ML20215L724
| ML20215L724 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/01/1987 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20215L691 | List: |
| References | |
| 87TSB01, 87TSB1, NLS-87-023, NLS-87-23, NUDOCS 8705120344 | |
| Download: ML20215L724 (31) | |
Text
1 To Serial: NLS-87-023 Proposed Technical Specification Pages Brunswick-1 Rosemount Analog Trip System (87TSB01) t I
e k.
I.
I PDk c
(5124 BAT /bac) t
-. =..
,,m,,-_.
m..
........~,......---.,--m.._,
- z
- Unit 1
SUMMARY
LIST OF REVISIONS M
Page No.,
Description of Changes 3/43-7,3/43-8, The test intervals for functional and 3/4 3-25 through calibration testing of the Rosemount 3/4 3-29b,3/4 3-37 Analog Trip Unit System were
- through 3/4 3-38a changed from monthly to semi-
'3/43-81,3/43 annually.
i f
(51248AT/bac)
(BSEP-1-99)
TABLE 4.3.1-1 E
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
M CHANNEL OPERATIONAL X
FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL
' CONDITIONS IN WHICil AND INSTRUMENT NUMBER CilECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED Ey 1.
( C51-I RM-K601 A, B,C,D, E, F,C,II) e a.
Neutron Flux - liigh 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 Honitor:
(C51-APRM-CH.A,B,C,D,E,F) w a.
Neutron Flux - liigh 15%
S S/U(b)(m), g(d)
Q 2
W ")
Q 5
I S
b.
Flow-Biased Neutron Flux - Iligh S
S/U(b),y g(e)(f),q y
c.
Fixed Neutron Flux - liigh, 120%
S S/U(b),y g(e),q g
W ")(")
NA 1, 2, 5 I
d.
Inoperative NA e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5 3.
Reactor Vessel Steam Dome O
Pressure - liigh (B21-PT-NO23A,B,C,D)
NA(k).NA RII) 1, 2 h
(B21-PTM-NO23A-1,B-1,C-1,D-1)
D SA SA 1, 2 l
f 4.
Low, Level 1 II)
(B21-LT-NOl7A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 (B 21-LDi-NOl 7 A-1, B-1,C-1, D-1 )
D SA SA 1, 2 l
'(BSEP-1-99)
TABLE 4.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVETLLANCE REQUIREMENTS en N
- CilANNEL OPERATIONAL O-FUNCTIONAL UNIT CilANNEL FUNCTIONAL ChlANNEL CONDITIONS IN WilICIIL
- AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED 4
- 5. Main Steam Line Isolation Valve -
NA M
R(h) 1 Closure (B21-F022A,B,C,D and B21-F028A,B,C,D)
II)
I5) 1, 2
- 6. Main Steam Line Radiation - liigh S
M R
(D12-RM-K603A,B,C,D)
- 7. Drywell Pressure - liigh (C71-PT-N002A,B,C,D)
NA(k)
NA RII) 1, 2 (C71-PTM-N002A-1,B-1,C-1,D-1)
D SA SA 1, 2
_l
- 8. Scram Discharge Volume Water Level - High NA Q
R 1, 2, 5 g
L (C11-LSH-N013A,B,C,D)
(Cll-LSii-4516A,B,C,D)
- 9. Turbine Stop Valve - Closure NA M
R(h) g(o)
(EUC-SVOS-1X,2X,3X,4X)
I
- 10. Turbine Control Valve Fast l
Closure, Control Oil Pressure -
I) g Low NA M
R I
(EllC-PSL-1756,1757,1758,1759)
@ 11. Reactor Mode Switch in Shutdown NA R
NA 1, 2, 3, 4,-5 Position (C71A-SI)
- 12. llanual Scram NA Q
NA 1,2,3,4,5-(C71A-S3A,B)
'(BSEP-1-99)'
TABLE'4.3.2-1 g
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
M CHANNEL OPERATIONAL b
CHANNEL FUNCTIONAL CHANNEL CONDITIONS -IN WilICil
' TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E
y 1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Low, Level 1 (B21-LT-NO17A-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 SA SA 1,_2, 3
'l 2.
Low, Level 2 (B21-LT-N024A-1,B-1 and B21-LT-NO25A-1,B-1)
NA(a)
NA
'R(b) 1, 2, 3 (B21-LTM-NO24A-1,B-1 and B21-LTM-N025A-1,B-1)
D SA SA-1,2,3 l
b.
Drywell Pressure - liigh Y
(C71-PT-N002A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (C71-PTM-N002A-1,B-1,C-1,D-1)
D SA SA 1,2,3 l
c.
Radiation - liigh D
W R
1, 2, 3 (D12-RM-K603A,B,C,D) 2.
Pressure - Low (B21-PT-NO15A,B,C,D)
NA(a)
NA
-R(b) i (B21-PTM-NO15A-1,B-1,C-1,D-1)
D SA SA 1
l g
3.
Flow - liigh O'
(B21-PDT-NOO6A,B,C,D; NA(a)
NA
' R(b) 1 B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; f
B21-PDT-N009A,B,C,D)
(B21-PDTM-NOO6A-1,B-1,C-1,D-1; D
SA.
SA 1
l B21-PDTM-NOO7A-1,B-1,C-1,D-1; B21-PDTM-NOO8A-1,B-1,C-1,D-1; B21-PDTM-NOO9A-1,B-1,C-1,D-1)
.(BSEP-1-99)
TABLE 4.3.2-1 (Continued) i Eg ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E!
p+
CHANNEL OPERATIONAL.
W CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 8 TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 5
hPRIMARYCONTAINHENTISOLATION(Continued) e d.
Main Steam Line Tunnel Temperature - High NA M.
R 1, 2, 3 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low (B21-PT-N056A,B,C,D)
NA(a)
NA R(b) g 29 i
(B21-PTM-N056A-1,B-1,C-1,D-1).
D SA SA 1, 2 #
l u,
I 2I f.
Turbine Building Area Temp-High' NA M
R 1, 2, 3 y
(B21-TS-3225A,B,C,D;
) y 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) e it B
h.
l 4
($SEP-1-99)2 TABLE 4.3.2-1 (Continued)~
~
ISOLATION ACTUATION INSTRIMENTATION SURVEILLANCE REQUIREMENTS s
CHAN
- c OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK-TEST CALIBRATION SURVEILLANCE REQUIRED.-
E' s 2.
SECONDARY CONTAINHENT ISOLATION a.
Reactor Building Exhaust Radiation - High D
M R
1,2,3,5, and *
(D12-RM-N010A,B) b.
Drywell Pressure - High (C71-PT-N002A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (C71-PTM-N002A-1,B-1,C-1,D-1)
D SA SA 1, 2, 3 l
c.
Low, Level 2 (B21-LT-NO24 A-1,B-1 and NA(a)
'NA RID) 1, 2, 3 g
B21-LT-NO25 A-1,B-1)
(B21-LTM-HO24 A-1,B-1 and D
SA SA 1,.2, 3.
-l 4
B21-LTM-NO25 A-1,B-1) u 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High D
M R
1, 2, 3 -
(C31-dFS-N603-1A,lB) b.
Area Temperature - High NA M
R.
1, 2, -3 (G31-TS-N600A,B,C,D,E,F) c.
Area Ventilation A Temp - High NA M
R 1, 2, 3 (C31-TS-N602A,B,C,D,E,F) f d.
SLCS Initiation NA R
NA 1, 2, 3 g
(C41A-SI) e.
Low, Level 2 n
'g (B21-LT-NO24 A-1,B-1 and NA(a)
NA R(b)
- 1, 2, 3 B21-LT-NO25 A-1,B-1)
(B21-LTM-NO24 A-1,B-1 and D
SA SA
,1, 2, 3 l
B21-LTM-NO25 A-1,B-1)
- (BSEP-1-99)
TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS H
CilANNEL OPERATIONAL 0
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICil
- TRIP FUNCTION AND INSTRUMENT NUMBER CliECK TEST CALIBRATION SURVEILLANCE REQUIRED ep 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Tsolation 1.
HPCI Steam Line Flow - liigh (E41-PDT-N004; Nga)
NA R(b) 1, 2, 3 E41-PDT-N005)
(E41-PDTS-NOO4-2; D
SA SA 1, 2, 3 l
E41-PDTS-NOO5-2) 2.
HPCI Steam Line liigh Flow Time Dclay Relay NA R
R 1,2,3 w)
(E41-TDR-K33; E41-TDR-K43) 9 g
3.
HPCI Steam Supply Pressure -
uw NA M
R 1, 2, 3 (E41-PSL-N001A,B,C,D) 4.
HPCI Steam Line Tunnel Temperature - liigh NA M
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; g
E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; y
E41-TS-3489) 5.
Bus Power Monitor NA R
NA 1, 2, 3 (E41-K55 and E41-K56) 6.
HPCI Turbine Exhaust Diaphragm Pressure - liigh NA M
Q 1, 2, 3 (E41-PSil-N012A,B,C, D)
(BSEP-1-99)
TABLE 4.3.2-1 (Continued)-
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
g CHANNEL OPERATIONAL 7:
CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WilICil 8 TRIP FUNCTION AND INSTRUMENT NilMBER CilECK TEST CALIBRATION-SURVEILLANCE REQUIRED Ey 7.
HPCI Steam Line Ambient Temp - liigh NA M
R 1,2,3 g
(E51-TS-N603C,D) 8.
HPC! Steam Line Area A Temp - High NA M
R 1, 2, 3 (E51-dTS-N604C,D) 9.
Emergency Area Cooler Temp - High NA M
Q 1,- 2, 3 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation a
S 1.
RCIC Steam Line Flow - liigh (E51-PDT-NOl7; NA(a)
NA R(b) 1, 2, 3 w
y E51-PDT-NOl8)
(E51-PDTS-NOl7-2; D
SA SA 1, 2, 3 l
E51-PDTS-NOl8-2) 2.
RCIC Steam Line Iligh Flow Time Delay Relay NA R
R 1, 2, 3 (E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply k
Pressure - Low NA M
'Q 1, 2, 3
{
(E51-PS-NOl9A,B,C,D)
S E
E?
4
,m
'(BSEP-1-99)
TABLE 4.3.2-1-(Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS e
' H CHANNEL OPERATIONAL 0
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH I
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST.
CALIBRATION SURVEILLANCE REQUIRED Ep 5.
SHUTDOWN CCOLING 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-NOl7A-1,B-1,C-1,D-1)
D SA SA 1, 2, 3 l
b.
Reactor Steam Dome Pressure -
High NA S/U(c),M R
1,2,3 t
(B32-PS-NOl8A,B) t' z~
Y When handling irradiated fuel in the secondary containment.
y C'
- When reactor steam pressure > $00 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.
N B
- 8" 1
h i'
=
i
s (BSEP-1-99) j.
~
p TABLE 4.3.3-1 7
.EHERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENES-
.g m
M-CliANNEL.
OPERATIONAL
.' O CIIANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICII i TRIP FUNCTION AVi INSTRUMENT NUMBER CHECK TEST
, CALIBRATION
_ SURVEILLANCE REQUIRED E
g 1. CORE SPRAY SYSTEM M
a.
Low, Level 3 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1,2,3,4,5 (B21-LTS-NO31A-4,B-4,C-4,D-4)
D SA SA-1,2,3,4,5 l
b.
Reactor Steam Dome Pressure - Low s
(B21-PT-NO21A,B,C,D)
NA(a)
NA.
R(b) 1,2,3,4,5 (B21-PTS-NO21A-2,B-2,C-2,D-2)
D SA SA 1,2,3,4,5 l
c.
Drywell Pressure - liigh (Ell-PT-N0llA,B,C,D)
NA(a)
NA R(b) 1, 2, 3 y
(Ell-PTS-N0llA-2,B-2,C-2,D-2)
D SA SA 1, 2, 3 l
d.
Time Delay Relay NA R
R 1,2,3,4,5 L
(E21-K16A,B)~
e.
Bus" Power Monitor NA R
NA 1,2,3,4,5 (E21-KlA,B)
- 2. LOW PRESTJRE COOLANT INJECTION HODE OF RIIR SYSTEM a.
Drywell Pressure - liigh (Ell-PT-N0llA,B,C,D)
NA(a)
NA R(b)~
1, 2, 3 (Ell-PTM-N0llA-1,B-1,C-1,D-1)
D SA SA 1,2,3 l
r b.
4 Low, Level 3 h
(B21-LT-M031A,B,C,D)
NA(a)
NA R(b) 1, 2, 3, 4*, 5*
( B21-LTS-1031 A-4, B-4, C-4, D-4 )
D SA SA 1, 2, 3, 4*, 5*
l zo c.
Reactor Vessel Shroud Level (B21-LT-NO36 and B21-LT-NO37)
NA(a)
NA
.R(b) 1, 2, 3, 4*,
5*
(B21-LTM-NO36-1 and B21-LTH-NO37-1) D SA SA 1, 2, 3, 4*, 5*
l
(BSEP-1-99)
TABLE 4.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5-m CllANNEL OPERATIONAL 9'
- CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WIIICil i TRIP FUNCTION AND INSTRUMENT NUMBER CIIECK TEST
. CALIBRATION SURVEILLANCE REQUIRED E
..y LOW PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM (Continued) d.
Reactor Steam Dome Pressure - Low NA(a)
NA' R(b) 1, 2, 3, 4*, 5*
(B21-PT-NO21A,B,C,D) 1.
RHR Pump Start and LPCI Injection Valve Actuation D
SA SA 1, 2, 3, 4*, 5*
l (B21-PTS-NO21A-2,B-2,C-2,D-2)
~
2.
Recirculation Loop Pump Discharge Valve Actuation D
SA SA 1, 2, 3, 4*, 5*
l (B21-PTM-NO21A-1,B-1,C-1,D-1) e.
RilR Pump Start - Time Delay Relay NA R
R 1, 2, 3, 4*, 5*
y 2
(STR-1A1,2 and STR-1B1,2) y h
f.
Bus Power Monitor NA R
NA 1, 2, 3, 4*, 5*
(El1-K106A,B)
- 3. IIICll PRESSURE COOLANT INJECTION SYSTEM a.
Low, Level 2 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 g
(B21-LTS-NO31A-2,B-2,C-2,D-2)
D SA SA 1, 2, 3
'l.
GD b.
Drywell Pressure - liigh h
(Ell-PT-N011A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 D
(El1-PTS-NO11A-2,B-2,C-2,D-2)
D SA SA 1, 2, 3 l
g c.
Condensate Storage-Tank Level - Low NA M
Q 1,2,3 (E41-LS-N002; E41-LS-N003) d.
Suppression Chamber Water Level - liigh NA M
Q 1, 2, 3 (E41-LSH-N015A,B) c.
Bus Power Monitor NA R
NA 1, 2, 3 -
(E41-K55 and E41-K56) 6
(BSEP-1-99)
TABLE 4.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS e
H CilANNEL OPERATIONAL O
CIIANNEL FUNCTIONAL CHANNEL CONDITIONS IN WillCII TRIP FUNCTION AND INSTRUMENT NilHBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED E
. p 4. AUTOHATIC DEPRESSURIZATION SYSTEM IC)
H a.
ADS Inhibit Switch D
R NA 1, 2, 3
[
(B21-CS-S5A,B) l b.
Low, Level 3 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-3,B-3,C-3,D-3)
D SA SA 1,2,3 l
c.
Low, Level 1 (B21-LT-NO42A,B)
NA(a)
NA R(b) 1, 2, 3
, ti.
(B21-LTM-NO42A-1,B-1)
D SA SA 1, 2, 3 l
v d.
ADS Timer NA R
R 1,'2, 3
g f,
(B21-TDPU-KSA,B) en l
D e.
Core Spray Pump Discharge Pressure - liigh NA M
Q 1,2,3 (E21-PS-N008A,B and
~
E21-PS-N009A,B) f.
RIIR (LPCI HODE) Pump Discharge Pressure - liigh NA M
Q 1, 2, 3 g
(Ell-PS-N016A,B,C,D and g
E11-PS-N020A,B,C,D) c.
g g.
Bus Power Monitor NA R
NA 1, 2, 3 m
(B21-K1A,B)
P.
t
,; e '*
(BSEP-1-99)L TABLE 4.3.6.1-1 AWS RECIRCllLATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS l g$
CHANNEL CHANNEL FUNCTIONAL.
CHANNEL W TRIP FUNCTION AND INSTRUMENT NUMBER CilECK
' TEST CALIBRATION I
g 1.
Low, Level 2 H
(B21-LT-N024A-2,B-2 and NA(a)
NA R(b) y B21-LT-H025A-2,B-2) l (B21-LTM-NO24A-2,B-2 and D
SA SA B21-LTM-NO25A-2,B-2) 2.
Reactor Vessel Pressure - liigh NA M
R (B21-PS-N045A, B, C, D)
M s~
Y co W
(a) The transmitter channel check is satisfied by the. trip unit channel j
check. A separate transeitter check is not. required.
I (b) Transmitters are exempted Icom the monthly channel calibration.
N a
EF 8
n O
4 4
m
=
TBSEP-1-99) 7 TABLE 4.3.7.1-1
. E REACTOR CORE ISOLATION COOLINC SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ey CHANNEL X
CHANNEL FUNCTIONAL CllANNEL.
-' FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK TEST CALIBRATION i- @
.a.
y ir
. Low, Level 2
)
NA R(b)
(B21-LT-N031A,B,C,D)
NA (B21-LTM-NO31A-1,B-1,C-1,D-1)
D.
SA SA l'
i b.
Reactor Vessel Water Level - liigh (B21-LT-N017A-2,C-2)
NA(a)
NA R(b) l' (B21-LTM-N017A-2,C-2)
D SA SA j
c.
Condensate-Storage Tank Level - Low a
i )
(E51-LSL-4463, E51-LSL-4464)
NA M
Q Y
8 1
(a) The transmitter channe' check is satisfied by the trip unit channel check. A separate' transmitter check is not required.
(b) Transmitters are exempced from the monthly channel calibration.
I B
a.
E fE 1
- =
p-g i
z
's:
l To Serial: NLS-87-023
~
Proposed Technical Specification Changes Brunswick-2 Rosemount Analog Trip System (87TSB01)
(5124 BAT /bac)
Unit 2 Summary List of Revisions Page No.
Description of Change 3/43-7,3/43-8 The test intervals for functional and 3/4 3-25 through calibration testing of the Rosemount 3/4 3-29b,3/4 3-37 Analog Trip Unit System were 3/43-81,3/43-92 _
changed from monthly to semi-through 3/4 3-38a, annually 4
A 4
e r
(5124 BAT /bme)
'(BSEP-2-100)
TABLE 4.3.1 E
-g REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
H CilANNEL OPERATIONAL b
FUNCTIONAL UNIT CHANNEL FUNCTIONAL-CHANNEL CONDITIONS IN WilICll:
8 -AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED Ey 1.
(C51-IRM-K601A,B,C,D,E,F,G,ll) y a.
Neutron Flux - liigh D
S/U(b)(c), g(d)
R 2
D W
R 3, 4, 5 Id) b.
Inoperative NA W
NA 2,3,4,5 2.
Average Power Range Monitor:
j (C51-APRM-CH.A,B,C,D,E,F)
S/U(b)(m)', g(d)
Q 2
lw a.
Neutron Flux - liigh 15%
S W ")
Q 5
I S
b.
Flow-Biased Neutron Flux - liigh S
S/U(b),y g(e)(f),q g
)
c.
Fixed Neutron Flux - liigh, 120%
S S/U(b),y g(e),q y
O d.
Inoperative NA W(")I")
NA 1, 2, 5 e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5 i
3.
Reactor Vessel Steam Dome i
Pressure - High i
(B21-PT-NO23A,B,C,D)
NA(k) NA RII) 1, 2 i @
(B21-PTM-NO23A-1,B-1,C-1,D-1)
D SA SA 1, 2 l
4.
E Low, Level 1 II)
(B21-LT-NO17A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 (B21-LTM-NOl7A-1,B-1,C-1,D-1)
D SA SA 1, 2 l.
(BSEP-2-100)
TABLE 4.3.1-1 (Coutinued)-
G
' REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
'Ey CHANNEL
. OPERATIONAL F
FUNCTIONAL UNIT CilANNEL FUNCTIONAL CIIANNEL CONDITIONS IN WilICII 8
AND INSTRUMENT NUMBER CiiECK TEST CALIBRATION (a)-
SURVEILLANCE REQUIRED i
-G i@
- 5. Main Steam Line Isolation Valve -
NA M
R(h) 3 Closure g
(B21-F022A,B,C,D and B21-F028A,B,C,D)
II)
R(3)'
1, 2
- 6. Main Steam Line Radiation - Iligh S
H
'(D12-RM-K603A,B,C,D)
- 7. Drywell Pressure - liigh II)
(C72-PT-N002A,B,C,D)
MA(k)
NA R
1, 2 t
(C72-PTM-NOO2A-1,B-1,C-1,D-1)
D SA SA 1, 2 l
- 8. Scram Discharge Volume Water Level - High NA Q
R 1, 2, 5
,u (Cl2-LSH-N013A,B,C,D)
(Cl2-LSH-4516A,B,C,D)
- 9. Turbine Stop Valve - Closure NA M
R(h) g(o)
(EUC-SVOS-1X,2X,3X,4X)
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure -
IO)
)
Low NA H
R I
l@
(EllC-PSL-1756,1757,1758,1759)
- E
- 11. Reactor Mode Switch in Shutdown NA R
NA 1,2,3,4,5
]@
Position (C72A-S1)
>EF
- 12. Manual Scram
. NA Q
NA 1,2,3,4,5 (C72A-S3A,B)
,3 -
(BSEP-2-100) 4 TABLE 4.3.2-1 N
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 12 CllANNEL OPERATIONAL b
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WillCil TRIP FUNCTION AND-INSTRUMENT NUMBER CHECK TEST CALIBRATION G
~ SURVEILLANCE REQUIRED
' M 1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Low, Level.1 (B21-LT-NOl7A-1,B-1,C-1,D-1)
NA(a)
NA R(b) 1, 2, 3 (B21-LTM-NOl7A-1,B-1,C-1,D-1)
D SA
.SA' 1, 2, 3 l
2.
Low, Level 2 (B21-LT-NO24A-1,B-1 and' B21-LT-NO25A-1,B-1)
NA(a)
NA R(b) 1, 2, 3' (B21-LDI-NO24A-1,B-1 and B21-LTM-NO25A-1,B-1)
D SA SA 1,2,3 l
u
- s I#
b.
Drywell Pressure - liigh
! Y (C72-PT-N002A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 j
(C72-PTM-NOO2A-1,B-1,C-1,D-1)
D SA SA 1, 2, 3
.l' c.
1.
Radiation - liigh D
W R
1, 2, 3 (D12-RM-K603A,B,C,D) 2.
Pressure - Low (B21-PT-NO15A,B,C,D)
NA(a)
NA R(b) g 4
(B21-PTM-NO15A-1,B-1,C-1,D-1)
D SA SA 1
l 3.
Flow - liigh
.p g
(B21-PDT-NOO6A,B,C,D; NA(a)
NA
' R(b)
- g ig.
B21-PDT-NOO7A,B,C,D;
- g B21-PDT-NOO8A,B,C,D; jre B21-PDT-NOO9A,B,C,D) l If (B21-PDTM-NOO6A-1,B-1,C-1,D-1; D
SA SA 1
B21-PDTM-NOO7A-1,B-1,C-1,D-1; B21-PDTM-NOO8A-1,B-1,C-1,D-1; B21-PDTM-NOO9A-1,B-1,C-1,D-1)
(BSEP-2-100)
TABLE 4.3.2-1 (continued)
E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL OPERATIONAL b
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICll
' TRIP FUNCTION AND INSTRUh2NT HilHBER CHECK TEST
' CALIBRATION SURVEILLANCE REQUIRED E
y PRIMARY CONTAINMENT ISOLATION (Continued) w i
4.
Flow..lligh D
SA SA 2, 3
'l (B21-PDTS-NOO6A-2; B21-PDTS-NOO7H-2; 4
B21-PDTS-NOO8C-2; B21-PDTS-NOO9D-2) d.
Main Steam Line Tunnel Temperature - liigh
.NA M
R 1, 2, 3 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; ti B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D)
,: uL e.
Condenser Vacuum - Low (B21-PT-N056A,B,C,D)
NA(a)
NA R(b) 3, 2#
1 (B21-PTM-NOS6A-1,B-1,C-1,D-1)
D SA SA 1, 2 #
l l
f.
Turbine Building Area Temp-liigh NA M
R 1, 2, 3 (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;
,O B21-TS-3231A,B,C,D;
' (
B21-TS-3232A,B,C,D)-
E E
t 4
-(BSEP-2-100)
TABLE 4.3.2-1 (Continued)
Ng ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E!
H CHANNEL OPERATIONAL 9
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 8-TRIP' FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E
g 2.
' SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust g
Radiation - High D
M-R 1,2,3,5, and *
(D12-RM-N010A,B) b.
Drywell Pressure - High (C72-PT-N002A,B,C,D)
NA(a)
NA.
R(b) 1, 2, 3 (C72-PTM-N002A-1,B-1,C-1,D-1)
D SA SA 1,-2, 3
-l~..
c.
Low, Level 2 (B21-LT-NO24 A-1,B-1 and NA(a)
NA
~R(b) 1, 2, 3 B21-LT-N025 A-1,B-1) g D
(B21-LTM-N024 A-1,B-1 and
-D SA SA 1, 2, 3 l
y B21-LTM-N025 A-1,B-1)
U 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High D
M R
1,,2, 3
(C31-dFS-N603-1A,lB) b.
Area Temperature - High NA.
M R
1, 2.,
3 (C31-TS-N600A,B,C,D,E,F) c.
Area Ventilation A Temp - High NA M
R 1, 2, 3 (G31-TS-N602A,B,C,D,E,F) g d.
SLCS Initiation NA R
NA 1, 2,. 3 (C41A-SI) k e.
R Low, Level 2 (B21-LT-N024 A-1,B-1 and NA(a)
LA R(b) 1, 2, 3 2
B21-LT-NO25 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and D
'S A -
1,'2, 3
l:
B21-LTM-N025 A-1,B-1)
(BSEP-2-100)'
TABLE 4.3.2-1 (Continued)
E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ey CHANNEL OPERATIONAL CHANNEL FUNCTIONAL-CIIANNEL CONDITIONS IN WHICH
' TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST-CALIBRATION SURVEILLANCE' REQUIRED'.
-E y 4.
CORE STANDBY COOLING SYSTEMS ISOLATION w
a.
liigh Pressure Coolant Injection System. Isolation 1.
IIPCI Steam Line Flow - High (E41-PDT-N004; NA(a)
NA R(b) 1, 2, 3 E41-PDT-N005)
(E41-PDTS-N004-2; D
SA SA 1, 2, 3 l
E41-PDTS-N005-2) 2.
HPCI. Steam Line High Flow Time Delay Relay NA R
R 1,' 2,;3 w
D (E41-TDR-K33; E41-TDR-K43) w 3.
IIPCI Steam Supply Pressure -
kw NA M
R 1, 2, 3 (E41-PSL-N001A,B,C,D) 4.
IIPCI Steam Line Tunnel Temperature - High NA
-M.
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; g-E41-TS-3317; E41-TS-3318; a
5.
E41-TS-3354; 5
E41-TS-3388; N
E41-TS-3489) f 5.
Bus Power Monitor NA R
NA 1, 2, 3 (E41-K55 and E41-K56)
. ~,-. _..
_c e
(BSEP-2-100)
TABLE 4.3.2al (Continued)
Eg ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREHENTS E
H CHANNEL OPERATIONAL M
CHANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICH I TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED E
H 6.
IIPCI Turbine Exhaust Diaphragm Pressure - liigh NA M
Q 1,'2, 3 (E41-PSH-N012A,B,C,D) 7.
IIPCI Steam Line Ambient Temp - liigh NA M
R 1, 2, _ 3 (E51-TS-N603C,D) 8.
IIPCI Steam Line Area a Temp - liigh NA M
R 1, 2, 3 (E51-dTS-N604C,D) 9.
Emergency Area Cooler y
Temp - High NA M
Q 1, 2, 3 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh (E51-PDT-N017; NA(a)
NA R(b) 1, 2, 3 E51-PDT-N018)
(E51-PDTM-NOl7-2; D
SA SA 1,
2., 3-l E51-PDTM-NOl8-2) 2.
RCIC Steam Line liigh. Aow Time Delay Relay NA R
R 1, 2, 3 g
(E51-TDR-K32; E51-TDR-K12) n.
hj 3.
RCIC Steam Supply S
Pressure - Low NA M
Q 1, 2, 3 (E51-PS-N019A,B,C,D) l y,
a I
'(BSEP-2-100)
TABLE 4.3.2-1 (Continued) l ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL' OPERATIONAL S
CliANNEL FUNCTIONAL CllANNEL CONDITIONS IN WHICH e TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALI BR ATION
-SURVEILLANCE REQUIRED G
G5. SilUTDOWN COOLING SYSTEM ISOLATION ra a.
Low, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(a)
NA R(b) 1 2, 3
( B21-LTM-N017 A-1, B-1, C-1, D-1)
D SA SA 1,2,3 l-b.
Reactor Steam Dome Pressure
.High NA S/U(c),H R
1, 2, 3 (B32-PS-NOl8A,B)
I$
l 3
w a
R an
.O e
(BSEP-2-100)
TABLE 4.3.3-1 Ng EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REOUI3tEMENTS H
CHANNEL OPERATIONAL O
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICH 8 TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED G
- 1. CORE SPRAY SYSTEM a.
Low, Level 3 (B21-LT-NO31A,B,C,D)
NA(a)
NA RU')
1,2,3,4,5 (B21-LTS-NO31A-4,B-4,C-4,D-4)
D SA SA 1,2,3,4,5 l
b.
Reactor Steam Dome Pressure - Low (B21-PT-N021A,B,C,D)
NA(a)
NA R(b) g,.2, 3, 4, 5 (B21-PTS-N021A-2,B-2,C-2,D-2)
D SA SA 1,2,3,4,5 l
c.
Drywell Pressure - liigh (Ell-PT-N0llA,B,C,D)
NA(a)
NA R(b) g,.2, 3
(Ell-PTS-N0llA-2,B-2,C-2,D-2)
D SA SA 1, 2, 3 l
d.
Time Delay Relay NA R
R 1,2,3,4,5 v
f, (E21-K16A,B) u e.
Bus Power Monitor NA R
NA 1, 2,;3, 4, 5 (E21-KlA,B)
- 2. LOW PRESSURE COOLANT INJECTION HODE OF RHR SYSTEM a.
Drywell Pressure - High (Ell-PT-N011A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (Ell-PTM-N0llA-1,B-1,C-1,D-1)
D SA SA 1, 2, 3 l
b.
N Low, Level 3 k
(B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3, 4*, 5*
g (B21-LTS-NO31A-4,B-4,C-4,D-4)
D SA SA 1, 2, 3, 4*, 5*
l u"
c.
Reactor Vessel Shroud Level y
(B21-LT-NO36 and B21-LT-NO37)
NA(a)
NA R(b) 1, 2, 3, 4*, 5*
(B21-LTM-NO36-1 and B21-LTM-NO37-1) D SA SA 1, 2, 3, 4*, 5*
l
(BSEP-2-100)'
TABLE 4.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS iA d
CHANNEL OPERATIONAL 9
CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WHICH e TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED G
Q LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued) d.
Reactor Steam Dome Pressure - Low NA(a)
NA R(b) 1, 7, 3, 4*, 5*
(B21-PT-N021A,B,C,D) 1.
RilR Pump Start and LPCI Injection Valve Actuation D
SA SA 1, 2, 3, 4*, 5*
l (B21-PTS-N021A-2,B-2,C-2,D-2) 2.
Recirculation Loop Pump Discharge Valve Actuation D
SA SA 1, 2, 3, 4*, 5*
l (B21-PTM-NO21A-1,B-1,C-1,D-1) e.
RIIR Pump Start - Time Delay Relay NA R
R 1, 2, 3, 4*, 5*
(STR-2A1,2 and s
STR-2B1,2) b f.
Bus Power Monitor NA R
NA 1, 2, 3, 4*, 5*
(El1-K106A,B) 30 tilGli PRESSURE COOLANT INJECTION SYSTEM a.
Low, Level 2 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2)
D SA SA 1, 2, 3 l
b.
Drywell Pressure - liigh g
(Ell-PT-N0llA,B,C,D)
NA(a)
NA R(b) 1, 2, 3 o
h (E11-PTS-N0llA-2,B-2,C-2,D-2)
D SA SA 1, 2, 3 l
0 c.
Condensate Storage Tank Level - Low NA M
Q 1, 2, 3 (E41-LS-N002; E41-LS-N003) f d.
Suppression Chamber Water Level - High NA M
Q 1, 2, 3 (E41-LSH-N015A,B) e.
Bus Power Monitor NA R
NA 1, 2, 3 (E41-K55 and E41-K56)
TABLE 4.3.3-1 (Continued)
EMERCENCY CORE COOLINC SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL 9
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH e TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED M 4. AUTOMATIC DEPRESSURIZATION SYSTEM e
w a.
ADS Inhibit Switch (B21-es-SSA,B)
D(c)
R NA 1, 2,' 3 -
b.
Low, Level 3 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-3,B-3,C-3,D-3)
D SA SA 1, 2,. 3 l'
c.
Low, Level 1 (B21-LT-NO42A,B)
NA(a)
NA R(b) 1, 2, 3
( B21-LTM-N042 A-1, B-1 )
D SA SA 1,. 2, 3 l
u d.
ADS Timer NA R
R-1,2,3 Y
(B21-TDPU-K5A,B) w E
Core Spray Pump Discharge e.
Pressure - Hig*
NA N
Q 1, 2, 3' (E21-PS-N008A,B and E21-PS-N009A,B) f.
RHR (LPCI MODE) Pump Discharge Pressure - High NA M
Q 1, 2, 3
-(Ell-PS-N016A,B,C,D and Ell-PS-N020A,B,C,D) ca g.
Bus Power Monitor NA' R
NA 1, 2, 3 h
(B21-KIA,B)
En b.
(BSEP-2-100)-
TABLE 4.3.6.1-1 E
G ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREHENTS M
I3 O
CilANNEL
' CHANNEL FUNCTIONAL CilANNEL 8 TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALI BRATION 5
d 1.
Low, Level 2 (B21-UT-N024A-2,B-2 and NA(a)
NA R(b)
B21-LT-N0?5A-2,B-2)
(B21-LTH-N024A-2,B-2 and D
SA SA l
B21-LTH-N025A-2,B-2) 2.
Reactor Vessel Pressure - liigh NA M
R (B21-PS-N045A, B, C, D)
M Y
![(a)
The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is*not required.
n k(b) Transmitters are exempted from the monthly channel calibration.
S
=
0
'(BSEP-2-100)
TABLE 4.3.7.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ti N
CHANNEL N
CHANNEL FUNCTIONAL CHANNEL I FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK-TEST CALIBRATION G4 a.
Low, Level 2 (B21-LT-NO31A,B,C,D)
NA(a)
NA' R(b)
(B21-LTM-NO31A-1,B-1,C-1,D-1)
D SA SA l
b.
Reactor Vessel Water Level - High
( B21-LT-N017A-2,C-2 )
NA(a)
NA R(b) l (B21-LTM-N017A-2,C-2)
D SA SA c.
Condensate Storage Tank Level - Low
{
(E51-LSL-4463, E51-LSL-4464)
NA ~
M Q
Y'
- S (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.
{i 8
8-B, To Serial: NLS-87-023
" Technical Justification for Changing the Rosemount Analog Trip Unit System Technical Specification Test Interval" l
(5124 BAT /bmc)