ML20065K065
| ML20065K065 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1994 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A585 | List:
|
| References | |
| ES-3.1, NUDOCS 9404190141 | |
| Download: ML20065K065 (14) | |
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ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 9
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i ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER S
TECHNICAL REVIEW PORC REVIEW DATE
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EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
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REV: 8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 2 of 9 f's
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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-draining it through the ruptured S/G tubes into the RCS.
B.
ENTRY CONDITIONS / SYMPTOMS 1.
ENTRY CONDITIONS - This procedure is entered from:
a.
E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects backfill method.
b.
ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, when blowdown is not available and plant staff selects backfill method, t
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REV: 8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL i=
PAGE 3 of 9 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP CAUTION int.DVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION C00LDOWN IF THE RCP IN Tile RUPTURED LOOP IS STARTED FIRST.
FOLDOUT page should be open AND monitored periodically, NOTE:
o Adverse CNMT values should be used whenever CNMT pressure is o
greater than 4 psig_or CNMT radiation is greatir than 10+05 R/hr, 1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure
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ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 4 of 9
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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP l
2 Check If SI ACCUMs should Be Isolated:
a.
Check the following:
- a. Go to ECA-3.1, SGTR WITil LOSS OF REACTOR COOLANT - SUBC00 LED ICS subcooling based on core RECOVERY DESIRED, Step 1, o
exit T/Cs - CREATER TilAN O'F USING FIGURE MIN SUBC00 LING o PRZR level - GREATER THAN 5%
(30% adverse CNMT!
b.
Dispatch A0 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
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- c. Close S1 ACCUM outlet valves
- c. Vent any unisolated ACCUMs:
- ACCUh M'0V - 841
- 1) Open vent valves for
- ACCUM b,
MOV-865 unisolated SI ACCUMs.
- ACCUM A, A0V-834A
- ACCUM B, A0V 834B
- 2) Open HCV 945.
d.
Locally reopen breakers for MOV-841 and MOV-865 i
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8-ES-3.1:
. POST-SGTR COOLDOWN USING BACKFILL PAGE 5 of 9
-o STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
Leakage from ruptured S/G into RCS wf11 dilute RCS boron.
concentration.
+
3 Verify Adequate Shutdown Margin
- b. Verify boron concentration -
- b. Borate as necessary.
CREATER TilAN REQUIREMENTS OF FIGURE SDM CAUTION IF CST LEVEL DECREASES TO LESS TilAN 5 FEET, TilEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFWc PUMPS).
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TDAFW pump flow control valves fail open on loss of IA.
- 4 Monitor Intact S/G Level:
- a. Narrow range level - CP. EATER
- a. Maintain total feed flow greater TilAN 5% (25% adverse CNMT)
'than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in the intact S/G.
- b. Control feed flow to maintain
- b. Jl narrow range level in the narrow range level between 17%
intact S/G continvbx u 5.ncrease
[25% adverse CNMT) and 50%
in'an uncontro1FW w o w THEN.
go to ECA-3.1, SGTR WITH LOSS OF.
REACTOR-COOLANT - SUBCOOLED RECOVERY DESIRED, Step l'.
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4 POST-SGTR COOLDOWN USING BACKFILL ES-3.1 PAGE 6 of 9-
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STEP ACTION / EXPECTED RESPONSE RESPONSE ~NOT OBTAINED NOTE:
Since ruptured S/C may continue to'depressurize to.less than thr minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be cielayed.
5 Initiate RCS Cooldown To Cold Shutdown:
- a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100*F/HR
- b. Use RHR system if in service c.
Dump steam to condenser from
- c. Manually or locally dump steam-intact S/G using intact S/G ARV, H no intact S/G available and RHR system NOT in service, THEN-perform the following:
o Use faulted S/G.
-OR.
t o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBC00 LED RECOVERY DESIRED, Step 1.
- 6 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%
Range Level - LEVEL GREATER adverse CNMT] using feed flow.
THAN 17% (25% adverse CNMT)
E either of the following conditions occurs, THEN stop feed-flow to ruptured S/G:
o Ruptured S/G pressure decreases
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in an uncontrolled manner.
-OR-e o Ruptured S/G pressure increases lI to 1020 psig.
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ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP
- 7 Control-RCS Makeup Flow And Letdown To Maintain PRZR Level:
a.
PRZR level - CREATER THAN 13%
a.
Increase RCS makeup flow-'as
{40% adverse CNMT]
.necessary and go to Step 8,
- b. PRZR level LESS UlAN 75% [65%
NOTE:
The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.
- 8 Depressurize RCS To Backfill From Ruptured S/G:
P Depressurize using normal PRZR
- a. J.f letdown is in service, THEN a.
spray depressurize using auxiliary
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spray valve (A0V-296), IF NO,,I,
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TJLE!! use one..PRZR FORV,
- b. Maintain PRZR level - BETWEEN 13% AND 75% [BETWEEN 40% AND 65%
adverse CNMT)
- c. Check ruptured S/G level -
c..Stop RCS depressurization',
CREATER THAN 5% (25% adverse CNMT]
d.
Energize PRZR heaters as necessary
- e. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN 0*F USING FIGURE MIN SUBC00 LING
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POST-SGTR COOLDOWN USING BACKFILL PAGE 8 of 9-n V
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 9 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 or 02 REMOVAL i
FROM PRIMARY SYSTEM BY BURPING VCT) 10 check If RHR Normal Cooling Can Be Established:
- a. RCS cold leg temperature - LESS
- a. Go to Step 11.
j THAN 350*F
- b. RCS pressure - LESS THAN b.' Go to Step 11.
400 psig (300 psig adverse CNMT)
Place RCS overpressure
- c. IF'RCS overpressure protection c.
protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC.of O-OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if.
OVERPRESSURE PROTECTION SYSTEM)
RHR system is placed in service.
- d. Establish RRR normal cooling l
(Refer to Attachment RHR COOL)
- 11 Monitor RCP Operation:
a.
RCPs - ANY RUNNING a.'Go to Step 12.
- b. Check the following:
- b. Go to Step 12.
o RCP ul seal D/P - LESS THAN 220 PSID
-OR-Check RCP seal leakage - LESS o
THAN 0.25 GPM c.
Stop affected RCP(s)
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-ES-3il POST-SGTR COOLDOWN.USING BACKFILL
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Core Exit T/Cs - LESS
. Return to Step 3.
THAN 200*F-13 Evaluate Long Term Plant Status:
- a. Maintain cold shutdown conditions (Refer to 0-2.3, PIANT AT COLD OR REFUELING SHUTDOWN) r
- b. Consult TSC
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REV: 8 ES-3.1 POST-SCTR COOLDOWN USING BACKFILL PAGE 1 of 1
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,l ES-3.1 APPENDIX LIST TITLE PAGES 1)
RED PATH
SUMMARY
1 2)
FIGURE MIN SUBCOOLING 1
3)
FIGURE SDM 1
4)
ATTACHMENT RHR COOL 2
5)
FOLDOUT 1
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REV: 8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1
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SUMMARY
a.
SUBCRITICALITY - Nuclear power greater than 5%
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 43% [46%
adverse CNMT]
c.
HEAT SINK - Narrow range level in all S/Gs less than 5%
[25% 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 CONTAINMENT - CNMT pressure greater than 60 psig e.
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.h EOP: IiiUE : ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 \\_/ FOLDOUT PAGE 1. 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. OB o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT]. 2. SECONDARY INTEGRITY CRITERIA IP 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. !<^ M (,) 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION LE RWST level decreases to less than 28%, THEN go to ES-1,3, TRANSFER TO COLD LEG RECIRCULATION, Step 1. 9. AFW SUPPLY SWITCHOVER CRITERION LE 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). 5. M_ILIJIPLE S/G TUBE RUPTURE CRITERI A If any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1. p}}