ML17262A895
| ML17262A895 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/06/1992 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A884 | List: |
| References | |
| ES-3.3, NUDOCS 9206160407 | |
| Download: ML17262A895 (34) | |
Text
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ES-3 '
POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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
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ES-3.3 TITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV 6
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 GENERATOR TUBE RUPTURE, if plant, staff selects steam dump method.
b ~
ES 3 ~ 2 g POST SGTR COOLDOWN USING BLOWDOWNg when blowdown is not available and plant staff selects steam dump method.
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T!TLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV' PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- 4 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 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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ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV 6
PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2
Check If SI ACCUMs Should Be Isolated:
a.
Check the following:
o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING a.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1
~
o PRZR level -
GREATER THAN 5%
[30% adverse CNMT]
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM outlet valves
~ ACCUM A, MOV-841
~ ACCUM B, MOV-865
- c. Vent any unisolated ACCUMs:
- 1) Open vent valves for unisolated SI ACCUMs.
- d. Locally reopen breakers for MOV-841 and MOV-865
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
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TITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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
- b. Borate as necessary.
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 THAN 5%
[25% adverse CNMT)
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT) and 50%
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5S
[25%
adverse CNMT] in intact S/G.
- b. IF narrow range level in the intact S/G continues to increase 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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ES-3.3 T1TLE:
POST-SGTR COOLDOWN USXNG STE~
REV:
6 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 intact S/G
- b. Manually or locally dump steam 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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ES-3.3 LITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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 LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%
[40$ ADVERSE CNMT) o Increase RCS makeup flow o Depressurize RCS using Step 6b.
Increase RCS o Increase RCS makeup flow makeup flow o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%
[40% ADVERSE CNMT]
AND 50%
Depressurize RCS using Step 6b.
Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal BETWEEN 50%
AND 75%
o Depressurize
[65% ADVERSE CNMTj RCS using Step 6b.
o Decrease RCS makeup flow Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal GREATER THAN 75%
[65% ADVERSE CNMTj o Decrease RCS makeup flow Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal b.
Use normal PRZR spray to obtain desired results for Step 6a
- b. IF letdown is in service, THEN use auxiliary spray (AOV-296).
IF NOT, THEN use one PRZR PORV.
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ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV0 6
PAGE 8 of 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 If RCS Cooldown Should Be Stopped:
a.
RCS cold leg temperatures
- LESS, THAN 350'F
- a. Return to Step 3.
- b. Stop RCS cooldown 9
Check Ruptured S/G Narrow Range Level GREATER THAN 174
[254 adverse CNMT]
Refill ruptured S/G to 67%
[55%
adverse CNMT) using feed flow.
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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ES-3. 3 TITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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:
o Intact S/G MSIV -
OPEN o
Annunciator G-15, STEAM DUMP LIT
- a. Manually or locally dump steam using ruptured S/G ARV and go to Step 11.
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%
[40% adverse CNMT) b.
PRZR level LESS THAN 75%
[65%
adverse CNMT]
- a. Increase RCS makeup flow as necessary and go to Step 12.
b.
Decrease RCS makeup flow to decrease level and go to Step 13.
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TlTLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV' 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 spray associated with running RCP
- a. IF letdown is in service, THEN 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.
- ANY RUNNING b.
Check the following:
o RCP 51 seal D/P LESS THAN 220 PSID a.
Go to Step 14.
b.
Go to Step 14.
-OR-o Check RCP seal leakage LESS THAN 0.25 GPM
- c. Stop affected RCP(s)
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POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Check If RHR Normal Cooling Can Be Established a.
RCS cold leg temperature LESS THAN 350'F
- a. Return to Step 9.
b.
RCS pressure LESS THAN 400 psig [300 psig adverse CNMTj
- c. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
- b. Return to Step 9.
- c. IF RCS overpressure protection system can NOT be placed in
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 intact S/G
- c. Manually or locally dump steam 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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ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 16 Check Core Exit T/Cs LESS THAN 200'F Return to Step 9.
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
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POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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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ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV 6
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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ES-3 '
TlTLE'OST-SGTR COOLDOWN USING STEAM DUMP REV:
6 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)
RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION DVERSE NM NORMAL CNMT'NADEQUATE 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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lag 4 ~
4.
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ES-3.3 TITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV:
6 PAGE 1 of 1 BORON CONCENTRATION (PPH) 1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONSERVATISH INCLUDED 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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TITLE:
POST-SGTR COOLDOWN USING STEAM DUMP REV 6
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 2 ~
o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54
[30% adverse CNMT]
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 4 ~
IF RWST level decreases to less than 28%,
THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
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).