ML20205A665

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Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal
ML20205A665
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 08/03/1988
From: Brinkman S, James Smith
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-2540D, NUDOCS 8810260061
Download: ML20205A665 (54)
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Text

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e .

STATION PROCEDUPE COVER SHEET

k. IDENTIFICATION i p Numberi E0P 25400 Rev. 3

Title:

FUNCTIONAL RECOVERY OF HEAT REMOVAL Prepared By: E EVE BRINKMAN

8. REV!c'W I have reviewed the above procedure and have found it 1.0 be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD ) 7/2Af9/ l Cubs L .c m

/

ug dL- %hr

/ /

F C. S_PECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRE 0t i Modifies intent of procedure and changes operation of systes as described in design documents. YES ( ) NO ,[A (If yes, perform written USQ determination and Safety *

  • Evaluation, and contact Manager, Safety Analysis Branch to determine need fer Integrated Safety Evaluation.) j ENVIe0NMENTAL p.EVIEW REQUIRED (Adverse environmental impact) YES ( ) NO
0. SSECIFIC SAFETY EVALUATION RFQUIRED t Affects response of safety systems, performance ,

of systems which may have been creoited in the .

safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO (If yes, perfnre written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

C. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO I F. PROCEDURE REQUIRES PCit/SORC REVIEW r (In addition to review, items with a YES response l must be documented in the PORC/50RC meeting minutes.) YES [ NO [ ]  ;

G. PORC/SORC APPR0 VAL PORC/SORC Meeting Number O' N *I3 l l H. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below: [

&sm-Staitipn/ Service /Udit Superintendent shlw Effective Date SF301/9/s/SES/87-12/lof1 r

80102f .61 001007 PDR A.JCK 05000213 p PDR ,

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l 1

FUNCTIONAL RECOVERY OF HEAT REMOVAL Ef , Rev.

f Pace No.

1-51 3 i

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l E0P 25400 r ,*e 1 l

Rev. 3 4

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j FUNCTIONAL RECOVERY OF HEAT REMOVAL j

i 1. PURPOSE 1

To provide a systematic prow. Jure to restore and maintain RCS heat removal

) through various means.

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j 2. JNTRY CONDIT!0N3 ,

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Function Recovery. E0P 2540, indicates that RCS heat removal requirements are not being satisfied. .

E0P 25400 Page 2 Rev. 3

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FUNCTIONAL RECOVERY OF HEAT REMOVAL

3. OPERATOR ACTIONS Instructions Contingency Actions CAUTION
1. Do not leave this procedure until heat ramoval requirements are satisfied. Other safety function (s) may be pursued concurrectly.
2. The recovery of the heat removal safety function is time -

sensitive. The path of last resort is 'once through RCS*

Cooling via the PORV's (Step 3.4). If it becoues apparent that feedwater will not he resi.oreu within minutes, then consideration should be given to use the remaining S/G inventory to cooldown.

3.1 Determine, based on present 3.1 Continue with this proc 6 dure, plant conditions, which success paths can be used to satisfy RCS heat removal requirements.

Refer to Figure 4.1, Heat Removal.

NOTE The success paths provided by this procedure are not necessarily listed in order of priority. Steps 3.2 through 3.5 are provided for high Secondary pressure conditions. Step 3.6 is provided for intermediate Secondary pressure conditioils. Steps 3.7 and 3.8 are provided for low Secondary pressure conditions. The success path to be chosen will depend on present plant conditions.

O E0P 25400 Rev. 3 Page 3 I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

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(v ) Instructions Contingency Actions RCS Heat Removal (main or auxiliary feed) 3.2 Establish RCS heat removal 3.2 using main or au>:iliary feedwater (Refer to Figure 4.2)

a. Direct Chemistry to sample a. Continue with this steam generators for activity, procedure and Determine radiation readings -

on steam piping (local)

CAUTIONS

-~

1. Steam generators are vital for RCS beat removal. One (s) steam generator must be used for this purpose even if multiple breaks are detected.
2. Do not isolate atmospheric dump valves, un1Jss they have failed open,
b. If an excess et sm demand or b. Continue with this tube rupture is detected in procedure either steam generator, Then, when RCS T is less than 520'F (C05) isolate the affected steam generator by the following
1. Raise the setpoint of the associated atmospheric dump to 975 psia (C05)
11. Close MSIV (C05) 111. Verify the MSI41 bypass closed (C05)

ECP 25400 Page 4 i

Rev. 3

Instructions Contingency Action, iv. Close the feed regulating valve (C05) ,

v. Close the main feed block valve (C05) vi. Close the auxiliary feed regulating valve (C05) vii. Close the auxiliary feed' air assisted check valve (C05) , ,

viii Verify blowdown is isolated ix. Close steam supply to steam .

driven auxiliary feed pump (C05)

x. C:ose main steam low point drains (C07).
c. Establish proper main feed- c.

water system configuration 1. J,f,mainfeedwater

i. One main feed pump is not available, operating (C05) Then manually start
11. Speed control at electric driven minimum (C05) (preferred) or steam til. Main feed regulating driven auxiliary valves closed (C05) feed pump (C05) iv. Feed regulating valve bypass valves open to and 70-80% (C05)
v. Main feed pump 11. Cose main feed pump discharge pressure discharge isolation 50-150 psi greater than valves 2-FW-38A and steam generator pressure B (C05)

(C05) o,,,r ,

EUP 25400 Page 5 Rev. 3

l I

Instructions Continaency Actions f i

vi. Feedpump discharge t isolation valve, t 2-FW-38A(8), of the ,

nonoperating pump j closed (C05)  ;

111. H DC power is ng available, Then  !

dispatch an  ;

operator with  !

portable lights and communications to e ,

align the steam i driven auxiliary )

teed pump for I l

operation by the  !

following I

. (1) Remove the four bolts [

connecting I the governor motor to the governor f (2) Slowly open l HV-4188,

{

combinid [

steam stop

{

inlet to the (

steam driven auxiliary feed [

pump t

O E0P 25400 Page 6 Rev. 3

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Instructions Contincency Actions v

i (3) Increase turbine j speed by l adjusting I governor speed control until f feed pump I discharge l pressure is l approximately 50 psi above i*

steam gener-

, i ator pressure.  !

(Read locally t

on auxiliary L t

feed pump i L

steam supply l l

pressure gage). I r

(4) Checkope[1  ;

2-FW-44,  !

auxiliary [

1 feed pump discarge f cross-tie f i

(local)

(5) Close 2-FW-43A i and 2-FW-438, aux fesd f regulating [

valves, and f

open aux feed

(

bypass valves to apprux. 50%

i open (local) j E0P 25400 Page 7 (

Rev. 3 i

[\

( _,

) Instructions C__ontingency Actions (6) Monitor incore thermo-couples to determine the affects of feedwater flow (ICC display)

(7) Close main feed pump discharge isolatio,n valves 2-FW-38A and B (local)

-' d. Ensure steam dump and d. If condenser vaccum

\_ / bypass valves functioning (backpressure) is not to remove RCS Heat (C04/5) 0-15 in. Hg. abs.,

Then operate atmosparic dump valves to remove RCS heat (C04/5).

e. If RCPs were stopped Then e. Continue with this determine if RCPs can be procedure restarteo by all of the following
i. Pressur;zer level greater than 35% and constant or increasing (CO3)
11. Pressure / Temperature limits of Figure 4.11 satisfied for Th (CO3/c.101) 111. One steam generator is removing heat (C05)

()

,_s tv. RCPs starting prerequisites are met per OP 2301C E0P 25400 Page 8 Rev. 3

e .

Instructions Contingency Actions b

CAUTION t l

Pressurizer level and pressure can be expected to decrease upon starting' RCPs due to loop shrinkage and/or void collapse. The level decrease may l L

be large enough to drain the pressurizer. RCP operation with a drained  :

pressurizer may continue provided HPSI and charging pumps are oper6 ting.

NPSH requirements are met, and the RCS T is at least 30*F subcooled.

h

. f. -

If conditions exist for RCP f. Verify Natural Circulation s .

operation, Then flow in the operating loop
1. Start HPSI and charging pumps 1. Pressurizer level (or verify operating) to make greater than 20%

up for RCS contraction (C03) 11 Start one RCP in each loop 11. Verify heat removal l

(B&D preferred) (CO3) from at least steam generator 111. Monitor RCS pressure and 111. Pressure Temperature f

corresponding Tc for adequate limits of Figure a pump NPSH, Figure 4.10 4.11 satisfied for Th (C03/C101) iv. Operate HPSI and charging pumps iv. Loop delta T (Th' to restore pressurizer level Tc) between 10 and i

to 35-45% (C03) and 45'F (CO3)

v. Tg constant or 4

decreasing (CO3) vi. T r h .onstant or decreasing (C03) 1O E0P 25400 Page 9 l Rev. 3 i

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( ) Instructions Contingency Actions

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g. Verify RCS heat removal by the g. If RCS heat removal not following satisfied, Then
i. Steam generator level i. Contirue heat trending to 70-80% (C05) removil actions
11. Pressurizer level greater 11. Consi6.ir the need 20% (CO3) for void control (Refer to E0P 2540C) ,

iii. Incore thermocouple 111. Evaluate use of temperature constant or another success decreasing (INTAMX or ICC path per figure 4.1 display .

h. h. Not applicable
1. Go to next safety function not being satisfied. (Refer to I T OPS Form T540-1)

V EI

11. If all safety functions are satisfied per OPS Form 2540-1 Then go to E0P 2540, step 3.10 l

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1 x- E0P 25400 Page 10 1

Rev. 3

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( ) Instructions Continaency Actions RCS Heat Removal using steam generators (auxiliary feed purps usina fire water) ,

3. 3 Establish RCS heat removal 3. 3 using steam generators supplied by auxiliary feed pumps taking suction from fire tank
a. Direct themistry to sample steam a. , Continue with this -

generator for activity, procedure and Determine radiation readings on steam piping (local)

I J

CAUTIONS

1. Steam generators are vital for RCS heat removal. One steam generator must be used for this purpose even if multiple breaks are detected.
2. Do not isolate atmospheric dump valves, unless they have failed open.
b. [f an excess steam demand b. Continue with this or tLbe rupture is procedure detected in either steam generator, Then, when RCS T is less than 520*F (C05),

isolate the affected steam

) generator by the following E0P 25400 Page 11 Rev. 3 I

_ _ _ _ _ _ _ - - - - _ _ _ _ _ _ . - - - - _ - - _ _ -- . - - - _ - - - . - - - - -_---_J

D e .

Instructions Continconey Actions

1. Raise the setpoint of the .

associated atmospheric dump to 975 psia (C05) it. Close MSIV (C05) iii. Verify the M51V bypass closed (C05) iv. Close the feed regulating valve (C05)

v. Close the main feed block i

valve (C05) v1. Close the auxiliary feed regulatirg valve (C05) vii. Close the auxiliary feed air assisted check valve (C05) viii. Verify blowdown is isolated

%.J (C05) ix. Close steam supply to steam driven auxiliary feed pump (C05)  ;

x. Close main steam low point drains (C07).
c. Establig a flowpath from c. Evaluate ese of Fire tank to auxiliary ancther suc. cess path, feedpumps per Figure 4.3 O E0P 25400 Page 12 Rev. 3

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g Instructions Contingency Actions

d. Manually start electric d. Jf DC power is not driven (preferred) or available, Then dis-steam driven .uxilia y patch an operator with feed pump (C05) portable lights and communications to align the steam drvien auxiliary feed pump for operation by the following i Remove the four i bolts connecting the governdr motor to the governor it. Slowly open HV-4188, combined steam stop inlet to the steam driven aux-111ary feed pump 111. Increase turbine speed by adjusting governor speed control until feed pump discharge pressure is approximately 50 psi above steam generator pressure.

(Read locally on auxiliary feed pump steam supply pressure gauge)

E0P 25400 Page 13 Rev. 3

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f Instructionj Contingency Actions

' iv. Check open 2-FW-44, l

j auxiliary feed pump j discharge cross-tie  !

(local) f

v. Close 2- N-43A and j 2-FW-438, aux feed

[

regulating valves, .

and open aux feed  ;

i bypass valves to i approx. 50% open ,

l (local). -

vi. Monitor indore  !

thermocouples to

{

determine the t affects of feed-l water flow (ICC ]

I display)

e. Close main feed cump e. Continue [

discharge isolatiun valves l 2-FW-38A and 8 (C05) f' 4

f. Ensure steam dump and f. E condenser vacuum bypass valves functioning (back pressure) is not i u remove RCS heat (C04/5) 0-15 in. Hg. abs.,

Then operate atmospheric dump valves to remove RCS heat (C04/5,).

g. H RCPs were stopped, Then g. Continue with this determine if RCPs can be procedure restarted by all of the following
1. Pressurizer level greater than 35% and constant or increasing (CO3)

E0P 25400 Page 14 Rev. 3

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=

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Instructions continaency Actions

11. Pressure / Temperature Ifmits of Figure 4.11 satisfied for Th (C03/C101) 111. One steam generator is removing heat (C05) iv. RCPs starting prerequisites ,

are met per OP 2301C [

CAUTION Pressurizer level and pressure can be expected to decrease upon starting  ;

RCPs/due to loop shrinkage and/or void collapse. The level decrease may {

be large enough to drain the pressurizer. RCP operation with a drained f pressurizer may continue provided HPS! and charging pumps are operating, i

NPSH requirements are met, and the RCS T h is at least 30*F subcooled.

h. Verify Natural Circulation
h. 11 condition exist for RCP operation,lhen flow in the operating loop
1. Start HF5! and charging pumps 1. Pressurizer level  !

(or verify operating) to make greater than 204 1

up for RCS contraction (CO3) i

11. Start one RCP in each loop 11. Verify heat removal ,

(B&D preferred)(CO3) from at least steam generator 111. Monitor RCS prwssure and 111. Pressure / Temperature corresponding T fr limits of Figure 4,11 l c l

adequate pump NPSH Figure 4.10 satisfied for T (C03/C101) tv. Operate HPSI and charging pumps iv. Loop celta T (T to restore pressurizer level T ) between 10 a.sd to 35-45% (C03) 45'F (CO3)

v. T constant or C

decreasing (CO3)

O vi. T constant or decreasing (C03)

E0P 25400 Page 15 Rev. 3

o Instructions Contingency Actions

[v)

1. Verify RCS heat removal 1. If RCS heat removal not by the following ,

satisfied, Then

1. Steam generator i. Continue heat level trending to removal actions 70-80% (C05) 11. Consider the need
11. Pressurizer level for void control greater than 20% (CO3) (Refer to E0P 25400) 111. Incore thermocouple 111. Evaluate use of temperature constant arother success or decreasing (INTAMX or path per Figurt 4.1 ICC display) .

j j. Not applicable

1. Go to next safety function not satisfied. (Refer to OPS Torm 2540-1)

(") _o_r

11. -If all safety functions are satisfied per OPS Form 2540-1 Then go to E0P 2540, step 3.10.

~ E0P 25400 Page 16 Rev. 3

w ____ -. ._. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - _

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Instructions Contingency Actions Heat Removal usina Once Throuch Cooling CAUTION This is a path of last resort when steam generator heat removal is ny available. The first indication that the secondary heat sink is lost is an increasing T . If this success path is chosen c

it must be fully implemented before T cexceeds 550*F.

3.4 Establish RCS heat removal 3.4 by once through cooling by the following , ,

i a. Verify RWST level a. Establish suction ,

greater than 10% path (local) and a suction, path to HPSI and charging pumps per Figure 4.4 (C01)

~

b. Verify HPSI discharge b. Establish discharge path path to RCS per Figure (local)

~

4.4 (C01) f I c. Verify charging path to c. g charging pumps RCS per Figure 4.4 (C01) to HPS! header (C01) l i

d. Ensure d.
i. All RCPs are stopped 1. Stop RCPs (CO3) j (CO3)
11. All proportioaal 11. Trip proportional l

heaters tripped heaters l

111. All backup heaters in iii. Place backup heaters pull to lock in pull to lock iv. 2-RC-403 and 2-RC-405, iv. Open valves l

PORV block valves, open E0P 25400 Page 17 1

Rev. 3

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( ,) Instructions Contingency Actions

e. Start all available HPSI e. Not applicable and charging pumps (C01/2)
f. Open steam dump and bypass f. Continue with this valves and atmospheric procedure dump valves (C05)
g. Open both PORVs by g. Not applicable
1. Install one bypass key for a high pressure trip module
11. Pull that module and one other high pressure trip <

module (RPS) t iii. Open PORV's using bypass

() h.

key Verify acceptable HPSI flow h. Verify valve lineup

? i per Figure 4.9 l

i. Verify RCS heat removal by i. If RCS heat removal not
i. Incore thermocouple satisfied, Then evaluate temperature less than use of another success i 545'F and constant or path per Figure 4.1 ,

decreasing (INTAMX sr ICC display) 1 EI ii. Incore thermocouple temperature decreasing ,

I (INTAMX or ICC display)

I 4

[ ~) '

\'/ E0P 25400 Page 18 Rev. 3 i 4

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o 4 -

i Instructions Contingency Actions l J. If the following conditions j. If PORVs fail to exist, Then Once Through close, Then  :

Cooling may be scopped 1. -

Close PORV b5cck by closing PORVs and stopping valves (CO3) h or throttling HPSI and or charging flow 11. Maintain once

i. Incore thermocouple through cooling temperature less .

than 500*8 and constant or decreasing (INTAMX or ICC

, display) - k

11. Heat remova', is available  ;

from another means.

I i k.

i

i. Go to next safety function k. Not applicable 1 not satisfied. (Refer to OPS (

j Form 2540-1), t 4 I i SI r I 11. If all safety functions are f

f i satisfied per OPS Form 2540-1, [

Then 90 to E0P 2540, step 3.10  ;

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l E0P 25400 Page 19 l Rev. 3 i

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- . I Instructions Continaency Actions RCS Heat removal usina steam aenerators and HPSI pumps (break flow) i CAUTION At least one HPSI pump must be operating at all times I

unless the HPSI pump termination criteria of Step 3.5k, are satisfied.

t NOTE The HPS! pump design minimum suction pressure is 10 psig.

This is indicated by LPSI pump discharge pressure (C01) or  ;

Increased containment wide range sump  !

by local indication.

level and pressure will contribute to this value.

i 3.5 Estab1'ish RCS heat removal 3.5 using HPSI pumps and steam O generators a.

i i

a. Verify RCS pressure [

1ess than 1200 psia (CO3) 1. Reduce RCS pressure by operation of auxiliary spray or PORVs  ;

2.T.

11. Evaluate use of another success path per Figure 4.1
b. Verify RWST level greater b. Verify containment sump than 10% and a suction level greater than 5 feet path to HPS! and charging and a suction path to pumps per Figure 4.5 (Col) HPSI pumps (Col)

O E0P 25400 Page 20 Rev. 3

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() Instructions Continaency Actions l

c. Verify HPSI and charging c. Es}'r,.11sh discharge paths discharge paths to RCS (C01/2/ local) per Figure 4.5 (C01/2)  ;
d. Operate HPSI and charging d. Continue with this pumps to establish RCS procedure heat removal (C01/2)
e. Verify HPSI flow require- e. Continue with this I ments satisfied per Figure procedure 4.9 .
f. Monitor HPSI pump performance f.

while on SRAS f. If HPSI flow is less

1. Total HPSI flow greater than required, Then than 60 gpm (30 gpm for turn off one one pump operation) charging pump at a
11. Total HPSI flow less than time ated then one 1350 gpm (less than 675 HPSI pump until the for one pump operation) remaining H.9S! pump 111. Stable motor current, discharge flow is greater pressure and flow than 30 gpm
11. If HPSI flow is greater than allowed. Then throttle HPSI pump flow until the required flow is attained O E0P 25400 Rev. 3 Page 21

O Instructions continaency Actions

.(

111. If cavitation l

occurs, Then throttle the effected pump's discharge until the cavitation stops  ;

6

g. Direct Chemistry to sample g. Determine radiation steam generators for activity readings on steam piping [

l (local) l

=

l i .

CAUTION $

1. Steam geiterators are vital for RCS heat removal. One steam generator must be used for this purpose even if  ;

4 multiple breaks, are detected.

J . 2. Do not isolate atenspheric dump valves, unless they l l

have failed npen.  ;

1, y

1 ,

f l

)

h. E an excess steam demand or h. Continue with this {

tube rupture is detected in procedure i either steam generator, Then, when RCS T s oss han 04, h

(C05), isolate the affected )

steam generator by the following Raise the setpoint of the  ;

1.

l associated atmospheric f dump to 975 psia (C05) i t

i 11. Close MSIV (C05)  !

j (11. Verify the M51V bypass c

! closed (C05) iv. Close the feed regulating L

I valve (C05) l i

E0P 25400 Page 22 Rev. 3 i  !

() Instructions Contingency Actions

v. Close the main feed block valve (C05) v1. Close the auxiliary feed regulating valve (C05) vii. Close the auxiliary feed air assisted check valve (C05) viii. Verify blowdown is isolated (C05) ix. Close steam supply to steam driven auxiliary feed pump (C05) .
x. Close main steam low point
  • drains (C07).

i

1. . Verify main or auxiliary 1. Manually start pumps (C05) l () feedwater flow to steam generators (C05)

I j. Operate steam dump and J. Operate atmospheric dump

, bypass valves to valves (C04/5) l reduce RCS Th*

hour (C04/5) i j k. If RCPs were stopped, Then k. Continue with this determine if RCPs can be procedure restarted by the following I
1. Pressurizer level greater than 35% and constant l or increasing (CO3)
11. Pressure Temperature limits of Figure 4.11 satisfied for Th (C03/C101)

E0P 25400 Page 23 Rev. 3

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Instructions Continaency Actions 111. Heat removal from at least ,

one steam generator (C05) ,

iv. RCP ttart prerequisites are met per OP 2301C i

t i

ytJTTON Pressurizer level and pressure can be expected to decrease upon starting l RCPs due to loop shrinkage and/or void collapse. The level decrease may  !

be large enough to drain the pressurizer. ,RCP operation may continue provided HPSI and charging pumps are operating, NPSH requirements are met,  ;

and the RCS hT is at least 30*F subcooled. *

1. If, conditions exist for RCP 1. Continue with this I operation. Then, procedure -
1. Start HPSI and charging pumps (or verify operating) to make I up for contraction
11. Start one RCP in each loop i (5&D preferred) (operating loop first) (C03) [

iii. Monitor RCS pressure and corres- I ponding Tc for adequate pump i

NPSH, Figure 4.10 t iv. Operate HPSI and charging pumps to restore pressurizer level 35-45% (C03)

O E0P 25400 Page 24 Rev. 3

e Instructions continaency Actions t

I

m. Monitor for RCS voiding, m. Continue with this Ind cations of voiding are procedure i
1. Pressurizer level increases greater than expected while using auxiliary spray (C03) 0T
11. Pressurizer level decreases ,

while operating charging or I HPSI pumps (C03) i or 111. Unheated thermocouples in ,

. i 4

upper head indicate saturated  ;

e conditions (ICC display) l r

9.E ,

I tv. Reactor vessel level less j

than 1005 (ICC level display) [

> }

) 3

! n. If all the following n. I.f, the termination cond-l conditions exist, Then. itions'do not exist, ,

r one facility at a time, Then HPSI and charging l I

HPSI and charging pumps pumps must continue to may be throttled or stopped operate (CO2/3)  !

1. Pressurizer level greater f l

than 354 and constant l or increasing (CO3)  ;

ii, Pressure / Temperature limits  ;

of Figure 4.11 satisfied for f l

j Th (C03/C101) 111. Heat removal from at i t

]

1 east one steam {

generator iv. Reactor vessel level above top of the hot leg Q43% (ICC level display)

E0P 25400 Page 25 Rev. 3

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l Instructions Continaency Actions

o. Verify RCS heat removal o. If RCS heat removal satisfied by the following not satisfied, Then
1. Incore thermocouple evaluate use of another temperature constant or success path per Figure decreasing (INTAMX or ICC 4.1 display)
11. HPSI flow satisfied per Figure 4.9 111. Heat removal from at least one steam generator -

(C05)

p. . p. Not appilcable
1. Go to next safety

() function not satisfied.

(Refer to OPS Form 2540-1)

EI it, if all safety functions satisfied per OPS Form 2540-1. Then go to E0P 2540, Step 3.10 O E0P 25400 Page 26 Rev. 3

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instructions Contingency Actions  !

t i

RCS Heat Removal usina steam generator (condensate pumos) 3.6 Establish RCS heat removal 3.6 using steam generators supplied by condensate pumps. Do the following

a. Direct Chemistry to a. Continue with this sample steam generators procedure for activity and .

Determine radiation readings on steam piping (local)

CAUTIONS

1. Steam generators are vital fo'r RCS heat removal. One steam generator must be used for this purpose even if multiple breaks are detected.
2. Do not isolate atmospheric dump valves, unless they are failed open.
b.  !! en excess steam demand b. Continue with this or tube rupture is detected procedure in either steam generator.

Then, when RCS Th ' ' I '"

than 520*F, (C05), isolate the affected steam generator by the following

1. Raise the setpoint of the O associated atmospheric dump to 975 psia (C05)

E0P 25400 Page 27 Rev. 3

,s

.I Instructions. Continaency Actions I r
11. Close M51V (C05) .

[

111.. Verify the MSIV bypass closed (C05) f tv. Close the feed regulating l

valve (C05) [

i

v. Close the main feed block i 1

valve (C05) vi. Close the auxiliary feed [

regulating valve (C05) r i vii. Close the auxiliary feed l air assisted check valve . l (C05)  !

I viii. Verify blowdown is isolated I l

4 (C05) [

1x. Close steam supply.to steam

driven auxiliary feed pump

) (C05) r f j x. Clese main steam low point i l l 1

drains (C07). i t

I 1 ,

j c. Verify power to at least c.  ;

one condensate pump (C05) 1. Restore power to one

]

condensate pump (C05/7) i or

! 11. Esaluate use of another f success path f i

d. Verify condenser hotwell d.  !
1. Ensure makeup from level greater than 20% f (Recorder C05) CST (local) $

9.C

11. Open makeup bypass  :

4 e

.i, valve (local)  !

h l ECP 25400 Page 28 l l Rey, 3 I

i 1

4

e .

i, Instructions Contingency Actions

e. Establish a flowpath from e. Evaluate use of another condenser hotwell to success path steam generator (s) per Figure 4.6 (local)

NOTE When MSI blo'ck permissive is actuated, MSI should he blocked.

i I f. Ojerate steam dump and f. Operate atmospheric dump 1

l bypass valves to reduce valves (C05) steem generator pressure .

4 d

to less than 400 psia (C05) j 1

g. Operate one condensate pump g. Eval'uate use of another to restore steam generator success path level (C05) l

?

h. @ tain steam generator h. Operate atmospheric dump l

pressure less than 400 psia valves (C05) by operation of steam l

i dump and bypass valves (C05) i I 1. H RCPs were stopped, Then 1. Continue with this determine if RCPs can be ptocedure restarted by the following

]'

i. Pressurizer level greater than 354 and constant j or increasing (C03)

{ it. Pressure /TemperatJre limits of Figure 4.11 satisfied for Th ( 03/C101) iii. One steam generator is removing heat (C05) j iv. RCPs starting prerequisites are met per OP 2301C

[ E0P 25400 Page 29 l

Rev. 3 i

e .

s

% ~

)

Instructions Continaency Actions i 1

l CAuf!ON Pressurizer level and pressure can be expected to decrease upon starting f

RCPs/due to loop shrinkage and/or void collapse. The level decrease may i be large enough to drain the pressurizer, RCP operation with a drained [

pressurizer may continue provided HPS! and charging pumps are operating, NPSH requirements are met, and the RCS T h

is at least 30*F subcooled. ,

f i

j

j. If conditions exist for RCP j. Verify Natural i operation, Then , Circulation flow in ,
i. Start HPS! and charging pumps the operating loo *p (or verify operating) to make 1. Pressurizer level up for RCS contraction greater than 20'4
11. ' Start one RCP in each loop it. Verify heat removal 3

(B&D preferred) (C03) from at least steam generator 111. Mont*or RCS pressure and iii. Pressure / Temperature correspondig Tg for adequate limits of Figure pump NPSH, Figure 4.10 4.11 satisfied for .

T h (CO3/C101) j iv. Operate HPSI ano .narging pumps iv. Loop delta (T -T)g h l to restore pressurizer level between 10 and j to 35-454 (CO3) 45'F (CO3)  !

t

v. Tg constant or decreasing (C03) vi. Th * "' t* "t "" -

decreasing (C03)

O E0P 25400 Page 30 Rev. 3

e .

Instructions Contingency Actions

k. Verify RCS heat removal by the k. If RCS heat removal not following satisfied Then
1. Incore thermocouple 1. Continue efforts temperature constant to remove heat or decreasing (INTAMX or or ICC display)
11. Pressurizer level 11. $ valuate use of greater than 20% and another success stable (C03) path per Figure 4.1 111. Steam generator level 10-80% (C05) ,
1. 1. Not applicable
1. Go to next safety function not satisfied. (Rsfer to OPS Form 2540-1)

SI

11. If all safety functions are satisfied per OPS Form 2540-1. Then go to E0P 2540, Step 3.10 O EOP 25400 Page 31 Rev. 3 s m_

e .

1 Instructions Continoency Actions Heat Removal usina Shutdown Coolina System

3. 7 Establish RCS heat removal 3.7 using shutdown cooling.

(Refer to Figure 4.7)

a. Initiate shutdown 4. Evaluate use of another 4-cooling per OP 2310 success path
b. Verify RCS heat removal b. 11 RCS heat removal

! by not satisfied Then-f 1. Th less than 300*F and evaluate use of a'nother constant or decreasing success path per (C101) Figure 4.1 4

and

() 11. Pressure / Temperature limits of Figure 4.11 satisfied for Th (C03/C101)

I c.

I

1. Go to next safety i

i function not satisfied i

1 2I

11. If all safety functions are satisfied per OPS 1

i Form 2540-1, Then go to E0P 2540, Step 3.10

)

i I

l 1

4 O E0P 25400 Page 32

Rev. 3 1

1

e .

Instructions Contingency Actions RCS Heat removal usina steam aenerators (fire pumps)

NOTE Notify Unit 1 Lefore using this success path.

3.8 Establish RCS heat removal 3.8 using steam generators supplied by Fire pumps

a. Direct Chteistry to ,
a. Continue with this*

sample steam generators procedure for activity and Determine radiation readings on steam piping (local)

CAUTION

1. Steam generators are vital for RCS heat removal. One steam generator must be used for this purpose even if multiple breaks are detected.
2. Do not isolate atmospieric dump valve, unless they have failed open.
b. J,f,an f excess steam demand or b. Continue with this tube rupture is detected in procedure either steam generator. Then, when RCS T h
  • '" h*"

520*F, (C05), isolate the O affected steam generator by the following E0P 25400 Page 33 Rev. 3

-- - - - - - ~ - - - - ~ - - --- - - --

~O-Instructions Contingency Actions

1. Raise the setpoint of the associated ats.ospheric i dump to 975 psia (C05)
11. Close M51V (C05) [

j 111. Verify the M5!V bypass f

closed (C05)  ;

i tv. Close the feed regulating ,

valve (C05) '

t i v. Close the main feed block  !

t.

] valve (C05) vi. Close the auxiliary feed -  ;

regulating valve (C05)

. vii. Close the auxiliary feed air l 6 i t assisted check valve (C05) i viii. Verify blowdown is isolated ,

(C05) ix. Close steam supply to steam (

driven auxiliary feed pump )

i (C05)

x. Close main steam low point i f drains (C07). f I

f I c. Verify operability of at c. Restore operability '

least one Fire pump (Unit 1 of at least one Fire Fire panel) pump (local)

J t

j d. Verify at least one Fire d. Evaluate use of another l tank level greater than success path l

10% (Unit 1) (

l

)

) e. Establish a flowpath from e. Evaluate use of another f Fire tank to steam success path i

generator (s) per Figure 4.8.

) E0P 25400 Page 34 Rev. 3

i i f

! t

' .i

e .

l t

r instructions Continaency Actions i

f. Operate steam dump and f. Operate atmospheric dump  ;

bypass valves to reduce vaives to reduce steam steam generator pressure generator pressure (C05/

to less than 75 psia (C05) local)  :

i

g. Verify auto start of at g. Manually start pumps I least one Fire pump at header pressure of 95 psig (Fire panel / local) j l

i

h. Maintain steam generator h. Operate atmospheric. dump pressure less than 75 psia valves (C05) '

by operation of steam dump and bypass valves (C05)

, f

1. Verify auxiliary feed flow 1. Verify flowpath j to 5/G j Ensure RCPs are stopped (C03) Step RCPs
j. j.

f l

k. Verify RCS heat removal k. M RCS heat removal hy the following not satisfied, Then
1. Incore thermocouple 1. Continue efforts temperature constant to remove heat ,

or decreasing (INTAMX or o.I ICC display) [

11. Heat removal from it. Evaluate use of at least one steam another success path ,

generator per Figure 4.1 111. Pressure Temperature licits {

of Figure 4.11 satisfied for l

Th (CO3/C101)

E0P 25400 Page 35 l Rev. 3 i ,

j l

)

I

_ _ - _ _ - __ _ , _ _ . _ _ _ _ _ _ _ , _ . _ , _,_. . _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ . . _ __ I

O

( M tructions Contingency Actions

1. 1. Not applicable
1. Go to next safety  !

function not satisfied i SI

11. If all safety functions j

are satisfied per OPS Form 2540-1,'then go

  • to E0P 2540, Step 3.10
4. FIGURES 4.1 RCS Heat Removal Success Paths -

4.2 RCS Heat Removal (Normal) 4.3 RCS Heat Removal (Aux feed pumps taking suction from Fire Tanks) 4.4 RCS Heat Removal using Once Through Cooling 4.5 RCS Heat Removal using HPSI and. charging pumps and Steam Generators 4.6 RCS Heat Removal (Condensate Pumps) 4.7 RCS Heat Removal using shutdown cooling system j 4.8 RC3 Heat Removal (Fire Pumps) .

4.9 Safety Injection System Delivery Curves 4.10 RCP NPSH Requirements 4.11 RCS Pressure / Temperature Limits j

- FINAL - l i

l l

r l }

l i

E0P 25400 Page 36 Rev. 3

7_______-_ ,

e .

1

() FIGURE 4.1 RCS Heat Removal Success Paths

$UCCE55 PATH METH00 STEP FIGURE RC5 heat RCS heat removal being 3. 2 4.2 Removal (normal) maintained by

a. Forced or natural circuiation
b. Main or auxiliary feedwater
c. Steam dump and -

bypass or atmos-pheric dump valves RCS Heat Removal RCS removal being maint- 3.3 4.3

() (auxiliary feed-pumps being tained by

a. Forced or natural supplied by circulation Fire tank b. Auxiliary feedwater supplied from Fire tank j c. Steam dump and I

bypass or l

atmospheric dump i valves O EOP 25400 Rev. 3 Page 37

e .

l l

N l

FIGURE 4.1 (cont)

SUCCESS PATM METHOD STEP FIGURE RCS Hest Removal RCS heat removal 3.4 4.4 using "once being maintained by thru cooling" HPSI and charging flow through PORVs l

l RCS Heat Removal RCS heat removal 3.5 4.5 using HPS! and being maintained by .

l charging pumps a. HPS! and charging l

and steam flow (break in RCS)

I generators and

b. Steam generator

() ,

heat removal by

1. Forced or natural circulation it. Main or auxiliary feed-l water j iii. Steam dump and bypass or atmopsheric dump valve O E0P 25400 Rev. 3 Page 38 l

e .

~

O Figure 4.1 (con't)

SUCCESS PATH _ METH00 STEP FIGURE RCS Heat Removal RCS heat removal being 3.6 4.6 (condensate pumps) maintain by (5/G Pressure a. Forced or natural

< 600 psia) circulation

b. Steam dump and bypass or atmos-pheric dump valves ,
c. Condensate pumps RC5 Heat Removal RCS heat removal 3.7 4.7 using shutdown being maintained cooling system ,

by shutdown cooling (RCS Pressure system

< 265 psia)

F RCS Heat Removal RC5 heat removal being 3.8 4.8 (fire pumps) maintained by (5/G Pressure a. Forced or natural

< 130 psia) circulation

b. Steam dump and bypass or atmos-peric dump valves
c. Fire pumps O ECP 25400 Page 39 Rev. 3

e Res arAT nrxovAL :; wonxxL )

Figure 4.2

[O STM DUMP +37 Pall .4 TVD l

CONDENSER f

<ls*Me Aas L_ , -

J .

i -

1 l

O . ,

1 CONDENSATE -

PUMP 3 s g% -  :

l '

l D D D s v/G _

l A C)/ 4 h .

u I

I

$ AUX FEED

(

I I

O 3 O ms [

3 7 7, l v v a  ;

n a f

^ l nar >

systru O '

C csr sc, 2 >ico g. . :a l

. _ >>n ,ses.3 l

I

( I

\

RCS HEAT REMOVAL (AUXILIA'RY FEEDWATER PUMPS TAXING SUCTION FROM FIRE TANKS) l Figure 4.3 l I

v l

. l

,_P._,_ -

! I hhh b -

r 7 h i

CONMNSEM *g G l

.;o n "418' $ A&S s -

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nRtpuMP I+

0

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.l FIRE FIRE -

L '

TAnx TANK

)

EOP 2540D page 41 ,

( f "t j Rev. 3 I l I

. I t

. I

. RCS MEAT REMOVAL USING ONCE THROUGH COOLING Figure 4.4

.m* -

.m' i crursuur 1- >

s~r

  • pggy my i

y6 r_ f "4 *** a, i 4 tom 6 g'** _ *m *

,h b v b v!n n

x

a<w.nz ,,

som i su eam( %p, l

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,,, rao mes  !

mes  !

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d,, ; s A...,

s e a i

{

E0P 25400 page 42  !

l Rev. 3

'l l , i

!O l 1

I I

1

l

( ,

Figure 4.5 pc5 MEAT RDt0 VAL USING MPSI AND CH.ARGING PUMPS AND l STEAM G::NERATORS yy yg D>

  • D, 1-r 1-r pg, g

, . _O ,O O

,h b hvk P esses

  • q l
x. v u ..,u
  • = p ,

tu.8N a' S W ~ t_ .

._ h ear, ra o m.vts W PAI N#PB g n a . st aqs .

Fu mPt-

++ .

^

""E 7 ' + 3 "/E'w ' *

  • L O*SeO .

{go44o i

= >

^

B ue. Af e MMV'b jm a u. .,, ~ v .

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, e

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mv.

841 Fllt PeelPA -

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ern., 7 ...

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Rev. 3

RCS HEAT RI.MOVAL (CONDENSATE PW,pS)

( ~

Figure 4.6 l STM. DUMP + 37 Pass Wyta f.

F CON M MSEM 7 h S/,G .

< ,, u, m .ha . , ,,

Livil >tois . ATWOS -

J .I

~ .

CONDENSATE ~

PUMPS

\[ ATMOS O O O '

~

f MAIN FEED PUMP

' T Fl!D l e '~~' p StGULAT!W6 [

VALVf6 h

g l i

l

[

ECP 2540D page 44 Rev.I f I

1 i

l

(-

RCs HEAT REMOVAL USING SHUTDOWN COOLING Figure 4.7 t

l LP51 PuMF6 f

ft$17CS

~

2 SI 06 l LPSI IN7ECTION

'~ YALWlJ E 51 U7 0

-Q C .

,' i

\

i s O

' ~ FIA O(  : _A- -

- p c

T 4 f*3I 651

~ '

%u v, 4WuT30WN 4m  !

C00&ING i fI P HEAT EXCH. Ld 6 ,

d y 42 5I 652 '

/

COWTAINMENT S @ Q I

\

l SPRAY I

E0P 2540D page 45 Rev.3 l t

r i

. I

RCS IEAT REMOVAL (' FIRE PUMPS )

~

Figure 4.s

p. fbt # '

,m . . . . . -

r PPPP 3 NA h

CON M N M # 2 *- '

<, is" He Ap '

L; J I

(

O b

~

AUt C C Cy O O ONINE

' 'g e F/RE PUMP

\

^

e O,, csr

, O ,'

l flRE FIRE -

L J TANX TANX

- EOP 25400 page 46 f g y Rev. 3 I

1300  :

= = =
= =  : , , -_- _.- -_ -_. . _, = _.

, *

= = -'

-' = = = , , =  ;  ; -.

7 g - g _.

, -=4

= = =  : =  : = = _- -

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12004 a W v = = = = = =

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9,=- -= ..

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,- WAccIP7M1.E EGICH - L 100 - - - - -

. - - . J _. - - - - - - - -

\ <

--S 3 0

0 000 1600 2400 3200 4000 TOTAL OF FOUR HPSI AND LPS1 HEADER FLOWS (GPit)

NOTES 1. This curve is based on one facility operating and at least one charging pump in operation.

2. J_f, containment pressure has exceeded 5 psig at any time during an event, then do not use this curve. Its accuracy is in doubt. When deter =ining Safety Tunction status:

Consider the Safety Tunction satisfied if all other safety function l parameters meet criteria.

i MlfilMUM REQUIRED SAFETY !!UECTION DELIVERY CURVE FIGURE 4.9 1

E0r 2540D 4:e

Pev. 3 l

[..-.-_.----_.-_-.-____ _- - . - - - - - - _ _ -- -

6

, 3200 L a i ,) i 3000 .

f\ -

2800

. mm .O _

RCP NPSH CURVE 2600 -

2400 .

2200 ,,

  • 2000 -

W -

5l 1800 -

U , MINIMUM PRESSURE E FOR R.C. PUMP 1600 5 - OPERATION 0

N1400 ,

i O g1200 g pggp h

$1000 -

800 -

\ ~

2 PUMPS SAME LOOP AND SURGE

- LINE LOOP 600

~

400 i

\ # ~

l 200 -

! MAXIMUM PRESSURE FOR SDC OPERATION l

1 1 i I 0 400 500 600 0 100 200 300 INDICATED REACTOR COOLANT TEMPERATURE Tcol d , *I EOP 2540D PAGE 48 REV. 3 9

2500 i i i

(G .-

NoT -

'a

- ACCE PTA88.E -

i 1 AC cG PTA ALE l j 2000 .  ; f I

I

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0 600 200 300 400 500 RCS TEMPERATURE (F)

  • This curve supercedes the 100F/HR cooldown curve any tirae the RCS has experienced an uncontrolled cooldown to below 500F,
    • This curve suoercedes the 30F Subcooling curve if, at any time, the containrent pressure has exceeded Spsig.

FIGURE 4.11 RCS PRESSURE / TEMPERATURE LIMITS E0P 25400 Page 49 Rev. 3 t

[ '

(}

~

RCS PRESSURE /TF.NPERATURE LIMIT DATA

%J PTS LIMIT 100*F/HR 30'F DEGRADED 200*F COOLDOWN SUBC00 LED CTMT SUBC00 LED CURVE RCS SATURATION MINIMUM MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRESSURE- PRESSURE PRESSURE PRESSURE

(*F) (psia) (psia) (psia) (psia) (psia) 600 1543 1919 1919 Upper Limit of 595 1487 1852 1852 2350 590 1432 1787 1787 i 585 1378 1723 1723 580 1326 1662 1662 595 1276 1602 1602 570 , 1227 1543 1543 565 1180 1487 1487 '

560 1133 1432 1432 555 1089 1378 1376 .

550 1045 1326 1326

  • 545 1003 1276 1276 540 963 1227 1227 535 924 1160 1180 530 885 1133 1133

(~ ~ 525 848 1089 1089 520 613 1045 1045 O- 515 778 1003 1003 510 744 963 963 505 . 712 924 924 500 681 885 885 495 650 848 848 490 621 813 813 485 593 773 773 480 566 744 744 475 540 712 712 470 515 681 687 657 W 465 490 650 460 467 621 633 2350 455 434' 593 607 2286 450 423 566 582 2208 445 402 540 561 2133 440 382 515 540 2060 435 362 490 522 1989 430 344 467 502 1919 425 326 434 483 1852 420 309 423 467 1787 415 292 402 451 1723 ,',

410 277 392 436 1662 405 262 362 408 1602 I 400 247 344 406 1543 l

E0P 25400 Page 50 l

Rev.3 l

l .

s. -.

l RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd)

)

PTS LIMIT 100'F/HR 30'F DEGRADED 200'F C00LDOWN SUBC00 LED CTMT SUBC00 LED CURVE RCS SATURATION MINIMUM MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE

(*F) (psia) (psia) (psia) (psia) (psta) 395 233 326 392 1487 Upper Limit 390 220 309 378 1432 of 2350 383 208 292 366 1378 380 196 277 353 1326 375 184 262 340 1276 370 173 247 329 1227 365 163 233 319 1180 160 153 220 309 1133 555 144 208 299 1D33

  • 350 135 196 289 1045 345 126 1 84 281 1003 ,

340 118 173 275 963 335 110 163 265 97I 330 103 153 256 885 325 96 144 251 848 320 90 135 242 813 i s) 315 84 126 236 778 310 78 118 230 744 305 72 110 2 2., .712 300 67 103 219 681 62 96 214 650 4 395 ,

290 58 90 210 621 2230

. 285 53 84 205 593 2100 ,

280 49 78 202 566 1970  ;

275 45 72 198 540 1850 270 42 67 196 515 1730 265 39 62 192 490 1620 260 35 58 190 467 1530 255 32 53 188 434 1450 250 30 49 184 423 1370 245 27 402 1300 240 25 382 1230 235 23 362 1170 230 21 344 1100  ;

225 19 326 1040 220 17 309 980 ,

215 16 292 930 210 14 277 880 262 840 I 205 13 200 12 247 800 O

l E0P 25400 Page 51 Rev. 3

Nelust Yt0<A-Shhb $'N"k 5 F0 APPROVhDBYUNIT,2 SUPERINTENDENT EFFECTIVE DATE PORC MTG NO.

CONTAINMENT ISOLATION VALVES CHANNEL 1 2-MS-220A #1 S/G Blowdown Isolation C05 2-CH-505 RCP Bleedoff to EDST CO2 2-CH-198 RCP Bleedoff to VCT CO2 2-RC-45 RCS Sample Isolation C72 2-AC-8 Enclosure Bldg. Purge Exhaust C01 2-EB-88 H2 M nitor Emergency Isolation C01 2-MS-191A #1 S/G Sample Isolation C05 .

2-LRR-43.2 PDT Pump Outside Isolation 'C03 2-AC-47 Containment Rad Monitor Isol. C01 2-EB-99 H2 Purge Outside Isolation C01 2-PMW-43C PMW to Containment Isolation C03 2-GR-11.2 Waste Gas Outside Isolation C03 2-AC-3 Enclosure Building Purge Supply C01 2-AC-15 Containment Rad Monitor Isol. C01 2-EB-100 H2 Purge Inside Isolation C01 2-AC-1 Purge Fan Discharge C01 2-SSP-16.2 Containment Sump Outside Isol. C06 F-39A "A" Containment Rad Monitor Fan RC14 O

OPS Form 2540E-1 Rev. 1 Page 1 of 2

i e e e

(

CONTAINMENT ISOLATION VALVES (Continued)

CHANNEL 2 2-MS-2208 #2 S/G Blowdown Isolation C05 2-RC-001 Hot Leg Sample Isolation C72 2-RC-002 Surge Line Sample Isolation C72 2-RC-003 Steam Space Sample Isolation C72 2-LRR-43.1 PDT Pump Inside Isolation C03 2-CH-516 Letdown Isolation CO2 2-AC-11 Purge Exhaust Discharge Damper C01 F-23 Containment Purge Supply Fan C01 2-MS-1918 #2 S/G Sample Isolation C05 ,

2-51-312 N2 to Containment Isolation 'C01 2-LRR-61.1 PDT Sample Isolation C72 2-EB-89 H2 M nitor Emergency Isolation C01 F-398 "B" Containment Rad Monitor Fan RC14 2-CH-506 RCP Bleedoff Inside Isolation CO2 2-GR-11.1 Waste Gas Inside Isolation C03 2-EB-92 H Purge Inside Isolation C01 2

2-AC-20 H2 Monitor Sample Isolation C01 2-CH-089 Regen HX Outlet Outside Isolation CO2 2-SSP-16.1 Containment Sump Inside Isolation C06 2-AC-12 Containment Rad Monitor Isolation C01 2-EB-91 H Purge Inside Isolation C01 2

O OPS Form 2540E-1 Rev. 1 Page 2 of 2 JUN 2 01986

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