ML22193A311
| ML22193A311 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/05/2021 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Baker R | |
| Shared Package | |
| ML20139A014 | List: |
| References | |
| Download: ML22193A311 (94) | |
Text
Quad Cities 2021 NRC EXAM Scenario 1 Exelon Nuclear 2021 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 1 Revision Number: 00 Date: 11/20/2020 Developed by:
Instructor Date Validated by:
SME or Instructor Date Reviewed by:
Operations Representative Date
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2021 NRC Scenario 1 Op-Test No.: ILT 20-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions: 90% Reactor power, SSMP and 2A Turb. Bldg. Exhaust Fan, and 1B Core Spray Pump are out of service.
Turnover: Place the 2A SWP in service and secure the 2B SWP. Continue load increase to full power with Recirc flow.
Critical Tasks:
- 1. While executing QGA 200, Primary Containment Control, when Torus pressure exceeds 5 psig and only if operating in the safe region of the drywell spray initiation limit (DSIL), INITIATE drywell sprays. (BWROG PC-5.1 INIT DW SPRAY)
- 2. Per QGA 100, RPV Control, with the automatic ADS timer initiated, INHIBIT ADS before an automatic actuation occurs and cooldown rates are exceeded. (BWROG RPV-4.2/5.2/6.2)
- 3. If the RPV level trend is not reversible with an L3 system capable of providing adequate core cooling, INITIATE an emergency depressurization before Minimum Steam Cooling RPV Water Level (MSCRWL). (BWROG RPV-1.1 LOSS HP INJ E/D TAF)
Event No.
Malf. No.
Event Type*
Event Description 1
None BOP N
Swap the 2A and 2B Service Water Pumps.
2 None ATC R
Raise Reactor power with Recirculation pumps.
3 NM08D ATC I/TS APRM 4 fails downscale / RBM 8 inoperable.
4 RD08A ATC C
1A CRD Pump reduced capacity.
5 DIHS15705C BOP C
1C TB Exhaust Fan trip w/ failure of standby fan to start.
6 PC04B SRO TS Drywell-Torus Vacuum Beaker fails open.
7 RR11A CREW M
LOCA (1A Recirc Pump discharge line break).
8 ED04B ED03B HP08 CREW Loss of Reactor Feed Pumps and HPCI.
9 CS04A BOP C
1A Core Spray Pump autostart failure.
Quad Cities 2021 NRC EXAM Scenario 1 10 None CREW TAF / RPV Blowdown.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:
Total Malfunctions (5-8): 7 Malfunction(s) after EOP (1-2): 8, 9 Abnormal Events (2-4): 3, 4, 6, 9 Major Transient(s) /E-Plan entry (1-2): 7 EOPs (1-2): 100 / 200 EOP Contingencies (0-2): 100ALC/ 100BD Critical Tasks (2-3): 3 ES-301-5 Quantitative attributes:
BOP Normal: 1 ATC Reactivity (1 per set): 2 BOP I/C (4 per set): 6, 9 ATC I/C (4 per set): 3, 4 SRO-I I/C (4 per set inc 2 as ATC): 3, 4, 5, 9 SRO Tech Spec (2 per set): 3, 6 ALL Major Transients (2 per set): 7
Quad Cities 2021 NRC EXAM Scenario 1
SUMMARY
Initial Conditions:
o The plant is currently at 90% power with the SSMP, 2C RB Exhaust Fan, and 1B Core Spray Pump out of service o Electrical Maintenance has requested the 2B Service water pump secured and removed from service for a motor inspection.
Event 1: Swap Service Water Pumps: The BOP will start the 2A Service Water pump and secure the 2B Service Water pump per QCOP 3900-01.
Event 2: Reactor Power Maneuver: The ATC will raise reactor power with Recircs to full power (2957 MWth) per QCGP 3-1 and the ReMA.
Event 3: APRM 4 Downscale Failure: After the reactivity addition is complete, APRM 4 fails downscale rendering both APRM 4 and RBM 8 inoperable. The SRO will contact Instrument Maintenance to investigate. The SRO will enter TS 3.3.2.1. Condition A (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore RBM channel). The SRO directs the ATC to bypass APRM 4 per QCOP 0700-04 and exits the TS LCO.
Event 4: 1A CRD Pump reduced capacity: The ATC reports annunciator 901-5 F-2, CRD CHARGING WATER LOW PRESSURE, alarm. ATC observes and reports lowering CRD parameters. An EO dispatched to the 1A CRD pump reports that the motor is running hot and possible bearing damage. The SRO directs the ATC to swap CRD pumps per QCOP 0300-23.
Event 5: 1C TB Exhaust Fan trip: The BOP acknowledges annunciator 912-5 A-2, and reports the 1C TB Exhaust Fan has tripped and the standby did not autostart. The BOP starts the standby, 1A TB Exhaust Fan successfully. Turbine Building D/P is restored to < 0 in. H2O.
Event 6: Drywell-Torus Vacuum Breaker fails open: The BOP reports annunciators 901-3 C-13 and 901-3 G-11 are in alarm. An EO performing a system walkdown with a new engineer reports a test pushbutton on the 2251-24 panel was inadvertently bumped and the 1601-32B Drywell to Torus Vacuum breaker has an open indication. Attempts to close it were not successful. The SRO enters TS 3.6.1.8 Condition C, One Vacuum Breaker not closed (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore).
Event 7/10: LOCA / TAF Blowdown: The crew will insert a manual scram on high Drywell pressure due to a break in the A Recirc Loop Suction Line. Actions per QGA 100 and QGA 100 Alternate Level Control leg will be taken to try and maintain RPV water level above -142 inches (MSCRWL). Containment parameters will be controlled per QGA 200 actions. When conditions permit, the crew will blowdown the RPV, and restore level with low pressure ECCS systems.
Event 8: Loss of Reactor Feed Pumps and HPCI: After the reactor scram and main turbine trip, the RAT fails to transfer to Bus 11 and Bus 12 trips on overcurrent resulting in a loss of all RFPs. The HPCI Aux Oil Pump trips on motor overload preventing HPCI startup.
Event 9: 1A Core Spray Pump autostart failure: The 1A Core Spray pump fails to autostart on high Drywell pressure. The BOP will manually start the pump.
Approximate Run Time: 1.5 Hours
Quad Cities 2021 NRC EXAM Scenario 1 CRITICAL TASKS:
Critical Task #1: While executing QGA 200, Primary Containment Control, when Torus pressure exceeds 5 psig and only if operating in the safe region of the drywell spray initiation limit (DSIL),
INITIATE drywell sprays before exceeding PSP limit. (BWROG PC-5.1 INIT DW SPRAY)
Clarification: This critical task is not met if Drywell sprays are not initiated after 5 psig Torus pressure. The evaluation should consider how promptly sprays are started after 5 psig is reached. This judgement should take into account the containment pressure trend and then determine when opportunity was available to initiate Drywell sprays. Crew resource availability and priorities should also be considered in this evaluation.
Critical Task #2: Per QGA 100, RPV Control, with the automatic ADS timer initiated, INHIBIT ADS to prevent an automatic actuation in which cooldown rates are exceeded. (BWROG RPV-4.2/5.2/6.2)
Clarification: This critical task is not met if RPV level and/or Drywell pressure reach their respective automatic ADS actuation setpoint(s), ADS initiates, and cooldown rates are exceeded due to ADS actuation.
Critical task #3: If the RPV level trend is not reversible with an L3 system capable of providing adequate core cooling, INITIATE an emergency depressurization before Minimum Steam Cooling RPV Water Level (MSCRWL). (BWROG RPV-1.1 LOSS HP INJ E/D TAF)
Clarification: This critical task is not met if the MINSRED ADS valves (5) are not taken to manual prior to -162 inches. This critical task may be trend dependent, and the evaluation team can adjust the criteria if level was stable near MSCRWL prior to unexpected plant change.
Quad Cities 2021 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-0700-P07 (Freq: LIC=B) Given an operating plant with an APRM failure, take actions to bypass the failed APRM and meet TS requirements in accordance with QCOP 0700-04 and QCAP 0230-19. (SOER 90-3 r1)
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.
SR-1000-P02 (Freq: LIC=B) Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA.
SR-0001-P26 (Freq: LIC=B) Given a reactor plant with rising drywell temperature due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure DSIL), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays before drywell temperature reaches 338 degrees in accordance with QGA 200.
SR-0203-P07 (Freq: LIC=A) Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PRA Task-Inhibiting ADS during an ATWS has a F-V value of 1.30E-02 for LERF.)
SR-0001-P01 (Freq: LIC=A) Given the plant with a loss of normal feedwater resulting in the inability to restore RPV water level above 0 inches, inject with Alternate Injection Systems (QGA Detail L2) to attempt to hold RPV water level above
-142 inches in accordance with QGA 100. (SOER 86-1 r8)
SR-0001-P02 Freq: LIC=A) Given the plant with an inability to restore and hold RPV water level above -142 inches with preferred or alternate injection subsystem (QGA Detail L1 and L2), initiate an emergency depressurization before RPV water level drops to MSCRWL (Minimum Steam Cooling Reactor Water Level) in accordance with QGA 100. (Important PRA Task - Emergency depressurization has a RAW of 1.44 E4 for CDF and a RAW of 1.59 E4 for LERF.)
SR-0001-P03 (Freq; LIC=A) Given a shutdown reactor plant with an emergency depressurization in progress due to an inability to maintain RPV water level above -142 inches, attempt to control RPV level above -142 inches using available injection systems or establish/maintain adequate core cooling using alternate methods in accordance with QGA 100.
SR-0002-P05 (Freq: LIC=B) (ILT-MP) Given a reactor plant at power, perform a power change discernible on neutron monitors using recirc flow in accordance with QCOP 0202-03 and QCGP 3-1.
Quad Cities 2021 NRC EXAM Scenario 1 Simulator Setup:
- 1. Reset to IC-21 (100% power).
- 2. Go to RUN.
- 3. Verify the following RWM Sequence is loaded: 6PHESD (or current shut down sequence)
- 4. Notch in FCL steps 36 to 39, reduce core flow as necessary until reactor power is 90%.
- 5. Place INFO cards as follows:
- b. Place the 1B Core Spray Pump in PTL and hang card.
- 6. Insert Commands for setup:
imf HP08 (Trip the HPCI Aux Oil Pump on motor overload) imf ED04B (Prevent closure of T-12 to Bus 11 feed breaker) imf CS04A (Fail 1A Core Spray Pump autostart) imf ED03B (Trip Bus 12 on overcurrent when the Mode Switch is taken to S/D) ior DIHS114011B PTL (Override the 1B CS Pump c/s in PTL)
- 7. Verify the following commands for scenario performance:
imf NM08D 0 (Fail APRM 4 downscale to 0%)
imf RD08A 40 2: (Degrade the 1A CRD pump to 40% over 2 min.)
imf RD07A (Trip the 1A CRD Pump) ior DIHS15705C trip (Trip the 1C Turbine Building Exhaust Fan) ior LOHS15705C2 on (Override the 1C TB EXH Fan AUTO TRIP light on) ior LOHS15705C1 off (Override the 1C TB EXH Fan OFF light off) imf ser1923 on (Override 912-5 A-2 on) dmf ser1923 (Delete 912-5 A-2 alarm override) dor LOHS15705C2 (Delete 1C TB EXH Fan AUTO TRIP light override) dor LOHS15705C1 (Delete 1C TB EXH Fan OFF light override) drf HV15R (Clear the 1B RB Exhaust Fan trip) imf PC04B 5 (Fail the 32B Drywell to Torus Vacuum breaker 5% open) imf RR11A.5 15: (A Loop Recirc Discharge line break at.5% severity over 15 min.)
- 8. Install Protected System placards and/or rings on the following equipment:
o RBCCW pumps o Fuel Pool Cooling Water pumps
- 9. Provide the following paperwork:
o Turnover o ReMA (Load Drop and Return) o Marked up copy QCOS 5600-08
Quad Cities 2021 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3 D-13, ELECT RELIEF VALVES 3A 3B OPEN, Rev. 07 o 901(2)-3 E-13, ELECT RELIEF VALVES 3C/3D/3E OPEN, Rev. 06 o 901(2)-3 E-14, ACOUSTIC MON SAFETY RLF VALVES OPEN, Rev. 07 o 901(2)-3 A-16, PRI CNMT HIGH PRESSURE, Rev. 16 o 901(2)-3 B-9, HPCI MOTOR OVERLOAD, Rev. 06 o 901(2)-3 C-13, TORUS VACUUM BKR VALVES OPEN DIV I, Rev. 12 o 901(2)-3 G-11, TORUS VACUUM BKR VALVES OPEN DIV II Rev. 10 o 901(2)-3 G-15, REACTOR VESSEL LOW LOW LEVEL, Rev. 18 o 901(2)-5 C-3, ROD OUT BLOCK, Rev. 11 o 901(2)-5 C-6, APRM DOWNSCALE, Rev. 05 o 901(2)-5 F-2, CRD CHARGING WATER HEADER LOW PRESSURE, Rev. 06 o 901(2)-5 F-8, RX VESSEL LOW LEVEL, Rev. 11 o QOA 900-8 E-1, 4KV BUS 11(21) AND 12(22) LOW VOLTAGE, Rev. 06 o QOA 900-8 F-3, 4KV BUS OVRCUR TRIP, Rev. 06 o QOA 912-5 A-2, TURBINE BLD 1 VENT EXH FAN TRIP, Rev. 05 QCOP 0300-23, CRD Pump Change Over, Rev. 19 QCOP 0700-04, Average Power Range Monitoring System Operation, Rev. 18 QCOP 1000-30, Post-Accident RHR Operation, Rev. 32 QCOP 3900-01, Service Water System Operation, Rev. 17 QCOP 5750-19, Drywell Cooler Operation, Rev. 11 QCGP 2-3, Reactor Scram, Rev. 99 QCGP 3-1, Reactor Power Operations, Rev. 89 QCOA 0201-01, Increasing Drywell Pressure, Rev. 30 QOA 5750-01, Turbine Building Supply or Exhaust Fan Trip, Rev. 13 QCOA 6500-01, 4 KV Bus 11(21) Failure, Rev. 0 QCOA 6500-02, 4 KV Bus 12(22) Failure, Rev. 0 QGA 100, RPV Control, Rev. 13 QGA 200, Primary Containment Control, Rev. 13 QGA 300, Secondary Containment Control, Rev. 09
Quad Cities 2021 NRC EXAM Scenario 1 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is currently at 90% power for load following.
b.) Unit 2 is at 100% Power.
c.) Technical Specification limitations:
Unit 1: Day 2 of 30, TS 3.7.9 Condition A, Safe Shutdown Makeup Pump inoperable.
Day 1 of 7, TS 3.5.1 Condition B, 1B Core Spray Pump inoperable.
Unit 2: None d.) On Line Risk is GREEN e.) Fire Risk is GREEN.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling 2.) Significant problems/abnormalities:
a.) The SSMP is out of service for a pump motor inspection and preventive maintenance. Expected return in 2 days.
b.) The 2A Turbine Building Exhaust Fan is out of service for fan replacement. Return to service expected in 3 days.
c.) The 2B Service Water has been running with high vibration levels resulting from the pump motor upper bearings. Mechanical Maintenance has requested the pump removed from service for a bearing replacement.
d.) The 1B Core Spray Pump is out of service for a motor inspection. Return to service expected in 4 days.
3.) Evolutions/maintenance for the oncoming shift:
a.) Start the 2A Service Water Pump and secure the 2B Service Water Pump per QCOP 3900-01 step F.3 and F.8 in preparation for the 2B SWP clearance order.
b.) Continue power ascension with Recircs to 2957 MWth per QCGP 3-1 after swapping the Service Water Pumps.
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 1 Page 1 of 1 Event
Description:
Swap the 2A and 2B Service Water Pumps Time Position Applicants Actions or Behavior SRO Directs BOP to start the 2A Service Water Pump and secure the 2B Service Water Pump in accordance with QCOP 3900-01.
BOP Identifies and locates Section F.3 of QCOP 3900-01 as the applicable section to be used for 2A Service Water pump start.
BOP Directs EO to verify proper motor bearing oil levels in the 2A Service Water Pump.
SIMOP ROLE PLAY: As EO, acknowledge the direction and report back that the 2A Service Water Pump upper and lower motor bearing oil levels are normal.
SIMOP ROLE PLAY: If requested, as the EO report that all personnel are clear of the 2A Service Water pump.
BOP Makes a plant announcement of the impending 2A Service Water Pump start BOP At panel 912-1, starts 2A Service Water Pump and monitors for proper starting current and increase in service water pressure.
BOP Directs EO to check 2A Service Water Pump for indications of abnormal operation and to monitor local Service Water Pump Discharge Header Pressure for a normal discharge pressure of 90 to 120 psig.
SIMOP ROLE PLAY: As EO, acknowledge the direction and report back:
The 2A Service Water Pump is operating normally and discharge pressure is 118 psig.
BOP Identifies and locates Section F.8 of QCOP 3900-01 as the applicable section to be used for 2B Service Water pump shutdown.
BOP At 912-1, places 2B Service Water Pump c/s to STOP.
BOP Monitors 1/2-3940-18, SW PMP SPLY PRESS and verifies that system pressure remains 85 to 120 psig BOP Directs EO to verify proper Pump Discharge Check Valve operation by ensuring pump shaft rotation stops.
SIMOP ROLE PLAY: As EO, acknowledge the direction and report back: The 2B Service Water Pump shaft has stopped rotating.
End of Event 1
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 1 Event No. 2 Page 1 of 1 Event
Description:
Raise Reactor power with Recirculation pumps.
Time Position Applicants Actions or Behavior Key Parameter Response: APRM power, Reactor pressure, MW(e)
Expected Annunciator(s): None Automatic Actions: FWRVs SRO Directs ATC to begin power ascension per QCGP 3-1 and the ReMA.
SRO Verifies compliance with the approved ReMA.
ATC Announces the power change to the control room.
BOP Provides peer check as requested for power change.
ATC Raises reactor power by one of the following methods:
At the 901-5 panel:
o Depresses RAISE pushbutton on 1-0262-22, MASTER SPEED DEMAND.
OR At the OWS:
o Select blue filled square in the Master Set box.
o Type the setpoint in the open OUT box o Verify setpoint.
o Select send at the keyboard.
ATC Monitors power increase on APRMs and Flow Control Line.
BOP Verifies Load Set is 10% above Main Generator load.
ATC Notifies SRO when target power is achieved.
End of Event 2
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 1 Event No. 3 Page 1 of 1 Event
Description:
APRM 4 fails downscale / RBM 8 inoperable.
Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, fail APRM 4 downscale by releasing the following command:
NM08D 0 Key Parameter Response:
On 901-5 panel: APRM 4 reads 0, APRM 4 DN SCL OR INOP light lit, RBM 8 BYPASS light lit On 901-37 panel: APRM 4 meter reads 0, APRM 4 DNSCL light lit, RBM 8 BYPASS and REF DNSCL lights lit, OPRM 4 and 8 TROUBLE lights lit Expected Annunciator(s): 901-5 C-3, 901-5 C-6, 901-5 H-1 Automatic Actions: Rod Out Block ATC Acknowledges and reports APRM Downscale and Rod Out Block alarms.
ATC Reports APRM 4 indicates zero and RBM 8 is bypassed. May refer to QCOA 0700-03.
SRO Directs BOP to verify APRM 4 and RBM 8 readings on 901-37 panel.
BOP Reports APRM 4 indicating 0% power and RBM 8 BYPASS and REF DNSCL lights are lit.
SRO Contacts Instrument Maintenance to investigate APRM 4.
SIM OP ROLE PLAY: As Instrument Maintenance Supervision, acknowledge the report and state: I will put a troubleshooting package together to check the circuit boards for APRM 4 and report to the control room.
SRO Verifies minimum operable APRM channels are met per TS 3.3.1.1. for RPS trip functions and per TRM 3.3.a. for rod block functions. Also verifies minimum operable OPRM channels are met per TS 3.3.1.3.
TS SRO Enters TS 3.3.2.1 Condition A, for RBM 8, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore inoperable RBM channel (Function 1.b).
SRO Directs ATC to bypass APRM 4 per QCOP 0700-04.
ATC Positions APRM BYPASS joystick to CH4 and verifies APRM 4 white BYPASS light is ON.
ATC Reports RBM 8 bypass light is OUT and all alarms are cleared.
SRO Exits TS 3.3.2.1 Condition A, RBM 8 operable with reference APRM 5.
End of Event 3
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 4 Page 1 of 2 Event
Description:
1A CRD Pump reduced capacity Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, degrade the 1A CRD pump to 40%
over 2 minutes with the following command:
RD08A 40 2:
Add command for crd current going up Key Parameter Response: Charging Wtr Press, Drive Wtr Press, Clg Wtr Flow, Clg Wtr Press, 1A CRD Pmp Cur add up arrow On CRD Flow Controller: Clg Wtr Flow, Flow Control Vlv opens Expected Annunciator(s): 901-5 F-2 Automatic Actions: None ATC Reports 901-5 F-2, CRD CHARGING WATER LOW PRESSURE, alarm and refers to annunciator procedure.
ATC Reports all CRD pressures and flows are lowering. Reports 1A CRD pump current is also lowering.
ATC Dispatches an EO to the 1A CRD pump to investigate.
SIM OP ROLE PLAY: As the EO dispatched to the 1A CRD pump, wait 1 minute then report:
The 1A CRD pump motor casing is very hot. I believe the motor is overheating.
If the crew does not start taking action to start the 1B CRD pump after the report, wait 2 minutes, then trip the 1A CRD pump:
imf RD07A SRO Directs ATC to swap CRD pumps per QCOA 0300-01.
ATC Notifies EO of impending 1B CRD Pump start and shutdown of the 1A CRD Pump.
ATC Verifies MO 1-301-2B, B PMP DISCH VLV, is closed.
ATC Throttles MO 1-301-2B to maintain 1400 to 1500 psig discharge pressure.
Event 4 Continued
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 4 Page 2 of 2 Event
Description:
1A CRD Pump reduced capacity Time Position Applicants Actions or Behavior ATC Closes MO 1-301-2A, A CRD PMP DISCH VLV.
ATC Contacts EO to verify proper operation of the 1B CRD Pump.
SIM OP ROLE PLAY: As the EO, acknowledge the command, wait 1 minute the report back:
The B CRD Pump is running normally, oil levels are good.
ATC Directs EO to perform the following steps:
o Close the 1-301-254A, A CRD PUMP MIN FLOW ISOLATION VLV.
o Open the 1-301-254B, B CRD PUMP MIN FLOW ISOLATION VLV.
BOP Monitors balance of plant.
SIM OP ROLE PLAY: As the EO, acknowledge the directions, wait 1 minute, then report:
The 1A CRD Pump Min Flow Isolation Valve is closed and the 1B CRD Pump Min Flow Isolation Valve is open.
End of Event 4
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 5 Page 1 of 1 Event
Description:
1C TB Exhaust Fan trip w/ failure of standby fan to start.
Time Position Applicants Actions or Behavior SIM OP NOTE: When directed by the Lead Evaluator, trip the 1A TB Exhaust Fan by simultaneously inserting the following four (4) commands:
DIHS15705C TRIP SER1923 ON LOHS15705C1 OFF LOHS15705C2 ON Key Parameter Response: TB BLDG TO ATMOS DP, TB TO ATMOS DP Expected Annunciator(s): 912-5 A-2, 912-5 C-2 Automatic Actions: 1A TB Exhaust Fan autostart (disabled for scenario))
BOP Reports the 1C TB Building Exhaust Fan has tripped and refers to 912-5 A-2 annunciator procedure.
BOP Reports the standby exhaust fan did not autostart.
BOP Dispatches an EO to the TB Exhaust Fan breaker at Bus 19.
BOP Acknowledges TB LOW DP OR U1 TB LOW AREA DP alarm and reports Turbine Building to Atmosphere DP is > 0 H2O.
SRO Directs actions of QOA 5750-01.
BOP Starts the 1A TB Exhaust Fan and monitors Turbine Building DP.
BOP Places the 1C TB Exhaust Fan c/s in PTL and notifies Radiation Protection of exhaust fan trip.
SIM OP NOTE: If the 1C TB EXH Fan c/s is taken to TRIP or PTL, then delete the overrides on the 912-5 A-2 alarm and c/s indicating lights:
SER1923 LOHS15705C1 OFF LOHS15705C2 ON BOP Reports Turbine Building DP is < 0 H2O SIM OP ROLE PLAY: As the EO dispatched to investigate the 1C TB Exhaust Fan breaker, report:
The breaker is tripped and will not reset. The discharge damper has closed. Ive got Electrical Maintenance here and they have requested to have the breaker taken out of service for an inspection.
End of Event 5
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 6 Page 1 of 2 Event
Description:
Drywell-Torus Vacuum Beaker fails open Time Position Applicants Actions or Behavior SIM OP NOTE: When directed by the Lead Evaluator, fail the 1-1601-32B Drywell to Torus Vacuum Breaker 5% open:
PC04B 5 Key Parameter Response: Torus pressure, Drywell to Torus DP Expected Annunciator(s): 901-3 C-13, 901-3 G-11 Automatic Actions: 1A Pump Back Air Compressor loads BOP Reports Division I and Division II Torus Vacuum Bkr Valves Open annunciators are in alarm.
BOP Refers to QCAN 901-3 C-13 and QCAN 901-3 G-11.
SRO Determines the 1-1601-32B Drywell to Torus Vacuum Breaker is open from the SER.
BOP Dispatches an EO to the 2251-24 panel to verify open and/or dual indication for the 1-1601-32B vacuum breaker.
SIM OP ROLE PLAY: As a System Engineer on a plant walkdown, 1 minute after the alarm, call into the control and report that you inadvertently bumped a pushbutton on the 2251-24 panel.
SIM OP ROLE PLAY: As EO, wait 1 minute after dispatch then call in from the 2251-24 panel and report: The 1-1601-32B Drywell-Torus Vacuum breaker shows dual indication on both Division I and Division II.
BOP Obtains SRO concurrence, then directs the EO to cycle the 1-1601-32B Vacuum Breaker by depressing the TEST pushbutton.
SIM OP ROLE PLAY: As the EO, acknowledge the direction to cycle the Vacuum Breaker, wait 1 minute, then report back:
The Vacuum Breaker position did NOT change when I depressed the TEST pushbutton. I made two attempts with no result. Position indication remains at INTERMEDIATE.
Event 6 continued
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 6 Page 2 of 2 Event
Description:
Drywell-Torus Vacuum Beaker fails open Time Position Applicants Actions or Behavior SRO Contacts Instrument Maintenance to investigate.
BOP Reports Drywell to Torus differential pressure is > 1.0 psid.
TS SRO Enters the following Technical Specification LCOs:
o TS 3.6.1.8, Condition C, One Suppression Chamber-to-Drywell Vacuum Breaker not closed. (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
ATC Monitors RPV power, pressure, and water level.
End of Event 6
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 7/8/9/10 Page 1 of 4 Event
Description:
LOCA -- 1A Recirc Pump Discharge Line Break.
Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, insert a.5% break in the 1A Recirc Pump Discharge piping ramped over 15 minutes using malfunction RR11A:
RR11A.5 15:
Key Parameter Response: Drywell and Torus pressure/temperature, RPV water level when injection sources are lost, RPV pressure Expected Annunciator(s): 901-3 A-16, 901-3 G-15, 901-4 A-17, 901-4 B-17, 901-5 D-11, Automatic Actions: Rx. scram, ECCS auto-starts, ECCS load shedding BOP Acknowledges 901-3 A-16, PRI CMNT HIGH PRESSURE, alarm and reports rising Drywell pressure.
SRO Enters and directs actions of QCOA 0201-01.
SRO Sets scram criteria on high Drywell pressure (2.0 psig).
BOP Attempts to locate and isolate leak. Checks Recirc pump seals, RBCCW alarms, PIC 1-1640-11, CONTAINMENT PRESS for normal operation.
BOP Starts all available Drywell cooling.
BOP Notifies Radiation Protection of elevated Containment pressure and evacuates the Reactor Building.
SRO Directs a manual reactor scram on high Drywell pressure.
ATC Depresses both RX SCRAM CH A and CH B Pushbuttons. Places the Reactor Mode Switch to SHUTDOWN.
ATC Reports all rods in, RPV water level < 0 inches and recovering, RPV pressure < 1060 psig and controlled with Main Turbine Bypass Valves.
Event 8
ATC/BOP Reports Bus 12 has tripped on overcurrent and Bus 11 feed breaker from the RAT did not close after Main Turbine tripped.
ATC/BOP Acknowledges 901-8 F-3, 4KV BUS OVRCUR TRIP, alarm and dispatches an EO to Busses 11 and 12 to investigate.
Event 7/8/9/10 Continued
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 7/8/9/10 Page 2 of 4 Event
Description:
LOCA -- 1A Recirc Pump Discharge Line Break.
Time Position Applicants Actions or Behavior QGA 100, RPV Control Actions SRO Enters QGA 100 (RPV water level below 0 in.) and re-enters QGA 100 and QGA 200 when Drywell pressure is above 2.5 psig.
ATC Carries out QCGP 2-3, Reactor Scram, actions.
ATC/BOP Verify auto actions for 0 in. RPV water level and 2.5 psig Drywell pressure.
Event 9
BOP Reports 1A Core Spray Pump did not auto-start and manually starts the pump.
Event 8
BOP Reports the following:
HPCI did not auto-start on 2.5 psig Drywell pressure.
The Aux Oil Pump AUTO TRIP light is lit.
Annunciator 901-3 B-9, HPCI MOTOR OVERLOAD is in alarm.
BOP Contact Electrical Maintenance to investigate HPCI Aux Oil Pump motor and breaker.
BOP Enables the REMOTE HPCI TURB TRIP pushbutton latch to secure HPCI and places MO 1-2301-14 valve c/s in PTL NEEDS PROCEDURE REFERNCE.
SRO Directs RCIC and CRD Pumps started for injection.
ATC/BOP Starts RCIC using the Manual Initiation Pushbutton and reports RCIC injecting at 400 gpm.
BOP Reports Bus 11 and Bus 12 are de-energized and dispatches an EO to investigate.
SIM OP ROLE PLAY: If dispatched to Bus 11 and Bus 12, wait 2 minutes then report:
Bus 12 has an overcurrent trip and the Bus 11 reserve feed from Transformer 12 failed to close. I cannot see any obvious reason for the Bus 11 reserve feed failure. Ill get Electrical Maintenance to assist.
ATC Reports RPV water level lowering.
Event 7/8/9/10 Continued
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 7/8/9/10 Page 3 of 4 Event
Description:
LOCA1A Recirc Pump Discharge Line Break Time Position Applicants Actions or Behavior QGA 100, Alternate Level Control Actions SRO Directs BOP to inhibit ADS.
CT2 BOP Places AUTO BLOWDOWN INHIBIT switch to INHIBIT.
ATC Starts both SBLC pumps and reports system injection.
ATC Reports RPV water level lowering.
ATC Reports RPV water level at -59 in. and lowering.
BOP/ATC Reports Group I isolation on RPV low-low level.
BOP Reports Low Pressure ECCS and Condensate pumps are available.
ATC Reports RPV water level at -142 inches.
SRO Verifies greater than 2 Injection Subsystems (L3) are lined up with pumps running.
QGA 200, Primary Containment Control Actions SRO Directs BOP initiate Torus Sprays when Torus pressure is > 2.5 psig.
BOP Starts Torus sprays and monitors containment response.
BOP Reports Torus pressure 5 psig and rising. Verifies Torus level below 17 ft.
SRO Checks the DSIL curve and verifies both Recirc pumps are tripped and Drywell Coolers are secured.
SRO Directs BOP to initiate Drywell Sprays.
CT1 BOP Starts Drywell Sprays and reports containment temperature and pressure are lowering.
Events 7/8/9/10 Continued
Quad Cities 2021 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.1 Event No. 7/8/9/10 Page 4 of 4 Event
Description:
LOCA1A Recirc Pump Suction Pipe Break Time Position Applicants Actions or Behavior BOP Secures Drywell or Torus sprays before the respective volume reaches 0 psig.
SRO Directs BOP to initiate Torus Cooling and monitor Torus temperature.
BOP Starts Torus Cooling on one or both loops and monitors Torus temperature.
BOP Starts both CAM subsystems and reports containment Hydrogen level at 0%.
QGA 100 RPV Blowdown Actions SRO Determines that PRV water level cannot be restored and held above -
142 in. and transitions to RPV Blowdown.
SRO Directs BOP to maximize injection to the RPV.
BOP Secures Containment Sprays and Torus Cooling.
SRO Verifies Torus level is above 5 ft.
SRO Directs all 5 ADS Valves opened and switches left in Manual.
CT3 BOP Opens all 5 ADS Valves and leaves switches in the MAN position.
BOP Confirms and reports 5 ADS valves are open by acoustic monitor indication on the 901-21 panel.
BOP Verifies all ECCS Subsystems inject at RPV pressure < 325 psig.
ATC Reports RPV water level above -142 in. (TAF) and rising.
SRO Directs BOP/ATC to establish RPV water level band of 0 to +48 in.
SRO Directs BOP to secure/operate ECCS systems as necessary to restore and maintain RPV water level in band.
ATC Report RPV water level above 0 inches and controlling in 0 to 48 in.
band.
SIMOP NOTE: When Blowdown has been performed and RPV water level restored in band, with concurrence of the Lead Examiner, place the simulator in FREEZE.
End of Scenario.
Quad Cities 2021 NRC EXAM Scenario 1 END OF SCENARIO
Quad Cities 2021 NRC EXAM Scenario 3 Exelon Nuclear 2021 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 3 Revision Number: 00 Date: 11/10/2020 Developed by:
Instructor Date Validated by:
SME or Instructor Date Reviewed by:
Operations Representative Date
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2021 NRC Scenario 3 Op-Test No.: ILT 20-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is at 75% power for Main Turbine Stop Valve Testing.
Turnover: Perform QCOS 5600-13, for Main Turbine Stop Valves 3 and 4.
Raise power per QCGP 3-1 and the ReMA.
Critical Tasks:
- 1. With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (above 5% reactor power) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)
- 2. Per QGA 101, RPV Control (ATWS), with a reactor scram required, the reactor not shutdown, and the automatic ADS timer initiated, INHIBIT ADS before an automatic initiation occurs. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)
- 3. During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION (with the exception of boron, CRD, and RCIC) into the RPV until conditions are met to re-establish injection. (BWROG RPV-6.3 /LVL TERM/PREVENT)
- 4. Per QGA 101, during an ATWS with RPV injection terminated and prevented, when RWL drops below -35, slowly raise and control injection rate to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water Level (MSCRWL) without causing a sustained rise in reactor power. (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)
Event No.
Malf. No.
Event Type*
Event Description 1
None BOP N
Test MSVs 3 and 4 per QCOS 5600-13.
2 None ATC R
Raise Reactor power with control rods.
3 RD02R ATC C
Stuck Control Rod 4
NM10A ATC I/TS RBM 7 downscale failure 5
AD01D BOP C/TS D Relief Valve fails open (setpoint drift)
Quad Cities 2021 NRC EXAM Scenario 3 6
SW11A BOP C
1A TBCCW Pump degrades 7
TU02C TU02E TU02I CREW M
Main Turbine Bearing high vibration / SCRAM 8
RD13A RD13B CREW C
Full Core Hydraulic ATWS (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:
Total Malfunctions (5-8): 6 Malfunction(s) after EOP (1-2): 8 Abnormal Events (2-4): 3, 4, 5, 6, Major Transient(s) /E-Plan entry (1-2): 7 EOPs (1-2): QGA 100 EOP Contingencies (0-2): QGA 101 Critical Tasks (2-3): 4 ES-301-5 Quantitative attributes:
BOP Normal: 1 ATC Reactivity (1 per set): 2 BOP I/C (4 per set): 5, 6 ATC I/C (4 per set): 3, 4 SRO-I I/C (4 per set inc 2 as ATC):3, 4, 5, 6 SRO Tech Spec (2 per set): 4, 5 ALL Major Transients (2 per set): 7
Quad Cities 2021 NRC EXAM Scenario 3
SUMMARY
Initial Conditions:
o The plant is currently at 75% power for Main Turbine Stop Valve testing.
o Perform QCOS 5600-13 for MSVs 3 and 4, then raise power per QCGP 3-1 and the ReMA.
Event 1: The BOP performs QCOS 5600-13 steps H.2.h., H.2.i., and H.2.j. for MSVs 3 and 4.
Event 2: Reactivity: The ATC will raise reactor power by withdrawing control rods per the ReMA.
Event 3: Stuck Rod: After two control rods have been withdrawn to target out, the third control rod will not move with normal drive water pressure (260 to 320 psid). The ATC take actions per QCOA 0300-02 step D.7 and throttle drive water pressure in 50 psid increments. When drive water pressure is raised to ~360 psid, the control rod will withdraw normally.
Event 4: RBM 7 Downscale: The ATC responds to RBM Downscale and Rod Out Block alarms. The SRO directs ATC to hold power constant and directs ATC/BOP to determine status of RBMs. ATC and BOP report RBM 7 is reading downscale at the 901-5 and 901-37 panels.
The SRO directs the ATC to bypass RBM 7 per QOA 700-05 and enters TS 3.3.2.1 Condition A (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore channel to operable status).
Event 5: D Relief Valve Fails Open: The BOP reports annunciators 901-3 E-13, E-14 and E-16 are in alarm. The BOP determines D ADS valve is open. The SRO directs actions of QCOA 0201-03. The relief valve closes when the keylock switch is taken to OFF. The SRO enters TS 3.4.3 Condition A (14 days to restore) and TS 3.5.1 Condition H (14 days to restore).
Event 6: 1A TBCCW Pump Degrades: The 1A TBCCW pump degrades 50% resulting in a low system pressure and associated alarms on the 912-1 panel. The BOP will start the standby and restore system parameters. The EO dispatched will report the 1A TBCCW pump motor casing hot.
Event 7: Main Turbine Bearing High Vibration / SCRAM. Main Turbine bearing #s 3, 5, and 9 fail resulting in high vibration (901-7 D-2) and temperature (901-7 G-1) alarms. The BOP monitors and reports vibration levels at VR 1-5640-60, MAIN TB VIBRATION, EXPANSION AND ECCENTRICITY on the 901-7 panel. The SRO directs actions of QCOA 5600-01. When bearing vibration levels reach 10 mils the ATC inserts a manual scram and the BOP trips the turbine.
Event 9: Hydraulic ATWS. A hydraulic lock on the North and South Scram Discharge Volumes prevents control rod insertion. The SRO directs actions of QGA 101. The ATC will take actions to shutdown the reactor by injecting SBLC and individually inserting control rods. The BOP will control RPV pressure in band. RPV water level will be controlled in until the Hot Shutdown weight of Boron is injected. The scenario ends when RPV level is restored to a band of 0 to 48 in. and RPV pressure is stable in band.
Approximate Run Time: 1.5 Hours
Quad Cities 2021 NRC EXAM Scenario 3 CRITICAL TASKS:
Critical Task #1: With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (above 5% reactor power) prior to torus temperature of 149°F and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)
Critical Task #2: Per QGA 101, RPV Control (ATWS), with a reactor scram required, the reactor not shutdown, and the automatic ADS timer initiated, INHIBIT ADS before an automatic initiation occurs. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)
Clarification: This critical task is not met if RPV level and/or drywell pressure reach their respective automatic ADS actuation setpoint(s) but ADS is not prevented before the conditions specified.
Critical Task #3: During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION (with the exception of boron, CRD, and RCIC) into the RPV until conditions are met to re-establish injection. (BWROG RPV-6.3 /LVL TERM/PREVENT)
Clarification: This critical task is not met if either of the reactor power or level thresholds is not met when terminate and prevent actions are taken or if both conditions are met and terminate and prevent actions are not taken at all. The timing of this evaluation is dependent upon execution of the level control leg of QGA 101. Though ATWS execution strategies may vary, the evaluation should include a level of expediency which adequately addresses the potential concern for thermal hydraulic instabilities. This expediency is subjective, so the evaluation team must assess whether the delay was acceptable and warranted.
In addition, the critical task is also not met if either Boron or CRD is secured when either or both are required to lower reactivity during an ATWS condition. The QGAs clearly prioritize reactivity reduction in all ATWS situations. Compromising the ability to accomplish this potentially places the plant at greater safety risk.
Critical Task #4: Per QGA 101, during an ATWS with RPV injection terminated and prevented, when RWL drops below -35, slowly raise and control injection rate to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water Level (MSCRWL, -162 in.) without causing a sustained rise in reactor power. (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)
Clarification: This critical task applies to the QGA 101 level leg step 4, when the RWL drops below -35 (two feet below feedwater spargers). This critical task is not met if RPV injection is recommenced BEFORE reaching -35. This would result in unnecessary reactivity addition (from subcooled water) while RWL is being intentionally lowered to suppress power.
Inversely, this critical task is not met if an attempt to inject is not recommenced prior to RWL reaching MSCRWL. If a prolonged loss of core cooling is observed (i.e., RWL allowed to lower below MSCRWL prior to recommencement of RPV injection), the evaluation team must determine the nature of the event and whether operator action contributed to it. If so, a judgement must be made to determine if this warrants a missed critical task here.
This critical task is also not met if RPV injection rate is too fast, resulting in a sustained positive reactivity event. The evaluation team must observe the power response as injection is recommenced and determine if the response has potential to cause fuel damage.
Quad Cities 2021 NRC EXAM Scenario 3 EXERCISE PERFORMANCE OBJECTIVES SR-0002-P04 Freq: LIC=B) (ILT-MP) Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCGP 3-1 and QCGP 4-1. (SOER 84-2 r7a)
SR-0203-P02 (Freq: LIC=B) Given an operating plant with a stuck open relief valve, take actions to attempt to close the valve in accordance with QCOA 0203-01.
SR-0203-P07 (Freq: LIC=B) Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101.
SR-300-P05 (Freq: LIC=I) Given a reactor plant during a startup with a stuck control rod, restore the ability to drive the control rod or declare the rod inoperable in accordance with QCOA 0300-02.
SR-0300-P07 (Freq: LIC=B) Given a reactor plant in an ATWS condition (QGA), perform the NSO actions to insert control rods in accordance with QCOP 0300-28.
SR-0700-P11 (Freq: LIC=I) Given an operating plant with an RBM failure, take actions to bypass the failed RBM and meet TS requirements in accordance with QOP 0700-05.
SR-3800-P05 (Freq: LIC=A) Given a trip of the running TBCCW pump, start the standby pump and verify proper operation per QCOA 3800-03. (Important PRA Task-Starting the standby TBCCW pump has a RAW of 9.44 E3 for CDF and a RAW of 8.31 E3 for LERF).
SR-1100-P02 (Freq: LIC=A) (ILT-MP) Given a reactor plant with an ATWS, inject boron prior to exceeding 110 degrees torus water temperature OR if core instability is observed in accordance with QGA 101 and QCOP 1100-02. (Important PRA Task - Starting SBLC has a F-V of 1.23E-02 for LERF).
SR-0001-P11 (Freq: LIC=B) Given a reactor plant with an ATWS, take action to reduce heat input into the containment in accordance with QGA 101. (SOER 83-8 r11) (ATWS is a key event in 2 of top 100 most probable PRA Core Damage Sequences)
SR-0001-P12 (Freq; LIC=A) Given a reactor plant with an ATWS and conditions are met to intentionally lower RPV water level (power above 5% or unknown),
terminate and prevent all RPV injection except for boron, CRD, and RCIC in accordance with QGA 101. (SOER 83-8 r11)
SR-0001-P14 (Freq: LIC=B) Given a reactor plant with an ATWS with RPV water level lowered and being maintained between MSCRWL (Minimum Steam Cooling Reactor Water Level) and the level to where it was lowered and SBLC tank level has dropped by 16 percent, raise RPV injection rate to attempt to restore RPV water level to between +0 and +48 inches; stop injection if power starts and continues to rise in accordance with QGA 101, (SOER 83-8 r11).
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts.
Quad Cities 2021 NRC EXAM Scenario 3 Simulator Setup:
- 1. Reset to IC-20 (75% power).
- 2. Go to RUN.
- 3. Insert control rods to stabilize FCL at ~ 90%.
- 4. Raise Recirc flow to restore reactor power to ~75%
- 5. Lower CRD Drive Water pressure to 270 psid.
- 6. Verify the following RWM Sequence is loaded: 6PESU2
- 7. Insert Scenario Setup Commands:
imf RD02R5431 00 (Stick control rod P-8 at position 00) dmf RD02R5431 (Delete malfunction when Drive Water pressure is > 350 psid) dmf TC02C/E/I (Delete turbine bearing hi vibration malfunctions. Trigger on MSV #2 closure)
- 8. Verify the following commands for scenario performance:
imf NM10A 0 (Fail RBM 7 downscale) imf AD01D 0 1: (Drift setpoint to 0% (850 psig) ramped over 1 min.)
imf SW12A 50 3: (Degrade the1A TBCCW pump 50% over 3 min.)
imf TU02C 70 12: (Bearing #3 severity 70% (~14 mils) ramped over 12 min.)
imf TU02E 60 12: (Bearing #5 severity 60% (~12 mils) ramped over 12 min.)
imf TU02I 50 12: (Bearing #9 severity 50% (~10 mils) ramped over 12 min.)
imf rd13a 100 (100% Hydraulic lock on North Scram Discharge Volume) imf rd13b 100 (100% Hydraulic lock on South Scram Discharge Volume)
Field Actions:
irf RD04R close/open (Close/Open 1-0301-25 valve as directed) irf QG08R activate (Bypass all RPS Auto Scrams) irf rd04r close/open (Close/open the 1-301-25 valve) irf QG14R activate (Remove ARI fuses)
- 9. Prepare a copy of QCOS 5600-01 as follows:
Sign off steps D.1, D.2, H.2.a. thru H.2.f.
N/A step H.2.
- 10. Setup DEHC screen for MSV testing. Select <TESTS><MSV-CV TEST>.
- 11. Install Protected System placards and/or rings on the following equipment:
o RBCCW pumps o Fuel Pool Cooling Water pumps
- 12. Provide the following paperwork:
o Turnover Sheet o ReMA o Marked up copy of QCOS 5600-13.
- 14. Place LOCA Load Shed placards on the 1A and 1C Circulating Water Pumps.
Quad Cities 2021 NRC EXAM Scenario 3 LIST OF POTENTIAL PROCEDURES Annunciator Procedures:
o 901(2)-3 E-13, ELECT RELIEF VALVES 3C/3D/3E OPEN, Rev. 06 o 901(2)-3 E-14, ACOUSTIC MON SAFETY RLF VALVES OPEN, Rev. 07 o 901(2)-5 C-3, ROD OUT BLOCK, Rev. 11 o 901(2)-5 C-7, RBM DOWNSCALE, Rev. 08 o 901(2)-5 F-8, RX VESSEL LOW LEVEL, Rev. 11 o 901-7 D-2, TURB GEN BRG HI/HI-HI VIBRATION, Rev. 08 o 901-7 G-1, TURB GEN BRG HI/HI-HI METAL TEMP, Rev. 05 o 912-1 C-2, TURB BLDG CLG WATER PUMP TRIP, Rev. 01 o 912-1 D-2, TURB BLDG COOLING WATER LOW PRESS, Rev. 04 o QOA 900-3 E-16, VALVE LEAK DET SYS HIGH TEMP, Rev. 16 QCOP 0250-02, Bypassing MSIV Group I Isolation Signal from Low Low Reactor Water Level, Rev. 15 QCOP 0300-28, Alternate Control Rod Insertion, Rev. 34 QCOP 1000-30, Post-Accident RHR Operation, Rev. 33 QCOP 1100-02, Injection of Standby Liquid Control, Rev. 13 QCOP 3800-02, Unit 1 TBCCW System Operation, Rev. 04 QOP 0700-05, Rod Block Monitor, Rev. 17 QCGP 3-1, Reactor Power Operations, Rev. 89 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 50 QCOA 0203-01, Failure of a Relief Valve to Close or Reseat Properly, Rev. 13 QCOA 0300-02, Inability to Drive a Control Rod: Control Rod Stuck, Rev. 24 QCOA 5600-01, Main Turbine High Vibration, Rev. 18 QCOA 5600-06, Main Turbine Bearing High Metal Temperature, Rev. 17 QCOS 5600-13, Bypass Valve, Turbine Main Stop Valve, and Combined Intermediate Valve Periodic Testing, Rev. 02 QGA 100, RPV Control, Rev. 13 QGA 101, RPV Control (ATWS), Rev. 17
Quad Cities 2021 NRC EXAM Scenario 3 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is currently holding load at 75% (2220 MWth) for Main Turbine Stop Valve testing. Rod step 25 is partially withdrawn with the FCL at ~90%.
b.) Unit 2 is at 100% Power.
c.) Technical Specification limitations:
None.
d.) On Line Risk is GREEN e.) Fire Risk is GREEN.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling 2.) Significant problems/abnormalities:
a.) None.
3.) Evolutions/maintenance for the oncoming shift:
a.) Perform QCOS 5600-13 for MSVs 3 and 4 to complete MSV testing started last shift.
An extra NSO is available to verify relay status on the 901-15 and 901-17 panels.
b.) Raise power per QCGP 3-1 and the ReMA. Withdraw control rods and raise the FCL to 100%, then increase load with Recirc pumps. The QNE is in the Control Room.
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 1 Page 1 of 2 Event
Description:
Test MSVs 3 and 4 per QCOS 5600-13.
Time Position Applicants Actions or Behavior SRO Directs BOP to resume Main Turbine Stop Valve testing per QCOS 5600-13.
BOP At the DEHC Operator Workstation on the 901-7 panel:
Selects <TESTS><MSV-CV TEST>
EVALUATOR/SIM OP ROLE PLAY: As the extra NSO, verify and report the relay status for procedure steps 6, 11, 17 and 22.
BOP At the DEHC Operator Workstation test MSV #3:
(1) Select MSV #3.
(2) Verify TEST PERMITTED indication is YES.
(3) Verify MSV3 FA solenoid indicates de-energized.
(4) Select TEST START (5) Verify MSV #3 begins to slow close with NO erratic OR excessively slow movement.
(6) Verify the following TURB STOP VLV CLOSURE SCRAM relays drop out:
(a) Relay 590-124E.
(b) Relay 590-124D.
(7) Visually verify valve closes on the screen trace AND by observing MSV3 FA solenoid status changing to display FAST CLOSE DETECTED.
(8) Select TEST OFF.
(9) Verify MSV #3 returns to the full open position.
(10) Verify MSV3 FA solenoid indicates de-energized.
(11) Verify the following TURB STOP VLV CLOSURE SCRAM SIGNAL relays pick up:
(a) Relay 590-124E.
(b) Relay 590-124D.
Event 1 continued
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 1 Page 2 of 2 Event
Description:
Test MSVs 3 and 4 per QCOS 5600-13.
Time Position Applicants Actions or Behavior BOP At the DEHC Operator Workstation test MSV #4:
(12) Select MSV #4.
(13) Verify TEST PERMITTED indication is YES.
(14) Verify MSV4 FA solenoid indicates de-energized.
(15) Select TEST START (16) Verify MSV #4 begins to slow close with NO erratic OR excessively slow movement.
(17) Verify the following TURB STOP VLV CLOSURE SCRAM relays drop out:
(a) Relay 590-124G.
(b) Relay 590-124H.
(18) Visually verify valve closes on the screen trace AND by observing MSV4 FA solenoid status changing to display FAST CLOSE DETECTED.
(19) Select TEST OFF.
(20) Verify MSV #4 returns to the full open position.
(21) Verify MSV4 FA solenoid indicates de-energized.
(22) Verify the following TURB STOP VLV CLOSURE SCRAM SIGNAL relays pick up:
(a) Relay 590-124G.
(b) Relay 590-124H.
BOP Selects EXIT on <MSV-CV TEST> screen.
BOP Forwards completed QCOS 5600-13 to the SRO.
EVALUATOR ROLE PLAY: As the Shift Manager, inform the SRO that:
The WEC SRO will review the surveillance and log it in the Shift Turnover.
End of Event 1
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 2 Page 1 of 1 Event
Description:
Raise Reactor Power per QCGP 3-1 Time Position Applicants Actions or Behavior Key Parameter Response: Rx. Pwr, Rx. Press, APRM power, MWE, FCL Expected Annunciator(s): None Automatic Actions: None SRO Directs ATC withdraw control rods in sequence to raise the FCL to 100% in accordance with the ReMA and assigns QV duties to the BOP.
ATC Updates control room on Unit 1 reactivity addition.
ATC Selects the control rod on the Rod Select Matrix and verifies selection using two separate indications. Verifies position and bounds on the RWM.
ATC Communicates maneuver to the BOP/QV.
BOP Verifies the following for each control rod to be moved:
- Correct control rod is selected
- Initial position
- Target position Method of movement (single notch or continuous)
Direction of movement BOP Informs the ATC that the selected control rod may be moved.
ATC Performs another self-check then moves the control rod to the desired position.
ATC Initials the Move Sheet when the control rod is at the target position.
ATC Monitors RPV water level, pressure, and APRM response.
EVALUATOR NOTE: The above process is repeated for each control rod moved.
End of Event 2
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 3 Page 1 of 1 Event
Description:
Stuck Control Rod Time Position Applicants Actions or Behavior Key Parameter Response: Control rod P-8 sticks at position 00 Expected Annunciator(s): None Automatic Actions: None ATC ATC selects and begins withdrawing control rod P-8 to position 00 as required.
BOP Verifies selection and withdrawal of control rod P-8 from position 00.
ATC Reports control rod P-8 will not withdraw beyond position 00.
SRO Directs actions of QCOA 0300-02, Inability to Drive a Control Rod:
Control Rod Stuck.
ATC Verifies the following:
No control rod block exists No RWM block exists Control rod Select lights are lit on both Control Rod Matrix and Full Core Display.
Drive Water pressure is between 260 and 320 psid.
ATC Attempts to withdraw control rod P-8 again and reports no rod movement.
ATC Throttles MO 1-302-8, CRD DRIVE WTR PCV, in 50 psid increments to a maximum of 400 psid, alternating between rod movement attempts and raising Drive Water pressure.
EVALUATOR NOTE: The control rod will move when Drive Water pressure is > 350 psid.
SIM OP NOTE: Verify malfunction RD02R5431 deletes from the SmartSummary screen when Drive Water pressure is > 350 psid.
ATC Reports control rod movement after Drive Water pressure is raised, and continues to move the rod to its target-out position.
ATC Return Drive Water pressure to the 260320 psid band.
End of Event 3
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 4 Page 1 of 1 Event
Description:
RBM 7 Downscale Failure Time Position Applicants Actions or Behavior SIM OP NOTE: When the next control rod is selected for withdrawal. insert/release the following commands to fail RBM 7 downscale:
NM10A 0 Key Parameter Response: With a control rod selected, indications are as follows:
901-5 panel: RBM 7 Downscale light lit and reads 0 units, ROD OUT PERMIT light is not lit.
901-37 panel: RBM 7 Downscale light lit and reads 0 units.
Expected Annunciator(s): 901-5 C-3, 901-5 C-7 Automatic Actions: Rod Out Block ATC Reports annunciators 901-3 C-3, ROD OUT BLOCK and 901-3 C-7, RBM DOWNSCALE are in alarm and refers to annunciator procedures.
ATC Determines RBM channel 7 has failed downscale and verifies a Rod Out Block is in effect by observing Rod Out Permit light is NOT lit.
BOP Verifies RBM 7 is indicating downscale at the 901-37 panel meter.
SRO Contacts Instrument Maintenance to investigate the RBM 7 failure.
SIM OP ROLE PLAY: As Instrument Maintenance supervision, report that you will:
Start a work package to troubleshoot and replace components as needed. It will take approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to complete the package and 1 shift to complete the work.
SRO Directs RBM 7 bypassed per QOP 0700-05.
ATC Bypasses RBM 7 by placing the RBM BYPASS joystick to the CH 7 position and logs the time.
TS SRO Enters TS 3.3.2.1 Control Rod Block Instrumentation, Condition A, Function 1.c, One Rod Block monitor inoperable (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore).
SIM OP NOTE: Insert a 100% Hydraulic Lock on the North SDV and South SDV by releasing the following malfunctions:
RD13A 100 RD13B 100 End of Event 4
Quad Cities 2021 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 5 Page 1 of 1 Event
Description:
D Relief Valve Fails Open Time Position Applicants Actions or Behavior SIM OP NOTE: At the Lead Evaluators direction, insert/release the following command to open the D Relief Valve by failing the setpoint to 0% (850 psig) ramped over 1 min.:
AD01D 0 1:
Key Parameter Response: MWE, Rx. Press, RPV water level perturbation Expected Annunciator(s): 901-3 E-13, 901-3 E-14, 901-3 E-16 Automatic Actions: TCVs reposition to restore RPV pressure BOP Acknowledges annunciators and reports the D Relief Valve indicates open.
ATC Reports Generator MWE lowering. RPV pressure and water level initially lowered but recovering.
BOP Verifies D Relief Valve open by Acoustic Monitor and Tailpipe temperature indications at the 901-21.
SRO Directs actions of QCOA 0203-01.
BOP Places the D Relief Valve key switch to the OFF position.
BOP Reports 901-3 E-13, E-14, and E-16 alarms have cleared.
BOP Reports D Relief Valve Acoustic Monitor indicates valve is closed and tailpipe temperature is lowering.
SRO Contacts Instrument/Electrical Maintenance have investigate spurious opening of D Relief Valve.
SIM OP ROLE PLAY: As Maintenance Supervision, state: Ill contact the System Engineer and come up with a plan to investigate the D Relief valve actuation.
TS SRO Enters the following Technical Specification:
o TS 3.4.3 Condition A, One relief valve inoperable (14 days)
SRO Informs SM that QCOS 1600-1, FAILURE OF A RELIEF VALVE TO CLOSE OR RESEAT PROPERLY is required to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Quad Cities 2021 NRC EXAM Scenario 3 BOP Monitors Torus water temperature.
End of Event 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 6 Page 1 of 1 Event
Description:
1A TBCCW Pump Degrades Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, degrade the 1A TBCCW Pump 50%
over 3 min. by inserting/releasing the following command:
SW12A 50 3:
Key Parameter Response: TBCCW DISCH HDR Press Expected Annunciator(s): 912-1 D-2 Automatic Actions: None BOP Acknowledges annunciator, reports TBCCW Discharge Header is 35 psig and lowering. Refers to annunciator procedure.
BOP Dispatches an EO to the 1A TBCCW pump.
SIM OP ROLE PLAY: As the EO dispatched to check the 1A TBCCW pump, wait 2 minutes to report that: The pump motor is running very hot.
SRO Directs start of 1B TBCCW pump.
BOP Notifies the EO of impending start of the 1B TBCCW pump and starts the pump.
BOP Monitors TBCCW pump discharge pressure for trends and reports TBCCW pump discharge pressure has returned to normal.
BOP Directs EO to check operation of the 1B TBCCW pump.
SIM OP ROLE PLAY: As the EO report wait 1 minute then report:
The 1B TBCCW pump is operating normally and oil level is good.
BOP Places the 1A TBCCW pump in PTL and places an orange ring/EST identifying that the 1A TBCCW pump is unavailable SRO/BOP Contacts Electrical Maintenance and reports status of the 1A TBCCW pump.
Quad Cities 2021 NRC EXAM Scenario 3 SIM OP ROLE PLAY: As the EM Supervisor state:
Ill request a Clearance Order for the pump to perform a motor inspection.
End of Event 6 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 7 Page 1 of 1 Event
Description:
Main Turbine Bearing High Vibrations Time Position Applicants Actions or Behavior SIM OP NOTE: At the Lead Evaluators direction, insert/release the commands to degrade Main Turbine Bearings 3, 5, and 9 over a 12 minute ramp:
TU02C 70 12: TU02E 60 12: TU02I 50 12:
Key Parameter Response: Main Turbine Bearings 3, 5, and 9 rise (VR 1-5640-60)
Expected Annunciator(s): 901-7 G-1, 901-7 D-2 Automatic Actions: None BOP Acknowledges 901-7 G-1, TURB BRG HI/HI-HI METAL TEMP and 901-7 D-2, TURB GEN BRG HI/HI-HI VIBRATION alarms and refer to annunciator procedures.
BOP Reports Main Turbine Bearing #3 temperature is 185 ºF and vibration is at 7 mils and rising. Vibration and temperatures on Bearings 5 and 9 are also rising.
SRO Sets scram criteria for high Main Turbine Bearing temperature at 250ºF vibration at 10 mils.
SRO Directs actions of QCOA 5600-01, Main Turbine High Vibration.
SRO Directs ATC to reduce power per QCGP 3-1 until bearing vibration levels are < 7 mils.
ATC/BOP Inserts control rods and reduces Recirc flow while BOP monitors and reports bearing vibration levels and temperatures at VR 1-5640-60 and TR 1-5640-61 recorders respectively.
BOP Reports Main Turbine Bearing #3 is at 10 mils and rising.
ATC Inserts a manual reactor scram and reports rods did NOT insert.
SRO Directs BOP to trip the Main Turbine.
SIM OP NOTE: Verify malfunctions TU02C/E/I delete when the Main Turbine trips.
Quad Cities 2021 NRC EXAM Scenario 3 BOP Simultaneously depresses both Main Turbine Trip Pushbuttons and verifies the turbine trips.
SRO Enters QGA 100, then transitions to QGA 101 and QCGP 2-3.
End of Event 7 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 8 Page 1 of 4 Event
Description:
Full Core Hydraulic ATWS Time Position Applicants Actions or Behavior QGA 101, RPV CONTROL (ATWS) IMMEDIATE OPERATOR ACTIONS CT1 CT3 ATC Reports a full core Hydraulic ATWS and performs the following Immediate Operator Actions:
o Arm and Depress ARI pushbuttons o Injects with 1 SBLC pump and records SBLC Tank level. (CT1) o Terminates and prevents all RPV injection except Boron, CRD, and RCIC. (CT3) o Runs back both Recirc pumps to minimum speed o Determines RPV pressure stable and < 1200 psig, then injects SBLC with 2 pumps.
CT2 BOP Inhibits ADS BOP Bypasses RPV Low Low Level Group I isolation by placing MSIV LO-LO BYPASS CH A/C KEYLOCK switches to BYPASS on the 901-15 and CH B-D switches to BYPASS on the 901-17 panel.
SIM OP ROLE PLAY: If the U2 BOP is assigned to bypass the Offgas high radiation isolation, then remove fuse 1701-704 (AA-F6) in the 901-10 panel and report:
The Off Gas High Radiation Isolation is bypassed ATC/BOP Report initial ATWS actions.
QGA 101 Power Leg Actions SRO Verifies reactor power > 5% and directs ATC to trip both Recirc pumps ATC Trips both Recirc pumps by closing the discharge valves or depressing the ASD A/B EMERGENCY STOP pushbuttons.
SRO Directs ATC to insert control rods per QCOP 0300-28.
Quad Cities 2021 NRC EXAM Scenario 3 SIM OP ROLE PLAY: If an EO is dispatched to close/open the CRD Charging Header Isolation Valve (1-0301-25) use the commands listed below as needed and report back with the status:
irf rd04r close/open CT1 ATC Bypasses RWM and inserts all CRAM rods, then inserts control rods starting with the center rod and spiraling out using EMERGENCY IN OR ROD MOVEMENT CONT switch.
Event 8 continued Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 8 Page 2 of 3 Event
Description:
Full Core Hydraulic ATWS Time Position Applicants Actions or Behavior ATC Directs an EO to pull ARI fuses at Panels 1-2201-70A and 1-2201-70B per QCOP 300-28.
SIM OP ROLE PLAY: As the EO dispatched to remove ARI fuses, wait 3 minutes, then insert/release the following command: QG14R activate Then call back and inform the ATC that:
The ARI fuses are pulled.
ATC Bypasses the SDV high level and attempts to reset the reactor scram, then directs the U2 BOP to install jumpers to bypass all automatic scram signals per QCOP 0300-28.
SIM OP/LEAD EVALUATOR ROLE PLAY: When directed by ATC to bypass auto scram signals, direct the SIM OP to insert/release the following command: QG08R activate Wait 3 minutes, then inform the ATC that:
The jumpers are installed to bypass all automatic reactor scrams.
ATC Resets the reactor scram and determines status of Scram Valves.
ATC When the SDV is drained, (alarm 901-5 A-14 clears), directs U2 BOP to individually scram control rods.
LEAD EVALUATOR ROLE PLAY: If directed to individually scram control rods as the U2 BOP, wait 3 minutes, then inform the ATC that:
Individual control rod scramming was NOT successful.
QGA 101 Pressure Leg Actions BOP Reports ADS valves cycling on RPV pressure.
SRO Directs BOP to lower RPV pressure to 940 psig using ADS valves.
Quad Cities 2021 NRC EXAM Scenario 3 BOP Opens ADS valves as necessary and reports RPV pressure at 940 psig.
SRO Directs BOP to maintain RPV pressure between 600 and 1000 psig using Main Turbine Bypass Valves.
EVALUATOR NOTE: If reactor power is > 38% and ADS valves are still needed for pressure control, then the SRO may assign a pressure band of 600 to 1000 psig.
Events 8 Continued Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 8 Page 3 of 3 Event
Description:
Full Core Hydraulic ATWS Time Position Applicants Actions or Behavior SRO Directs BOP to verify isolations/actuations for 0 inches RPV water level when it is intentionally lowered.
SRO Directs ATC and BOP to terminate and prevent injection into the RPV except for Boron, CRD, and RCIC.
CT3 ATC Places the Low Flow and both Feed Regulator Valve Flow Control Stations in MAN and reduces each controller output to zero.
ATC Closes both MO 1-3206A/B FW REG ISOL VLVs.
CT3 BOP Trip-Latches the REMOTE HPCI TURB TRIP pushbutton.
SRO Directs ATC to report RPV water level at -35 inches.
BOP Reports RPV water level at -35 inches and lowering.
SRO Assigns ATC an RPV water level band of -162 in. to -35 in.
CT4 BOP Re-establishes injection with Condensate/Feed system to control RPV water level in band.
SRO Directs ATC to monitor SBLC Tank level and report when tank level lowers by 16%, (Tank level of 69%, Hot Shutdown weight of Boron).
ATC Reports SBLC Tank level at 69%.
SRO Directs ATC to raise water level above 0 inches and control RPV water level between 0 and 48 inches.
ATC Increases injection with Condensate and Feedwater and slowly raises level above 0 inches and establishes an RPV water level band of 0 to 48 inches.
Quad Cities 2021 NRC EXAM Scenario 3 QGA 200, Primary Containment Control Actions BOP Reports Torus level at -2 inches.
SRO Enters and directs actions of QGA 200.
SRO Directs BOP to start Torus Cooling.
Event 8 Continued Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.3 Event No. 8 Page 3 of 3 Event
Description:
Full Core Hydraulic ATWS Time Position Applicants Actions or Behavior BOP Starts one or both loops of Torus Cooling per QCOP 1000-30.
SRO Directs both to start both CAMs BOP Starts both CAMs per QCOP 2400-01.
BOP Monitors and reports Containment parameters as needed.
SIM OP NOTE: At the direction of the Lead Evaluator, freeze the simulator when the Hot Shutdown Boron Weight (SBLC Tank Level ~ 69%) is injected and a controlled RPV water level rise has been established.
End of Scenario
Quad Cities 2021 NRC EXAM Scenario 3 END of SCENARIO
Quad Cities 2021 NRC EXAM Scenario 4 Exelon Nuclear 2021 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 4 Revision Number: 00 Date: 11/10/2020 Developed by:
Instructor Date Validated by:
SME or Instructor Date Reviewed by:
Operations Representative Date
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2021 NRC Scenario 4 Op-Test No.: ILT 20-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is operating at 100% power, holding load.
Day 2/30 TLCO 3.3.b. Condition A, 3C Relief Valve Acoustic Monitor.
Turnover: Perform QCOS 0203-01, Safety and Relief Valve Acoustic Monitor Surveillance, for 1-203-3C Relief Valve as a PMT.
Critical Tasks:
- 1. The Crew will take action to isolate the RPV and reduce the release of radioactivity by manually closing the MSIVs, Main Steam drains and verifying the Off-Gas System is isolated prior to a required QGA 400 entry.
- 2. With a primary system discharging into the reactor building and the discharge cannot be isolated, verify/INITIATE an emergency depressurization when two or more areas of the same parameter (radiation, temperature, or water levels) are above max safe IAW QGA 300 and appropriate RPV blowdown leg.
Event No.
Malf. No.
Event Type*
Event Description 1
None BOP N
Acoustic Monitor Test 2
FW08A ATC C
1A Feed Reg Valve Lockup 3
RD04R ATC C /TS Control Rod Drifts Out 4
SER0201 BOP C/TS ADS Timer Actuation 5
ED05B BOP C
Trip of Bus 16 and Re-energization 6
FW14A ATC R
1A1 Feedwater Heater Tube leak /
Emergency Power Reduction.
7 None BOP C
Reclose LP Heater String Bypass Valve 8
CR01 RD14A CREW M
SDV leak & Fuel Failure RPV Blowdown (2 areas above max safe rad levels)
Quad Cities 2021 NRC EXAM Scenario 4 9
DIHS10590303 CREW C
Scram Reset Switch Failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:
Total Malfunctions (5-8): 7 Malfunction(s) after EOP (1-2): 1 Abnormal Events (2-4): 2, 3, 4, 5 Major Transient(s) /E-Plan entry (1-2): 8 EOPs (1-2): QGA 100 / 300 EOP Contingencies (0-2): 100BD Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:
BOP Normal: 1 ATC Reactivity (1 per set): 5 BOP I/C (4 per set): 4, 5 ATC I/C (4 per set): 2, 3 SRO-I I/C (4 per set inc 2 as ATC): 2, 3, 4, 5 SRO Tech Spec (2 per set): 3, 4 ALL Major Transients (2 per set): 8
Quad Cities 2021 NRC EXAM Scenario 4
SUMMARY
Initial Conditions:
o The plant is operating at 100% power, holding load.
o TLCO 3.3.b. Condition A, Function 2, for the 1-203-3C Relief Valve Acoustic Mon.
Event 1: BOP Normal: Perform QCOS 0203-01, Safety and Relief Valve Acoustic Monitor Surveillance, as a PMT for the 1-203-3C Relief Valve.
Event 2: 1A FRV Lockup: The 1A Feed Reg Valve locks up due to a loose connector on the LVDT. Instrument Maintenance will tighten the loose connection and the ATC reset the lockup and restore the 1A FRV control to automatic mode.
Event 3: Control Rod Drift: The ATC responds to a drift alarm and reports control rod H-10 is drifting out. The SRO directs actions of QCOA 0300-11 and the control rod is fully inserted, scrammed and electrically disarmed. The SRO declares the rod inoperable and enters TS 3.1.3 Condition C.
Event 4: ADS Timer Actuation: The BOP reports annunciator 901-3 B-13, AUTO BLOWDN TIMER START, in alarm. The SRO directs the BOP to take actions of the QCAN. The BOP attempts to reset the Timer, then inhibits ADS. The SRO declares ADS inoperable and enters Event 5/6: 1A1 Feedwater Heater Tube Leak: A tube leak in the 1A1 Heater results in a Low Pressure Heater String isolation. The SRO directs actions of QCOA 3500-01 and the ATC performs an emergency power reduction per QCGP 3-1. When total feedwater flow is < 7.6 Mlb/hr and the heater high level alarm has cleared (901-6 G-1), the BOP closes the 1-3403 LP HTR STRING BYP VLV terminating the reactivity transient.
Event 7: Fuel Failure/SDV Leak: A Fuel failure results from the reactivity transient. The crew will respond to virus high radiation alarms and announce evacuation of the Reactor and Turbine Buildings. Radiation Protection will be directed to set up access control and Chemistry to obtain coolant and effluent samples. The SRO directs a manual reactor scram on OffGas Hi Hi effluent. An RP Tech reports large steam and water leak from the North Scram Discharge Volume. Radiation level on the 1st, 2nd, and 3rd floor of the Reactor Building and the Torus area will exceed max safe levels. The SRO will direct an RPV blowdown per QGA 100.
Event 8: Scram Reset Switch Failure: The ATC will attempt to isolate the SDV leak by resetting the reactor scram, however, the switch fails and the scram cannot be reset.
Approximate Run Time: 1.5 Hours
Quad Cities 2021 NRC EXAM Scenario 4 CRITICAL TASKS:
Critical Task #1: The Crew will take action to isolate the RPV and reduce the release of radioactivity by manually closing the MSIVs, Main Steam drains and verifying the Off-Gas System is isolated prior to a required QGA 400 entry.
Critical Task #2: With a primary system discharging into the reactor building and the discharge cannot be isolated, verify/INITIATE an emergency depressurization when two or more areas of the same parameter (radiation, temperature, or water levels) are above max safe IAW QGA 300 and appropriate RPV blowdown leg within 10 minutes.
Clarification: The critical task is not met if an emergency depressurization is NOT performed when multiple areas reach max safe values for the same parameter with an unisolable primary system leak discharging into the areas -or-if an emergency depressurization is performed before indications are present in multiple areas. In some cases, regarding radiation levels, control room indications will not provide adequate information. In such cases, local surveys will be needed and sound operational judgement will need to be applied. The evaluation team must determine if the local reports justify performing an emergency depressurization in such cases, especially where accessibility is limited.
Quad Cities 2021 NRC EXAM Scenario 4 EXERCISE PERFORMANCE OBJECTIVES SR-0203-P04 (Freq: LIC=I) Given an operating reactor plant, perform the Monthly Safety and Relief Valve Acoustic Monitor Surveillance in accordance with QCOS 0203-01.
SR-0300-P03 (Freq: LIC=I) Given an operating plant with a drifting control rod, insert/disarm the drive and attempt to determine the cause in accordance with QCOA 0300-04 and QCOA 0300-11.
SR-0600-P02 (Freq: LIC=B) Given an operating reactor plant and a condition resulting in a lockup of an operating FWRV, determine the cause and return the FWRV to automatic operation in accordance with QCOA 0600-01 and QCOP 0600-18.
(SOER 84-4 r1)
SR-3500-P02 (Freq: LIC=A) Given an operating plant when an A heater high level (loss of FW heating) occurs, perform actions to control reactor power and reclose LP heater bypass valve in accordance with QCOA 3500-01 and QCOA 0400-01.
SR-1700-P03 (Freq: LIC=B) Given a reactor plant at power and a fuel clad failure or high activity in off-gas, take action to reduce the release in accordance with QCOA 1700-05 or QCOA 1700-04. (SOER 90-2 r2)
SR-0001-P40 (Freq: LIC=A) Given a reactor plant with a reactor building area radiation alarm, temperature alarm, differential pressure at or above 0 inches, or area water level above 1 inch, attempt to isolate all discharges into an area except systems needed for damage control or other QGA actions in accordance with QCOA 0201-5 and QGA 300.
SR-0001-P41 (Freq: LIC=A) Given an operating reactor plant with a primary system discharging into the reactor building, verify manual scram, enter/re-enter QGA 100 before any area exceeds the maximum safe operating temperature/radiation/water level in accordance with QGA 300. (BWROG SC-1.1)
SR-0001-P42 (Freq: LIC=A) Given a reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, verify/initiate an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water levels) in accordance with QGA 300. (Important PRA Task-Emergency Depressurization has a RAW of 1.44 E4 for CDF and a RAW of 1.59 E4 for LERF)
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts.
Quad Cities 2021 NRC EXAM Scenario 4 Simulator Setup:
- 1. Reset to IC-21 (100% power) and Go to RUN.
- 2. Verify the following RWM Sequence is loaded: 6PHESD (or current shut down sequence)
- 3. Clear annunciators
- 4. Save setup to an IC
- 5. Place INFO cards as follows: None.
- 6. Insert Commands for setup:
ior DIHS10590303 norm (Override the Scram Reset Switch in NORMAL) imf RD14A 100 5: (Insert a 100% break ramped over 5 min. on the North SDV triggered on the Mode Switch in S/D) imf RD13A 95 (Insert a 95% blockage on the North SDV)
- 7. Verify the following commands for scenario performance:
Event 2: imf FW08A (Lock-up the 1A FRV) ior AOVI10642A 0 (override 1A FRV position indication to 0) dmf FW08A (Delete the 1A FRV lockup)
Event 3: imf RD04R3039 (Drift out control rod H-10)
Event 4: imf SER0201 on (Override annunciator 901-3 B-13 on) dmf SER0201 (Clear annunciator 901-3 B-13 override)
Event 5: imf FW14A 100 5: (Insert a 1A1 Heater tube failure at 100% ramped over 5 min.)
Event 7: imf CR01 100 10: (Insert a 100% fuel failure ramped over 10 min.)
ior RM02E 4.5 (Override SJAE Mon 1 to indicate 4.5 E+04 units) ior RM02F 5 (Override SJAE Mon 2 to indicate 5 E+04 units)
Override Reactor Building 1st, 2nd, and 3rd Floor ARMs to read elevated rad levels:
ior RM0111 50 5: ior RM0108 35 6: ior RM0106 28 7:
ior RM0112 35 5: ior RM0109 30 6: ior RM0107 25 7:
ior RM0113 30 5:
Remote functions:
irf SW10R RUN (Local start of the U1 DGCWP) irf RD06R3039R INOP (Control rod H-10 out of service)
- 8. Install Protected System placards and/or rings on the following equipment:
o RBCCW pumps o Fuel Pool Cooling Water pumps
- 9. Provide the following:
o Holding Load and Load Following REMA o Turnover Sheet o Marked up copy of QCOS 0203-01, for the 1-203-3C Relief Valve Acoustic Monitor only.
Quad Cities 2021 NRC EXAM Scenario 4 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o
901(2)-3 A-1, REACTOR BUILDING AREA RADIATION MONITOR CHANNEL HIGH RADIATION, Rev. 08 o
901(2)-3 A-2, MAIN STEAM LINE HIGH RADIATION, Rev.12 o
901(2)-3 D-1, TURBINE BUILDING AREA RADIATION MONITOR CHANNEL HIGH, Rev. 07 o
901(2)-3 B-13, AUTOMATIC BLOWDOWN TIMER START, Rev. 07 o
901(2)-3 C-2, HIGH-HIGH RADIATION AT SJAE OUTLET, Rev. 09 o
901(2)-3 D-13, ELECT RELIEF VALVES 3A 3B OPEN, Rev. 07 o
901(2)-3 E-14, ACOUSTIC MON SAFETY RLF VALVES OPEN, Rev. 07 o
901(2)-5 A-3, CONTROL ROD DRIFT IN OR OUT OF CORE, Rev. 08 o
901(2)-5 A-6, APRM UPSCALE / HIGH Rev. 08 o
901(2)-5 G-7, 1(2) A FEEDWATER ACTUATOR TROUBLE, Rev. 06 o
901(2)-5 F-8, RX VESSEL LOW LEVEL, Rev.11 o
901(2)-6 G-1, FEEDWATER HEATER 1(2) A1 HIGH LEVEL, Rev. 04 QCOP 0600-18, Main Feedwater Regulator Operation, Rev. 27 QCOA 0201-05, Primary System Leaks (Slow Leaks) Outside Primary Containment, Rev. 11 QCOA 0201-09, Reactor Low Water Level, Rev. 28 QCOA 0400-02, Core Instabilities, Rev. 27 QCOA 0600-01, Feedwater Regulator Lockup, Rev. 15 QCOA 1700-04, Abnormal Off Gas Radiation, Rev. 24 QCOA 1700-05, Abnormal Main Steam Line Radiation, Rev. 19 QCOA 1800-01, Area High Radiation, Rev. 07 QCOA 3500-01, Feedwater Temperature Reduction with Main Turbine Online, Rev. 43 QCGP 2-3, Reactor Scram, Rev. 99 QCGP 3-1, Reactor Power Operations, Rev. 89 QGA 100, RPV Control, Rev. 13 QGA 300, Secondary Containment Control, Rev. 14
Quad Cities 2021 NRC EXAM Scenario 4 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is currently at 100% power (2951 MWth) on the 101% FCL. Rod step 19 is partially withdrawn.
b.) Unit 2 is at 100% Power.
c.) Technical Specification limitations:
Unit 1: TLCO 3.3.b. Condition A, Function 2, 1-203-3C Relief Valve Acoustic Monitor inoperable.
Unit 2: None d.) On Line Risk is GREEN e.) Fire Risk is GREEN.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling 2.) Significant problems/abnormalities:
a.) None.
3.) Evolutions/maintenance for the oncoming shift:
a) Perform QCOS 0203-01, Safety and Relief Valve Acoustic Monitor Surveillance, for 1-203-3C Relief Valve as a PMT.
b) Continue holding load per QCGP 3-1.
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 1 Page 1 of 1 Event
Description:
Acoustic Monitor Test Time Position Applicants Actions or Behavior SRO Directs BOP to perform QCOS 0203-01 to test the 3C Relief Valve Acoustic Monitor.
BOP Obtains and records the following data on QCOS 0203-01, Attachment A for steps H.1 thru H.4.
BOP Performs steps H.1. thru H.3. as follows:
BOP At the 1-203-3C FLOW DETECTOR on the 901-21 panel:
o Selects channel A o Places display switch in I (Input) and records Input level o Places the display switch to T and records Threshold Setpoint o Returns display switch to I BOP Performs step H.4. to test alarms and indications as follows:
BOP Places and holds TEST/RESET switch to TEST and verifies the following:
o Input level surpasses the Threshold Setpoint.
o OPEN red light comes on o CLOSED green light goes off as Threshold Setpoint is reached.
o MEMORY amber light comes on.
o At Panel 901(2)-3 E-14, ACOUSTIC MON SAFETY RLF VALVES OPEN, alarm is received.
o Process Computer alarm, SAFETY/ELECTROMATIC VLV 203-3C OPEN alarm is received.
BOP Performs step H.5. for proper operation by verifying the following:
o Input level is < 0.09 prior to testing.
o Acoustic monitor alarms when Threshold Setpoint is exceeded.
o Threshold Setpoint is >.09 and <.11 when display switch is in the "T" position BOP Determines no discrepancies for acoustic monitor in step H.6.
BOP Signs off surveillance as satisfactory in step H.8. and on Attachment A.
BOP Forwards completed surveillance to the SRO.
End of Event 1
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 2 Page 1 of 3 Event
Description:
1A Feed Reg Valve Lockup Time Position Applicants Actions or Behavior SIM OP NOTE: As directed by the Lead Evaluator, insert/release commands for a 1A Feed Reg Valve lockup and loss of valve position indication:
FW08A AOVI10642A 0 Key Parameter Response: 1A Feed Reg Valve fails as is (i.e. locks up),
1A VLV RESET light is lit.
Expected Annunciator(s): 901-5 G-7 Automatic Actions: 1A FWRV transfers to MANUAL ATC Reports and acknowledges annunciator 901-5 G-7, 1A FW ACTUATOR TROUBLE.
SRO Directs BOP to take actions per QCAN 901(2)-5 G-7.
ATC Monitors RPV water level and verifies A FWRV is in MAN.
ATC Verifies B FWRV is in AUTO and controlling vessel level.
ATC/BOP Dispatches EO to the Feed Reg Valves to investigate.
SIM OP ROLE PLAY: As the EO dispatched to the Feed Reg Station, wait 1 minute then report:
I dont see any apparent problem with the 1A FWRV itself, however the Nematron local display is showing alarms for Valve Position and Tracking Difference between Input and Valve Position for the 1AFWRV.
SRO Directs ATC/BOP to refer to QCOA 0600-01.
SRO Contacts QNE for Thermal Limit adjustment due to > 38.5% RTP and one FRV in manual.
SIM OP ROLE PLAY: As the QNE, state:
Ill check the COLR and QCGP 4-1 and apply the thermal limit penalties within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the problem cannot be resolved in the next hour.
Event 2 continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 2 Page 2 of 3 Event
Description:
1A Feed Reg Valve Lockup Time Position Applicants Actions or Behavior ATC Contacts Electrical Maintenance to check fuse F13 at Panel 901-5, TB-HH.
SIM OP ROLE PLAY: As the EM directed to check fuse F-13 in the 901-5 panel, (OR called to troubleshoot), walk inside the panels, wait one minute, then come out and report:
Fuse F-13 on TB-HH is blown. I brought up a like-for-like replacement that has been checked for continuity and can install it.
EVALUATOR / SIM OP ROLE PLAY: If the crew contacts System Engineering for an evaluation before replacing the fuse, report the following to the crew:
One hour has passed, System Engineering has completed the evaluation and recommends replacing fuse F-13.
SIM OP ROLE PLAY: When permission is given to install the replacement fuse, walk inside the panels, and delete the malfunction:
dmf FW08A Then come out and report:
The replacement fuse is installed.
SRO Directs ATC to reset the lockup and return 1A Feed Reg Valve to automatic operation per QCOP 0600-18.
BOP Performs peer-checks for FWLC operations.
ATC Resets 1A FWRV lock-up per QCOA 0600-01, step D.5. as follows:
o Verifies position demand (DEM%) signal on 1-640-19A and on the OWS/R-time (+/-1%) match the VLV POS INDICATOR %.
o Depresses 1A VLV RESET pushbutton and holds for 5 sec.
o Verifies 901-5 G-7 alarm resets.
o Verifies RPV water level is stable.
Event 2 Continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 2 Page 3 of 3 Event
Description:
1A Feed Reg Valve Lockup Time Position Applicants Actions or Behavior ATC Places 1A FWRV in AUTO per QCOP 0600-18 step F.5.b.
o Balances position of the FRVs by adjusting 1A FWRV position demand signal at the controller OR at the OWS.
o Verifies FWLC is SEQUENCE MANUAL at the OWS.
o Places 1A FWRV in AUTO using AUTO pushbutton on the controller OR at the OWS.
ATC Reports both FWRVs are operating in AUTO and RPV water level is stable.
SIM OP ROLE PLAY: As the EO dispatched to the 1A FRV, after the fuse is replaced, report:
Everything looks normal, the Hydraulic pump is running, oil pressure is normal, input signal demand and valve position are displaying on the Nematron.
End of Event 2
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 3 Page 1 of 2 Event
Description:
Control Rod Drifts Out Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, insert/release block command to drift control rod H-10 out of the core:
RD04R3039 Key Parameter Response: MWE, Rx. Press.
Expected Annunciator(s): 901-5 A-3 Automatic Actions: None ATC Acknowledges alarm 901-5 A-3, ROD DRIFT and reports control rod H-10 is drifting out.
SRO Directs actions of QCOA 0300-11, Control Rod Drift.
- 1) Two or more Control Rods drift AND all RPS scram solenoids are lit.
- 2) Four or more Control Rods drift.
ATC Selects Control Rod H-10 and inserts it to position 00 and reports it will NOT latch.
ATC Reapplies and maintains insert signal and reports the Control Rod will stay inserted to at least position 04.
SRO Notifies the Shift Manager.
SRO Contacts a Qualified Nuclear Engineer (QNE).
SIM OP ROLE PLAY: If contacted as the QNE, inform the operator that you will:
Adjust the rod sequence to compensate for the inoperable control rod and verify no thermal limits were violated.
BOP/SRO Demands an OD-20 on the PPC per QCOP 9950-20.
BOP Requests the individual Control Rod scram test key.
EVALUATOR ROLE PLAY: When requested, give the BOP the Control Rod Scram Test Key.
Event 3 continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 3 Page 2 of 2 Event
Description:
Control Rod Drifts Out Time Position Applicants Actions or Behavior BOP Places the individual Control Rod scram test switch to the scram position for rod H-10 at Panel 901-16.
BOP Dispatches an EO to HCU 30-39 and directs closure of the 1-305-105, CRD EXH VLV.
SIM OP ROLE PLAY: As the EO dispatched to HCU 30-39, wait 2 minutes, insert/release the remote function:
RD06R3039R INOP Then report:
The 1-301-105, CRD EXH VLV on HCU 30-39 is closed.
If directed to electrically disarm the control rod, also report:
Ive disconnected the four amphenol plugs for HCU 30-39 per QCOP 300-07.
TS SRO Enters Technical Specification 3.1.3 Condition C, One or more control rods inoperable. (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to insert / 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to disarm)
ATC Monitors Reactor power, pressure, and water level and reports all parameters are stable.
End of Event 3
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 4 Page 1 of 2 Event
Description:
ADS Timer Actuation Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, insert/release the Smart program to override and clear annunciator 901-3 B-13 as required using the following 2 commands:
SER0201 ON dmf SER0201 Key Parameter Response: None Expected Annunciator(s): 901-3 B-13 Automatic Actions: None (No ECCS pumps are running)
BOP Reports and acknowledges annunciator 901-3 B-13, AUTO BLOWDN TIMER START.
SRO Directs actions of QCAN 901(2)-3 B-13.
ATCBOP Reports that Drywell pressure is < 2.43 psig and RPV water level is > -
56.78 inches BOP Depresses and holds pushbutton TIMER RESET for 3 seconds.
BOP Verifies that alarm does NOT clear BOP Places AUTO BLOWDOWN INHIBIT keylock switch to INHIBIT ATC/BOP Contacts Electrical Maintenance to investigate Div I ADS Timer.
SIM OP ROLE PLAY: As the EM Supervisor, acknowledge the request and state:
Ill get the System Engineer and start inspecting Division I ADS logic string and 110 sec Timer for possible causes of the alarm. Well obtain permission from the Shift Manager and inform you before opening panel doors in the Aux Electric Room.
Event 4 Continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 4 Page 2 of 2 Event
Description:
ADS Timer Actuation Time Position Applicants Actions or Behavior TS SRO Enters the following Technical Specifications:
TS 3.5.1 Condition H, One ADS valve inoperable. (14 days)
TS 3.5.1 Condition J, Two or more ADS valves inoperable. (Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 150 psig dome pressure in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />)
(NOTE: The SRO may conservatively enter the actions for an inoperable Div I ADS 110 sec Timer)
TS 3.3.5.1, Condition A and G, One or more required channels inoperable. (Declare ADS valves inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore channel to operable status in 8 days)
End of Event 4
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 5/6 Page 1 of 2 Event
Description:
1A1 Feedwater Heater Tube leak / EPR Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, insert/release command to insert a 1A1 Feedwater Heater tube failure at a severity of 100% ramped over 5 min.:
FW14A 100 5:
Key Parameter Response: APRM power, MWE Expected Annunciator(s): 901-6 G-1, 901-6 E-4/5/6, 901-5 A-6, 901-5 C-3 Automatic Actions:
LP Heater String isolates (MO 1-3401A and MO 1-3402A close)
LP Heater String Bypass opens (MO 1-3403)
D Heater Emergency Drain Valves open Rod Out Block ATC/BOP Acknowledge and report 901-6 G-1, HEATER 1A1 HIGH LEVEL alarm.
BOP Reports LP Heater String 1 Isolation Valves have closed and the LP Heater String Bypass Valve has opened.
SRO Directs actions of QCOA 3500-01, Feedwater Temperature Reduction with Main Turbine Online.
SRO Sets scram criteria at 105% rated thermal power and/or indications of core instabilities.
SRO Directs an Emergency Power Reduction to 7.6 Mlb/hr Feedwater flow.
ATC Reduces Recirc Pump speeds by at least 30% using the MANUAL RUNBACK pushbutton.
ATC Inserts CRAM rods until all of the following conditions are met:
(1) Reactor power has stopped increasing.
(2) FCL is less than the MELLLA boundary.
(3) Operation is outside Instability Region II.
Event 5/6 continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 5/6 Page 2 of 2 Event
Description:
1A1 Feedwater Heater Tube leak / EPR Time Position Applicants Actions or Behavior SRO Directs ATC to refer to QCOA 0400-02 and continue monitoring for core instabilities.
BOP Monitors D Heater Inlet and Outlet temperatures using computer points F146 and F178 respectively.
ATC Reports Feedwater flow < 7.6 Mlb/hr.
SRO Directs BOP to close MO 1-3403, LP HTR STRING BYP VLV, when annunciator 901-6 G-1 clears.
Event 6 BOP Reports alarm 901-6 G-1 has reset and closes MO 1-3403 valve.
SRO Contacts QNE to verify core thermal limits and CRDA requirements.
SIM OP ROLE PLAY: As the QNE, state:
Ill monitor thermal limits and review the appropriate sections of the COLR for any required changes. Ill also verify the CRDA requirements are met.
SRO Contacts the Chemistry Department to perform sampling for power change > 20% RTP.
SIM OP ROLE PLAY: As Chemistry Supervision, state:
Ill dispatch a Tech to start sampling reactor water for I-131 Equivalent per CY-QC-120-503 Attachment 1 and report the results as soon as possible.
BOP Continues to monitor D Heater Outlet temperature vs QCOA 3500-01 Attachment A limits to determine if any further actions or notifications are required.
EVALUATOR NOTE: The crew may move to secure a Reactor Feed Pump and a Condensate Pump. If EOs are dispatched for local actions, the SIM OP will acknowledge the calls and proceed to the next event with concurrence from the Lead Evaluator.
End of Event 5/6
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 7/8 Page 1 of 5 Event
Description:
Fuel Failure / SDV Leak / SCRAM Reset Switch Failure Time Position Applicants Actions or Behavior SIM OP NOTE: At the direction of the Lead Evaluator, insert the block command for a 100%
fuel failure ramped over 10 minutes:
CR01 100 10:
When CR01 has timed out, override both SJAE Radiation Monitors to 4.5 E+04 and 5.0 E+04 units. This will force the 901-3 C-2 alarm in:
RM02E 4.5 RM02F 5 SIM OP NOTE: When the Mode Switch is taken to S/D, verify the command for a break on the North Scram Discharge Volume is inserted at a severity of 100% ramped over 5 minutes:
RD14A 100 5:
Key Parameter Response: Rx Bldg radiation levels, Turbine Bldg radiation levels Expected Annunciator(s): 901-3 A-1, 901-3 D-2, 901-5 A-8, 901-56 A-1 Automatic Actions: (listed below)
Isolations: Group II, Off-Gas, Rx Building and Control Room Ventilation Initiations: SBGTS BOP Acknowledges and reports the following annunciators:
901-3 D-2, OFF GAS HI RADIATION 901-56 A-1, DRYWELL HIGH RAD CONC BOP Announces evacuation of Reactor Building over the plant PA system.
BOP Refers to QCAN, notifies Radiation Protection of conditions and requests access control.
BOP Notifies Chemistry of abnormal Off Gas activity.
SIM OP ROLE PLAY: As the Radiation and Chemistry Supervisors, acknowledge reports of high Off Gas and area radiation levels. Concur with direction to establish access control and obtain samples.
SRO Directs BOP to enter QCOA 1800-01 and QCOA 1700-04 and monitor Off Gas activity levels.
Events 7/8 Continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 7/8 Page 2 of 5 Event
Description:
Fuel Failure / SDV Leak / SCRAM Reset Switch Failure Time Position Applicants Actions or Behavior BOP BOP acknowledges 901-56 A-1, DRYWELL HIGH RAD CONC alarm.
Reports Drywell radiation 20 R/hr and rising.
ATC Reports Group II isolation on Drywell high radiation.
BOP Verify Reactor Building Ventilation isolates and SBGT autostarts on Group II isolation signal.
ATC Reports Control Room Ventilation has isolated.
SRO Sets scram criteria at Off-Gas HI-HI alarm setpoint, (901-3 C-2).
ATC/BOP Acknowledges and reports 901-3 C-2, OFF GAS HI-HI RADIATION, alarm.
SRO Directs ATC to insert a manual reactor scram.
ATC Inserts a manual reactor scram.
SRO Directs BOP to isolate the Off Gas System and close the MSIVs per QCOA 1700-04.
BOP Places the control switch for AO 1-5406 to the CLOSE position and verifies the following valves close:
AO 1-5406, OG DISCH TO STACK AO 1-5408A, OFFGAS FILT DRN AO 1-5408B, HOLDUP PIPE DRN CT1 BOP Closes all MSIVs.
BOP Verifies all MSIV Drain Valves are closed.
QGA 100, RPV CONTROL actions SRO Enters and directs actions of QGA 100.
ATC Reports all rods in, RPV water level < 0 inches and recovering, RPV pressure < 1060 psig.
SRO Directs BOP/ATC to verify auto actions for 0 inches RPV water level.
Events 7/8 Continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 7/8 Page 3 of 5 Event
Description:
Fuel Failure / SDV Leak / SCRAM Reset Switch Failure Time Position Applicants Actions or Behavior SRO Directs ATC to maintain RPV water level between 0 in. and 48 in. using Condensate and Feedwater system.
SRO Directs pressure band of 800-1000 psig.
SRO Direct the ATC/BOP to start a reactor cooldown at < 100 ºF/hr using ADS valves.
ATC Opens ADS valve and starts a reactor cooldown.
SRO Directs BOP to start Torus Cooling.
BOP Starts Torus Cooling on one or both loops and monitors Torus temperature.
BOP Acknowledges and reports 901-3 A-1, RX BLDG HI RADIATION, alarm and refers to annunciator procedure.
BOP Monitors ARM trip units and 1-1806-1, AREA RADIATION MONITOR on the 901-11 panel. Reports HPCI Cubicle at 100 mr/hr and rising.
QGA 300, SECONDARY CONTAINMENT CONTROL actions SRO Enters and directs actions of QGA 300.
ATC Dispatches EO to start U1 Diesel Generator Cooling Water Pump.
SIM OP ROLE PLAY: If dispatched to start the U1DGCWP, wait 2 minutes, insert/release remote function: SW10R RUN Then call back and report:
The Unit 1 DGCWP has been started and is running.
ATC Dispatches EO to monitor Reactor Building basement area water levels SIM OP ROLE PLAY: As the EO dispatched to monitor area water levels, wait 5 minutes, then report:
Ive checked the RB Basement and all corner rooms. There are no steam leaks or any accumulation of water on the floor. The RP Tech is seeing elevated dose rates and has recommended moving to a low dose area.
Events 7/8 Continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 7/8 Page 4 of 5 Event
Description:
Fuel Failure / SDV Leak / SCRAM Reset Switch Failure Time Position Applicants Actions or Behavior SRO Verifies Fuel Pool level is normal by absence 901-4 B-24, FUEL POOL STORAGE HI/LO LEVEL, alarm.
SRO Directs BOP to verify Fuel Pool temperature < 125ºF.
BOP Verifies Pt. #6 on recorder 1-1040-5, RHR TEMPS on 901-3 panel is <
125ºF.
SIM OP ROLE PLAY: As a Radiation Protection Tech, call in and report:
There is a large leak in the North Scram Discharge Volume. There is a lot of steam and water pouring out. No one else is in the area because of the access control. Area dose rates are also rising.
SRO Directs ATC to reset the reactor scram to stop the leak.
ATC Attempts a scram reset and reports the scram will not reset.
ATC Reports the SCRAM RESET switch is not working properly.
SRO Determines that a Primary System is discharging into the Reactor Building (SDV Leak) and cannot be isolated.
SRO Contacts Electrical Maintenance to investigate.
SIM OP ROLE PLAY: If contacted, as EM Supervisor, state: Well gather the necessary Electrical schematics and Wiring Diagrams and report to the Control Room.
SIM OP NOTE: Ramp the Reactor Building ARMs using the following commands to attain max safe rad levels on the 1st and 2nd floor and elevated readings on the 3rd floor:
RM0106 28 7:
RM0107 25 7:
RM0108 35 6:
RM0109 30 6:
RM0111 50 5:
RM0112 35 5:
RM0113 30 5:
BOP Reports ARMs 11, 12, and 13 (Reactor Building 1st Floor) are reading
>3000 mr/hr.
SRO Verifies reactor is scrammed and re-enters QGA 100.
Events 7/8 continued
Quad Cities 2021 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No.4 Event No. 7/8 Page 5 of 5 Event
Description:
Fuel Failure / SDV Leak / SCRAM Reset Switch Failure Time Position Applicants Actions or Behavior BOP Reports ARM 9, (Reactor Building 2nd Floor) is now indicating >3000 mr/hr.
RPV BLOWDOWN (QGA 100 at )
SRO Enters QGA 100 and concurrently directs Blowdown steps of QGA 100 at.
SRO Verifies all rods in to at least position 04.
BOP Verifies Drywell pressure < 2.5 psig.
BOP Verifies Torus level is above 5 ft.
SRO Directs BOP to open all 5 ADS valves and leave switches in MAN position.
CT2 BOP Opens all 5 ADS valves and leaves switches in MAN.
BOP Confirms all ADS valves are open by the acoustic monitor indications on the 901-21 panel.
ATC/BOP Monitor RPV depressurization to < 100 psig.
SIM OP NOTE: When Blowdown has been performed and with concurrence of the Lead Examiner, place the simulator in FREEZE.
End of Scenario
Quad Cities 2021 NRC EXAM Scenario 4 END OF SCENARIO
Quad Cities 2021 NRC EXAM Scenario 5 Exelon Nuclear 2021 NRC Exam Scenario Scenario Number:
NRC Scenario 5 Revision Number: 00 Date: 11/20/2020 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2021 NRC Scenario 5 Op-Test No. ILT 20-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is currently at 75% power and holding load for a revision to the ReMA.
Turnover: Perform the Core Spray Monthly surveillance for the 1B Core Spray pump.
Critical Tasks:
- 1. With a failure of both Recirc Pump Inboard and Outboard seals, accompanied by an increase in Drywell pressure OR temperature, isolate the leak by closing the pump suction and discharge valves.
- 2. When executing QGA 200, Primary Containment Control, when Torus level cannot be maintained above 11 feet, manually SCRAM and INITIATE emergency RPV depressurization.
Event No.
Malf. No.
Event Type*
Event Description 1
None BOP N/TS Perform Core Spray Monthly Surveillance (1B Core Spray pump) 2 NM14L1633 ATC I
LPRM Upscale failure 3
ANO9128A8 SRO TS SSMP Room Cooler inoperable.
4 DIHS156041A LOHS156041A BOP C
1A Gland Exhauster trip.
5 DIFC10262222 RAISE ATC C
Recirc Pump Master Controller fails high 6
RR06A RR06B BOP C/TS Recirc Pump Seal Leak 7
None ATC R
Emergency Power Reduction for Loss of Recirc Pump 8
PC07 CREW M
Torus Leak 9
RP05A/C CREW C
Scram / Spurious Group I Isolation 10 None CREW C
Blowdown on Low Torus Level
Quad Cities 2021 NRC EXAM Scenario 5 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes:
Total Malfunctions (5-8): 6 Malfunction(s) after EOP (1-2): 9 Abnormal Events (2-4): 2, 4, 5, 6 Major Transient(s) /E-Plan entry (1-2): 8 EOPs (1-2): 100, 200, 300 EOP Contingencies (0-2): 100BD Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:
BOP Normal: 1 ATC Reactivity (1 per set): 7 BOP I/C (4 per set): 4 & 6 ATC I/C (4 per set): 2 & 5 SRO-I I/C (4 per set inc 2 as ATC): 2,4,5,6 SRO Tech Spec (2 per set): 3 & 6 ALL Major Transients (2 per set): 8
Quad Cities 2021 NRC EXAM Scenario 5
SUMMARY
Initial Conditions:
o The plant is operating at 75% power, holding load for a ReMA revision.
Event 1: The BOP performs QCOS 1400-04, Core Spray Pump Operability Test for the 1B Core Spray Pump.
Event 2: LPRM Upscale Failure: LPRM 16-33C fails upscale high causing APRM 2 to also indicate high. The SRO will direct the ATC and BOP to bypass the LPRM per QCOP 0700-
- 03. Prior to bypassing the LPRM, the crew will determine APRM 2 will NOT have the minimum required C level inputs. The SRO will direct the ATC to bypass APRM 2, then LPRM 16-33C.
Event 3: SSMP Room Cooler Inoperable: The BOP will dispatch an EO to the SSMP Room in response to the 912-8 A-8, Safe Shutdown System Trouble alarm. The EO will report that the Compressor Trip light is lit on the Room Cooler. The EO will attempt a reset as directed by the BOP, however, it will be unsuccessful. The SRO will declare the SSMP inoperable due to an inoperable room cooler and enter TS 3.7.9 Condition A (14 days) for both Units.
Event 4: 1A Gland Exhauster Trip: The running Gland Seal Exhauster will trip. The BOP will start the standby Exhauster and adjust Gland Exhaust pressure.
Event 5: Master Recirc Controller Failure: The Master Recirc Controller will fail high resulting in APRM power, Total Core Flow, and Recirc Pump speeds all showing an increasing trend.
There are several ways for the ATC operator to take manual control and terminate the transient, ie. speed hold, placing Recirc controllers in individual manual, or depressing the LOWER pushbutton on the Master Controller.
Event 6: Recirc Pump Seal Leak: The ATC will report degradation of the 1A Recirc pump seals. When Drywell pressure and temperature rise the SRO will direct the ATC to trip the 1A Recir pump and isolate it by closing the pump suction and discharge valve. The SRO enters TS 3.4.1 Condition C Event 7: Emergency Power Reduction: The SRO will direct the action for QCOA 0202-04 for the loss of a Recirc Pump. The ATC will insert control rods and the BOP will lower the operating Recirc pump speed. The plant will be stabilized at a lower power with operation within MELLLA and outside of ICA Region II.
Event 8: Torus Leak: The BOP will respond to annunciator 901-3 A-14, TORUS HIGH/LOW LEVEL and report Torus level at -0.5 inches and lowering. The EO dispatched to the Reactor Building basement reports a large leak in the ECCS ring header. QGA 200 is entered when Torus level drops below -2 inches. Attempts to raise Torus level and repair the leak are unsuccessful and the reactor is scrammed at 12 ft. Torus level.
Event 9: Scram/Group I: A spurious Group I occurs simultaneously with the manual scram.
The crew will use ADS valves to initiate a cooldown as the Group I will not reset.
Event 10: Blowdown: The crew will blowdown the RPV at 11 ft. Torus level by opening all five ADS valves.
Approximate Run Time: 1.5 Hours
Quad Cities 2021 NRC EXAM Scenario 5 CRITICAL TASKS:
Critical Task #1: With a failure of both Recirc Pump Inboard and Outboard seals, accompanied by an increase in Drywell pressure OR temperature, isolate the leak by closing the pump suction and discharge valves prior to 2.5 psig Drywell pressure.
Critical Task #2: When executing QGA 200, Primary Containment Control, when Torus level cannot be maintained above 11 feet, manually SCRAM and INITIATE emergency RPV depressurization.
Clarification: This critical task is not met if emergency depressurization is not performed when conditions indicate that Torus level cannot be held above 11 feet.
Meeting this critical step neither requires nor prohibits actions before the limit is reached. The actions may be taken as soon as it is decided that the limit will ultimately be exceeded or delayed until Torus level actually reaches the limit. If Torus level drops below the limit, the actions must be performed and they may not be delayed while attempts are made to restore Torus level to >11 feet. If necessary, this will require some discussion among the evaluation team.
This critical step is also not met if the reactor has NOT been scrammed before emergency depressurization is initiated. This would result in automatic PCIS and RPS actuations due to MSIV closure.
Quad Cities 2021 NRC EXAM Scenario 5 EXERCISE PERFORMANCE OBJECTIVES SR-0202-P04 (Freq: LIC=A) Given an operating reactor plant with a loss of one reactor recirculation pump, take actions to determine the cause, stabilize plant parameters and to exit the instability region in accordance with QCOA 0202-
- 04.
SR-0202-P09 Given a reactor plant with power increasing due to a failure of RR flow control, take actions to manually control pump speed and stabilize plant parameters in accordance with QCOA 0202-02.
SR-0700-P06 (Freq: LIC=B) Given an operating reactor plant with an LPRM failure, take actions to bypass the failed LPRM and meet TS requirements in accordance with QCOP 0700-03.
SR-2400-K21 SR-2400-K21 (Freq: LIC=B) Given a CAM operating mode and various plant conditions, PREDICT how CAM / plant parameters will respond to manipulation of the following CAM local/remote controls:
- b. H2-O2 Mon Inlet Valve Selector Switch
- c. CAM Power Control Switch SR-2400-K32 (Freq: LIC=B) Given CAM operability status OR key parameter indications, various plant conditions and a copy of Tech Specs, DETERMINE Tech Spec compliance and required actions, if any.
SR-2900-K32 (Freq: LIC=B) Given SSMP System operability status OR key parameter indications, various plant conditions and a copy of Tech Specs, DETERMINE Tech Spec compliance and required actions, if any.
SR-5600-K22 (Freq: LIC=B) Given a Main Turbine and Auxiliary Systems operating mode and various plant conditions, PREDICT how system/plant parameters will respond to the following Main Turbine and Auxiliary Systems component or controller failures:
- f. Gland Steam Exhauster trip SR-0002-P03 (Freq: LIC=A) Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts.
SR-1600-P23 (Freq: LIC=A) Given a reactor plan with lowering torus water level, take action to protect personnel, attempt to stop the leak and restore level in accordance with QCOA 1600-05 and QGA 200.
SR-0001-P34 (Freq: LIC=A) Given a reactor plant with lowering torus water level, trip and/or prevent HPCI operation (unless needed for core cooling) when torus water level cannot be maintained above 11 feet in accordance with QGA 200. (BWROG PC-3.2)
Quad Cities 2021 NRC EXAM Scenario 5 Simulator Setup:
- 1. Reset to IC-20
- 2. Go to RUN.
- 3. Verify the following RWM Sequence is loaded: 6PHESU (or current startup sequence)
- 4. Bypass LPRMs 48-33-C and 32-49-C.
- 5. Verify all APRMs reading ~ 75%.
- 6. Insert Commands for setup:
ior dihs156041a (3) trip (On trigger 3, override the1A Gland Exhauster control switch to TRIP) ior lohs156041a4 (3) on (On trigger 3, override the 1A Gland Exhauster Amber Trip light ON) imf ser0986(3) on (On trigger 3, set annunciator 901-7 E-12 in alarm) trgset 4 rdv10305118.LT. 0.99 (Set trigger 4 true when RPS B is tripped) imf rp05a (4) (Actuate a Channel A Group I isolation on trigger 4) imf rp05b (4) (Actuate a Channel B Group I isolation on trigger 4) imf mc08 (4) 100 25: (Set Main Condenser air in-leakage to 100% ramped over 25 minutes on trigger 4)
- 7. Verify the following commands for scenario performance:
irf pc11r ackn (reset alarms at 901-64A panel in Cable Spreading Room for A CAM) imf NM14L1633C 100 (Fail LPRM 16-33C Hi-Hi) imf ano9128a8 on (override alarm 912-8 A-8, Safe Shutdown System Trouble, on) trg! 3 (trip the 1A Gland Seal Steam Exhauster using trigger 3) ior DIFC10262222 raise (overrides the Recirc master controller raise pushbutton)
Imf RR06A 100 5: (Fail the A Recirc pump Inboard Seal 100% over 5 min.)
Imf RR07A 100 5: (Fail the A Recirc Pump Outboard Seal 100% over 5 min.)
irf cu13r 0 :30 (Close the 1A RWCU Demin FCV 1-1279-15A ramped over 30 seconds) irf cu9r out (Isolate the 1A RWCU Demin) irf cu14r 0 :30 (Close the 1B RWCU Demin FCV 1-1279-15B ramped over 30 seconds) irf cu10r out (Isolate the 1B RWCU Demin) imf pc07 35 20: (Torus ECCS suction leak at 35% ramped over 20 minutes) irf sw10r run (Start the U1 Emergency Diesel Generator Cooling Water pump)
Quad Cities 2021 NRC EXAM Scenario 5 Simulator Setup continued:
- 8. Take the following components Out of Service:
None
- 9. Provide a current revision of the following procedures, signed off as specified:
Provide a copy of QCOS 1400-04 marked up as a partial surveillance to test the 1B Core Spray Pump and a stopwatch.
Provide a SDTC for the 1B Core Spray Pump inoperable.
- 10. Provide a Holding Load ReMA
- 11. Provide the Lead Examiner with the following:
Verify the LPRM Bypass Log is available and LPRM 16-33C is not logged.
Blank LPRM Bypass Card Blank EST card
- 12. Perform the applicable Post Simulator Exam Security Actions of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.
Quad Cities 2021 NRC EXAM Scenario 5 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3 A-14, TORUS HIGH/LOW LEVEL, Rev. 09 o 901(2)-3 A-16, PRI CNMT HIGH PRESSURE, Rev. 16 o 901(2)-5 D-7 LPRM HIGH, Rev. 12 o 901(2)-5 D-10/15, RPS CHANNEL A/ B REACTOR SCRAM, Rev. 06 o 901(2)-5 A-10 RPS CHANNEL A MANUAL SCRAM, Rev. 07 o 901(2)-5 A-15 RPS CHANNEL B MANUAL SCRAM, Rev. 06 o 901(2)-5 F-5, CONDENSER VACUUM LO, Rev. 08 o 901(2)-5 D-7, LPRM HIGH, Rev. 12 o 901(2)-5 A-6, APRM UPSCALE/HIGH, Rev. 08 o 900-7 E-12, GLAND STM EXH MOTOR TRIP, Rev. 03 o 901(2)-7 H-3, CONDENSER LO VACUUM 24 IN. HG, Rev. 9 o 900-54 C-7, NORMAL PROCESS FLOW HI/LO, Rev. 05 o 900-55 B-5, H2 & O2 MON SYSTEM CMN FAIL, Rev. 04 o 912-8 A-8, SAFE SHUTDOWN SYSTEM TROUBLE, Rev. 05 QCGP 2-3, Reactor Scram, Rev. 99 QCGP 3-1, Reactor Power Operations, Rev. 89 QGA 100, RPV Control, Rev. 13 QGA 200, Primary Containment Control, Rev. 13 QCOA 0201-01, Increasing Drywell Pressure, Rev. 30 QCOA 0202-02, Reactor Recirculation System Failure, Flow Controller Fails High, Rev. 23 QCOA 0202-04, Reactor Recirc Pump Trip-Single Pump, Rev. 47 QCOA 0202-06, Recirculation Pump Seal Failure, Rev.27 QCOA 1600-05, Leak in Torus, Rev. 10 QCOP 0202-03, Reactor Recirculation System Flow Controller Operation, Rev. 26 QCOP 0700-03, Local Power Range Monitoring (LPRM) Operation, Rev. 22 QCOP 0700-04, Average Power Range Monitoring System Operation, Rev.
18 QCOP 1000-30, Post-Accident RHR Operation, Rev. 33 QCOP 2900-01, Safe Shutdown Makeup Pump System Preparation for Standby Operation, Rev. 41 QOP 5600-01, Gland Seal System, Rev. 25 QCOS 1400-04, Core Spray Pump Operability Test, Rev. 19 QCOS 1600-04, Weekly Primary Containment Oxygen Concentration, Rev. 36 QCAP 0200-10, Emergency Operating Procedure (QGA) Execution Standards, Rev. 57
Quad Cities 2021 NRC EXAM Scenario 5 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is operating at 75% power (2220 MWth) on the 100% FCL. Rod step 25 is partially withdrawn. Currently holding load for a ReMA revision.
b.) Unit 2 is at full power.
c.) Technical Specification limitations:
(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.
e.) Fire Risk is GREEN.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling 2.) Significant problems/abnormalities:
None.
3.) Evolutions/maintenance for the oncoming shift:
a.) Perform QCOS 1600-04, Core Spray Pump Operability Test for the 1B Core Spray Pump. An EO has performed pre-start checks and has secured the area.
b.) Increase to full power after revised ReMA is reviewed and approved.
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 1 Page 1 of 2 Event
Description:
Perform QCOS 1400-04 for the 1B Core Spray Pump Time Position Applicants Actions or Behavior SRO Directs the BOP to perform QCOS 1400-04, Core Spray Pump Operability Test for the 1B Core Spray Pump.
BOP Starts the 1B Core Spray Pump and verifies the MO 1-1402-38B, CS PMP MIN FLOW VLV opens.
BOP Notifies the SRO of entry time for B Core Spray Loop inoperability.
SRO Enters a Short Duration Time Clock for 1B Core Spray Pump inoperable. (TS LCO 3.5.1 Condition B)
BOP Throttles open MO 1-1402-4B, CS BYP AND TEST VLV to establish flow rate of > 4500 gpm at > 216 psig.
BOP Verifies MO 1-1402-38B valve closes.
BOP Contacts the EO at the pump to report pump suction pressure on PI 1-1402-40B.
SIM OP ROLE PLAY: When contacted, as EO report:
The 1B Core Spray pump suction pressure is 4 psig as indicated on PI 1-1402-40B.
If asked about pump status, state:
Post start checks are sat, pump is running normally, oil levels are good, no apparent problems.
BOP Verifies pump suction pressure is > 3 psig and records pump suction pressure.
BOP Records pump discharge pressure and flowrate. Verifies pump discharge pressure is > 216 psig and flowrate > 4500 gpm and initials both blocks.
BOP Closes and times MO 1-1402-4B. Records closing time.
BOP Verifies MO 1-1402-38B opens as system flow decreases.
BOP Stops the 1B Core Spray Pump.
BOP Closes MO 1-1402-38B valve.
BOP Notifies the SRO to exit the LCO for B Core Spray Loop inoperable.
BOP Performs standby lineup verification for B Loop Core Spray valves.
Event 1 Continued
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 1 Page 2 of 2 Event
Description:
Perform QCOS 1400-04 for the 1B Core Spray Pump Time Position Applicants Actions or Behavior BOP Signs off surveillance as satisfactory and returns it to the SRO for approval signature.
ATC Continuously monitors RPV power, pressure, and water level.
SIM OP / EVALUATOR NOTE: If dispatched to bleed off pressure to clear the 901-3 B-16 alarm, acknowledge the command and proceed to the next event with concurrence of the Lead Evaluator.
End of Event 1
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 2 Page 1 of 2 Event
Description:
LPRM Fails High Time Position Applicants Actions or Behavior SIMOP: At the Lead Evaluators direction, fail LPRM 16-33C upscale high by releasing the following command:
NM14L1633C 100 Key Parameter Response: LPRM 16-33C indicates upscale high reading, APRM 2 indicates ~
108%, Rod Block Expected Annunciator(s): 901(2)-5 D-7, 901(2)-5 H-1 Automatic Actions: None ATC Acknowledges annunciators and reports the following:
LPRM 16-33C indicates High APRM 2 is ~82%
SRO Directs actions of QCAN 901(2)-5 D-7, LPRM HIGH.
BOP At Panel 901-37, selectsLPRM 16-33C on the APRM 2 chassis and verifies indication is > 100 units and informs the SRO.
SRO/ATC Compares LPRM readings on Process Computer per QCOP 9950-02, Drifting LPRM Diagnostics program.
ATC May select a nearby control rod and verifies surrounding LPRM readings are in normal range.
SRO Notifies QNE of failed LPRM.
SIM OP ROLE PLAY: If contacted, as the QNE, acknowledge the failed LPRM report.
SRO Directs BOP to bypassLPRM 16-33C per QCOP 0700-03.
BOP Locates APRM 2 meter at 901-37 panel and verifiesLPRM 16-33C HI light is LIT on upper panel section.
Event 2 Continued
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 2 Page 2 of 2 Event
Description:
LPRM Fails High Time Position Applicants Actions or Behavior BOP Determines if bypassing the LPRM will result in the APRM becoming inoperable by placing the APRM METER FUNCTION switch to COUNT.
BOP Determines scale will indicate > 65% after LPRM is bypassed by subtracting 5% from scale reading.
BOP Determines < 2 detectors on C level as indicated on upper section of panel and informs the SRO.
SRO Refers to TS 3.3.1.1 and TRM 3.3.a. and determines the minimum number of operable channels will be met after bypassing APRM 2.
SRO Directs ATC to bypass APRM 2 per QCOP 0700-04.
ATC Requests verifier and positions the APRM BYPASS joystick to CH 2 ATC Verifies white BYPASS light illuminates for APRM 2.
LEAD EVALUATOR NOTE: Provide a blank Equipment Status Tag when requested.
ATC Places Equipment Status Tag on the APRM joystick.
BOP At the 901-37 panel: Rotates thumbwheel for LRRM 16-33C to the BY position and verifies Bypass light is lit on the upper section of panel.
BOP Fills out and hangs LPRM Bypass Card on thumbwheel.
BOP Depresses TRIP RESET button on LPRM meter and verifies Upscale light is NOT lit.
BOP Completes LPRM Bypass Log.
SIM OP ROLE PLAY: If contacted to remove the Ion Chamber Power Supply (ICPS), as Instrument Maintenance Supervisor, state:
Ill send a couple of Techs to remove the ICPS for the failed LPRM.
End of Event 2
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 3 Page 1 of 1 Event
Description:
SSMP Room Cooler Inoperable.
Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: When directed by the Lead Examiner, actuate annunciator 912-8 A-8 using the following command: imf ano9128a8 on Key Parameter Response: None.
Expected Annunciator(s): 912-8 A-8, SAFE SHUTDOWN SYSTEM TROUBLE Automatic Actions: None.
BOP Reports annunciator 912-8 A-8, Safe Shutdown System Trouble is in alarm and refers to annunciator procedure.
BOP Dispatches an EO to the Safe Shutdown Makeup Pump Room to investigate.
SIM OP ROLE PLAY: As the EO, wait 1 minute, then report back that:
The COMPRESSOR TRIP INDICATING LIGHT is lit on the side of the SSMP Room Cooler.
BOP Reports condition to the SRO and directs the EO to attempt a reset per QCOP 2900-01 step F.17.
SIM OP ROLE PLAY: As the EO, wait 4 minutes, then call back and report that you have:
Performed QCOP 2900-01 step F.17 and the COMPRESSOR TRIP INDICATING LIGHT will NOT reset. The light is still lit and the compressor is NOT running.
BOP Reports to the SRO that the SSMP Room Cooler compressor is tripped and will not reset.
BOP Contacts Mechanical Maintenance for assistance.
ATC Continuously monitors RPV power, pressure, and water level.
TS SRO Declares SSMP inoperable due to an inoperable Room Cooler. Enters the following administrative actions for Units 1 and 2:
TS 3.7.9, Condition A, SSMP inoperable (14 days).
SIM OP ROLE PLAY: If contacted, as Maintenance Supervisor, state that you will:
Prepare a troubleshooting package and dispatch a crew to investigate the SSMP Room Cooler Compressor.
End of Event 3
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 4 Page 1 of 2 Event
Description:
1A Gland Steam Exhauster Trip Time Position Applicants Actions or Behavior SIM OP: When directed by the Lead Examiner, trip the 1A Gland Exhauster by realeasing the following commands:
imf ser0986 (3) on ior dihs156041a (3) trip ior lohs156041a4 (3) on Key Parameter Response: 1A Exhauster Amber Trip light on and Red Running light off:
Lowering Vacuum on Gland Seal Exhaust Vacuum indication, 1-5140-70.
Expected Annunciator(s):
901-7 E-12, GLAND STM EXH MOTOR TRIP Automatic Actions: MO 1-5400-E1, A CNDSR EXH ISOL VLV E1 closes when the GSE Motor breaker trips.
BOP Acknowledges annunciator 901-7 E-12, and reports the 1A Gland Steam Exhauster has tripped.
SRO Directs BOP to perform the actions of QOA 900-7 E-12.
BOP Starts the 1B Gland Steam Exhauster.
BOP Throttles open MO 1-5405B, B CNDSR EXH DISCH VLV D-2.
BOP On the tripped Gland Steam Exhauster, throttles closed MO 1-5405A, A CNDSR EXH DISCH VLV D-1.
BOP On the tripped Gland Steam Exhauster, verifies MO 1-5400-E1, A CNDSR EXH ISOL VLV E1 automatically closes.
BOP Refers to QOP 5600-01, step F.2.d.
BOP Verifies NO valid level alarms on Gland Condenser Hotwell or Shell.
ATC Continuously monitors RPV power, pressure, and RPV water level.
Event 4 Continued
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 4 Page 2 of 2 Event
Description:
1A Gland Steam Exhauster Trip Time Position Applicants Actions or Behavior BOP Throttles the MO 1-5405B to obtain 10 inches to 15 inches of vacuum as indicated on the 1-5140-70, GLAND SEAL EXH VACU.
BOP Verifies GLAND SEAL SPLY PRESS is between 2.5 and 5.0 psig.
BOP Dispatches an EO to MCC 15-1 to investigate the tripped breaker.
SIM OP ROLE PLAY: As the EO, wait 2 minutes after being dispatched to MCC 15-1 and call back to report:
The breaker for the Gland Steam Exhauster Motor at MCC 15-1 cubicle B2 is tripped.
There is no obvious problem at the breaker and you have contacted EMD to investigate.
SIM OP NOTE: If the BOP places the c/s for the 1A Gland Exhauster in PLT, then at the direction of the Floor Instructor, delete the following overrides:
dmf ser0986 dor lohs156041a4 dor dihs156041a End of Event 4
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 5 Page 1 of 1 Event
Description:
Reactor Recirculation Pump Master Controller Fails High Time Position Applicants Actions or Behavior SIM OP NOTE: At the evaluators instruction, fail the Reactor Recirculation Master Controller RAISE pushbutton with the following command:
ior difc10262222 raise Key Parameter Response: APRM power, Reactor pressure, MW(e)
Expected Annunciator(s): 901-5 A-5, *901-4 F-7 Automatic Actions: *70% Recirc Pump Speed Runback if no action taken before > 85%
steam flow and > 90% feed flow are reached.
ATC Reports APRM power, total core flow, and Reactor Recirculation pump speeds are rising.
SRO Directs actions of QCOA 0202-08 or QCOP 0202-02 based on the method chosen to stop the Recirc Pump speed increase.
ATC Performs one of the following to terminate the power increase:
Place the 1-0262-25A and 1-262-25B Loop A/B SPEED CONTROLLERS in individual Manual mode (QCOP 0202-03 step D.1).
Holds speed on both Recirc pumps by placing the ASD SPEED HOLD Selector switches to the HOLD position QCOA 0202-08 step C.1) and verify both Recirc pumps are in MANUAL mode.
SRO Directs actions of QCOA 0202-02 for Recirc Flow Controller failing high and QCOA 0202-08 for Recirc Flow Controller trouble.
BOP/ATC Contacts Instrument Maintenance and/or Engineering to investigate cause of the Master Controller failure.
SIM OP ROLE PLAY: If contacted as IMD or Engineering, acknowledge the report of the Master Controller failure and state you will assist with troubleshooting.
ATC/BOP Adjusts Load Set if necessary.
LEAD EVALUATOR: If the Recirc run up was terminated using SPEED HOLD, the speed controllers must be placed in manual or the 70% runback reset before resetting the SPEED HOLD. When the crew has adequately addressed the situation, move to the next event.
End of Event 5
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 6 Page 1 of 2 Event
Description:
1A Recirc Pump Inboard and Outboard Seal Leak Time Position Applicants Actions or Behavior LEAD EVALUATOR NOTE: Assure the ATC operator completes the actions for tripping and isolating the 1A Recirc pump.
SIM OP NOTE: At the direction of the Lead Evaluator, release/insert the following commands to fail both 1A Recirc Pump seals 100% ramped over 5 minutes.
imf RR06A 100 5:
imf RR07A 100 5:
Key Parameter Response: Inboard Seal Press, Outboard Seal Press, Drywell pressure,
Drywell Temperature Expected Annunciator(s): 901-3 A-16 Automatic Actions: None ATC Reports the 1A Recirc pump inboard seal pressure lowering.
SRO Directs actions of QCOA 0202-06, Recirculation Pump Seal Failure.
ATC Monitors inboard and outboard Recirc seal pressures at the 901-4 panel and temperatures from computer points W118 and W120.
BOP Monitors Drywell pressure and temperature on PR 1-1640-12 and TR 1-2340-9 at the 901-3 panel.
ATC Reports both 1A Recirc inboard and outboard seal pressures lowering.
BOP Reports Drywell pressure and temperature rising.
SRO Directs BOP to trip and isolate the 1A Recirc pump.
BOP Trips the 1A Recirc pump using the ASD INPUT Breaker Control Switch OR EMERGENCY STOP on the 901-4 panel.
CT1 BOP Closes MO 1-0202-04A, PMP SUCT VLV, then Closes MO 1-0202-5A, PMP DISCH VLV.
BOP Dispatches an EO to secure seal injection per QCOP 0202-35.
Event 6 continued
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 6 Page 2 of 2 Event
Description:
1A Recirc Pump Inboard and Outboard Seal Leak Time Position Applicants Actions or Behavior TS SRO Enters the following Technical Specification:
TS 3.4.1. Condition C, One Recirc Loop in Operation (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to satisfy LCO requirements)
If Drywell pressure is > 1.5 psig, then the following Technical Specification is entered:
TS 3.6.1.4. Condition A, Drywell pressure not within limit (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore)
SIM OP ROLE PLAY: If contacted, as Instrument Maintenance Supervisor, state:
I will send an IM Tech to the control room with a procedure to adjust the APRM and Rod Block monitor setpoints for single loop operation.
SIM OP ROLE PLAY: If contact as EO, state that:
I have a copy of QCOP 0202-35 and will isolate seal injection on the 1A Recirc pump.
SIM OP ROLE PLAY: If contacted, as the QNE, state:
Ill implement the Thermal Limits for single loop operations.
ATC Reports the 1A Recirc pump seals are depressurizing.
SRO Directs BOP to refer to QCOA 0202-04, Reactor Recirc Pump Trip-Single Pump.
SRO Directs BOP to refer to QCOA 0201-01, Increasing Drywell Pressure.
End of Event 6
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 7 Page 1 of 1 Event
Description:
Emergency Power Reduction / Loss of Recirc Pump Time Position Applicants Actions or Behavior SRO Directs actions of QCOA 0202-04, Reactor Recirc Pump Trip-Single Pump.
SRO Sets scram criteria of core oscillations and trip of 2nd Recirc pump.
ATC Inserts Cram Rods and control rods to lower FCL as necessary to avoid/exit ICA Region II or maintain reactor operation below MELLLA line.
ATC/BOP Reduces 1B Recirc Pump speed to < 78% and maintains pump motor current < 770 amps as indicated on 1-202-730B, PMP CUR. (If necessary resets SPEED HOLD per QCOP 0202-39).
ATC/BOP Verifies MO 1-202-5A, PMP DISCH VLV is closed and does NOT re-open the valve after 5 minutes.
ATC Continues load drop with control rods and Recirc pump until core flow is < 50 Mlb/hr and core thermal power is < 50% RTP.
ATC/BOP Reduces operating loop flow to < 49 Mlb/hr.
BOP Contacts Chemistry Department to obtain RETS due to load drop.
SIM OP ROLE PLAY: As Chem Tech, state:
Ill obtain RETS samples and inform the Unit Supervisor of the results.
BOP Monitors differential temperature between operating and idle Recirc Loops AND RPV bottom head temperature.
BOP Contacts and informs the QNE of the tripped Recirc pump and control rod insertion.
SIM OP ROLE PLAY: As the QNE, acknowledge the report and state that you will:
Monitor thermal limits and prepare further instructions for control rod maneuvers when the plant is stabilized.
BOP Secures Reactor Feed and Condensate Pumps as necessary.
BOP Monitors Off Gas radiation levels.
End of Event 7
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 8/9/10 Page 1 of 3 Event
Description:
Torus Leak / Group I / Blowdown Time Position Applicants Actions or Behavior SIM OP: At the direction of the Lead Evaluator, insert a 35% severity leak over 20 minutes on the Torus ECCS Suction Header using malfunction PC07:
imf pc07 35 20:
Key Parameter Response: Torus level as indicated on 1-1602-7, 1-1602-3, and 1-1640-10B Expected Annunciator(s):
901-3 A-13, DW LOW PRESS CNMT SPRAY INHIBITED 901-3 A-14, TORUS HIGH/LOW LEVEL 901-3 B-14, TORUS TO RX BUILDING NEGATIVE DP 901-4 C (& D) 18, RX BLD FLOOR DRAIN SUMP A (& B) HIGH LEVEL Automatic Actions: None BOP Acknowledges annunciator 901-3 A-14, Torus High/Low Level, and reports Torus level and trend ATC/BOP Dispatches EO to the Reactor Building basement and corner rooms to investigate.
BOP Monitors Torus Water Level and reports levels and trends.
SIMOP ROLE PLAY: As EO dispatched to RB basement, wait 4 minutes and report back:
There is a large leak from the Torus ECCS suction header outside of the B RHR Room UPSTREAM of the 1-1001-6B valve.
There is 2 inches of water on the floor.
I have called Mechanical Maintenance for assistance.
SRO Directs actions of QCOA 1600-05, Leak in Torus SRO Sets scram criteria of 12 ft. Torus level BOP/ATC Evacuates personnel from the Reactor Building BOP/ATC Notifies Radiation Protection to obtain air samples for oxygen content and radioactivity in the Reactor Building basement BOP/ATC Notifies Radwaste to start processing water from the leak BOP Reports Torus level at -2 inches and lowering.
SRO Enters QGA 200 and directs actions Events 8/9/10 continued
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 8/9/10 Page 2 of 3 Event
Description:
Torus Leak / Group I / Blowdown Time Position Applicants Actions or Behavior SRO Directs actions of QCOP 1600-12 to fill the Torus BOP Opens HPCI min flow valve MO 1-2301-14 to gravity drain from the CCSTs to the Torus per QCOP 2300-02.
BOP Opens RCIC min flow valve MO 1-1301-60 to gravity drain from the CCSTs to the Torus per QCOP 1300-03.
BOP Monitors and reports containment parameters.
SRO Enters QGA 300 and directs actions.
ATC/BOP Dispatches an EO to start the U1 Diesel Generator Cooling Water pump.
SIM OP ROLE PLAY: As the EO, acknowledge the order, wait 2 minutes, then start the U1 Diesel Generator Cooling Water pump with the following command then report back to the control room:
irf sw10r run SIM OP ROLE PLAY: If asked about Maintenance progress on securing leak, report:
The team thinks they can plug the leak and are still working.
BOP Reports Torus level at 12 ft. and lowering ATC Inserts a manual reactor scram and performs actions post scram actions per QCGP 2-3, Attachment A.
SRO Enters QGA 100 and directs actions.
SRO Directs ATC/BOP to verify auto actions/isolations for 0 inches RPV water level.
ATC/BOP Report all Group II and Group III isolations are verified ATC/BOP Report a Group I isolation occurred but no isolation condition present.
SRO Directs ATC to control RPV water level in a band of 0 to +48 in. with the Condensate and Feedwater system.
ATC Controls RPV water level in 0 to +48 in. band using the Condensate/Feed System.
SIM OP ROLE PLAY: If contacted, as the EM Supervisor, state:
We will start troubleshooting by checking the GROUP I PCI relays and fuses in the 901-15 and 901-17 panels.
Quad Cities 2021 NRC EXAM Scenario 5 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2021 NRC Scenario No. 5 Event No. 8/9/10 Page 3 of 3 Event
Description:
Torus Leak / Group I / Blowdown Time Position Applicants Actions or Behavior SRO Directs the BOP to initiate an RPV cooldown using ADS valves at
< 100°F/hr.
BOP Initiates an RPV cooldown using ADS valves.
BOP Starts up RWCU system in reject mode per QCOP 1200-07 Attach. A (Hard Card)
BOP Dispatches EO to the RWCU Demin Panel 2201-61.
SIM OP ROLE PLAY: If dispatched as EO to isolate the RWCU Demins, wait 2 minutes, then call back and remove the 1A and 1B Demins respectively, using the commands below.
Note: (the BOP will throttle open MO 1-1201-133, DEMIN BYPASS VLV as each one is taken off line.)
irf cu13r 0 :30 irf cu14r 0 :30 irf cu09r out irf cu10r out SRO Before Torus Water Level reaches 11 ft. orders HPCI system trip latched to prevent operation.
BOP Depresses the HPCI system trip pushbutton and latches it in place when directed.
SRO Before Torus Water Level reaches 11 feet, Re-enters QGA 100 and executes an RPV Blowdown at SRO Verifies Drywell pressure < 2.5 psig.
SRO Verifies Torus level > 5 ft.
SRO Orders all 5 ADS valves opened CT2 BOP Opens ADS valves as directed and leaves all switches in the MAN position.
ATC/BOP Monitor RPV depressurization and report when RPV pressure is less than 100 psig.
SIM OP NOTE: When Blowdown has been performed and/or as directed by the Lead Evaluator, place the simulator in FREEZE.
End of Scenario
Quad Cities 2021 NRC EXAM Scenario 5 END OF SCENARIO