ML20215N910

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Proposed Tech Specs,Lowering MSIV Closure Signal from Reactor Pressure Vessel (RPV) Level 2 to RPV Level 1
ML20215N910
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 10/23/1986
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20215N895 List:
References
NUDOCS 8611100060
Download: ML20215N910 (15)
v • d • e


Text

_ _ - ._ __

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I TABLE 3.3.2-1 Y

u, ISOLATION ACTUATION INSTRUMENTATION l  ? VALVE GROUPS MINIMUM OPERABLE APPLICABLE j Fi CHANNELS PER OPERATIONAL OPERATED BY

' e TRIP SYSTEM (b) CONDITION ACTION c TRIP FUNCTION SIGNAL (a) ij -

z 4 1

  • A. AUTOMATIC INITIATION e ,
1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Level 1,2,3 20

' (1) Low, Level 3 7 2 J

2 1,2,3 20

, l

- - > - (2) Low Low, Level 2 2, 3 2 1,2,3 20 I b. ' Drywell Pressure - High 2,7,/o

c. Main Steam Line 1, 2, 3 21

' Radiation - High 1 2

1) 1,2,3 22

' 3 2

, w 23 Pressure - Low 1 2 1

) 2) 21 w 3) Flow - High 1 2/1fne(d) 1, 2, 3 i! U d. Main Steam Line Tunnel 2 1,2,3 21 Temperature - High 1 Main Steam Line Tunnel l

e. I II) ,2 II) ,3 III 21 i A Temperature - High 1 2-l 2 1, 2* , 3* 21

! f. Condenser Vacuum - Low 1 l

j 2. SECONDARY CONTAINMENT ISOLATION i a. Reactor Building Vent Exhaust I#)I*) 2 1, 2, 3 and ** 24 Plenum Radiation - High 4 2 1,2,3 24

b. Drywe11 Pressure - High 4(c)(e)

I {

a

c. Reactor Vessel Water Level - Low Low, Level 2 4 ICII*) 2 1, 2, 3, and 24

&. d. Fuel Pool Vent Exhaust 2 1, 2, 3, and ** 24 .

l Radiation - High 4(c)(e) j ,,

4 E.

y g1100060861023 '

p ADOCK 05000373 PDR i

l l

J

IABLE 3.3.2-2 4

r-2' ISOLATION ACIUA110N INSTRUMENTATION SETPOINTS '

ALLOWABLE

$ IRIP SE1POINI VALUE k 1 RIP FUNCIl0N

' A. AU10MATIC INIIIAfl0N

1. PRIMARY CONTAINMENT ISOLA 110N
a. Reactor Vessel Water Level > 11.0 inches
  • g low, Level 3 > 12.5 inches
  • 57 inches
  • 1) 2 tow Low, level 2 50 inches *

[l.69psig [l.89psig 7 m )ywell Dr Pressure - High b -

b5ul b c. Main Steam Line i 3.6 x full background-Radiation - liigh 13.0 x full power background 1 834 psig

- 1) 3 854 psig

2) Pressure . Low i 116 psid Flow - High 1 111 psid 3)
d. Main Steam Line Tunnel i 146*F Temperature - High 1 140*F l
e. Main Steam Line Tunnel < 42*F t'

A lemperature - liigh < 36*F I 5.5 inches Hg vacuum

a. Reactor Building Vent Exhaust < 15 mr/hr

< 10 mr/hr ~

Plenum Radiation - liigh 1 1.89 psig Drywell Pressure - liigh 5 1.69 psig b.

c. Reactor Vessel Water 1 -57 inches
  • Level - Low Low, Level 2 1 -50 inches *
d. fuel Pool Vent Exhaust i 15 mr/hr Radiation - liigh 1 10 mr/hr
3. REAC10R WAIER CLEANUP SYSTEM ISOLATION 3 87.5 gpa 5 70 gpm y a. Aflow - liigh lleat Exchanger Area temperature y h. i 187*F

- liigh $ 181*f g 9 Ileat Exchanger Area Ventilation < 91*F g c. < 85"f

" AI ' liigh RA NA g it. SlCS l itiation

'l -57 inches

  • e
e. Reactor Vessel Water level -

$ low. tow, level 2 3 -50 inches

  • 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 Water Level
1) Low, Level 3 NA
2) Low Low, Level 2 <1 * ,,13(a).,

[5cM h/ b. Drywell Pressure - High -

13 G' c. Main Steam Line Radiation - High(b) < 1.0*/< 13 C

,),,

1) l

-2) Pressure - Low I 2.0*/7 13((a),,

3) Flow - High 7 0.5*/7 13 a)a*
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 .
a. ReactorBuildinggntExhaustPlenum < 13(,)

Radiation 'High

b. Drywell Pressure - High {13
c. ReactorVesselWaterLevel-Low, Level (g) < 13
d. Fuel Pool Vent Exhaust Radiation - High 513(a)
3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. 'a Flow - High < 13(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 _ 13(a)

(

l 4. ' REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line Flow - High < 13(a)###
b. RCIC Steam Supply Pressure - Low 7 13(a)
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 FUNCTIONAL CHANNEL CONDITIONS FOR WHICH P CHANNEL CHECK TEST CALIBRATION SURVEILLANCE REQUIRE 0 TRIP FUNCTION 7

g A. AUTOMATIC INITIATION Z l. PRIMARY CONTAINMENT ISOLATION

" Reactor Vessel Water level

a. R 1, 2, 3 Low, Level 3 NA M

,- 1) R 1, 2, 3 Low Low, level 2 NA M 2)

/ I

b. Drywell Pressure - High NA M Q 1, 2, 3

. <P-j / c. Main Steam Line Radiation - High 5 H R 1, 2, 3

1) M Q l
2) Pressure - Low NA M R 1, 2, 3 l
3) Flow - High NA
d. Main Steam Line Tunnel R 1, 2, 3 Temperature - High NA M w

NA M Q 1, 2*, 3*

D e. Condenser Vacuum - Low w f. Main Steam Line Tunnel R 1, 2, 3 A Temperature - High NA M

, 2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent Exhaust 1, 2, 3 and **

Plenum Radiation - High S M R M 1, 2, 3

b. Drywell Pressure - High NA Q g
c. Reactor Vessel Water R 1, 2, 3, and l Level - Low Low, Level 2 NA M
d. Fuel Pool Vent Exhaust R 1, 2, 3 and **

Radiation - High S M

3. REACTOR WATER CLEANUP SYSTEM ISOLATICN j

M R 1, 2, 3

a. A Flow - High S EI b. Heat Exchanger Area 1, 2, 3 Temperature - High NA M Q E

& c. . Heat Exchanger Area- 1, 2, 3

@ Ventilation AT - High NA M Q 1, 2, 3 R NA

d. SLCS Initiation NA 5 e. Reactor Vessel Water R 1, 2, 3 1

Level - Low Low, Level 2 NA M l 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
3) Low Low Low, Level 1 5 1.0*/ $13(a)**

Insert D page 3/4 3-20

3) Low Low Low, Level 1 NA M R 1,2,3 i

2292K

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v. .

i TABLE 3.6.3-1 (Continued)

! 9 .

j .g . PRIMARY CONTAINMENT ISOLATION VALVES r-m MAXIMUM ISOLATION TIME i e VALVE GROUP I ") (Seconds) l g . VALVE FUNCTION AND NUMBER Automatic Isolation Valves (Continued)

- 11. Containment Monitoring Valves 2 <5 i ICM017A,B

, ICM018A,B ICM019A,B ICM020A,B i

I ICM0218((h)

ICM022A(h) l R ICH025A(h) 1CM026B h)

~

  • ICM027 j i ICM028 j M 1CM029 1CM030 ICM031 3CM032 1CM033 1CM034 ,j
12. Drywell Pneumatic Valves (2) 11N001A and B /o < 30 t IIN017 #0 7 22 11N074 joU 522 2

11N075 < 22

  1. 75 i IIN031 -

[ 13. RHR Shutdown Cooling Mode Valves 6 t s 1E12-F008 < 40 l I E 1E12-F009 7 40 I i S 1E12-F023 7 90

  1. 7 29 1E12-F053 A and'B 1E12-F099A and B I9)II) .

-< 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

i

\

1

' TABLE 3.3.2-1 E

g ISOLATION ACTUATION INSTRUMENTATION f /

\

F m VALVE GROUPS MINIMUM OPERABLE APPLICABLE
  • OPERATED BY CHANNELS PER OPERATIONAL SIGNAL (a) TRIP SYSTEM (b) CONDITION ACTION
g TRIP FUNCTION

.  % AUTOMATIC INITIATION u A.

I

1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Level 20 (1) Low, Level 3 7 2 1, 2, 3 (2) Low Low, Level 2 2, 3 2 1,2,3 20 g

? 20

/ * b'. Drywell Pressure - High 2, 7, to 2 1,2,3

?

c. Main Steam Line Radiation - High 1 2 1,2,3 21

,. 1) 1,2,3 22 3 2 2 1 23 i , 2) Pressure - Low 1 21

3) Flow - High 1 2/11ne(d) 1, 2, 3 j )

I <;> d. Main Steam Line Tunnel 21 Temperature - High 2 1,2,3 l p 1 i e. Main Steam Line Tunnel 1(1), 2(1), 3(1) 21 A Temperature - High 1 2 i

Condenser Vacuus - Low 'l 2 1, 2", 3* 21 f.

l

2. SECONDARY CONTAINHENT ISOLATION'
a. Reactor B'uilding Vent Exhaust Plenum Radiation - High 4(c)(e) 2 1, 2, 3 and ** 24 1,2,3 24
b. Drywell Pressure - High 4(c)(e) 2

) c. Reactor Vessel Water 1, 2, 3, and , 24 a

Level - Low Low, Level 2 4(c)(e) 2 l d. Fuel Pool Vent Exhaust 1, 2, 3, and ** 24 i Radiation - High 4(c)(e) 2 l

i I

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I TABLE 3.3.2-2 9 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

{

T ALLOWABLE VALUE l l-m TRIP SETPOINT

! TRIP FUNCTION l c: A. AUIDMATIC INITIATION 4 z y 1. PRIMARY CONTAINMENT ISOLATION i

i 32 a. Reactor Vessel Water Level > 12.5 inches * > 11.0 inches *

1) Low, Level 3 I -57 inches
  • l Low Low, Level 2 5 -50 inches
  • 31.89psig \
2) 31.69psig j 'b. Drywell Pressure - High irait c. Main Steam Line ,

5 3.0 x full power background 1 3.6 x full background i

1) Radiation - High 3 834 psig J
2) Pressure - Low 1 854 psig 5 116 psid
3) Flow - High 5 111 psid
d. Main Steam Line funnel <.146*F Temperature - High 5 140*F u,
e. Main Steam Line Tunnel a Temperature - High 5 36*F

$ 42*F

> 5.5 inches Hg vacuum l u, > 7 inches Ng vacuum j,

ui

f. Condenser Vacuum - Low

- 2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent ~ Exhaust < 15 mr/h 4

Plenum Radiation - High < 10 mr/h 31.89psig l

b. Drywell Pressure - High 31.69psig
c. Reactor Vessel Water 2 -57 inches
  • i Level - Low Low, Level 2 1 -50 inches
  • i j d. Fuel Pool Vent Exhaust 5 15 mr/h 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

~ l 'I i

!s c.

- High Heat Exchanger Area Ventilation

-< 181*F

$ 91*F i

AT - High $ 85* N.A.

2 N.A.

o d. SLCS Initiation

e. Reactor Vessel Water Level - > -57 inches
  • y Low Low, Level 2 2 -50 inches
  • TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME RESPONSE TIME (Seconds)#

TRIP FUNCTION A. AUTOMATIC INITIATION

1. P11 MARY CONTAINMENT ISOLATION Q

. a. Reactor Vessel Water Level N.A. ,

1) Low, Level 3 Low Low, Level 2 < 1.
  • 13C "

m m 2) -

/W N / 1. Drywell Pressure - High O c. Main Steam Line

1) -Radiation - High(b)

<1.0*/<13(a)**

a),,

2) Pressure - Low 72.0*/713(C")s*

70.5*/713 O 3) Flow - High ~

Main Steam Line Tunnel Temperature - High R.A.

d. N.A.
e. Condenser Vacuum - Low N.A.
f. Main Steam Line Tunnel A Temperature - High
2. SECONOARY CONTAINMENT ISOLATION
a. ReactorBuilding(gntExhaustPlenum  ;)

Radiation - High <13(C

> b. Drywell Pressure - High- 713C ""))

c. ReactorVesselWaterLevel-Low, Level (f) 713(*)

~13

d. Fuel Pool Vent Exhaust Radiation - High 1
3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - High 113(*)"

Heat Exchanger Area Temperature - High N.A.

b. N.A.
c. Heat Exchanger Area Ventilation AT-High N.A ,
d. SLCS Initiation 113(,)
e. Reactor Vessel Water Level - Low Low, Level 2 I 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
  • ) #
a. RCIC Steam Line Flow - High <13(C 713 ")
b. RCIC. Steam Supply Pressure - Low RCIC Turbine Exhaust Diaphragm Pressure - High R.A.
c. N.A.

l d. RCIC Equipment Room Temperature - High i RCIC Steam Line Tunnel Temperature - High N.A.

e. N.A.

i

f. RCIC Steam Line Tunnel ATemperature - High N.A.

(

g. Drywell Pressure - High N.A. j ,,

'h. RCIC Equipment Room A Temperature - High

5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION RHR Equipment Area ATemperature - High N.A.
a. N.A.
b. RHR Area Cooler Temperature - High RHR Heat Exchanger Steam Supply Flow High N.A.

c.

3/4 3-18 Amendment No. 14 LA SALLE - UNIT 2 1

  • I TABLE 4.3.2.1-1 g

ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREMENTS g OPERATIONAL CHANNEL i

{ CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED

' ' CHECK TEST CALIBRATION TRIP FUNCTION A. AUTOMATIC INITIATION 3

I m 1. PRINARY CONTAlletENT ISOLATION

a. Reactor Vessel Water Level R 1, 2, 3 Low, Level 3 NA M
1) M R 1, 2, 3 'l
2) Low Low, Level 2 NA 1, 2, 3 j M Q

' b. Drywell Pressure - High NA I NMd@ c. Main Steam Line R 1, 2, 3 Radiation - High 5 M 4

1) M Q 1
2) Pressure - Low NA I

M R 1, 2, 3 l '*

3) Flow - High NA
d. Main Steam Line Tunnel R 1, 2, 3 Temperature - High NA M l R
  • NA M Q 1, 2*, 3" I e. Condenser Vacuun - Low i T f. Main Steam Line Tunnel M R 1, 2, 3 El A Temperature - High NA
2. SECONDARYCONTAI;94ENTISOLATION I a. Reactor Building Vent Exhaust 1, 2, 3 and **

Plenum Radiation - High 5 M R l M Q 1, 2, 3 l

b. Drywell Pressure - High NA Reactor Vessel Water 8
c. R 1, 2, 3, and l 'd Level - Low Low, Level 2 NA M
d. Fuel Pool Vent Exhaust R 1, 2, 3 and **

l Radiation - High S M

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

$ M R 1, 2, 3 s a. A Flow - High S 11 b. Heat Exchanger Area 1, 2, 3 Temperature - High NA M Q

" c. Heat Exchanger Area 1, 2, 3 Ventilation AT - High NA M Q E NA R HA 1, 2, 3

d. SLCS Initiation o e. Reactor Vessel Water R 1, 2, 3 g Level - Low Low, Level 2 NA M

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
3) Low Low Low, Level 1 g 1.0*/ $13(a)**

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 *I (Seconds)

Automatic Isolat' ion Valves (Continued)

11. Containment Monitoring Valves 2 < 5 2CM017A,8 2CM018A,8 2CM019A,8 2CM020A,8 '

2CM0218(h) 2CM022A(h) 1 g 2CM025A((h) 2CM0268 h)

+- 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 4

2IN074 3. o i 22 21N075 10 2 22

2INO31 .

1

  • 3 :i i

g 13. RHR Shutdown Cooling Mode Valves 6

, a 2E12-F008 < 40 2E12-F009 l

) h=

3 40

< 90 2E12-F023 l E+ 2E12-F053 A and 8 7 29 y 2E12-F099A and B I9)III h30 8

e

= .. - - . .

NOTE: SEALE als eseCMM A80vt VML 2W00 WAT8ft LEVEL 8eceaWuCLAfung.

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se m ="' **"' **"') -

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l 0-REACTOR VESSEL WATER LEVEL Bases Figure B 3/4 3-1 LA SALLE - UNIT 2

---.B_/4. - - .3-7 -.__-__

. ,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 i significant hazards consideration.

1 1

, 2292K I

l i

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