ML20204J147

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Rev 4 to Emergency Operating Procedure E-0, Reactor Trip or Safety Injection
ML20204J147
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/03/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
E--1, E-0-01, NUDOCS 8810240550
Download: ML20204J147 (16)
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Text

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JUN 0 31988 NUMBER 1 TILE REV. lSSUE/DATE E.0 REACTOR TRIP OR SAFETY INJECTION Rev. 4 i

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SYMPTOMS REQUIRING A REACTOR TRIP

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l i

o High Pressurizer Pressure 2300 PSIG

[

(two out of three pressurizer pressures on channels 1,2 and 3).

l o

High Pressurizer Level-86%

(two out of three pressurizerlevels on channels 1,2 and 3).

o High Neutron Flux - 25%,74% or 109%

(two out of four Power Range Channels, depending on Trip Selector Switch I

I position).

l High Steam Line Delta P - 110% of fullload steam flow o

(two out of four steamline eli;ow tap AP indicators).

o Core Cooling Actuation Signal (one out of two Safety Injection WL relays actuated).

o Loss of Feedwater Flow coincident with Low Steam Generator Levelin the same Steam Generator (feedwater now lower than steam flow by 20% and narrow range level at or less than 10%),

o Low Pressurizer Pressure - Variable between 1700-2300 PSIG (two out of four pressure channels, depending on power level, in effect when power levelis greater than 10%).

r o

Steam Line Trip Valve closure (one out of four valves when power levelis greater than 10%).

I o

Turbine Trip (any turbine trip when power level is greater than 10%).

o High Start up Rate i

(one out of two intermediate range startup rates equal to or greater than I

5 DPM when power level is less than 10%)

o Loss of Reactor Coolant Flow (one loop Dow less than 90% nominal flow when power level is greater than 74%),

o Loss of Reactor Coolant Flow (two loop flows less than 90% nominal flow when power level is greater than 10%

and less than 74%).

l 0010240550 801007 DR ADOCK O 23

JUN 0 31988 o

NUMBER TTTIE REV. ISSUE /DATE E.0 REACTOR TRIP OR SAFETY INJECTION Rev. 4 l

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A.

PURPOSE i

This procedure provides actions to verify proper response of the automatic protection systems i

following manual or automatic actuanon of a reactor trip or safety injection, assess plant condition and identify the appropciste recovery procedure.

l B.

SYMPTOMS OR ENTRY CONDITIONS i

1.

The following are symptoms that require a reactor trip-1 o

SEE OPPOSITE PAGE.

2.

The following are symptoms of a reactor trip:

o Any reactor trip first out annunicator lit.

o Rapid decrean in indicated neutron level.

o All control rods inserted with rod bottom lights lit.

o Reactor trip breakers open.

3.

The following are symptoms that require a Safety Injection / Containment Isolation 4

actuation:

l o

Containment pressure greater than or equal to 5 PSIG.

o Pressurizer pressure equal to or less than 1700 PSIG.

l 4.

The following are symptoms of a Safety Injection / Cr-tainment Isolation actuation:

o "CORE COOLING ACTUATED" annunicator lit.

I o

SI pumps running.

o SI WL Relays tripped, o

Containment isolation valves closed.

o HCP WL Relays tripped.

Page 1 of 15 1

JUN 0 31985 NUMBER TITLE REV. ISSUE /DATE i

E0 REACTOR TRIP OR SAFETY INJECTION Rev.4 i

i STEP ACITON/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o STEPS 1 THROUGH 14 ARE ISISfEDIATE ACTION STEPS.

o FOLDOUT PAGE SHOULD BE OPEN.

o EPIP 131, EbfERGENCY ASSESShfENT, SHOULD BE lbfPLEbfEhTED.

I VERIFY REACTOR TRIP :

a. Push reactor trip button
b. Check the following:
b. QQ IQ FR S.1, RESPONSE TO NUCLEAR o Reactor trip breakers - OPEN POWER GENERATION /ADVS, o Neutron flux - DECREASING Step 1.

o All rod bottom lights - LIT 2

VERIFY TUR.BIhT TRIP:

a. Push turbine trip button
b. Check the following:
b. Close all four main steamline
1. Both turbine trip valves CLOSED trip valves.

.QR

2. All turbine control valves - CLOSED l
c. Check turbine speed -
c. Close all four main steamline LESS THAN 2300 RPM trip valves.

l 3

VERIFY POWER TO AC AND DC BUSES:

I

a. Check ac emergency buses energized -
a. Attempt to restore power to at AT LEAST ONE DtAIN least one train.

I IE EQI restored, l

Buses 8,4 and 5 THEN QQIQ ECA 0.0, QR STATION BLACKOUT, Step 1.

l Buses 9,6 and 7 I

b. Check ac emergency buses energized -
b. Attempt to restore power to BOTli TRAINS deenergized ac emergency buses.

Buses 8,4 and 5 I

bHD Buses 9. 6 and 7

c. Check de buses energized -
c. GQIQ EOP 3.149.

BOTli BUSES PARTIAL LOSS OF DC, Step 1.

4 CHECK IF SI ACRJADID:

IE SI REQUIRED, IllES MANUALLY ACTUATE.

o Check SI WL Relays -

IE NOI REQUIRED, l

IHEN 0D IQ ES-0.1, ONE QB BODITRIPPED REACTOR TRIP RESPONSE, STEP 1. ;'

Page 2 of 15

JUN 0 31988 NUMBER TUU REV. ISSUE /DATE l

E0 REACTOR TRIP OR SAFETY INJECTION Rev. 4 i

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STEP -

. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5

VERIFY FEEDWATER ISOLATION:

o Check all four motor operated feedline Close all four motor operated feedline isolation valves CLOSED isolation valves.

6 VERIFY FW PUMP RUNNING:

i

a. Check at least one main feedwater
a. Check AUTO AUX feedwater actuated.

pump - RUNNINO I

E NQIactuated, i

))]EN start AUX feedwater pumps.

~ b. Open all four feedwater bypass valves b.E bypass valves fail to open, IlEN perform the following:

1. Open FW MOV-35 to feed all SGs simultaneously.
2. Start AUX feedwater pumps.
  • E FW MOV 35 fails to open,

311EN perform the following:

a. Stop AFW pumps b.Open FW MOV 35.

c, Restart AFW pumps. *2 7

VERIFY CONTAINMENTISOLABON ACIUATED:

a. Check HCP WL Relays TRIPPED
a. Manually 08 locally close containment isolation valves (SEE OPPOSITE PAGE).

8 CHECK MAIN STEAM FLOW INDICATION:

a. Check elbow tap steam flows -
a. Close all four main steamline trip LESS DIAN 30 %

valves.

ASI2 steam flow recorders -

INDICATE NO FLOW

b. Check RCS temperature -

b.Close all four main steamline cip NOT DECREASINO IN AN valves.

UNCONTROLLED MANNER DUE TO EXCESSIVE SRIAM FLOW Page 3 of 15

JUN 0 31988 NUMBER TITIE REV. ISSUE /DATE E0 REACTOR TRIP OR SAFETY INJECTION Rev.4 I

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

9 VERIFY EMERGENCY DIESEL MANUALLY START EMERGENCY GENERATORS RUNNINO DIESEL GENERATORS.

10 VERIFY SERVICE WATER PUMPS MANUALLY START SERVICE RUNNINO WATER PUMPS.

(ONE PUMP FOR EACH DIESEL GENERATOR) 11 VERIFY SI PUMPS RUNNING:

a. Check HPSI pumps RUNNING
a. Start HPSI pumps.
b. Check LPSI pumps - RUNNING
b. Start LPSI pumps,
c. Perform the following to start Charging pumps:
1. Check CH MOV 257 - CLOSED
1. Manually QR Ixcally clow CH MOV-257.
2. Check BA MOV-373 OPEN
2. Manuallyopen BA MOV 373 QR BA MOV 32.
3. Check off site power AVAILABLE
3. GQIQ Step 9.
4. Take charging pump control switches lY to the "Trip" then to the "Start" position I

12 VERIFY CONTAINMENT AIR RECIRCULATION SYS'mM OPERATING:

a. Check all face dampers - OPEN
a. Open all face dampers,
b. Checx all CARFANS - RUNNING
b. IE off site power available, IllEN start all operable CARPANS.

IE b'QT available.

TliEN verify one CARFAN auto starts on each diesel generator. Start a third CARFAN within 15 minutes.

1 IE only one diesel generator operable.

THEN start second CARFAN within 10 minutes.

Start third CARFAN within 15 minutes utilizing altemate CARFAN power supply.

Page 4 of 15 i

JUN 0 31955 NUMBER TITLE REV. ISSUE /DATE I

E0 REACTOR TRIP OR SAFETY INJECTION Rev. 4

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S1TP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED l

13 VERIFY CCW PUMPS RUNNING E POWER AVAILABLE, THEN MANUALLY STARTCCW PUMPS.

14 VERIFY CONTAINMENT SPRAY NOT REQUIRED:

a. Check containment pressure -
a. Manually initiate containment spray.

LESS THAN 40 PSIG WHEN containment pressure decreases to 35 PSIG, THEN close containment spray valves.

E only one LPSI pump operable, THEN open RH MOV 31 (fire main to containment spray).

WHEN containment aressure decreases to 35 PSIC THEN close RH MOV 31.

15 VERIFY SI FLOW:

a. Check charging flow indication -
a. VERIFY power available, f

INDICATING FLOW THEN perform the following:

a.

Start charging pumps by taking control switches to the "Trip' then to the "Start" position.

b. Check open QB open CH MOV 2928 and CH MOV 292C.
b. Check RCS pressure.
b. QQIQ Step 16 LESS THAN 1475 PSIG (OBSERVE NOTE PRIOR (1700 PSIO FOR ADVERSE TO STEP 16).

COM'AINMENT)

c. Check HPSIpump AMP meters-
c. Start HPSI pumps and GREATER THAN 115 AMPS open allloop SI MOVs.
d. Check RCS pressure -
d. QQ IQ Step 16.

LESS THAN 405 PSIG (OBSERVE NOTE PRIOR i

(635 PSIG FOR ADVERSE TO STEP 16).

CONTAINMENT)

a. Check LPSI sump AMPmeters-
e. Start LPS! pumps and GREATERliAN 60 AMPS.

open both core deluge MOVs.

Page 5 of 15

JUN 0 31988 NUMBER TTHE REY. ISSUE /DATE i

E0 REACTOR TRIP OR SAFETY INJECTION Rev.4 l

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STEP ACTION /EXPECIED RESPONSE RESPONSE NOT OBTAINED NOTE:

o AFTER VERIFYING THAT A TOTAL AFW FLOW OF GREATER THAT 320 GPhi CAN BE OBTAINED AND AfAINTAINED, AFW FLOW MAY BE THROTTLED TO LESS THAN 320 GPhi TO AfD IN AfAINTAINING RCS TEbfPERATURE.

o AUTO AUX FEEDWATER,IF ACTUATED, AfUST BE DEFEATED BEFORE SG LEVELS CAN BE CONTROll.ED WITH THE l

FEEDWATER BYPASS AOVs.

l i

16 VERIFY TOTAL AFW FLOW ESTABLISH TOTAL AFW FLOW GREATER THAN 320 GPM GREATER THAN 320 GPht.

j E NQIESTABLISHED, THEN GQIQ FR H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, STEP 1.

17 VERIFY CONTAINh1EST ISOLA 110N AND SI VALVE AMGNMENT:

a. Check SI valves IN PROPER
a. hianually align valves.

Eh1ERGENCY ALIGNMENT l

(SEE OPPOSITE PAGE)

  • E h1CC 5 is deenergized, l

ETxrform die following to j

estabk1 a charging path:

1. Stop both charging pumps and
2. place control switches in TPO.

Locally close CH htOV 257.

3. Locally open BA h10V 373.
4. Check power available to htCC 8, THEN stan one Charging Pump i

AUX oil pump.

I

5. Place the Charging Pump UV trip bypass switch, on the charging pump with the running AUX oil pump, in the "bypass" position.
6. Stan the charging pump with the running AUX oil pump.
7. Fully open CH FCV 110 and CH FCV Il0A.
  • 1 b, c.

tainment isolation valves -

b. hianually OR locally close CLo w containment isolation valves.

(SEE OPPOSITE PAGE)

Page 6 of 15

r JUN 0 31988 NUMBER TTILE REV. ISSUE /DATE 3

E.0 REACTOR TRIP OR SAFETY INJECTION Rev.4 l

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STEP l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 CHECK RCS AVERAGE E LESS THAN 535' F TEMPERATURE STABLE AT M DECREASING, OR TRENDING TO 535' F.

THEN PERFORM THE FOLLOWING:

a. Stop dumping steam.
b. E cooldown continues, reduce total AUX feedwater flow to 320 GPM until wide range levelin at least one SG is greater than 63 %,

(67 % for adverse containment).

IllFS control AUX feedwater flow to maintain SG levels,

c. E cooldowr continues.

THEN close steam dump isolation valves, MS MOV 520 and MS MOV-553.

d.E cooldown continues, THEN close all four main steam line trip valves and check all four bypass valves closed.

f. E cooldown decreases TAVG 50' F below steady state TAVG E LOCA is EQIin progress, IBFS Emergency Borate the RCS (SEE OPPOSITE PAGE)

E GREATER THAN 535' F M INCREASING, THEN PERFORM 111E FOLLOWING:

a. Dump steam to the main condenser.

E NQIavailable, THEN dump steam using one QR more of the following:

1. Atmos sheric steam dump valve.
2. Terry Turbine steam supply valves.
3. Hog Jet steam supply valves.

I 1

Page 7 of 15

JUN 0 31o88 NUMBER TIT 12 REV. ISSUE /DATE I

E0 REACTOR TRIP OR SAFETY INJECTION Rev.4

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STEP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTADiED 19 CHECK PRZR PORVs AND SPRAY VALVFS:

a. Check PORVs - CLOSED
a. WHEN PRZR pressure less than 2350 PSIG, THEN close PORVs.

E PORV NOIclosed.

l THEN cic.: its block valve.

l E block valve NOIclosed, f

THEN QQ IQ E-1.

LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

b. Check PORV block valves CLOSED
b. WHEN PRZR pressure less than 2350 PSIG, THEN close block valves,
c. Check PRZR spray valves CLOSED
c. WHEN PRZR pressure less than 2000 PSIG, THEN close spray valves.

l l

I E HQIclosed, THEN stop RCP(s) supplying open I

spray valve (s).

l

d. E #3 RCP SQIrunning, j

THEN place control switch for loop 3 spray valve, PR AOV-574,in the closed position l

l Page 8 of 15

gw NW1BER Tnu t

E0 REACTOR TRIP OT

."-N I

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STEP ACTION / EXPECTED REST ONSC

' ;TAINED l

l i

i NOTE:

SEAL IN)., YlON FLOW SHob. u R-lr

' 4!L ;.. 'Ps, W

l 20 CHECK IF RCPs SHOULD BE STOPPED:

a. Check HPSI QR Charging pump-t

, 21.

i AT LEAST ONE RUNNING

b. Check RCS pressure -
b. CQ IQ Step 21.

LESS THAN 1150 PSIG l

(1380 PSIG FOR ADVERSE CONTAINMENT)

c. Stop all RCPs
d. Close all seal water return MOVs i
c. IE containment pressure greater than 5 PSIG, THEN perform the following:

1, Close CH-TV-240, CH TV-241 (Seal water retum trip valves) 2.

Close CC-TV 1411 (CCW retum from RCP oil coolers)

I i

l i

t l

l I

i f

I l

I l

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t Page 9 of 15

JUNOd1968 I

NUMBER TTI1E REY. ISSUE /DATE E0 REACTOR T.nP OR SAFETY INJECTION Rev.4 i

i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

l r

7 CAUTION:

AN INTERAfEDIATE TO LARGE BREAK LOCA COULD CAUSE THE SG(s) TO EXHIBIT THE SAbfE SYbfPTOhi

( UNCONTROll.ED DEPRESSURIZATION ) AS A l

FAULTED SG.

f L

J 21 CHECK SECONDARY INTEGRITY:

l 1'

a. Check all SG pressures -
a. E any SG pressure is decreasing in STABLE DE INCREASING an uncontrolled manner AER the SG is NO.Iisolated.

THEN QQIQ E 2 FAULTED SG ISOLATION, Step 1.

b. Check all SG pressures -
b. E any SG is completely depressurized GREATER THAN 100 PSIG AND the SG is NQIisolated.

THEN QQIQ E 2, l

FAULTED SG ISOLATION Step 1.,

22 CHECK SG TUBE INTEGRITY:

QQ IQ E-3, STEAM GENERATOR RUPTURE, o Check air ejector radiation monitor -

STEP 1.

NORMAL o Check SG blowdown radiation monitor -

NORMAL I

23 CHECK RCS INTACT:

QQIQ E 1, LOSS OF REACTOR OR SECONDARY,

o Check containment radiation monitors -

COOLAST, STEP 1.

j NORMAL j

I o Check containment pressure -

NORMAL l

o Check containment sump level-l STABLE l

l l

l Page 10 of 15

JUN00IS8B NUMBER EU REY. ISSUE /DAR E-0 REACTOR TRIP OR SAFETY INJECTION Rev.4 t

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STEP ACTION /EXPECED RESPONSE RESPONSE NOT OBTAINED 24 CHECK IF SI FLOW SHOULD BE REDUCED:

a. Check RCS subcooling-
a. DO NOT STOP SI PUMPS.

GREATERTHAN 32 F QQIQ St p 26.

l (SEE OPPOSITE PAGE FOR ADVERSE CONTAIh%iENT)

[

b. Check secondary heat sink:
b. DO NOT STOP SI PUMPS.

o Total AUX feedwater flow -

GREATER THAN 320 GPM DE o

Wide range levelin at least one SG -

i GREATER THAN 63 %

(67 % FOR ADVERSE CONTAINMENT)

c. Check RCS pressure -
c. DO NOT STOP S1 PUMPS.

I STABLE OR INCREASINO QQIQ Step 26.

j

d. Check PRZR level-
d. DO NOT STOP SI PUMPS.

OREATER THAN 10 %

Attempt to stablize RCS pressure (24 % FOR ADVERSE using normal PRZR spray.

CONTAINMENT)

RETURN IQ Step 24 a.

{

25 GQIQ ES 1,1, Si TERMINATION, STEP I l

i 26 INITIATE MONTTORING CRITICAL l

SAFETY FUNCTION STATUS TREES l

l I

I Page 11 of 15

JUN 0 31988 NUMBER T7 TIE REV. ISSUE /DATE E0 REACTOR TRIP OR SAFETY INJECTION Rev.4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

Af0NITOR DWST LEVEL. START AfAKEUP TO DWST BEFORE LEVEL DECREASES TO S4,000 GALLONS.

l L

J l

27 CHECK SG LEVELS:

f

a. Check wide range levels -
a. hiaintain total AUX feedwater flow I

GREATER THAN 63 %

greater than 320 GPhi until wide range l (67 % FOR ADVERSE

evelin at least one SG is greater CONTAINhiEST) than 63 %

(67 % for adverse containment),

j

b. IE any SG wide range level continue
b. Control AUX feedwater flow to maintain wide range levels between to increase in an uncontrolled manner, 63 % to 69 %

THEN Q.Q IQ E 3, (67 % and 69 % for adverse STEAh! GENERATOR TUBE l

containment)

RUPTURE, Step 1.

28 CHECK SECONDARY RADIATION:

QQIQ E 3, STEAh! GENERATOR TUDE l

o Sample SGs fm activity -

RUP'rURE, STEP 1.

t NONE DETECTABLE 1

o Check steam line radiation levels -

INDICATE BACKGROUND 29 CHECK PAB RADIATION NORhiAL DETERhtINE CAUSE OF ABNORhfAL RADIATION LEVELS.

I IE DUE TO LOSS OF RCS COOLAST l OUTSIDE CONTAINhiENT, j

THEN QQ IQ ECA 1,2, LOCA OUTSIDE CONTAINhtENT, STEP 1.

I 30 CHECK PRT CONDmON NORhiAL:

DEERhilNE CAUSE OF ABNORhiAL :

CONDmONS.

j o Pressure 3 PSIG TO 8 PSIG WHEN HCP WL RELAYS RESET, t

o Temperature 80* F TO 120' F THEN PERFORhi NECESSARY l

o Level 80 % TO 87 %

ACrlONS TO RETURN CONDmONS '

TO NORhiAL l

I Page 12 of 15

JUN 0 31983 NUMBER TTTLE REV. ISSUE /DATE E.0 REACTOR TRIP OR SAFETY INJECTION Rev.4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7

r 1

CAUTION:

o IF OFF SITE POWER IS LOST AFTER RESE1 TING SI, hfANUAL ACTION AfAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPEbfENT.

o IF CONTROL SWITCH FOR ANY SHUTDOWN CHARGING PUAfP WAS TAKEN TO THE TRIP POSITION, THE PCAfP(S)

AfAY AUTO START WHEN BOTH SI WL RELAYS ARE RESET.

L J

31 RESET SI AND CONTAINMENT ISOLATION:

a. Check containment pressure -
a. Perform the following:

LESS THAN 5 PSIG

1. Open CKTs A13 and B13 in DC panels A and B.
2. Reset SI WL Relays.

3 IEchuging pump control switch (es) are b'QIin TPO, THEN restore low discharge i

pressure auto stan for shutdown charging pump (s) by taking pump control switch (es) to the "Trip position then releasing switch (es) to the "Auto" position.

l 4..

ftQIQ Step 32.

l

b. Reset SI and containment isolation (SEE OPPOSITE PAGE) l l

l Page 13 of 15

JUN O 31988 NUMBER TTTU REV. ISSUE /DATE E0 REACTOR TRIP OR SAFETY INJECTION Rev,4 J

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

32 CHECK CONTAINMENT START ONECOSTAINMENT INSTRUMENT AIR PRESSURE lhTRUMENT AIR COhiPRESSOR l

GREATER THAN 118 PSIG TO ESTABLISH INSTRUMENT AIR PRESSURE.

I F

7 CAUTION:

Af0NITOR RCS PRESSURE. lF RCS PRESSURE DECREASES TO LESS THAN 40$ PSIG (633 PSIG FOR ADVERSE l

CONTAINbfEhT), AfANUALLY START THE LPSI PUbfPS TO SUPPLY WATER TO THE RCS.

I I

L J

33 CHECK IF LPSI PUMPS SHOULD BE STOPPED:

a. Check RCS pressure -
a. GQIQ E 1.

I GREATER THAN 405 PSIG LOSS OF REACTOR OR (635 PSIG FOR ADVERSE SECONDARY COOLAhT, CONTAINMENT)

Step 1.

b. Check RCS pressure -
b. QQ IQ Step M.

STABLE Q1 INCREASING i

c. Stop LPSI pumps and place in standby l

i i

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t 1

Page 14 of 15

JUN 0 31988 NUMBER TTIU REV. ISSUE /DATE E.0 REACTOR TRIP OR SAFETY INJECTION Rev.4 i

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

)

34 CHECK IF DIESEL GENERATORS SHOULD BE STOPPED:

i

a. Verify ac emergency buses energized -
a. Try to restore off site power to BOTH TRAINS BY OFF SITE both trains.

l POWER (SEE OPPOSITE PAGE)

BUSES 8,4 and 5 IE NOI restored.

AED,

'DiEN load the following equipement BUSES 9,6 and 7 on the ac emergency buses:

I i

1.

MCC 5.

2.

Control air compressors.

3.

Semi vital 120 V buses.

4 Closed cooling system pumps.

5.

Battery charger 1 A.

6.

One component cooling water pump.

7.

One service water pump for ca'.h diesel genentor.

8.

IE semce wateris supplied to RHR heat exchangers, THEN use at least two service i

I water pumps.

9.

Start CART ANS as required to limit containment pressure and I

temperature, i

b. Stop any unloaded diesel generator and place it in standby (SEE OPPOSITE PAGE) 35 RETURNIQ STEP 18 j

l Eht Page 15 of 15

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