ML19277E978
| ML19277E978 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/19/2019 |
| From: | Exelon Generation Co LLC |
| To: | NRC/RGN-III/DRS/OLB |
| Seymour J | |
| Shared Package | |
| ML17214A828 | List: |
| References | |
| Download: ML19277E978 (9) | |
Text
18-1 NRC 1 Page 1 of 24 Simulation Facility Braidwood Scenario No.:
NRC 1 Operating Test No.: 18-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-18 Turnover Unit 1 is at 75% power, steady state, equilibrium Xenon, BOL. On-line risk is green.
Following completion of turnover, the Shift Manager requests the BOP swap GC pumps per BwOP GC-5, SWITCHING THE STANDBY AND OPERATING GC PUMPS, due to elevated vibrations on 1A GC pump. EOs have been briefed and are standing by at the stator water cooling skid. The 1A FW pump is OOS for a motor bearing replacement. 1FT-543 is OOS for troubleshooting by FIN.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF FW43 IMF FW49C IMF FW01 IOR ZLO1FW002A1 OFF IOR ZDI1FW002A CLS IRF FW027 0 IMF TC03 IOR ZDI1HSTG010 NORM IMF MS01A 100 IMF MS01B 100 IMF MS01C 100 IMF MS01D 100 Trigger 1 (RP:SI(1).EQ. TRUE)
IMF HV18B IMF RX03H 0 1A AF pump fails to start 1C CD/CB pump auto-start failure 1A MFP OOS Main turbine auto trip failure Main turbine manual trip pushbutton failure 1A-1D MSIVs failed open SI actuation trigger 0B MCR Return Fan trip on SI Place 1FT-543 OOS for troubleshooting 1
None N-BOP N-SRO Swap stator water cooling (GC) pumps 2
IRF ED019 OPEN T-SRO Loss of Instrument Bus 114 3
IMF SLIM12ManPB PRESSED IMF SLIM12OutIncPB PRESSED IMF SLIM12pwrFail_mft TRUE I-ATC I-SRO Master Pressurizer Level Controller (1LK-0459) output fails high 4
IMF PB2198 ON IMF FW44 T-SRO 1B AF pump local alarm (Air Box Trip) 5 IMF FW22D IMF FW49C (preload)
C-BOP C-SRO 1D CD/CB pump trip with 1C CD/CB pump auto-start failure 6
IMF FW02A TRIP R-ATC N-BOP R-SRO 1B FW pump trip with turbine runback 7
IMF CV03 C-ATC C-SRO Boric Acid Transfer Pump Trips during runback.
18-1 NRC 1 Page 2 of 24 8
IMF RP09A IMF FW19B 3.5 M-All Inadvertent FWI / 1B SG feedline break / loss of heat sink 9
Preload C-BOP C-SRO Turbine auto & manual trip failure 10 Preload C-BOP C-SRO 0B MCR Return Fan trip on SI 11 Preload C-All 1A AF pump fails to start
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient SCENARIO OVERVIEW Unit 1 is at 75% power, steady state, equilibrium Xenon, BOL. On-line risk is green. Following completion of turnover, the Shift Manager requests the BOP swap GC pumps per BwOP GC-5, SWITCHING THE STANDBY AND OPERATING GC PUMPS, due to elevated vibrations on 1A GC pump. EOs have been briefed and are standing by at the stator water cooling skid. The 1A FW pump is OOS for a motor bearing replacement. 1FT-543 is OOS for troubleshooting by FIN.
After completing shift turnover and relief, the crew will perform BwOP GC-5 to swap the operating GC pumps. The BOP will start the 1B GC pump and shutdown the 1A GC pump with the ATC giving peer checks as applicable. An EO will report a good start/shutdown of the GC pumps.
When BwOP GC-5 is complete, Instrument Bus 114 will deenergize and show signs of damage with no fire. The crew will check controlling channels and respond per 1BwOA ELEC-2. Time permitting, the crew may perform actions for the deenergized PRNI channel per 1BwOA INST-1. Bistables will not be bypassed due to requiring additional NSO support (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> delay). The SRO will enter Tech Spec 3.8.9 Condition B for the instrument bus failure.
After the crew has completed actions for the Instrument Bus 114 failure, the Master Pressurizer Level Controller (1LK-0459) output will fail high prior to losing power. The crew will take manual control of the 1CV121 controller and manually control charging flow to restore PZR level. The SRO will establish a critical parameter for pressurizer level being in manual control.
When the crew has completed taking the actions for the Master Pressurizer Level Controller failure, a trouble alarm will come in for the 1B AF Pump. The crew will dispatch an EO to the 1B AF pump. The EO will report that the 1B AF Pump Air Box Tripped annunciator is in alarm on the local control panel. The airbox trip lever will not reset. The SRO will enter Tech Spec 3.7.5 Condition A for the 1B AF pump.
After the SRO has evaluated Tech Specs for the 1B AF pump, the 1D CD/CB pump will trip with the standby 1C CD/CB pump failing to auto-start. The crew will start the 1C CD/CB pump per 1BwPR 1 A9 and dispatch an EO to the breaker and pump to investigate. The crew will enter 1BwOA SEC-1 (Attachment C) for the CD/CB pump trip.
After the crew has started the 1C CD/CB pump and stabilized the plant, the hydraulic transient will cause a trip of the 1B FW pump. The crew will respond per 1BwPR 1-16-A1,B1,C1 and initiate a turbine runback and enter 1BwOA SEC-1 (Attachment A). The ATC will borate to restore rod position above the rod insertion limit.
During the runback, the boric acid transfer pump will trip. The crew will respond per BwAR 1-9-A4 and align alternate per BwOP AB-23.
After sufficient reactivity control is observed and the Unit 0 boric acid transfer pump is aligned to Unit 1, an inadvertent feedwater isolation and 1B SG feedline break inside Cnmt will occur. The crew will trip the reactor, verify reactor trip and enter 1BwEP-0 to address the reactor trip. During the immediate actions, the main turbine will fail to trip and the BOP will have to manually runback the
18-1 NRC 1 Page 3 of 24 turbine. The B train ESF loads will have to be manually started due to the loss of Instrument Bus 114.
When SI actuates, the 0B VC Return Fan will trip requiring the crew to swap to the 0A VC train. The 1A AF pump will fail to start and the crew will enter 1BwFR-H.1 due to a loss of heat sink. Wide range SG levels will be less than 43% (adverse Cnmt) and the crew will initiate bleed and feed. Scenario completion criteria is the establishment of bleed and feed.
Critical Tasks:
- 1. Manually trip the main turbine before a severe challenge (ORANGE path) develops to either subcriticality or integrity critical safety function or before transition to 1BwCA-2.1, whichever happens first. (Westinghouse - CT-13) (K/A Number - EPE007 EA1.07, Importance - 4.3/4.3)
- 2. Establish RCS bleed and feed before either PZR PORV opens automatically as a result of a loss of heat sink. (Westinghouse - CT-44) (K/A Number - EPEE05 EA1.1, Importance - 4.1/4.0)
18-1 NRC 2 Page 1 of 23
Simulation Facility Braidwood Scenario No.:
NRC 2 Operating Test No.: 18-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-21 Turnover Unit 1 is at 100% power, steady state, equilibrium Xenon, BOL. Online risk is green.
Following completion of turnover, Radiation Protection is standing by for a shutdown of the 1PR11J for a filter change. 1FT-543 is OOS for troubleshooting by FIN.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF SI01B IRF RP30 OUT IMF SI12A IOR ZDI1CV8112 OPEN IRF ED500 1220 IMF RX03H 0 1B SI pump fails to start Phase A slave relay fails to actuate (1CV8100, 1IA065, 1PS228A/B, 1PR001A, 1CV8152) 1A SI pump auto-start failure 1CV8112 failed open Set AND computer to current AND MWe Place 1FT-543 OOS for troubleshooting.
1 None N-BOP N, T-SRO 1PR11J filter change 2
IRF ED500 1120 R-ATC N-BOP R-SRO Advanced Nuclear Dispatch (AND) order to lower load by 100 MWe at 4 MW/minute 3
IMF RX28J 0 T-SRO 1FT-444 RCS Loop flow Transmitter Failure.
4 IMF CV42B SHAFT SHEAR C-ATC T, C-SRO 1B CV pump shaft shear 5
IMF RX03G 0 15min I-BOP I-SRO 1FT-542 Fails Low over 15 minutes.
6 IMF RP11A DMF RP11A C-BOP C-SRO Inadvertent Phase B (train A only) 7 IMF CV27D 30 IMF TH06D 1500 M-All 1D RCP seal failure causing an RCS LOCA 8
Preload C-ATC C-SRO 1A SI pump fails to auto-start on SI with 1B SI pump tripped 9
Preload C-ATC C-SRO 1CV8100 fails to auto-close on Phase A with 1CV8112 failed open
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
18-1 NRC 2 Page 2 of 23
SCENARIO OVERVIEW Unit 1 is at 100% power, steady state, equilibrium Xenon, BOL. Online risk is green. Following completion of turnover, Radiation Protection is standing by for a shutdown of 1PR11J for a filter change.
After completing shift turnover and relief, the crew will shutdown the 1PR11J at Rad Protections request. The BOP will shutdown 1PR11J. The SRO will enter Tech Spec 3.4.15 Condition B while the 1PR11J is shutdown and exit the Tech Spec LCO when 1PR11J is restarted.
The BOP will restart 1PR11J after the filter change is complete.
Once 1PR11J is restarted, an Advanced Nuclear Dispatch (AND) order will be given to lower load by 100 MWe. The AND ramp computer will indicate a ramp to 1120 MWe is requested and the crew will call to confirm the ramp. Once the ramp is confirmed, the ramp down to 1120 MWe will be commenced at 4 MW/min per the operator aid. The ATC will borate the RCS and the BOP will perform the ramp.
Once sufficient reactivity control has taken place, the 1FT-414 will fail low. The crew will respond per BwAR 1-13-D3. The SRO will enter 1BwOA INST-2 attachment L and inform the shift manager. The SRO will enter Tech Spec 3.3.1 Conditions A & K.
Following the 1FT-414 failure, the 1B CV pump shaft will shear. The ATC will respond to the failure and will isolate letdown per 1BwPR 1-9-LD. The SRO will enter 1BwOA PRI-15, LOSS OF NORMAL CHARGING. Charging will be restored by starting the 1A CV pump, letdown will be restored per 1BwOA ESP-2. The SRO will enter Tech Spec 3.5.2 Condition A and TRM 3.1.d Condition A.
Once the crew has restored charging and letdown and the SRO has evaluated Tech Specs, 1FT-542 will slowly fail low. The BOP will respond to lowering SG level in the 1D SG and take the controller for 1FW-540 to manual and restore level per BwAR 1-15-D3. The SRO will enter 1BwOA INST-2 attachment H to respond to the event and establish a critical parameter for 1D SG level.
Once 1D SG level is normalized and BwOA INST-2 actions are complete, an Inadvertent Phase B (train A only) will actuate. The crew will respond per BwAR 1-5-A7 and verify seal injection flow is between 8-13 gpm to each RCP, reset Phase B and open the Phase B isolation valves to restore CC to the RCPs.
After the crew has recovered from the Inadvertent Phase B, the 1D RCP seal package will fail and cause an RCS LOCA. The crew will trip the reactor, verify reactor trip, initiate SI and enter 1BwEP-0 to address the reactor trip and small break LOCA. The SI will be complicated by the 1A SI pump failing to auto-start on the SI with the 1B SI pump having a ground overcurrent trip. Additionally, 1CV8100 will fail to auto-close on the Phase A with 1CV8112 failed open. The crew will start the 1A SI pump and manually close 1CV8100. The crew will transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT. The crew will continue in 1BwEP-1 and transition to 1BwEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION. Scenario completion criteria is when the RCS cooldown step is completed in 1BwEP ES-1.2.
Critical Tasks:
- 1. Restore CC flow to the RCPs following the inadvertent phase B prior to 10 minutes elapsing (requiring a reactor trip, NRC designated CT). (K/A Number - 103, A4.04, Importance - 3.5/3.5)
- 2. Manually start 1A SI pump prior to transitioning out of 1BwEP-0. (Westinghouse - CT-7) (K/A Number - 013 A4.01, Importance - 4.5/4.8)
- 3. Manually close 1CV8100 before transitioning out of 1BwEP-0. (Westinghouse - CT-11) (K/A Number - EPE009 EA1.08, Importance - 4.0/4.1)
>100 gpm or SI pump discharge flow >200 gpm), prior to exiting out of 1BwEP-1. (Westinghouse
- CT-16) (K/A Number - EPE009 EK3.23, Importance - 4.2/4.3)
18-1 NRC 3 Page 1 of 24 Simulation Facility Braidwood Scenario No.:
NRC 3 Operating Test No.: 18-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-49 Turnover Unit 1 is at ~10-8 amps in the IR, steady state, xenon-free, BOL. On-line risk is green. Step 26 of 1BwGP 100-2, PLANT STARTUP, is ready to be performed to realign feedwater to the steam generators, 1FW009A-D are closed. Following completion of step 26, continue the startup per the 1BwGP 100-2T1 flowchart.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF SW01B IMF RP01 IOR ZDIRT2 NORMAL IMF MS01A 96 IMF MS01B 90 IMF MS01C 93 IMF MS01D 88 1B SX pump trip Auto reactor trip failure 1PM05J reactor trip switch failure 1A-1D MSIVs failed open 1
None N-BOP N-SRO Realign feedwater to the Steam Generators 2
None R-ATC R-SRO Withdraw control rods to 2%-3% power 3
IMF RX15inc RAISE I-ATC I-SRO Master Pressurizer Pressure Controller (1PK-0455A) setpoint fails high 4
IMF NI06B -11 IMF PN2174 ON IOR ZLO1NYN36DS202 ON T-SRO IRNI channel N-36 fails low (loss of detector voltage) 5 IOR ZDI1CV8401A CLS C-ATC C-SRO 1CV8401A (1A letdown HX inlet valve) fails closed 6
IOR ZDI1WO01PA TRIP DOR ZDI1WO01PA C-BOP C-SRO 1A Containment Chilled Water pump trip 7
IMF SW01A IMF SW01B (preload)
T-SRO 1A SX pump trip with 1B SX pump failure to manually start 8
IMF MS07C 4 M-All Uncontrolled depressurization of all Steam Generators 9
Preload C-ATC C-SRO Auto reactor trip failure with 1PM05J reactor trip switch failure
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
18-1 NRC 3 Page 2 of 24 SCENARIO OVERVIEW Unit 1 is at ~10-8 amps in the IR, steady state, xenon-free, BOL. On-line risk is green. Step 26 of 1BwGP 100-2, PLANT STARTUP, is ready to be performed to realign feedwater to the steam generators, 1FW009A-D are closed. Following completion of step 26, continue the startup per the 1BwGP 100-2T1 flowchart.
After completing shift turnover and relief, the crew will perform step 26 of 1BwGP 100-2 to realign feedwater to the Steam Generators. The BOP will perform the procedure and realign feedwater with peer checks from the ATC as appropriate.
Once feedwater is realigned, the SRO will direct the ATC to raise reactor power to 2-3%. The crew will follow the plant startup flowchart, 1BwGP 100-2T1, and perform step 27 to withdraw control rods until 2-3% reactor power is reached. The ATC will maintain reactor power at 2-3% by adjusting RCS Boron concentration or rod position as required.
After the crew has stabilized reactor power at 2-3%, the Master PZR Pressure Controller (1PK-0455A) setpoint fails high. The SRO will direct the ATC to respond per BwAR 1-12-C1. The ATC will place the controller, 1PK-455A, in manual and maintain PZR pressure in the desired band.
Once the crew has stabilized PZR pressure, IRNI channel N-36 will fail low due to a loss of detector voltage. The crew will enter 1BwOA INST-1, NI MALFUNCTION, and address the failed IRNI channel.
The SRO will enter Tech Spec 3.3.1 Conditions A and F.
After the IRNI failure Tech Spec determination is made, 1CV8401A, 1A letdown HX inlet valve, will fail closed isolating letdown flow. The ATC will respond to the malfunction and will complete the letdown isolation per 1BwPR 1-9-LD. The crew will restore letdown flow through the 1B letdown HX using BwOP CV-17 & CV-22.
After letdown is restored, the 1A Containment Chilled Water pump will trip. The 1A Containment Chilled Water pump trip causes a trip of the 1A Containment Chiller. The crew will start the standby 1B Containment Chilled Water pump and Chiller per BwOP VP-1. Containment pressure and temperature will slowly rise with the loss of Containment cooling. The US should refer to Tech Spec 3.6.4 and 3.6.5.
After the crew has started the 1B Containment Chilled Water Pump, the 1A SX pump will trip. The SRO will direct the BOP to respond to the SX pump trip per 1BwPR 1-2-A1. The BOP will attempt to start the 1B SX pump, but the 1B SX pump will not start. The BOP will continue the prompt response actions and request Unit 2 to crosstie SX between the units. The crew will dispatch an EO to investigate the 1A and 1B SX pump trips. The SRO will enter Tech Spec 3.7.8 Condition A for both SX pumps and LCO 3.0.3.
After the SRO determines a unit shutdown is required by LCO 3.0.3, the 1C SG will become faulted, main steam line isolation will fail and the automatic reactor trip will fail. The 1C steamline break will generate a reactor trip signal, but the automatic reactor trip will not function. The crew will manually trip the reactor from 1PM06J (1PM05J Rx trip switch will not work), verify reactor trip, initiate SI, attempt to close the MSIVs and enter 1BwEP-0. The crew will continue through 1BwEP-0 and transition to 1BwEP-2 with 4 faulted SGs. Once the crew determines that all MSIVs are failed open, the crew will transition to 1BwCA-2.1. The crew will throttle AF flow to each SG to 45 gpm. Scenario completion criteria is when both RH pumps are placed in standby in 1BwCA-2.1.
Critical Tasks:
- 1. Manually trip the reactor from the control room before transitioning out of 1BwEP-0. (Westinghouse -
CT-1) (K/A Number - EPE007 EA2.02, Importance - 4.3/4.6)
- 2. Manually control AF flowrate to not less than 45 gpm per SG to minimize the RCS cooldown rate before a severe (Orange path) challenge develops to the integrity CSF. (Westinghouse - CT-33) (K/A Number - EPE E12 EA2.2, Importance - 3.4/3.9)
18-1 NRC Spare Page 1 of 25 Simulation Facility Braidwood Scenario No.:
NRC Spare Operating Test No.: 18-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-16 Turnover Unit 1 is at 53%, steady state, Equilibrium Xenon, MOL. On-line risk is green. Following turnover, the Unit 1 SX pumps will be swapped per BwOP SX-7 to allow for Unit 2 surveillance testing. EOs are briefed and standing by for the SX pump swap.
Event No.
Malf. No.
Event Type*
Event Description Preload IOR ZDI1VP01CDV NORMAL IMF CH01D IMF TH11A 0 IMF TH11B 0 Trigger 1 (RP:SI(1).EQ. TRUE)
IOR ZDI1IA066 CLS IOR ZLO1IA0661 OFF IRF ED053C OPEN Fail 1D RCFC vibration reset pushbutton 1D low speed RCFC trip Both PZR PORVs fail closed SI actuation trigger 1IA066 fails closed on SI 1AF013A breaker trips on SI 1
None N-BOP N-SRO Swap Unit 1 SX pumps 2
SET CH:1VSVP003D = F SET CH:1VSVP003D = T C-BOP C, T-SRO 1D high speed RCFC high vibration 3
IMF RX21A 2500 T-SRO PZR pressure channel, 1PT-455, fails high 4
IMF RX17B FALSE IMF RX17A TRUE C-ATC C-SRO Rod Control failure results in auto rod withdrawal 5
IMF CV19 IMF d6mod131c12f ALARM C-ATC C-SRO 1CV112A diverts letdown flow to the HUT 6
IOR ZDI1OG02PA TRIP DOR ZDI1OG02PA C-BOP C-SRO 1A GS Condenser Exhauster fan trip 7
IMF TH08.001 R-ATC N-BOP R, T-SRO High RCS activity requiring plant shutdown 8
IMF TH03A 650 IMF TH11A/B 0 (preload)
M-All 1A SGTR with loss of PZR pressure control 9
Preload C-ATC C-SRO 1AF013A breaker trips on SI
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
18-1 NRC Spare Page 2 of 25 SCENARIO OVERVIEW Unit 1 is at 53%, steady state, Equilibrium Xenon, MOL. On-line risk is green. Following turnover, the Unit 1 SX pumps will be swapped per BwOP SX-7 to allow for Unit 2 surveillance testing. EOs are briefed and standing by for the SX pump swap.
After completing shift turnover and relief, the crew will perform BwOP SX-7 to swap Unit 1 SX pumps. The BOP will swap SX pumps by starting the 1B SX pump, then stopping the 1A SX pump using peer checks as appropriate.
After the SX pump swap is complete, the 1D high speed RCFC will develop a high vibration condition. The BOP will respond using BwAR 1-3-C5 and stop the 1D RCFC. The SRO will enter Tech Spec 3.6.6 Condition C.
After the SRO has evaluated Tech Specs for the 1D RCFC vibration, PZR pressure channel, 1PT-455, will fail high. The crew will respond to the 1PT-455 failure and the SRO will enter 1BwOA INST-2.
The crew will remove 1PT-455 from service in Ovation and request to bypass bistables (no NSOs are currently available, 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> delay). The SRO will enter Tech Spec 3.3.1 Conditions A, E & K; 3.3.2 Conditions A & D and 3.3.4 Condition A.
Once the SRO has evaluated Tech Specs from the 1PT-455 failure, an automatic rod control failure will cause rods to step out. The SRO will order the ATC to respond per 1BwPR 1-10-RD. The ATC will place rods in manual to stop the rod withdrawal. The SRO will enter 1BwOA ROD-1 to address the rod control failure. Rods will remain in Manual control for the remainder of the scenario.
After the plant is stabilized from the rod control failure, a 1CV112A failure will divert letdown flow to the HUT. 1CV112A will fail and divert letdown flow to the HUT requiring the ATC to place the 1CV112A control switch to the VCT position. If VCT level lowers to the automatic makeup setpoint (37%) before action is taken, an automatic VCT makeup will not occur, and a manual VCT makeup will be required.
Once the crew has restored letdown flow to the VCT, the 1A GS Condenser Exhauster fan will trip.
The 1A GS Condenser Exhauster fan trips and the BOP will start the 1B GS Condenser Exhauster fan per BwAR 1-18-A8/BwOP GS-7 to prevent water intrusion into the main generator oil system.
Following the 1A GS Condenser Exhauster fan trip, high RCS activity will occur requiring unit shutdown. The BOP will respond to an RMS alarm for the 1PR06J and inform the SRO. The SRO will enter 1BwOA PRI-4 to address the high RCS activity. The SRO will direct Chemistry to sample the RCS for activity. The sample results will show dose equivalent I-131 at 84 µCi/gm. The SRO will enter Tech Spec 3.4.16 Conditions A and C and commence a unit shutdown.
After sufficient reactivity control is demonstrated, the 1A SG will develop a tube rupture. The BOP will respond to the main steamline rad monitor alarm. The ATC will determine that PZR level is lowering >
2% per minute. The SRO will direct the ATC to trip the reactor, verify reactor trip, insert an SI and enter 1BwEP-0. Following the reactor trip, 1IA066 will fail closed and the 1AF013A breaker will trip. The crew will transition to 1BwEP-3 to address the SGTR. The ATC will isolate AF to the 1A SG by closing 1AF005A and dispatch an EO to locally fail air and close the valve. The crew will not be able to establish PZR pressure control in 1BwEP-3 and will transition to 1BwCA-3.3, SGTR WITHOUT PRESSURE CONTROL.
Scenario completion criteria is when high head ECCS is secured.
Critical Tasks:
- 1. Isolate feedwater flow into and steam flow from the ruptured SG before transition to 1BwCA-3.1 occurs. (Westinghouse - CT-18) (K/A number - EPE038 EA1.32, Importance - 4.6/4.7)
- 2. Establish/maintain RCS temperature so that transition from 1BwEP-3 does not occur because the RCS temperature is too high (1BwCA-3.1) or too low (1BwFR-P.1). (Westinghouse - CT-19) (K/A number -
EPE038 EA1.36, Importance - 4.3/4.5)
- 3. Terminate SI before ruptured SG PORV or safety valve water release. (Westinghouse - CT-35) (K/A Number - EPE038 EA1.30, Importance - 4.0/3.8)