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) | |
Text
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ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 9 ;
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1 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER S l
TECHNICAL REVIEW PORC REVIEW DATE - ' 3 b ' 'f O
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PLANT SUPERINTENDENT ll - ') . lj t ?
EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
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l 9404190141 940424 PDR P ADOCK 05000244 PDR
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, REV: 8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 2 of 9 f's . e-
'sj 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-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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- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION int.DVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION C00LDOWN IF THE RCP IN Tile RUPTURED LOOP IS STARTED FIRST.
NOTE: o FOLDOUT page should be open AND monitored periodically, o Adverse CNMT values should be used whenever CNMT pressure is 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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- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 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 o ICS subcooling based on core RECOVERY DESIRED, Step 1, 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
[" 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 l
- 2) Open HCV 945.
- d. Locally reopen breakers for i MOV-841 and MOV-865 i
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- 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).
((0_Tl: 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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. REV: .8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 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:
.1 o Ruptured S/G pressure decreases j in an uncontrolled manner. l
-OR-e o Ruptured S/G pressure increases lI to 1020 psig. 'I I
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- ES-3.1 POST-SGTR COOLDOWN USING BACKFILL
'PAGE 7 of 9
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STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 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% b. Decrease RCS makeup-flow to _
adverse CNMT) decrease level and go to Step'10.
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
- a. Depressurize using normal PRZR a. J.f letdown is in service, THEN
~
spray depressurize using auxiliary spray valve (A0V-296), IF NO,,I,
] 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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ES-3~1-REV: 8 j POST-SGTR COOLDOWN USING BACKFILL
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- - STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
9 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 or 02 REMOVAL i FROM PRIMARY SYSTEM BY l BURPING VCT) l 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)
- 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 .
O- 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-o Check RCP seal leakage - LESS THAN 0.25 GPM .
- c. Stop affected RCP(s)
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'REV: 8 '~
-ES-3il POST-SGTR COOLDOWN.USING BACKFILL '
'PAGE 9 of.9
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i 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
-END-3 O
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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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RED PATH
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
- e. CONTAINMENT - CNMT pressure greater than 60 psig
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i EOPi ilILE: REV: 8 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE.1 of 1
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FIGl'7 1Dji NOTE: o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod. o To obtain core burnup, use PPCS turn on code BURNUP. BORON CONCENTRATION (PPM) 1800 ---
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.h EOP: IiiUE : ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1
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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.
(,)
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- 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.
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