ML17262A895

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Rev 6 to EOP ES-3.3, Post-SGTR Cooldown Using Steam Dump.
ML17262A895
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/06/1992
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A884 List:
References
ES-3.3, NUDOCS 9206160407
Download: ML17262A895 (34)
v • d • e


Text

EOP:

REV: 6 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION, GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EF EC VE DATE CATEGORY 1.0 REVIEWED BY:

920bib0407 920b05 PDR ADOCK 05000244 P PDR

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EOP: TITLE:

REV 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 2 of 12 A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by dumping steam.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:
a. E-3 STEAM staff selects GENERATOR TUBE RUPTURE, steam dump method.

if plant, b ~ ES 3 ~ 2 I POST SGTR COOLDOWN US NG BLOWDOWNg plant staff g

when blowdown is not available and selects steam dump method.

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EOP: T!TLE:

REV' ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.

o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.

NOTE: o FOLDOUT page should be open AND monitored periodically.

Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

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EOP:

REV 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If SI Isolated:

ACCUMs Should Be

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step 1 ~

exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%

[30% adverse CNMT]

b. 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

c. Close SI ACCUM outlet valves c. Vent any unisolated ACCUMs:

~ ACCUM A, MOV-841 1) Open vent valves for

~ ACCUM B, MOV-865 unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.
d. Locally reopen breakers for MOV-841 and MOV-865

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EOP TITLE:

REV: 6 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration- b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE: TDAFW pump flow control valves fail open on loss of IA.

4 Check Intact S/G Level:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT) than 200 gpm until narrow range level greater than 5S [25%

adverse CNMT] in intact S/G.

b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase

[25% adverse CNMT) and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

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EOP: T1TLE:

REV: 6 ES-3.3 POST-SGTR COOLDOWN USXNG STE~

PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should be completed as quickly as possible, not to exceed 100'F/hr. I 5 Xnitiate RCS, Cooldown To 350'F:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Dump steam to condenser from b. Manually or locally dump steam intact S/G from intact S/G using S/G ARV.

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

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EOP: LITLE:

REV: 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 7 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage:

a. Perform appropriate action(s) from table:

PRZR RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase RCS Increase RCS o Increase RCS

[40$ ADVERSE CNMT) makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b. S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS

[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS

[65% ADVERSE CNMTj RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS

[65% ADVERSE CNMTj makeup flow PRZR and ruptured heaters S/G pressure equal

b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

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EOP:

REV0 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 8 o f 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8 Check Be If RCS Stopped:

Cooldown Should

a. RCS cold leg temperatures - LESS, a. Return to Step 3.

THAN 350'F

b. Stop RCS cooldown 9 Check Ruptured S/G Narrow Refill ruptured S/G to 67% [55%

Range Level GREATER THAN adverse CNMT) using feed flow.

174 [254 adverse CNMT]

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:

o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR-o Ruptured S/G pressure increases to 1020 psig.

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EOP: TITLE:

REV: 6 ES-3. 3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.

NOTE: Steam release from ruptured S/G may be stopped when RHR System is in service.

10 Initiate Cooldown Of Ruptured S/G:

a. Verify condenser available: a. Manually or locally dump steam using ruptured S/G ARV and go to o Intact S/G MSIV - OPEN Step 11.

o Annunciator G-15, STEAM DUMP LIT

b. Dispatch AO to locally open ruptured S/G MSIV bypass valve
c. Dump steam to condenser using steam dump pressure controller 11 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
a. PRZR level - GREATER THAN 13% a. Increase RCS makeup flow as

[40% adverse CNMT) necessary and go to Step 12.

b. PRZR level - LESS THAN 75% [65% b. Decrease RCS makeup flow to adverse CNMT] decrease level and go to Step 13.

EOP: TlTLE:

REV' ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The upper head region may void during depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:

a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray associated with running RCP depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.
b. Energize PRZR heaters as necessary
c. Maintain RCS pressure at ruptured S/G pressure
d. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING 13 Check If RCPs Must Be Stopped:
a. RCPs - ANY RUNNING a. Go to Step 14.
b. Check the following: b. Go to Step 14.

o RCP 51 seal D/P - LESS THAN 220 PSID

-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM

c. Stop affected RCP(s)

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EOP-REV: 6 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Can Be IfEstablished RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Return to Step 9.

THAN 350'F

b. RCS pressure - LESS THAN b. Return to Step 9.

400 psig [300 psig adverse CNMTj

c. Place RCS overpressure c. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
d. Establish RHR normal cooling (Refer to Attachment RHR COOL) 15 Continue RCS Cooldown To Cold Shutdown:
a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Use RHR System
c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step l.

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EOP:

REV: 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check Core Exit T/Cs LESS Return to Step 9.

THAN 200'F 17 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
b. Consult TSC

-END-

EOP:

REV: 6 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) FIGURE SDM
4) ATTACHMENT RHR COOL
5) FOLDOUT

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EOP:

REV 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY Nuclear power greater than 54
b. CORE COOLING Core exit T/Cs greater than 1200'F

-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 434 [46%

adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 5%

[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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EOP:

TlTLE'OST-SGTR REV: 6 ES-3 ' COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 SUBCOOLING 600 REGION 500 DV ERSE NM CNMT'NADEQUATE 400 300 200 NORMAL TEMPERATURE INCREMENTS 10'F 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

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EOP: TITLE:

REV: 6 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONSERVATISH INCLUDED 1000 800 600 400 BO TE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)

NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

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EOP: TITLE:

REV 6 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT " SUBCOOLED RECOVERY DESIRED, Step 1:

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

[30% adverse CNMT]

2 ~ SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.

3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

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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