ML17250B110
| ML17250B110 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/09/1990 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250B096 | List:
|
| References | |
| ECA-3.2, NUDOCS 9004200676 | |
| Download: ML17250B110 (58) | |
Text
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 1 of 24 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LA T SUPERINTE E T
~f~.i.
EFFECT VE DATE QA 4 NON-QA REVIEWED BY:
CATEGORY 1.0 DATL=
TlM" DATE
~
I ~
Sooeaooe7a 900eio PDR ADO'5000244 p,
PNV TJME
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ECA-3.2 SGTR.WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 2 of 24 A.
PURPOSE This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from:
a.
ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, when RWST level is low without a corresponding increase in containment sump level.
b.
ECA-3.1',
SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, when the ruptured S/G level is high and plant staff selects saturated recovery method.
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 3 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28K, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
NOTE:
o Steps 1 through 14 of ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, should be performed before continuing with this procedure.
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 greater than 10-
~ R/hr.
1 Add Makeup To RWST As Necessary:
o Refer to S-9J, BLENDING TO RWST
-OR-o Refer to S-3.2D, TRANSFERRING WATER FROM CVCS HUT(S) TO RWST TO SFP
-OR-o Refer to Attachment SFP-RWST
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ECA-3. 2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
~ 8 PAGE 4 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION o
IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SV PUMPS AND ONE CCV PUMP WILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION VILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
o RCS PRESSURE SHOULD BE MONITORED.
IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
2 Check If RHR Pumps Should Be Stopped:
a.
Check RCS pressure:
\\
- 1) Pressure
- GREATER THAN 250 psig [465 psig adverse CNMT]
2)
RCS pressure
- STABLE OR INCREASING
- b. Stop RHR pumps and place in AUTO a.
Go to Step 3.
3 Check If S/G Secondary Side Is Intact,:
o Pressure in both S/Gs - STABLE OR INCREASING o
Pressure in both S/Gs - GREATER THAN 100 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldovnT
~ Steamlines
~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 5 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 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 5X [25X adverse CNMT]
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5X [25%
adverse CNMT] in at least one S/G.
- b. Control feed flow to maintain narrow range level between 17%
[25X adverse CNMT] and 50X
- b. IF narrow range level in the intact S/G continues to increase in an uncontrolled
- manner, THEN consider isolating unnecessary release paths:
~ TDAFW pump steam supply valves
~ S/G blowdown valves
~ Refer to Attachment RUPTURED S/G
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 6 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Shutdown margin should be monitored during RCS cooldown.
Refer to Figure SDM.
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 intact S/G
- c. Manually or locally dump steam using intact S/G ARV.
IF no intact S/G available, THEN perform the following:
o Use faulted S/G.
-OR-o IF RHR system NOT in
- service, THEN use ruptured S/G.
6 Check RCS Subcooling Based On Go to Step 18.
Core Exit T/Cs GREATER THAN O'F USING FIGURE MIN SUBCOOLING 7
Check Safeguards Pump Status o
SI pumps - ANY RUNNING
-OR-Go to Step 14.
o RHR pumps
- ANY RUNNING IN INJECTION MODE
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8 PAGE 7 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Place PRZR Heater Switches In The Following Positions:
o PRZR heater control group - PULL STOP o
PRZR heater backup group - OFF CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.
THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE:
o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o When using PRZR PORV, select one with an operable block valve.
9 Depressurize RCS To Refill PRZR a.
Use normal PRZR spray valve associated with running RCP
~ PCV-431A for A RCP
~ PCV-431B for B RCP b.
PRZR level - GREATER THAN 13%
[40X adverse CNMT]
- c. Stop RCS depressurization a.
Use one PRZR PORV.
IP IA NOT available, THEN refer to Attachment N2 PORVS.
IP no PORV available, THEN use auxiliary spray valve.
- b. Continue with Step 10.
WHEN level greater than 13X [40X adverse
- CNMTJ, THEN stop RCS depressurization.
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ECA'-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 8 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
10 Check If An RCP Should Be Started:
- a. Both RCPs STOPPED b.
RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING c.
PRZR level - GREATER THAN 13%
[40% adverse CNMT]
- d. Try to start an RCP
- 1) Establish conditions for starting an. RCP o
Bus llA or llB energized o
Refer to Attachment RCP START
- 2) Start one RCP a.
Stop all but one RCP and go to Step 11.
b.
Go to Step 18.
- c. Return to Step 9.
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 9 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 11 Check If One Of Three SI Pumps Should Be Stopped:
- a. Three SI pumps
- RUNNING b.
RCS subcooling based on core exit T/Cs - GREATER THAN 10'P
[10'F adverse CNMT] USING FIGURE MIN SUBCOOLING
- c. Check PRZR level - GREATER THAN 13K [40X adverse CNMT]
- d. Stop one SI pump a.
Go to Step 12.
- b. IP RCS hot leg temperatures greater than 325'F [270'P adverse CNMT] OR IP RHR normal cooling in service, THEN go to Step 18.
IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'P
[270'P adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step llc.
IP no RHR pump can be operated in in)ection mode, THEN go to Step 18.
c.
Do NOT stop SI pump. Return to Step 9.
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 10 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 12 Check If One Of Two SI Pumps Should Be Stopped:
a.
Tvo SI pumps
- RUNNING b.
RCS subcooling based on core exit T/Cs - GREATER THAN 35'F
[35'F adverse CNMT] USING FIGURE MIN SUBCOOLING c.
PRZR level - GREATER THAN 13X
[40X adverse CNMT]
- d. Stop one SI pump a.
Go to Step 13.
- b. IP RCS hot leg temperatures greater than 325'F [270'F adverse CNMT] OR IP RHR normal cooling in service, THEN go to Step 18.
IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'P
[270'P adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c.
IF no RHR pump can be operated in injection mode, THEN go to Step 18.
c.
Do NOT stop SI pump. Return to Step.9.
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SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 11 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
-13 Check If Last SI Pump Should Be Stopped:
a.
One SI pump - RUNNING
- b. Determine required RCS subcooling from table:
- a. IP any RHR pump running in in5ection mode, THEN go to Step 18.
IP NOT, THEN go to Step 14.
Charging Pump Availability NONE ONE TWO RCS Subcooling Criteria Insufficient subcooling to stop SI pump.
215'P
[215'P adverse CNMT]
150'P [150'F adverse CNMT]
80'F [80'F adverse CNMT]
c.
RCS subcooling based on core exit T/Cs - GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING d.
PRZR level - GREATER THAN 13%
[40% adverse CNMT]
e.
Stop running SI pump
- c. IF RCS hot leg temperatures greater than 325'F [270'F adverse CNMT] OR IP RHR normal cooling in service, THEN go to Step 18.
IP RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F
[270'F adverse CNMT], THEN ensure at least one RHR pump running in infection mode and go to Step 13d.
IF no RHR pump can be operated in injection mode, THEN go to Step 18.
d.
Do NOT stop SI pump.
Return to Step 9.
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ECA-3. 2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 12 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED.
14 Control Charging Flow To Maintain RCS Inventory:
BETWEEN 68X AND 73%
[73% AND 76% adverse CNMT]
-OR-o RVLIS fluid fraction (any RCP running) - BETWEEN 80X AND 90X Start charging pumps as necessary and ad)ust charging flow to maintain RCS inventory.
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 13 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
15 Check RCP Status:
a.
RCPs - AT LEAST ONE RUNNING a.
Perform the following:
- 1) Establish conditions for starting an RCP:
o Verify bus llA or llB energized.
o Refer to Attachment RCP START.
- 2) Start one RCP.
IF an RCP can NOT be started, THEN verify natural circulation
'Refer to Attachment NC).
IF natural circulation NOT
- verified, THEN increase dumping steam.
- b. Stop all but one RCP
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 14 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
'k * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- CAUTION o
VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.
THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
o IF SI HAS BEEN TERMINATED, THE ACCUMS SHOULD BE ISOLATED PRIOR TO DEPRESSURIZING THE RCS TO LESS THAN 1000 PSIG.
NOTE:
o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o When using PRZR PORV, select one with an operable block valve.
16 Depressurize RCS To Saturation At Core Exit:
- a. Determine saturation pressure for core exit T/Cs using Figure TSAT b.
Use normal PRZR spray valves associated with running RCP
~ PCV-431A for.A RCP
~ PCV-431B for B RCP
- c. Energize PRZR heaters as necessary
- d. Depressurize RCS until EITHER of the following conditions satisfied:
o PRZR level - GREATER THAN 75X
[65X adverse CNMT]
-OR-b.
Use one PRZR PORV.
IF IA NOT available, THEN refer to Attachment N2 PORVS.
IF PORV NOT available, THEN use auxiliary spray valve (AOV-296).
o RCS pressure
- AT SATURATION FROM STEP 16a
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 15 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 17 Verify Adequate Shutdown Margin
- b. Borate as necessary.
18 Verify SI Flow Not Required:
a.
Core exit T/Cs - DECREASING
- b. Check RVL'IS indication:
o Level (no RCPs)
- GREATER THAN 68X [73X adverse CNMT)
-OR-
- a. Increase dumping steam.
IF core exit T/Cs do NOT
- decrease, THEN manually operate SI pumps as necessary.
- b. Manually operate SI pumps as necessary.
o Fluid Fraction (any RCP running) - GREATER THAN 80X
0 4
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 16 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 19 Check If SI ACCUMs Should Be Isolated:
a.
RCS subcooling based on core exit T/Cs - GREATER THAN 0 F
USING FIGURE MIN SUBCOOLING b.
PRZR level - GREATER THAN 5%
[30% adverse CNMT]
~ MOV-841, MCC C position 12P
~ MOV-865, MCC D position 12C
- d. Close SI ACCUM discharge valves
~ MOV-841
~ MOV-865
- e. Locally reopen breakers for MOV-841 and MOV-865
- a. IP both RCS hot leg temperatures less than 400'F, THEN go to Step 19c.
IP NOT, THEN go to Step 20.
- b. Return to Step 9.
- d. Vent any unisolated ACCUMs:
- 1) Open vent valves for unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
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ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 17 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite power:
o Emergency D/G output breakers OPEN
- a. Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POVER).
o AC emergency bus voltage-GREATER THAN 420 VOLTS o
AC emergency bus normal feed breakers CLOSED
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 21 Minimize Secondary System Contamination:
- a. Isolate re)ect from hotwell to CST:
o Place hotwell level controller (HC-107) in MANUAL at 50%
o Verify hotwell level - STABLE
- b. Verify local actions to complete isolation of ruptured S/G (Refer to Attachment RUPTURED S/G)
- a. IF hotwell level increasing, THEN direct HP to sample hotwells for activity..
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SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 18 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 22 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least two SW pumps-RUNNING
- b. Verify AUX BLDG SW isolation valves OPEN
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED
- a. Manually start pumps as power supply permits (258 kw per pump).
IF less than two SW pumps can be operated, THEN go to Step 23.
23 Check RCP Cooling a.
Check CCW to RCPs Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o
Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW
- EXTINGUISHED
- b. Check RCP seal injection o
Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM
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ECA-3. 2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 19 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED O
24 Check If Seal Return Flow Should Be Established:
- a. Verify instrument bus D-ENERGIZED
- b. Verify RCP gl seal outlet temperature
- LESS THAN 235'P
- c. Verify RCP seal outlet valves-OPEN
~ AOV-270A
~ AOV-270B
- d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313 e.
Open RCP seal return isolation valve MOV-313
- f. Verify RCP fl seal leakoff flov
- LESS THAN 5.5 GPM
- g. Verify RCP fl seal leakoff flow
- GREATER THAN 0.25 GPM
- a. Perform the following:
- 1) Ensure steam dump mode control in MANUAL.
b.
Go to Step 25.
- c. Manually open valves as necessary.
e.
Perform the folloving:
- 1) Place MOV-313 svitch to OPEN.
- 2) Dispatch AO vith key to RVST gate to locally open MOV-313.
- f. IP any RCP seal leakoff flov greater than 5.5 gpm THEN:
o Close the affected RCP seal discharge valve
~ RCP A, AOV-270A
~ RCP B, AOV-270B o
Trip the affected RCP IP both RCP seal discharge valves are shut, THEN go to Step 25.
- g. Refer to AP-RCP.l, RCP SEAL MALFUNCTION.
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PAGE 20 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
25 Check If Source Range Detectors Should Be Energized:
a.
Source range channels-DEENERGIZED a.
Go to Step 25e.
- b. Check intermediate range flux-EITHER CHANNEL LESS THAN 1O-xo AMPS
- b. Perform the following:
- 1) IF neither intermediate range
,channel is decreasing, THEN initiate boration.
c.
Check the following:
o Both intermediate range channels
- LESS THAN 10-AMPS
- 2) Continue with Step 26.
WHEN flux is LESS THAN 10-'~ amps on any operable
- channel, THEN do Steps
- 25c, d and e.
- c. Continue with Step 26.
WHEN either condition met, THEN do Steps 25d and e.
-OR-o Greater than 20 minutes since reactor trip
- d. Verify source range detectors-ENERGIZED
- d. Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2
of 2).
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel IF source ranges can NOT be
- restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 26.
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8 PAGE 21 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 26 Establish Normal Shutdown Alignment:
a.
Check condenser
- AVAILABLE
- a. Dispatch.AO to perform Attachment SD-2.
- b. Perform the following:
o Open generator disconnects
~ 1G13A71
~ 9X13A73 o
Place voltage regulator to, OFF o
Open turbine drain valves o
Rotate reheater steam supply controller cam to close valves o
Place reheater dump valve switches to HAND o
Stop all but one condensate pump
- c. Verify adequate Rx head cooling:
- 2) Verify at least one control rod shroud fan - RUNNING
- 3) Verify one Rx compartment cooling fan - RUNNING
- d. Verify Attachment SD COMPLETE 1)
Go to Step 27.
- 2) Manually start one fan as power supply permits (45 kw)
- 3) Perform the following:
o Dispatch AO to reset UV relays at MCC C and MCC D.
o Manually start one fan as power supply permits (23 kw).
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ECA-3.2 TITLE:
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PAGE 22 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION FEED FLOV SHOULD NOT BE ESTABLISHED TO ANY RUPTURED S/G VHICH IS ALSO FAULTED UNLESS IT IS NEEDED POR RCS COOLDOVN.
27 Check Ruptured S/G(s)
Narrow Range Level GREATER THAN 174
[254 adverse CNMT]
Refill ruptured S/G to 67X [55X adverse CNMT] using feed flow.
IP either of the following conditions occurs, THEN stop feed flow to ruptured S/G unless needed for RCS cooldown:
o Ruptured S/G pressure decreases in an uncontrolled manner.
-OR-o Ruptured S/G pressure increases to 1020 psig.
28 Check If RCPs Must Be Stopped:
a.
- ANY RUNNING b.
Check the following:
o RCP gl seal D/P - LESS THAN 220 PSID a.
Go to Step 29.
b.
Go to Step 29.
-OR-o Check RCP seal leakage
- LESS THAN 0.25 GPM
- c. Stop affected RCP(s)
0
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 23 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 29 Check Condenser Steam Dump Available CONDENSER VACUUM GREATER THAN 20 INCHES HG Use intact S/G ARV for RCS temperature control.
30 Check If RHR Normal Cooling Can Be Established:
a.
RCS cold leg temperature LESS THAN 350'P a.
Go to Step 31.
b.
RCS pressure
- LESS THAN 400 psig [300 psig adverse CNMT]
- c. Place letdown pressure controller in MANUAL CLOSED b.
Go to Step 31,
- d. Check following valves OPEN
~ AOV-371, letdown isolation valve
~ AOV-427, loop B cold leg to REGEN Hx
~ At least one letdown orifice valve (AOV-200A, AOV-200B, or AOV-202)
- e. Verify pressure on PI-135 - LESS THAN 400 PSIG
- d. Perform the following:
- 1) Reset both trains of XY relays for AOV-371 and AOV-427.
- 2) Open AOV-371 and AOV-427.
- 3) Open one letdown orifice valve.
e.
Go to Step 31.
- f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OP THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
t'
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ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 24 of 24 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 31 Check Core Exit T/Cs LESS THAN 200'F Return to Step 4.
32 Evaluate Long Term Plant Status:
- a. Maintain cold shutdown conditions
- b. Consult TSC
-END-
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PAGE 1 of 1 ECA-3.2 APPENDIX LIST TITLE PAGES 1)
RED PATH
SUMMARY
2)
FIGURE MIN SUBCOOLING 3)
FIGURE SDM 4)
FIGURE TSAT 5)
ATTACHMENT SFP-RWST 6)
ATTACHMENT N2 PORVS 7)
ATTACHMENT NC 8)
ATTACHMENT SEAL COOLING 9)
ATTACHMENT RCP START 10)
ATTACHMENT D/G STOP 11)
ATTACHMENT AUX BLDG SW 12)
ATTACHMENT RUPTURED S/G 13)
ATTACHMENT SD-1 14)
ATTACHMENT SD-2 15)
ATTACHMENT RHR COOL 16)
FOLDOUT
ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
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 43~
[464 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
EOP:
ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication S
PRESSURE (PSIG)
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
20 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOLING REGION E CNMT ADVERS TEMPERATURE INCREMENTS 10'F NORMAL CNMT 0
250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
EOP:
ECA-3.2 1' TLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV:
8 PAGE 1 of 1
FIGURE SDM BORON CONCENTRATION (PPM) 1800 1600 BORON INCREMENTS 20 PPM 1400 1200 ADEQUATE SDM 1000 8OO 600 400 BORAT 200 BURNUP INCREMENTS 100 MWD/MTU 0
0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 CYCLE BURNUP (MVD/MTU)
NOTE: To obtain core burnup, use PPCS turn on code BURNUP.
EOP:
ECA-3.2 TITLE:
SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED REV 8
PAGE 1 of 1
FIGURE TSAT SAT 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
URATION PRESSURE (PSIG)
PRESSURE INCREMENTS 20 PSIG TEMPERATURE INCREMENTS 10'P 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('P)
0