ML20215J995
| ML20215J995 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/06/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20215J998 | List: |
| References | |
| NPF-11-A-050, NPF-18-A-033 NUDOCS 8705110020 | |
| Download: ML20215J995 (18) | |
Text
-
o UNITED STATES
'g y )'
g NUCLEAR REGULATORY COMMISSION
-E WASHINGTON, D. C. 20555 k.%
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.50 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 23, 1986, as supplemented by letters dated November 5, 1986, and March 6, 1987, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Enviror. mental Protection Plan The Technical Specifications contained in Apperdix A, as revised through i
Amendment No.50, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8705110020 870506 j
PDR ADOCK 0500 3
i P
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T 4...
9,..
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- I 3.
This amendment is effective upon date of issuance.
FOR THE tiUCLEAR REGULATORY COMt11SSION l
,n
/w p
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V, and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: May 6, 1987 l
4 4
i
,7-.__+__,-y_,.
~e
,,,.., -,. +
n'A is Ma.,
yf ENCLOSURE TO LICENSE AMENDMENT h0.50 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-18 3/4 3-18 l
3/4 3-20 3/4 3-20 3/4 6-26 3/4 6-26 B3/4 3-7 83/4 3-7
- l WS.
7 NOTE. SC ALE IN INCHES ASCVE VESSEL ZERO WATER LEVEL NOMENCLATURE SETPOINT HEIGHT ABOVE INSTRUMEN T LEVEL NO.
VESSEL ZERO ON.)
READING 800 (8) 583 55.5 (7) 568 40.5 (4)
$$9 31.5 750 (3) 540 12.5 VESSEL
- 7 45 Ft. ANGE ~
(2) 477.5
-50 700 (1) 398.5 129 (0) 324 203 650 M AIN STE AM CLOSE HPCS INJ. VLV.
- 644 -
LINE SHUT COWN RCIC 600 WlOE NARROW 587.5 RANGE HANGE
$83 (8)
I (8) " 55.5 568 (7) " 559 (4)
(7) - 40.5 Mi ALARM 550
- 540 (3)
(4) = 3 8.5 LO AL ARM (3) 12.5 RE ACTCR SCR AM 80TTOM OF STEAM- - 527.5 ZERO
-0
-0 O
INSTRU.
ORYER SKIRT FEED 500 493.25 3
WATER pmay g (2) 50 l
7j$
9
~
(2 l
450 FUEL TRIP RECIRC PUMPS ZONE INITI ATE RCIC. MPCS.
l NE "I'1 400
- 3s8.5 (1)
(1)2 129 388
- TAF
~
3o d
CONTRIBUTE TO AOS.
START DIESEL,
CLOSE MSiv'S 300 -
A CTIVE FUEL 2!0 if 216
= 216
- S AF BAF 311 200 RECIRC q
RE CIRC
- 181 - 01 ARGE E
SUCTION - I f 2.5 -
NOZZLE 150 100 50 0-REACTOR VESSEL WATER LEVEL BASES FIGURE B 3/4 3-1 LA SALLE - UNIT 1 8 3/4 3-7 LA SALLE - UNIT 1 Amendment No.50
]
t jV:#
TABLE 3.3.2-1 v'
b ISOLATION ACTUATION INSTRUMENTATION
$p VALVE GROUPS MINIMUM OPERABLE APPLICABLE OPERATED BY CHANNELS PER OPERATIONAL TRIP FUNCTION SIGNAL (a)
TRIP SYSTEM (b)
CONDITION ACTION E
tj A.
AUTOMATIC INITIATION H
1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level (1) Low, Level 3 7
2 1,2,3 20 (2) Low Low, level 2 2, 3 2
1,2,3 20 (3) Low Low Low, Level 1 1, 10 2
1,2,3 20 b.
Drywell Pressure - High 2, 7, 10 2
1,2,3 20 c.
Radiation - High 1
2 1,2,3 21 R
3 2
1,2,3 22 2)
Pressure - Low 1
2 1
23 y
3)
Flow - High 1
2/line(d) 1,2,3 21 d.
Main Steam Line Tunnel Temperature - High 1
2 1,2,3 21 e.
Main Steam Line Tunnel II), 2(I), 3(i) 21 ATemperature - High 1
2 I
f.
Condenser Vacuum - Low 1
2 1, 2*, 3*
21 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Vent Exhaust Plenum Radiation - High 4(c)(e) 2 1, 2, 3 and **
24 b.
Drywell Pressure - High 4(c)(e) 2 1,2,3 24 EI c.
Reactor Vessel Water k
Level - Low Low, Level 2 4(c)(e) 2 1, 2, 3, and 24 a
5 d.
Fuel Pool Vent Exhaust E
Radiation - High 4(c)(e) 2 1, 2, 3, and,, 24 l
g:
5
i TABLE 3.3.2-2 jf?*
5; ISOLATION ACTUATION INSTRUMENTATION SETPOINTS Sk' E
ALLOWABLE f:
TRIP FUNCTION TRIP SETPOINT VALUE m
I A.
AUTOMATIC INITIATION i
EE 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
> 12.5 inches *
> 11.0 inches
- 2)
Low Low, Level 2 5 -50 inches
- 5 -57 inches
- 3)
Low Low Low, Level 1 I -129 inches
- I -136 inches
- l b.
Drywell Pressure - High 51.69psig 51.89psig c.
Radiation - High 1 3.0 x full power background 1 3.6 x full background 2)
Pressure - Lcw 3)
Flow - High
_ > 854 psig
> 834 psig 4
d.
Main Stcam Line Tunnel
-< 111 psid
-< 116 psid 30 e.
Main Steam Line Tunnel
-< 140"F
-< 146*F Temperature - High u,
A Temperature - High
< 36*F
< 42"F u.
4 f.
Condenser Vacuum - Low I 7 inches Hg vacuum 5 5;5 inches Hg vacuum m
2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Vent Exhaust Plenum Radiation - High
=< 10 mr/hr
< 15 mr/hr b.
Drywell Pressure - High
{1.69psig
{1.89psig c.
Reactor Vessel Water i
Level Low Low, Level 2
-> -50 inches *
-> -57 inches
- d.
Fuel Pool Vent Exhaust Radiation - High 1 10 mr/hr 115 mr/hr 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION J
a.
A Flow - High 7
5 0 gpm 5 87.5 gpm b.
Heat Exchanger Area Temperature c.
Heat Exchanger Area Ventilation
-< 181*F
-< 187 F jF
- High AT - High
< 85*F
< 91*F-E d.
SLCS Initiation HA NA in e.
. Low Low, level 2
> ~50 inches
- it -57 inches
- 1.
1 df
n
't
.1l N.,,-
TAfA.E 3. 3. 2-3 1
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
A.
AUTOMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION i
a.
Low, Level 3 NA 2)
Low Low, Level 2 5 13(3) 3)
Low Low Low, Level 1 1 1.0*/1 13(3),,
b.
Drywell Pressure - High 1 13(a)
' c.
Radiation - High(b)
< 1.0*/< 13(a)**
52.0*/713fa,,
2)
Pressure - Low 3)
F1ow - High.
50.5*/513 d.
Main Steam Line Tunnel Temperature - High NA e.
Condenser Vacuum - Low NA f.
Main Steam Line Tunnel a Temperature - High NA 2.
SECCA 0ARY CONTAINMENT ISOLATION Reactor Buildinggnt Exhaust Plenum
< 13(a) a.
Radiation - High b.
Drywell Pressure - High 513 ReactorVesselWaterLevel-Low, Level (g) 1 13(3) c.
d.
Fuel Pool Vent Exhaust Radiation - High 1 13 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION IFlow-High s 13(a)##
a.
b.
Heat Exchanger Area Temperature - High NA c.
Heat Exchanger Area Ventilation AT-High NA d.
SLCS Initiation NA e.
Reactor Vessel Water Level - Low Low, Level 2 1 13(a) 4.
REn: TOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High
< 13(a)###
b.
RCIC Steam Supply Pressure - Low 513(a) c.
RCIC Turbine Exhaust Diaphragm Pressure - High NA d.
RCIC Equipment Room Temperature - High NA e.
RCIC Steam Line Tunnel Temperature - High NA f.
RCIC Steam Line Tunnel a Temperature - High NA g.
Drywell Pressure - High NA h.
RCIC Equipment Room a Temperature - High NA 5.
LRHR SYSTEM STEAM CONDENSING MODE ISOLATICN a.
RHR Equipment Area a Temperature - High NA b.
RHR Area Cooler Temperature - High NA c.
RHR Heat Exchanger Steam Supply Flow High NA LA SALLE - UNIT 1 3/4 3-18 Amendment No.~50
l
?
TABLE 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION _Silri[ff@$ ICE REQUIREMENTS 7"
E r-C94hNEL OPERATIONAL i*
CHANNEL Fin!CTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED m
A.
AUTOMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION 5
a.
Low, Level 3 NA M
R 1,2,3 2)
Low Low, Level 2 NA M
R 1,2,3 3)
Low Low Low, Level 1 NA M
R 1,2,3 l
b.
Drywell Pressure - Hi h NA M
Q 1,2,3 0
c.
Radiation - High S
M R
1,2,3 2)
Pressure - Low NA M
Q 1
3)
Flow - High NA M
R 1,2,3 d.
Main Steam Line Tunnel Temperature - High NA M
R 1,2,3 u>
e.
Condenser Vacuum - Low NA M
Q 1, 2*, 3*
2 f.
Main Steam Line Tunnel A Temperature - High NA M
R 1,2,3 w
E$
2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Vent Exhaust Plenum Radiation - High S
M R
1, 2, 3 and **
b.
Drywell Pressure - High NA M
Q 1,2,3 c.
Reactor Vessel Water Level - Low Low, Level 2 NA M
R 1, 2, 3, and d.
Fuel Pool Vent Exhaust Radiation - High S
M R
1, 2, 3 and **
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High S
M R
1,2,3 g
o b.
Heat Exchanger Area E.
Temperature - High NA M
Q 1,2,3 R
c.
Heat Exchanger Area 5
. Ventilation AT - High NA M
Q 1,2,3 z
d.
SLCS Initiation NA R
NA 1,2,3 P
e.
Reactor Vessel Water g
Level - Low Low, Level 2 NA M
R 1,2,3
m _
?
TABLE 3.6.3-1 (Continued)
E PRIMARY CONTAINMENT ISOLATION VALVES N.'
$l-MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds)
Eq Automatic Isolation Valves (Continued) i 11.
Containment Monitoring Valves 2
15 1CM017A,B 1CM018A,B ICM019A,B ICM020A,B ICM021B(h)
ICM022A(("h)
)
ICM025A(h)
ICM026B w'g ICM027 ICM028 4
1CM029 t
m ICM030 ICM031 ICM032 1CM033 1CM034 12.
Drywell Pneumatic Valves IIN001A and B 10
< 30 11N017 10 7 22 11N074 10 7 22 4
IIN075 10 7 22 IIN031 2
75
-13.
RHR Shutdown Cooling Mode Valves 6
g IE12-F008.
1 40
=
IE12-F009
< 40 7
[
_ 90 m
1E12-F053 A and B
< 29 1E12-F099A and B(9)(I) 1 30 g:
~s UNITED STATES g
gr [ g NUCLEAR REGULATORY COMMISSION f.j WASHINGTON, D. C. 20555 i
k...../
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.33 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 23, 1986, as supplemented by letters dated November 6, 1986, and March 6, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the previsions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, er.d the Envirormental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
-2 3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
((/
,. /&nf
/f Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V, and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance:
May 6,1987
b,.,
/
ENC,LOSURE TO LICENSE AMENDMENT f;0.33 C
FACILITY OPERATING LICENSE NO. NPF-18 DOCKET N0. 50-374 Replace the following pages of'the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 3-11 l
3/4 3-11 3/4 3-15 3/4 3-15 t
3/4 3-18 3/4 3-18 l
3/4 3-20 3/4 3-20 3/4 6-29 3/4 6-29 B3/4 3-7 E3/4 3-7 i
i t
i i
.hs M *,
J NOTE: SC ALE 6N aNCHES ABOVE VESSEL ZERO WATER LEVEL NOMENCLATURE SETPOINT HEIGHT ABOVE INSTRUMENT LEVEL NO.
VESSEL ZERO (IN.)
READING (8) 583 55.5 (7) 568 40.5 559 3 f.5 750 (3) 540 12.5 VESSEL
" I'3 ~"~ FL ANGE ~
(2) 477.5 50 700 (II 398 5
- 848 -
LINE SMUT DOWN ACIC 600 W10E NARROW 587.5 RANGE RANGE 583 (8)
I (810 55.5 568 (7) 33a
_559 (4)
(7) - 4 0.5 Mi AL ARu
- 540 (3)
(4) - 31.5 LO AL ARM (3) 12.5 RE ACTOR SCR AW
" BOTTOM OF STEAM- - $ 2 7.5 ZERO
-0
-0 O
INSTRU.
DRYER SKIRT FEED 500 I
- 493.25 l
WATER p Ay g (2) 50 l
~ 8I 47 2
450 l
FUEL Trip RECIRC PUWPS g
ZONE INITIATE RCIC. MPCS.
NE.
- 811 400 30 6
CONTRIBUTE TO ADS.
START DIESEL.
300 CLOSE WSIV'S A CTIVE FUEL 250 -
U 216
=. 216
- SAF e4F 3i, 200 RECIRC
- 181 -Di ARGE SUCTION - t 72. 5 -
NOZZLE 150 100 30 0-REACTOR VESSEL WATER LEVEL j
BASES FIGURE B 3/4 3-1 LA SALLE - UNIT 2 83/43-7 LA SALLE - UNIT 2 Amendment No. 33
TABLE 3.3.2-1 I
\\
r-g ISOLATION ACTUATION INSTRUMENTATION r-E VALVE GROUPS MINIMUM OPERABLE APPLICABLE OPERATED BY CHANNELS PER OPERATICNAL g
TRIP FUNCTION SIGNAL (a)
TRIP SYSTEM (b)
CONDITION ACTION Z
A.
AUTOMATIC INITIATION y
1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level (1) Low, Level 3 7
2
.1, 2, 3 20 (2) Low Low, Level 2 2, 3 2
1,2,3 20 (3) Low Low Low, Level 1 1, 10 2
1,2,3 20 b.
Drywell Pressure - High 2, 7, 10 2
l',
2, 3 20 c.
1)
Radiation - High 1
2 1,2,3 21 3
2 1,2,3
.22 2)
Pressure - Lov 1
2 1
23 ca h
3)
Flow - High 1
2/line(d).
1, 2, 3 21 d.
Main Steam Line Tunnel Temperature - High 1
2' 1, 2,.3 21 e.
Main Steam Line Tunnel A Temperature High 1
2 1(i), 2(i), 3(i) 21 f.
Condenser Vacuum Low 1
2 1, 2*, 3*
21 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Vent Exhaust Plenum Radiation - High 4(c)(e) 2 1, 2, 3 and **
24 b.
Drywell Pressure - High 4(c)(e) 2 1,2,3 24 m
c.
Reactor Vessel Water l
Level - Low Low, Level 2 4(c)(e) 2 1, 2, 3, and 24 5
d.
Fuel Pool Vent Exhaust Radiation - High.
4(c)(e) 2 1, 2, 3, and ** 24' O
Y TABLE 3.3.2-2 f
9'
\\'
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS u,
i F
ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE h
A.
AUTOMATIC INITIATION h '
1.
PRIMARY CONTAINMENT ISOLATION N
a.
Reactor Vessel. Water Level 1)
Low, Level 3
> 12.5 inches *
> 11.0 inches
- 2)
Low Low, Level 2
[-50 inches *
[-57 inches
- 3)
Low Low Low, Level 1
> -129 inches *
> -136 inches
- l b.
Drywell Pressure - High 5 1.69 psig 5 1.89 psig-c.
Radiation - High 5 3.0 x full power background 5 3.6 x full background 1
2)
Pressure - Low
> 854 psig
> 834 psig 3)
Flow - High 5 111 psid 5 116 psid d.
Main Steam Line Tunnel u,
}
Temperature - High 5 140 F
< 146*F e.
Main Steam Line Tunnel u,
j 4
A Temperature - High 5 36 F 5 42 F c'
f.
Condenser Vacuum - Low
> 7 inches Hg vacuum
> 5.5 inches Hg vacuum 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Vent Exhaust flenum Radiation - High 5 10 mr/h 5 15 mr/h b.
Drywell Pressure - High 5 1.69 psig 5 1.89 psig j
l c.
. Reactor Vessel Water Level - Low Low, Level 2
> -50 inches *
> -57 inches
- I d.
Fuel Pool Vent Exhaust Radiation - High 5 10 mr/h 5 15 mr/h
-g.
3.
REACTOR WATER CLEANUP SYSTEM. ISOLATION j
R a.
AFlow - High 5 70 gpm 5 87.5 gpm p
g b.
Heat Exchanger Area Temperature g
- High
< 131 F
. < 187*F c.
Heat Exchanger Area Ventilation
.j z
AT - High 5 85 5 91*F l
O u>
d.
SLCS Initiation' N.A.
N.A.
e.
Reactor Vessel Water. Level -
Low Low, Level 2
> -50 inches *
> -57 inches
- 1
..p.
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION-RESPONSE TIME (Seconds)#
A.
AUTOMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel t!ater Level 1)
Low, Level 3 N.A 2)
Low Low, Level 2 113(,)
51.g513.0(a)**
3)
_ Low Low Low, Level 1 b.
Drywell Pressure - High 113 c.
Radiation - High(b)
<1.0*/<13(a)**
72.0*/713((a)a, 2)
Pressure - Low 70.5*/713 a)*a 3)
Flow - High d.
Main Steam Line Tunnel Temperature - High N.A.
~
e.
Condenser Vacuum - Low N.A.
f.
Main Steam Line Tunnel A Temperature - High N.A.
2.
SECONDARY CONTAINMENT ISOLATION Reactor Buildinggnt Exhaust Plenum
<13(3) a.
Radiation - High b.
Drywell Pressure - High 513f ReactorVesselWaterLevel-Low,Levely) 513(a)
<13 c.
Fuel Pool Vent Exhaust Radiation - High d.
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 113(a)##
b.
Heat Exchanger Area Temperature - High N.A.
c.
Heat Exchanger Area Ventilation AT-High N.A.
d.
SLCS Initiation N.A e.
Reactor Vessel Water Level - Low Low, Level 2 113(a) 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High
<13(a)###
b.
RCIC Steam Supply Pressure - Low 513(^)
c.
RCIC Turbine Exhaust Diaphragm Pressure - High N. A.-
d.
RCIC Equipment Room Temperature - High N.A.
e.
RCIC Steam Line Tennel Temperature - High N.A.
f.
RCIC Steam Line Tunnel ATemperature - High N.A.
g.
Drywell Pressure - High N.A.
h.
RCIC Equipment Room A Temperature - High N.A.
5.
RHR SYSTEM STEAM CONDENSING MODE ISOLATION a.
RHR Equipment Area ATemperature - High N.A.
b.
RHR Area Cooler Temperature - High N.A.
c.
RHR Heat Exchanger Steam Supply Flow High N.A.
LA SALLE - UNIT 2 3/4 3-18 Amendment No. 33
TABLE 4.3.2.1-1
(.
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
~
h CHANNEL OPERATIONAL m
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED A.
AUTOMATIC INITIATION
[
1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3 NA M
R 1, 2, 3 2)
Low Low, Level 2 NA M
R 1,2,3 3)
Low Low Low, Level 1 NA M
R 1,2,3 l
b.
Drywell Pressure - High NA M
Q 1,2,3 c.
Radiation - High S
M R
1,2,3 2)
. Pressure - Low NA M
Q 1
3)
Flow - High NA M
R 1,2,3 m
N d.
Main Steam Line Tunnel
[
Temperature - High NA M
R 1,2,3 4
e.
Condenser Vacuum - Low NA M
Q 1, 2*, 3*
o f.
Main Steam Line Tunnel A Temperature - High NA M
R 1,2,3 2.
SECONDARY CONTAINMENT ISOLATION i
a.
Reactor Building Vent Exhaust Plenum Radiation - High S
M R
1, 2, 3 and **
b.
Drywell Pressure - High NA M
Q 1,2,3 c.
Reactor Vessel Water Level - Low Low, Level 2 NA M
R 1, 2, 3, and,
d.
Fuel Pool Vent Exhaust Radiation - High S
M R
1, 2, 3 and **
3 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION k
a.
A Flow - High S
M R
1,2,3 g
b.
Heat Exchanger Area g
Temperature - High NA M
Q 1,2,3 c.
Heat Exchanger Area z
,o Ventilation AT - High NA M
Q 1,2,3 d.
SLCS Initiation NA R
NA 1,2,3 m
w e.
Reactor Vessel Water Level - Low Low, Level 2 NA M
R 1,2,3 1
7 TABLE 3.6.3-1-(Continued)
I a
5 PRIMARY CONTAINMENT ISOLATION VALVES
$l-MAXIMUM m
ISOLATION TIME VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds)
Automatic Isolation Valves (Continued) 11.
Containment Monitoring Valves 2
- 5 2CH017A,8 2CM018A,B 2CM019A,B 2CM020A,B 2CM021B((h) 2CM022A(h) 2CM025A(h) h)
2CM026B m}
2CM027 2CM028 4
2CM029 e
2CM030 2CM031 2CM032 2CM033 2CM034 12.
Orywell Pneumatic Valves 2IN001A and B 10
< 30 2IN017 10 7 22 2IN074 10 7 22 2IN075 10 E 22 2IN031 2
7 13.
RHR Shutdown Cooling Mode Valves 6
- 5
[
=
< 40 2E12-F009 7 40 E
2E12-F023 7 90 2E12-F053 A and B E 29 2E12-F099A and B(9)(I) 30 e
.