017A-1, B-1, C-1, D-1 )
b.
Reactor Steam Dome Pressure-7, 8 1
1,2,3 27 liigh (B32-PS-N018A,B) 1
,a, v
g g
a c-9y
+
, +
R
- f.~
TABLE'3.3.2-2'(Continued) d.
- g.
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS ALLOWABLE TRIP FUNCTION'AND INSTRUMENT-NUMBER TRIP SETPOINT VALUE-
-2 l'
U L3. REACTOR WATER CLEANUP SYSTEM ISOLATION
~
u_
'i a.
A Flow - High
< 53 gal / min
< 53 gal / min-(G31-dFS-N603-1A,IB) b.
Area Temperature - liigh -
< 150*F'
< 150*F (G31-TS-N600A,B,C,D,E,F) c.
Area Ventilation Temperature A Temp - liigh
< 50*F
< 50*F (G31-TS-N602A,B,C,D,E,F) d.-
SLCS Initiation NA NA y
(C41A-SI) s.
e.
y 4
Low, Level 2
> + 112 inches
- __> + 112 inches *
(H21-LTM-NO24A-1,B-1 and o
821-LTM-N025A-1,B-1) 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - liigh
< 300% of rated flow
< 300% of rated flow (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Line liigh Flow Time Delay Relay 3 < t < 7 seconds 3 < t < l2 seconds
.(E41-TDR-K33; g
E41-TDR-K43) m g,
3.
HPCI Steam Supply Pressure - Low
),100 psig
__ 100 psig I
a (E41-PSL-N001A,B,C,D)
E Y
) a:
(BSEP--2-18).
- tn 58 TABLE 3.3.2-2 (Continued)
Ei,
5 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS g
O ALLOWABLE
. TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE liPCI Steam Line Tunnel ~ Temperature - High -
<-200*F
< 200*F H
4.
j (E41-TS-3314; N
E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; l
E41-TS-3489) 5.
Bus Power Monitor NA NA l
R (E41-K55 and E41-K56)
I l
[
6.
IIPCI Turbine Exhaust. Diaphragm l
J
,8 -
Pressure - liigh 1 10 psig i 10 psig 3o (E41-PSil-N012A,B,C,D) 7.
!!PCL Steam Line ' Ambient Temp - High
< 200'F
< 200*F (E51-TS-N603C,D) 8.
IIPCI Steam Line Area A Temp - High
< 50*F
< 50*F (E51-dTS-Nb04C,D) 9.
Emergency Area. Cooler Temp - Iligh
< 175'F
< 175'F l
(E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation c
1.
RCIC Steam Line Flow - High
< 300% of rated flow
< 300% of rated flow k
(E51-dPIS-N017 and E51-dPIS-N018)
- s 2.
RCIC Steam Line High Flow Time Delay Relay 3 < t < 7 seconds 3 < t < 12 seconds (E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply Pressure - IAw
),50 psig J_ 50 psig l
l (E51-PS-N019A,B,C,D)
- s (BSEP-2-18).
lN TABLE'3.3.2-2'(Continued)
E.
E, ISOI). TION ACTUATION INSTRUMENTATION SETPOINTS 5-ALLOWABLE TRIP FIINCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE'
.E l
E' 4'.
RCIC Steam Line Tunnel Temp - High
< 175'F
< 175'F l
9 (E51-TS-3319; E51-TS-3320; E51-IS-3321; E51-TS-3222; p
E51-TS-3323; I
E51-TS-3355; E51-TS-3487).
l 5.
Bus Power Monitor NA NA (E51-K42 and E51-K43)
{
6.
RCIC Turbine Exhaust Diaphragu l
Preen;ure - liigh 1 10 psig i 10 psig 4
(1:,51 -PS-N012 A, B, C, D) l j
7.
RCIC Steam Line Ambient Temp - High
< 200*F
< 200*F (E51-TS-N603A,B) 8.
KCIC Steam Line Area A Temp - High
< 50*F
< 50'F l
(E51-dTS-N604A,B) 9.
RCIC Equipment Room Ambient Temp - liigh
< 175'F
< 175'F (E51-TS-N602A,B) 10.
RCIC Equtpment Room A Temp - High
< 50*F
< 50*F l
(E51-dTS-N601A,B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION g
o o-a.
l Low, Level 1
> + 162.5 inches *
> + 162.5 inches *
(B21-LTt!-N017A-1,B-1,C-1,D-1) zy b.
Reactor Steam Dome Pressure - liigh 1 140 psig i 140 psig (B32-PS-N018A,B)
- Vessel water levels refer to REFERENCE LEVEL ZERO.
l o
II -
b.,.
(BSEP-2-18) l TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION aMD INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
'l.
_ PRIMARY CONTAINMENT ISOLATION
~' '
a.
1.
Low, Level 1
'f,13 (B21-LT-N017A-1,B-1,C-1,D-1)
-(B21-LTM-N017A-1.B-1,C-1,D-1) 2.
Low, Level 2 l
<l.0*
(B21-LT-N024A-1,B-1 and
~~
B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1, B-1 and
~
B21-LTM-N025A-1,B-1) b.
Drywell Pressure - High
<13 (C72-PS-N002A,B,C D)
-~
c.
Radiation - High(b)
--<1.0*
1 l
(D12-RM-K603A,B,C,D)
- 2. ' Pressure - Low (B21-PT-N015A,B,C,D)
~~<13 L
(B21-PTM-N015A-1,B-1,C-1,D-1) 3 '. Flow - High (B21-PDT-N006A,B,C,D;
~~<0,5*
B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D)
.(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; B21 -PDTM-N008A-1,3-1, C-1, D-1 ;
B 21-PDTM-N00 9A-1, B-1, C-1, D-1 )
4,. Flow - High (B21-PDTS-N006A-2;
~~<0.5*
B21-PDTS-N007B-2;
.B21-PDTS-500BC-2; B21-PDTS-N009D-2) d.
Main Steam Line Tunnel Temperature - High (B21-TS-N010A,B,C,D;
-~<13 B21-TS-N0llA,B,C,D;
~B21-TS-N012A,B,C,D;
.B21-TS-N013A,B,C,D)
,e.
Condenser Vacuum - Low
<13 (B21-PS-N056A,B,C,D)
~~
. BRUNSWICK-UNIT'2 3/4 3-22 Amendaent No.
(BSEP-2-18) d TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION ANu INSTP.LS!ENT NUMBER RESPONSE TIME (Seconds)#
f.
Turbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b) it3 a.
(D12-RM-N010A,B) b.
Drywell Pressure - High 113 (C72-PS-N002A,B,C,D)
Reactor Vessel Water Level - Low, Level 2 11.0*
l c.
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(L21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 3.
. REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 113 (G31-dFS-N603-1A,IB) b.
Area Temperature - High
<13 (G31-TS-N600A,B,C,D,E,F)
~
Area Ventilation Temperature AT - High
-<13 c.
(G31-TS-N602A,B,C,D,E,F) d.
Reactor Vessel Water Level - Low, Level 2
<l.0*
l e.
(B21-LT-NO24 A-1,B-1 and B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1)
I i
i BRUNSWICK - UNIT 2 3/4 3-23 Amendment No.
J-
[
- ' : C (BSEP-2-18) a;
- ~..
TABLE 3.3.2-3 (Continued)
- a
'l
. ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NINBER RESPONSE TIME (Seconds)#
4.; CORE STANDBY COOLING SYSTEMS ISOLATION i.
High Pressure Coolant Injection System Isolation a.
- 1. 'HPCI Steam Line Flow - High
--<13(a)##
l
'(E41-dPIS-N004 and r
E41-dPIS-N005)
' 2.. HPCI. Steam Line High Flow Time Delay Relay-NA 7
^
(E41-TDR-K33; E41 -TDR-K43) 3.
HPCI' Steam Supply Pressure - Low
'-<13 l
'(E41-PSL-N001A,B,C,D) 4.
HPCI Steam Line Tunnel Temperature - High (E41-TS-3314;
~<13 E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488;.
E41-TS-3489)
-5.
Bus' Power Monitor NA l
(E41-K55 and E41-K56)-
l
'6.
HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N012A,B,C,D) l 7.
HPCI Steam Line. Ambient Temperature - High NA (E51-TS-N6s3C,D) 8.
HPCI Steam Line Area NA l
(E51-dTS-N604C,D)
- 9. -. Emergency Area Cooler Temperature - High NA l
(E41-TS-602A,B)
'~
'b.
-Reactor Core Isolation.Cocling System Isolation (E51-dPIS-N017 and.
~~<13(")#
l 1.-
RCIC Steam Line Flow
.High-E51-dPIS-N018) 2.
RCIC Steam Line liigh Flow
- Time Delaf Relay NA
,(E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply Pressure - Low NA l
(E51-PS-N019A,B,C,D):
[ BRUNSWICK - UNIT 2-3/4'3-24 Amendment No.
(BSEP-2-18) i TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INT-"IUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
4.'
~
RCIC Steam Line' Tunnel Temp - High l
NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 5.
Bus Power Monitor NA l
(E51-K42.and E51-K43)
- 6. 1 RCIC Turbine Exhaust Diaphram l
Pressure - High NA
~(E51-PS-N012A,B,C,D) 7.
RCIC Steam Line Ambient Temperature - High NA l
(E51-TS-N603A,B) 8.
RCIC Steam Line Area A Temp - High NA l
-(E51-dTS-N604A,B)
- 9.. Emergency Area Cooler Temperature - High NA l
(E51-TS-N602A,B)
- 10..RCIC Equipment Room A Temp - High NA f
(E51-dTS-N601A,B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION
-Reactor Vessel Water Level - Low, Level 1 NA a.
(B21-LT-N017A-1,B-1,C-1,D-1)
. ( B21-LTM-N017A-1, B-1, C-1, D-1 )
b..
Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B)
' BRUNSWICK - UNIT 2 3/4 3-24A Amendment No.
(BSEP-2-18)
TABLE 3.3.2-3 (Continued)
~
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME NOTES (a)
The isolation system instrumentatJon 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 from response time testing. Response time shall be measured from detector. output or the input of the first electronic component in the channel.
~
Isolation actuation instrumentation response time only.
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.
. Includes time delay added by the time delay relay (E41-TDR-K33 and E41-TDR-K43).
Includes time delay added by the time delay relay (E51-TDR-K32 and E51-TDR-K12).
i
.BRUNSWlCK - UNIT 2 3/4 3-24B Amendment No.
q, y
(BSEP-2-18) l" TABLE 4.3.2-1 (Continued) z i
ISOLATION ACTUATION INSTRIMENTATION SURVEILLANCE REQUIREMENTS-j R
' CHANNEL OPERATIONAL
-c CHANNEL-FUNCTIONAL-CHANNEL CONDITIONS IN.WHICH 4
h'TRIPFUNCTIONANDINSTRUMENTNUMBER CllECK TEST =
CALIBRATION
-SURVEILLANCE REQUIRED
.l H
N 4.
CORE STANDBY COOLING SYSTEMS ISOLATION-'
a.
-.High Pres'sure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow
- 1gh D
M' Q
1, 2,.3 (E41-dPIS-N004;
'E41-dPIS-N005) 2.
IfPCI Steam Line liigh Flow Time Delay Relay NA R
R 1, 2, 3 (E41-TDR-K33;
{
E41-TDR-K43) l y
3.
IIPCI Steam Supply Pressure -
l n
Low NA-M R
1, 2, 3 l
(E41-PSL-N001A,B,C,D) 4.
IIPCI Steam Line Tunnel' Temperature - liigh NA M
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315;-
E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; l
E41-TS-3489) i g
5.
Bus Power Monitor NA R
NA 1, 2, 3 g-(E41-K55 and E41-K56) k l
6.
IIPCI Turbine Exhaust Diaphragm Pressure - liigh NA M
Q 1, 2, 3 20 (E41-PSil-N012A, B,C, D)
- n- ~,
,1:,
s gp e " '
j
'(BSEP-2-18)
.. '. 1
- to..[.
TABLE'4.3.2-1 (Contir.ued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS' H9-I
' CHANNEL
.OPERATIONAI; CHANNEL.
. FUNCTIONAL CHANNEL CONDITIONS:'IN WHICH:
g^~
,y TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST' CALIBRATION
' SURVEILLANCE REQUIRED-7.
IIPCI Steam Line Ambient'
[
NA --
M R
1, 2, 3 Temp - liigh.
(E51-TS-N603C,D) 8.
- IIPCI Steam Line Area '
A Temp. - liigh NA M
R 1, ?,,
(E51-dTS-N604C,D)
I
'9.
Emergency Area Cooler g
Temp - Illgh NA M
Q 1, 2, 3 (E41-TS-N602A,B)-
U
^
b.
Reactor Core. Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh NA M
- Q 1, 2, 3 (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Line liigh Flow Time Delay Relay NA R
R 1, 2, 3 (E51-TDR-K32;.
E51-TDR-K12) 3.
RCIC Steam Supply l
1 Pressure - Low NA M
Q 1, 2, 3 i
(E51-PS-N019A,B,C,D) l l
4.
RCIC Steam Line Tunnel E
liigh Temperature NA M
R 1, 2, 3 l
(E51-TS-3319; E
E51-TS-3320;'
E51-TS-3321;
.l z
E51-TS-3322; I
E51-IS-3323; E51-TS-3355; E51-T3-3487) l I
~
s b.
.(BSEP-2-13)
A
~ TABLE 4.3.2-1 (Continued)
- - -ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-w.
0 v3 channel OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH-Q TRIP FUNCTION AND INSTRUMENT NUMBER'
'CllECK TEST CALIBRATInM-SURVEILLANCE REQUIRED' 8
', 2, 3 l
5.
Bus Power Monitor NA R
NA
~
g 1
.(E51-K42 and E51-K43)
,4 Hs' 6.
RCIC Turbine Exhaust l
Diaphragm Pressure - High NA M
R 1,'2, 3
(E51-PS-N012A,B,C,D) 7.
RCIC Steam Line Ambient l
l Temp - liigh NA-M R
1, 2, 3 l
4 (E51-TS-N603A,B) 8.
RCIC Steam Line Area l
A Temp - liigh NA M
R 1, 2, 3 id (E51-dTS-N604A,B) c.
w 9.
RCIC Equipment Room Ambient l
e's Temp - !!!gh N.i M
Q 1, 2, 3
.7 (E51-TS-N602A,B) r j
10.
RCIC Equipment Room A l
Temp - liigh NA M
Q 1, 2, 3 (E51-dTS-N601A,B) 5.
SilUTDOWN COOLING SYSTEM ISOLATION l
a.
Low, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(a)
NA R(b) 1,2,3 (B21-LTil-N017A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 b.
Reactor Steam Dome Pressure -
g e
liigh NA S/U(C),M R
1, 2, 3 E.
(B32-PS-N018A,B)
J' E
- When handling irradiated fuct in the secondary containment.
z
- When reactor steam pressure > 500 psig.
(a) The transmitter channel check' is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
(c) If not performed within the previous 31 days.
-