ML20215N910
| ML20215N910 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/23/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20215N895 | List: |
| References | |
| NUDOCS 8611100060 | |
| Download: ML20215N910 (15) | |
Text
_ _ -
e l.*
I TABLE 3.3.2-1 Y
ISOLATION ACTUATION INSTRUMENTATION u,
l
?
VALVE GROUPS MINIMUM OPERABLE APPLICABLE j
Fi OPERATED BY CHANNELS PER OPERATIONAL e
TRIP FUNCTION SIGNAL (a)
TRIP SYSTEM (b)
CONDITION ACTION ij cz 1
A.
AUTOMATIC INITIATION 4
e 1.
PRIMARY CONTAINMENT ISOLATION a.
(1) Low, Level 3 7
2 1,2,3 20
- - > - (2) Low Low, Level 2 2, 3 2
1,2,3 20 l
I
- b. ' Drywell Pressure - High 2,7,/o 2
1,2,3 20 c.
Radiation - High 1
2 1, 2, 3 21 3
2 1,2,3 22
)
2)
Pressure - Low 1
2 1
23 w
2/1fne(d) 1, 2, 3 21 3)
Flow - High 1
w i !
U d.
Main Steam Line Tunnel Temperature - High 1
2 1,2,3 21 l
e.
Main Steam Line Tunnel II)
II)
III A Temperature - High 1
2-I
,2
,3 21 i
l f.
Condenser Vacuum - Low 1
2 1, 2*, 3*
21 l
j 2.
SECONDARY CONTAINMENT ISOLATION i
a.
Reactor Building Vent Exhaust I#)I*)
2 1, 2, 3 and **
24 Plenum Radiation - High 4
b.
Drywe11 Pressure - High 4(c)(e) 2 1,2,3 24 c.
Reactor Vessel Water ICII*)
2 1, 2, 3, and 24
{
Level - Low Low, Level 2 4
I a
2 1, 2, 3, and ** 24 d.
Fuel Pool Vent Exhaust 4(c)(e) l Radiation - High j
E.
4 y
g1100060861023 ADOCK 05000373 p
PDR i
l l
J
IABLE 3.3.2-2 ISOLATION ACIUA110N INSTRUMENTATION SETPOINTS 4
r-2' ALLOWABLE VALUE IRIP SE1POINI k
1 RIP FUNCIl0N
' A.
AU10MATIC INIIIAfl0N 1.
PRIMARY CONTAINMENT ISOLA 110N
> 11.0 inches
> 12.5 inches
- 57 inches
- a.
m )ywell Pressure - High
[l.69psig
[l.89psig g
1) low, Level 3 50 inches
- 2 tow Low, level 2 b
Dr 7
b5ul b c.
Main Steam Line 13.0 x full power background i 3.6 x full background-1)
Radiation - liigh 1 834 psig 2)
Pressure
. Low 3 854 psig i 116 psid 3)
Flow - High 1 111 psid d.
Main Steam Line Tunnel i 146*F Temperature - High 1 140*F l
Main Steam Line Tunnel
< 42*F t'
e.
< 36*F I 5.5 inches Hg vacuum A lemperature - liigh I 7 inches lig vacuum Y
f.
Condenser Vacuus - Low G
2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Vent Exhaust
< 15 mr/hr
< 10 mr/hr a.
~ 1.89 psig Plenum Radiation - liigh 1
b.
Drywell Pressure - liigh 5 1.69 psig Reactor Vessel Water 1 -57 inches
- Level - Low Low, Level 2 1 -50 inches
- c.
d.
fuel Pool Vent Exhaust i 15 mr/hr Radiation - liigh 1 10 mr/hr REAC10R WAIER CLEANUP SYSTEM ISOLATION 3 87.5 gpa 3.
y a.
Aflow - liigh 5 70 gpm y
h.
lleat Exchanger Area temperature i 187*F
$ 181*f g
- liigh 9
Ileat Exchanger Area Ventilation
< 91*F g
c.
< 85"f RA AI ' liigh NA g
it.
SlCS l itiation Reactor Vessel Water level -
'l -57 inches
- e low. tow, level 2 3 -50 inches
- e.
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
A.
AUTOMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3 NA
,,13(a).,
2)
Low Low, Level 2
<1
[5cM h/
b.
Drywell Pressure - High 13 G'
c.
Radiation - High(b)
< 1.0*/< 13
,),,
C I 2.0*/7 13((a),,
l
-2)
Pressure - Low 7 0.5*/7 13 a)a*
3)
Flow - High d.
Main Steam Line Tunnel Temperature - High RA e.
Condenser Vacuum - Low NA f.
Main Steam Line Tunnel a Temperature - High NA 2.
SECONDARY CONTAINMENT ISOLATION ReactorBuildinggntExhaustPlenum
< 13(,)
a.
Radiation 'High b.
Drywell Pressure - High
{13
< 13 ReactorVesselWaterLevel-Low, Level (g) c.
d.
Fuel Pool Vent Exhaust Radiation - High 513(a) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION
< 13(a)##
a.
'a Flow - High b.
Heat Exchanger Area Temperature - High NA c.
Heat Exchanger Area Ventilation AT-High NA d.
SLCS Initiation NA
_ 13(a) e.
Reactor Vessel Water Level - Low Low, Level 2
(
l 4.
' REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
< 13(a)###
a.
RCIC Steam Line Flow - High 7 13(a) b.
RCIC Steam Supply Pressure - Low c.
RCIC Turbine Exhaust Diaphragm Pressure - High RA 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 b.
RCIC Equipment Room a Temperature - High NA 5.
RHR SYSTEM STEAM CONDENSING MODE ISOLATION a.
RHR Equipment Area a Temperature - High NA b.
RHR Area Cooler Temperature - High NA c.
RHR Heat Exchanger Steaa Supply Flow High NA-LA SALLE - UNIT 1 3/4 3-18 Amendment No. M
l TABLE 4.3.2.1-1 9
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL U
P CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH 7
TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRE 0 g A.
AUTOMATIC INITIATION Z
l.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3 NA M
R 1, 2, 3
/
2)
Low Low, level 2 NA M
R 1, 2, 3 I
b.
Drywell Pressure - High NA M
Q 1, 2, 3
. <P-j /
c.
Radiation - High 5
H R
1, 2, 3 2)
Pressure - Low NA M
Q l
3)
Flow - High NA M
R 1, 2, 3 l
d.
Main Steam Line Tunnel Temperature - High NA M
R 1, 2, 3 D
e.
Condenser Vacuum - Low NA M
Q 1, 2*, 3*
w w
f.
Main Steam Line Tunnel A Temperature - High NA M
R 1, 2, 3 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 g
Level - Low Low, Level 2 NA M
R 1, 2, 3, and l
c.
Reactor Vessel Water d.
Fuel Pool Vent Exhaust Radiation - High S
M R
1, 2, 3 and **
3.
REACTOR WATER CLEANUP SYSTEM ISOLATICN j
a.
A Flow - High S
M R
1, 2, 3 EI b.
Heat Exchanger Area E
Temperature - High NA M
Q 1, 2, 3 c.
. Heat Exchanger Area-Ventilation AT - High NA M
Q 1, 2, 3 d.
SLCS Initiation NA R
NA 1, 2, 3 5
e.
Reactor Vessel Water Level - Low Low, Level 2 NA M
R 1, 2, 3 l
1 0
Insert A page 3/4'3-11 (3) Low Low Low, Level 1 1,10 2
1,2,3 20 l
Insert B page 3/4 3-15
- 3) 1.wr Low Lw, Level 1 1-129 inches
- 1-136 inches
- Insert C page 3/4 3-18 5 1.0*/ 13(a)**
- 3) Low Low Low, Level 1 Insert D page 3/4 3-20
- 3) Low Low Low, Level 1 NA M
R 1,2,3 i
2292K
1 v.
TABLE 3.6.3-1 (Continued) i 9
PRIMARY CONTAINMENT ISOLATION VALVES j
.g r-MAXIMUM m
ISOLATION TIME i
e l
g
. VALVE FUNCTION AND NUMBER VALVE GROUP ")
(Seconds)
I Automatic Isolation Valves (Continued)
- 11. Containment Monitoring Valves 2
<5 i
ICM017A,B ICM018A,B ICM019A,B ICM020A,B i
ICM0218((h)
ICM022A(h)
I ICH025A(h) h)
l R
1CM026B
~
ICM027 j
i ICM028 j
M 1CM029 1CM030 ICM031 3CM032 1CM033 1CM034
,j
- 12. Drywell Pneumatic Valves (2) 11N001A and B
/o
< 30
- 0 7 22 t
IIN017 11N074 jo 522 U
2 11N075
< 22 IIN031 75 i
[
- 13. RHR Shutdown Cooling Mode Valves 6
t s
< 40 l
I E
1E12-F009 7 40 I
i S
1E12-F023 7 90 1E12-F053 A and'B 7 29 I9)II) 1E12-F099A and B
-< 30 4
~.
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Sases Figure B 3/4 3-1 j
REACTOR VESSEL WATER LEVEL LA SALLE - UNIT 1 3 3/4 3-7 L
i
\\
1 TABLE 3.3.2-1 E
ISOLATION ACTUATION INSTRUMENTATION f
g
/
F
\\
VALVE GROUPS MINIMUM OPERABLE APPLICABLE m
OPERATED BY CHANNELS PER OPERATIONAL g
TRIP FUNCTION SIGNAL (a)
TRIP SYSTEM (b)
CONDITION ACTION A.
AUTOMATIC INITIATION u
I 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 g
/ *
b'.
Drywell Pressure - High 2, 7, to 2
1,2,3 20
?
c.
Radiation - High 1
2 1,2,3 21 3
2 1,2,3 22 i
2)
Pressure - Low 1
2 1
23 2/11ne(d) 1, 2, 3 21 j
)
3)
Flow - High 1
I d.
Main Steam Line Tunnel l
p Temperature - High 1
2 1,2,3 21 i
e.
Main Steam Line Tunnel i
A Temperature - High 1
2 1(1), 2(1), 3(1) 21 l
f.
Condenser Vacuus - Low
'l 2
1, 2", 3*
21 2.
SECONDARY CONTAINHENT ISOLATION' Reactor 'uilding Vent Exhaust B
a.
Plenum Radiation - High 4(c)(e) 2 1, 2, 3 and **
24 b.
Drywell Pressure - High 4(c)(e) 2 1,2,3 24
)
c.
Reactor Vessel Water 1, 2, 3, and,
Level - Low Low, Level 2 4(c)(e) 2 24 a
l d.
Fuel Pool Vent Exhaust i
Radiation - High 4(c)(e) 2 1, 2, 3, and ** 24 l
i I
k
i l
I TABLE 3.3.2-2 9
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
{
T ALLOWABLE VALUE l
l-TRIP SETPOINT m
TRIP FUNCTION A.
AUIDMATIC INITIATION l
c:
4 zy 1.
PRIMARY CONTAINMENT ISOLATION i
> 11.0 inches
- 32 a.
i
> 12.5 inches
- l 1)
Low, Level 3 I -57 inches
- 2)
Low Low, Level 2 5 -50 inches
- j
'b.
Drywell Pressure - High 31.69psig 31.89psig
\\
1)
Radiation - High 5 3.0 x full power background 1 3.6 x full background i
irait c.
Pressure - Low 1 854 psig 3 834 psig J
3)
Flow - High 5 111 psid 5 116 psid d.
Main Steam Line funnel
<.146*F Temperature - High 5 140*F Main Steam Line Tunnel
$ 42*F u,
e.
a Temperature - High 5 36*F
> 5.5 inches Hg vacuum l
j, f.
Condenser Vacuum - Low
> 7 inches Ng vacuum u,
ui 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Vent ~ Exhaust
< 15 mr/h a.
Plenum Radiation - High
< 10 mr/h b.
Drywell Pressure - High 31.69psig 31.89psig 4
l i
c.
Reactor Vessel Water 2 -57 inches
- Level - Low Low, Level 2 1 -50 inches
- i d.
Fuel Pool Vent Exhaust 5 15 mr/h j
Radiation - High 1 10 ar/h 3.
REACTOR' WATER CLEANUP SYSTEM ISOLATION
$ 87.5 gpa a.
AFlow - High
$ 70 gpm ks b.
Heat Exchanger Area Temperature
< 187*F
- High
-< 181*F l 'I
~
i Heat Exchanger Area Ventilation
$ 91*F s
c.
AT - High
$ 85*
N.A.
i 2
N.A.
d.
SLCS Initiation o
> -57 inches
- e.
Low Low, Level 2 2 -50 inches
- y
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME RESPONSE TIME (Seconds)#
TRIP FUNCTION A.
AUTOMATIC INITIATION 1.
P11 MARY CONTAINMENT ISOLATION Q
N.A.
1)
Low, Level 3 C
< 1.
- 13 "
2)
Low Low, Level 2 m
m
/W N /
1.
Drywell Pressure - High 1)
-Radiation - High(b)
<1.0*/<13(a)**
c.
a),,
72.0*/713(C")s*
2)
Pressure - Low 70.5*/713 O
3)
Flow - High R.A.
~
d.
Main Steam Line Tunnel Temperature - High N.A.
e.
Condenser Vacuum - Low f.
Main Steam Line Tunnel A Temperature - High N.A.
2.
SECONOARY CONTAINMENT ISOLATION ReactorBuilding(gntExhaustPlenum
<13(C
- )
a.
Radiation - High b.
Drywell Pressure - High-713 ""))
C ReactorVesselWaterLevel-Low, Level (f) 713(*)
c.
~13 d.
Fuel Pool Vent Exhaust Radiation - High 1
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION 113(*)"
a.
A Flow - High N.A.
b.
Heat Exchanger Area Temperature - High N.A.
Heat Exchanger Area Ventilation AT-High c.
N.A Reactor Vessel Water Level - Low Low, Level 2 113(,)
d.
SLCS Initiation e.
I 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
- ) #
<13(C RCIC Steam Line Flow - High 713 ")
a.
b.
RCIC. Steam Supply Pressure - Low RCIC Turbine Exhaust Diaphragm Pressure - High R.A.
c.
N.A.
l d.
RCIC Equipment Room Temperature - High RCIC Steam Line Tunnel Temperature - High N.A.
i e.
f.
RCIC Steam Line Tunnel ATemperature - High N.A.
i N.A.
Drywell Pressure - High
(
g.
'h.
RCIC Equipment Room A Temperature - High N.A.
j,,
5.
RHR SYSTEM STEAM CONDENSING MODE ISOLATION N.A.
RHR Equipment Area ATemperature - High a.
b.
RHR Area Cooler Temperature - High N.A.
RHR Heat Exchanger Steam Supply Flow High N.A.
c.
LA SALLE - UNIT 2 3/4 3-18 Amendment No. 14 1
I TABLE 4.3.2.1-1 g
ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREMENTS g
CHANNEL OPERATIONAL
{
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH i
' CHECK TEST CALIBRATION SURVEILLANCE REQUIRED TRIP FUNCTION 3
A.
AUTOMATIC INITIATION m
1.
PRINARY CONTAlletENT ISOLATION I
a.
Low, Level 3 NA M
R 1, 2, 3 2)
Low Low, Level 2 NA M
R 1, 2, 3
'l b.
Drywell Pressure - High NA M
Q 1, 2, 3 j
I NMd@
c.
Radiation - High 5
M R
1, 2, 3 I
2)
Pressure - Low NA M
Q 1
4 3)
Flow - High NA M
R 1, 2, 3 l '*
d.
Main Steam Line Tunnel l
R Temperature - High NA M
R 1, 2, 3 I
e.
Condenser Vacuun - Low NA M
Q 1, 2*, 3" i
T f.
Main Steam Line Tunnel El A Temperature - High NA M
R 1, 2, 3 2.
SECONDARYCONTAI;94ENTISOLATION I
a.
Reactor Building Vent Exhaust Plenum Radiation - High 5
M R
1, 2, 3 and **
l b.
Drywell Pressure - High NA M
Q 1, 2, 3 l
8 Level - Low Low, Level 2 NA M
R 1, 2, 3, and l 'd c.
Reactor Vessel Water d.
Fuel Pool Vent Exhaust l
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 s
11 b.
Heat Exchanger Area Temperature - High NA M
Q 1, 2, 3 c.
Heat Exchanger Area E
Ventilation AT - High NA M
Q 1, 2, 3 d.
SLCS Initiation NA R
HA 1, 2, 3 o
e.
Reactor Vessel Water Level - Low Low, Level 2 NA M
R 1, 2, 3 g
l
Insert A page 3/4 3-11 (3) Low Low Low, Level 1 1,10 2
1,2,3 20 Insert B page 3/4 3-15
- 3) Low Low Low, Level 1 1-129 inches
- g-136 inches
- Insert c page 3/4 3-18 g 1.0*/ 13(a)**
- 3) Low Low Low, Level 1 Insert D page 3/4 3-20
- 3) Low Low Low, Level 1 NA M
R 1,2,3 t
l l
2292K i
l i
TABLE 3.6.3-1 (Continued) 9 PRIMARY CONTAINMENT ISOLATION VALVES 5
E MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUleER VALVE GROUP *I (Seconds)
I Automatic Isolat' ion Valves (Continued) 11.
Containment Monitoring Valves 2
- 5 2CM017A,8 2CM018A,8 2CM019A,8 2CM020A,8 2CM0218(h) 2CM022A(h) 2CM025A((h) h)
2CM0268 g
1
+-
2CH027 l
T 2CM028 j
g 2CM029 2CM030 2CM031 2CH032 i
2CM033 2CM034 i
- 12. Drywell Pneumatic Valves y
I 21N001A and 8
.30
< 30
{
21N017 10 2 22 2IN074
- 3. o i 22 4
21N075 10 2 22 1
2INO31 3 :i g
- 13. RHR Shutdown Cooling Mode Valves 6
i a
< 40 l
)
h 2E12-F009 3 40
=
< 90 l
E+
2E12-F053 A and 8 7 29 I9)III h30 y
2E12-F099A and B 8
e
=..
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l 0-REACTOR VESSEL WATER LEVEL Bases Figure B 3/4 3-1 LA SALLE - UNIT 2 3-7
---.B /4. - -. -.
.,e ATTAC19EENT C SIGNIFICANT HAZARDS CONSIDERATION commonwealth Edison has evaluated the proposed Technical Specifica-tion Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10CFR50.92, operation of LaSalle County Station Unit 1 and Unit 2 in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because it could reduce the probability of an accident previously evaluated (stuck open safety / relief valve)'and could reduce the potential consequences of certain events by allowing the main condenser to remain available for a' longer time. This allows more energy to be removed from the primary system and containment without adversly effecting offsite dose rates. This will also effect the repressurization rate after MSIV closure if the reactor vessel level does reach level 1.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because the MSIVs still close on reactor low level, therefore for any accident where core uncovery is postulated this change has minimal effect. No new accidents are postulated.
- 3) Involve a significant reduction in the margin of safety because by permitting more energy to be removed from the containment and dissipated in the condenser following a reactor scram, and reducing the challenges to SRVs, an increase in the margin of safety will be provided.
Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will i
not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the-proposed change does not constitute a significant hazards consideration.
i 1
1 2292K I
l i
J