ML17250B101

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Rev 4 to E-2, Faulted Steam Generator Isolation
ML17250B101
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/09/1990
From: Widay J
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17250B096 List:
References
E-2, NUDOCS 9004200639
Download: ML17250B101 (62)
v • d • e


Text

EOP:

E-2 TITLE:

FAULTED STEAM GENERATOR ISOLATION REV:

4 PAGE 1 of 7 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE T SUPERINT ND NT EFFECTIVE DATE

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~ ~'x QA NON-QA CATEGORY 1.0 REVIEWED BY:

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EOP:

E-2 TITLE:

FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 2 of 7 A.

PURPOSE This procedure provides actions to identify and isolate a faulted steam generator.

B.

ENTRY CONDITjONS/SYMPTOMS 1.

ENTRY CONDITIONS This procedure is entered from:

a.

E-O, REACTOR TRIP OR SAFETY INJECTION, with the following symptoms:

1)

Any S/G pressure decreasing in an uncontrolled manner.

2)

Any S/G completely depressurized.

b ~

E 1 ~

LOSS OF REACTOR OR SECONDARY COOLANTg E

3 f STEAM GENERATOR TUBE RUPTURE g ECA 3

1 ~

SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, and ECA 3 ~ 2 g SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED, with the following symptoms and/or conditions:

1)

Any S/G pressure decreasing in an uncontrolled manner.

2)

Any S/G completely depressurized.

3)

Faulted S/G isolation not verified.

c ~

FR H 5 g

RESPONSE

TO STEAM GENERATOR LOW LEVELS when the affected S/G is identified as faulted.

d.

Other procedures whenever a faulted S/G is identified.

EOP:

E-2 TITLE:

FAULTED STEAM GENERATOR ISOLATION REV:

4 PAGE 3 of 7 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION o

AT LEAST ONE S/G MUST BE MAINTAINEDAVAILABLEFOR RCS COOLDOWN.

o ANY FAULTED S/G OR SECONDARY BREAK SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

NOTE:

o Critical Safety Function Status Trees should be monitored.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10

~ R/hr.

1 Check MSIV Of Affected S/G(s)

CLOSED Manually close valve.

2 Check If Any S/G Secondary Side Is Intact:

o Check pressure in S/G A - STABLE OR INCREASING

-OR-IF both S/G pressures decreasing in an uncontrolled manner, THEN go to ECA-2.1, UNCONTROLLED

'EPRESSURIZATION OF BOTH STEAM GENERATORS, Step l.

o Check pressure in S/G B - STABLE OR INCREASING 3 Identify Faulted S/G:

o ANY S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER

-OR-o ANY S/G COMPLETELY DEPRESSURIZED Search for initiating break and go to Step 6.

~ Main steamlines

~ Main feedlines

~ S/G blowdown system

~ Sample system

EOP:

E-2 FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 4 of 7 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 4 Isolate Feed Flow To Faulted S/G:

o Close faulted S/G MDAFW pump discharge valve

~ S/G A, MOV-4007

~ S/G B, MOV-4008 o

Pull stop faulted S/G MDAFW pump o

Close faulted S/G TDAFW flow control valve

~ S/G A, AOV-4297

~ S/G B, AOV-4298 o

Verify faulted S/G MFW regulating valve and bypass valve - CLOSED Manually close valves.

IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.

~ S/G A, HCV-466 and HCV-480

~ S/G B, HCV-476 and HCV-481 o

Verify MFW pump discharge valves

- CLOSED

~ 'S/G A, MOV-3977

~ S/G B, MOV-3976 o

Verify MDAFW pump crosstie valves - CLOSED

~ MOV-4000A

~ MOV-4000B

EOP:

E-2 FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 5 of 7 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 5 Isolate Steam Flow From Faulted S/G:

o Verify faulted S/G ARV - CLOSED

~ S/G A; AOV-3411

~ S/G B) AOV-3410 o

Close faulted S/G TDAPV pump steam supply valve and place in PULL STOP Manually close valves.

IP valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.

~ S/G A, MOV-3505A

~ S/G B, MOV-3504A o

Verify faulted S/G blowdown and sample valves

- CLOSED

~ S/G A, AOV-5738 and AOV-5735

~ S/G B, AOV-5737 and AOV-5736 o

Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G) 6 Check CST Level GREATER THAN 5 FEET Switch to alternate APV water supply (Refer to ER-APW.l, ALTERNATE VATER SUPPLY TO APW PUMPS).

EOP:

E-2 FAULTED STEAM GENERATOR ISOLATION REV:

4 PAGE 6 of 7 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 7

Check Secondary Radiation Levels NORMAL o

Steamline radiation monitor (R-31 and R-32) o Air ejector radiation monitor (R-15) o S/G blowdown radiation monitor (R-19) o Request HP sample S/Gs for activity IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.

IF abnormal radiation levels detected in any S/G, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

8 Adjust Steam Dump To Minimize RCS Heatup:

a. Determine allowable intact S/G pressure using maximum hot leg temperature (Refer to Attachment INTACT S/G PRESSURE)
b. Check condenser steam dump available:

o Verify intact S/G MSIV -

OPEN o

Verify annunciator G-15, STEAM DUMP - LIT

c. Verify steam dump mode selector switch in MANUAL
b. Perform the following:
1) Adjust intact S/G ARV to pressure determined from Figure INTACT S/G PRESSURE.

2)

Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.

d. Adjust condenser steam dump controller in AUTO to pressure determined from Figure INTACT S/G PRESSURE

EOP:

E-2 TITLE:

FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 7 of 7 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 9

Go To E

1 I LOSS OF REACTOR OR SECONDARY COOLANT, Step 1

-END-

E-2 FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 1 of 1 E-2 APPENDIX LIST TITLE PAGES 1)

FIGURE INTACT S/G PRESSURE 2)

ATTACHMENT FAULTED S/G

EOP:

E-2 TITLE:

FAULTED STEAM GENERATOR ISOLATION REV 4

PAGE 1 of 1 FIGURE INTACT S G PRESSURE INTACT S/G PRESSURE (PSIG) 1100 1000 S/G PRESSURE INCREMENTS 10 PSIG 900 800 700 INTACT S/G PRESSURE SETPOINT 600 50O 400 300 200 100 TEMPERATURE INCREMENTS 10'P 200 250 300 350 400 450 500 550 600 650 700 MAXIMUM HOT LEG TEMPERATURE ('P)

EOP:

ES-0.3 TlTLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 1 of 15 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EF ECT VE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID XN VESSEL REV:

2 PAGE 2 of 15 A.

pURpOSE This procedure provides actions to continue plant cool-down and depressurization to cold shutdown, with no accident in

progress, under conditions that allow for the potential formation of a void in the upper head region.

B.

SYMPTOMS=AND OR ENTRY CONDITIONS 1.

ENTRY CONDITIONS This procedure is entered from:

A)

B)

ES-0.2, NATURAL CIRCULATION COOLDOWN, after completing the first 9 steps, if rapid cooldown or depressurization.is required.

ES-0.2, NATURAL CIRCULATION COOLDOWN, if depressurization is required which may result in upper head voiding.

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION"COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION o

IF SI ACTUATION OCCURS DURING THIS PROCEDURE, E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.

o THE PIRST 13 STEPS OF ES-0.2, NATURAL CIRCULATION COOLDOWN, SHOULD BE PERFORMED BEFORE CONTINUING WITH THIS PROCEDURE.

NOTE:

o Foldout page should be open and monitored periodically.

o If conditions can be established for starting an RCP during this procedure, then Step 1 should be repeated.

1 Try To Start An RCP:

a. Verify Bus llA or Bus llB-

,ENERGIZED

b. Check RVLIS indication:

o At least one train of RVLIS-AVAILABLE o

Level (no RCPs)

- GREATER THAN 95X

c. Establish conditions for starting an RCP (Refer to Attachment RCP START)
d. Start one RCP e.

Any RCP - RUNNING

f. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION a.

Go to Step 2.

b. Perform the following:
1) Increase PRZR level to 65X using charging and letdown.

2)

Dump steam to establish subcooling based on core exit T/Cs greater than 20'P using Figure MIN SUBCOOLING.

c.

Go to Step 2.

e.

Go to Step 2.

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WXTH STEAM VOID XN VESSEL REV 2

PAGE 4 of 15 STEP ACTION/EXPECTED RESPONSE.

RESPONSE

NOT OBTAINED NOTE:

Saturated conditions in the PRZR should be established before trying to decrease PRZR level.

2 Establish PRZR Level To Accommodate Void Growth:

a.

Check PRZR level - BETWEEN 20X AND 30X

b. Place charging pump speed controllers in MANUAL
a. Control charging and letdown as necessary.

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WXTH STEAM VOID IN VESSEL REV:

2 pA>E 5 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAXNED CAUTION o

BORON ADDITXON TO ESTABLISH, CSD CONCENTRATION SHOULD BE COMPLETE BEFORE DECREASING RCS TEMPERATURE LESS THAN 500'F.

o THE AT BETWEEN PRZR LIQUID 'ANLI THE HOT LEG TEMPERATURE SHOULD NOT BE PERMITTED TO EXCEED 200'F.

XF THIS LIMIT IS EXCEEDED, THEN NOTIFY TECHNICAL ENGXNEERING OR THE MAXIMUM hT OBSERVED.

NOTE:

RCS hot leg temperatures will decrease after cooldown is stopped due to decrease in loop delta Ts.

3 Decrease RCS Hot Leg Temperatures To 500'F:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 50'F/HR
b. Control RCS pressure between 1900 psig and 1950 psig c., Maintain RCS cold leg

.temperatures and pressure-WITHIN LIMITS OF RIGURE NC C/D WITH VOID IN UPPER HEAD

d. Maintain stable PRZR level using charging e.

Check RCS hot leg temperatures-LESS THAN 500'F

e. Return to Step 3a.
f. Stop RCS cooldown

'I f

a1

'a

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 6 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLYUNBLOCK IF PRZR PRESSURE INCREASES TO GREATER THAN 1992 PSIG.

4 Verify SI Blocked:

o SI block switches in BLOCK

~ Train A

~ Train B o

SAFETY INJECTION BLOCKED status light - LIT Perform the following:

a. Verify PRZR pressure less than 1950 psig.
b. Place SI block switches to BLOCK: )

~ Train A

~ Train B

c. Verify SAFETY INJECTION BLOCKED status light lit.

d.

Go to Step 5.

IF SI can NOT be blocked, THEN maintain PRZR pressure greater than 1750 psig and S/G pressure greater than 514 psig until SI blocked.

~

)

~ ~

EOP:

ES-0.3 TITLE NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 7 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.

THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE:

o If charging line to PRZR vapor aT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.

o WHEN using a PRZR

PORV, THEN select one with an operable block valve.

o If auxiliary spray is in use, spray flow may be increased by closing.normal charging valve AOV-294 and normal PRZR spray valves.

5 Depressurize RCS To 1500 PSIG:[

a.

Check letdown - IN SERVICE

b. Depressurize RCS using auxiliary spray valve (AOV-296)
c. Check RCS pressure-APPROXIMATELY 1500 PSIG
d. Stop RCS depressurization
a. Try to establish letdown (Refer to Attachment LETDOWN).

IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 5c.

b. IF auxiliary spray valve NOT available, THEN use one PRZR PORV.
c. Return to Step 5a.

f l

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 8 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 6 Isolate SI ACCUMs:

a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

~ MOV-841, MCC C position 12F

~ MOV-865, MCC D position 12C

b. Close SI ACCUM discharge valves

~ ACCUM A, MOV-841

~ ACCUM,B, MOV-865

c. Locally open breakers for MOV-841 and MOV-865
b. Perform the following:

I

'I

1) Dispatch personnel to locally close valves, as necessary.
2) Maintain RCS pressure greater than 1000 psig until both SI ACCUMs isolated.

IF any SI ACCUM can NOT be isolated AND RCS depressurization to less than 1000 psig is required, THEN:

1) Open vent valves for unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.
3) Maintain RCS pressure greater than SI ACCUM pressure.

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EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV 2

PAGE 10 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 8

Control PRZR Level:

a. Level - GREATER THAN 20X.
b. Level - LESS THAN 90%
a. Control charging and letdown to increase PRZR level to greater than 20X.
b. Perform the following:
1) Turn on PRZR heaters to increase RCS pressure by 100 psi.
2) Decrease PRZR level to less than 30% by one of the following:

o Control charging as necessary.

-OR-o Continue cooldown to shrink RCS inventory.

9 Check RVLIS Indication:

a. At least one train of RVLIS-AVAILABLE a.

Go to Step 10.

b. Check RVLIS level (no RCPs)-

GREATER THAN 84X

b. Perform the following:
1) Repressurize RCS to maintain RVLIS level greater than 84%.
2) Return to Step 7.

'5. t8

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 11 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE'NOT OBTAINED 10 Maintain Letdown Flow:

a.

Open letdovn orifice isolation valves as necessary

b. Adjust lov pressure letdovn pressure controller as necessary ll Maintain Required RCP Seal Injection Flow And Labyrinth Seal D/P:

o Seal injection flow to each RCP

- GREATER THAN 6 GPM o

Labyrinth seal D/P to each RCP-GREATER THAN 15 INCHES OP WATER IR RCP seal injection in service, THEN perform the following:

o Adjust charging flov to REGEN Hx (HCV-142) as necessary.

-OR-o Dispatch AO to adjust seal in)ection needle valves if necessary.

~ RCP A, V-300A

~ RCP B, V-300B IP RCP seal injection NOT in

service, THEN go to Step 12.

~ I

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EOP:

ES-0 '

TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 12 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 12 Check If SI System Normal Shutdown Alignment Should Be Established:

a.

RCS cold leg temperature

- LESS THAN 350'P b.

RCS pressure

- LESS THAN 1500 PSIG

c. Lock out SI system as follows:
1) Place all SI pump switches in PULL STOP
a. Return to Step 7.
b. Stabilize RCS temperature and return to Step 7.
2) Locally close breakers for SI pump discharge valves to cold legs

~ MOV-878B, MCC D position 8C

~ MOV-878D, MCC D position 8P

3) Close SI pump discharge to cold legs

~ MOV-878B

~ MOV-878D

4) Locally open breakers for MOV-878B and MOV-878D

L4

~ '

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 13 of 15 STEP

,ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 13 Check If RHR Normal Cooling Can Be Established:

a.

RCS pressure

- LESS THAN 400 PSIG)

a. Stabilize RCS temperature and return to Step 7.
b. Verify all SI pump switches in PULL STOP
b. Return to Step 12.

c.

Sample the RHR system to ensure adequate boron concentration (Refer to Attachment RHR SAMPLE)

. c'.. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

e. Establish RHR normal cooling (Refer to Attachment RHR COOL)
d. IF RCS overpressure protection system can NOT be placed in
service, THEN consult Plant staff to determine if RHR normal cooling should be established and go to Step 14.

14 Continue RCS Cooldown To Cold Shutdown

t~

4

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOXD IN VESSEL REV 2

PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT, OBTAINED CAUTION DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS IS LESS THAN 200'P MAY RESULT IN ADDITIONALVOID FORMATION IN THE RCS.

15 Continue Cooldown Of Inactive Portion Of RCS:

a. Cool upper head region using control rod shroud fans
b. Cool S/G U-tubes by dumping steam from all S/Gs
c. Check RVLIS indication:
1) At least one train of RVLIS-AVAILABLE
2) Level (no RCPs)

- GREATER THAN 95Po 1)

Go to Step '16.

2) Stabilize RCS pressure and return to Step 14.

1

EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION IF NO CONTROL ROD SHROUD FANS ARE RUNNING, THE UPPER HEAD REGION MAY REMAIN ABOVE 200'F FOR UP TO 29 HOURS AFTER REACHING CSD.

16 Determine If RCS Depressurization Is Permitted:

a.

Check PRZR level - LESS THAN 30%

b. Entire RCS - LESS THAN 200'F

~ Core exit T/Cs

~ Upper head T/Cs

~ RCS hot leg temperature

~ RCS cold leg temperature

c. Check control rod shroud fan status

- BOTH-RUNNING DURING COOLDOVN

d. Refer to 0-2.3, PLANT AT COLD SHUTDOVN
a. Perform the following:
1) Turn on PRZR heaters to maintain PRZR pressure stable.
2) Decrease PRZR level to less than 30% by one of the following:

o Control charging as necessary.

-OR" o

Continue cooldown to shrink RCS inventory.

b.

Do NOT depressurize RCS.

Return to,Step 14.

c. Consult Plant staff to determine wait period for upper head cooling.

-END-

4

~ 0 e

EOP:

TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 1 of 1 ES-0.3 APPENDIX LIST TITLE PAGES 1)

RED PATH

SUMMARY

2)

FIGURE MIN SUBCOOLING 3)

FIGURE NAT C/D WITH VOID IN UPPER HEAD 4)

ATTACHMENT RCP START 5)

ATTACHMENT RHR COOL 6)

ATTACHMENT RHR SAMPLE 7)

ATTACHMENT LETDOWN 8)

FOLDOUT

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EOP:

ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV 2

PAGE 1 of 1 RED PATH

SUMMARY

a.

SUBCRITICALITY Nuclear power greater than 54 CORE COOLING Core exit T/Cs greater than 1.200'F

-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43~ [464 adverse CNMT]

c.

HEAT SINK Narrow range level in all S/Gs less than 54

[254 adverse CNMT] AND total feedwater flow less than 200 gpm d.

INTEGRITY Cold leg temperatures decrease greater than 100 F in last 60 minutes AND RCS cold leg temperature less than 285'F e.

CONTAINMENT CNMT pressure greater than 60 psig

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ES-0 '

TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV' PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:

Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

S PRESSURE (PSIG)

SUBCOOLED REGION DV A

ERS RCS PRESSURE INCREMENTS 20 PSIG NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

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EOP:

ES-0. 3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 1 of 1 RCS 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

PRESSURE (PSIG)

RCS PRESSURE INCREMENTS 20 PSIG FIGURE NC C

D WITH VOID IN UPPER HEAD RCS TEMP FOR S/G SI (514 PSIG)

SI UNBLOCK A

V 0I D

NORMAL

.I RANGE TEMPERATURE INCREMENT'T6 10'F 0

50 100 150 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE ( F)

0

EOP:

ES-0.3 TITLE NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV:

2 PAGE 1 of 1 FOLDOUT PAGE 1.

RCP TRIP CRITERIA 2 ~

IF BOTH conditions listed below occur, THEN trip both RCPs:

a.

SI pumps AT LEAST TWO RUNNING b.

RCS pressure minus maximum S/G pressure LESS THAN 175 PSIG SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST level decreases to 104, THEN ensure SI pump automatic switchover to RWST.

3.

SI ACTUATION CRITERIA IF EITHER condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step l.

o RCS subcooling based on core exit T/Cs LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING OR o

PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 4 ~

AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

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EOP:

TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)

REV!SION:

STEP DIFFERENCE FOR GINNA EMERGENCY OPERATING PROCEDURES ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL Page 1 of 6

4 4%gr

EOP ES-0.3 TITLE:

NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL. (WITH RVLIS)

REV IS I OII:

STEP DIP REV NUMBER A

E ED S

S PROCEDURE REV NUMBER PROCEDURE REV DATE e jr~

Page 2 of 6

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