ML22139A295

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Retake Administered Scenario 1 and 2
ML22139A295
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/24/2019
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Baker R
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Download: ML22139A295 (44)
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Quad Cities 2019-301 NRC EXAM Scenario 1 Exelon Nuclear 2019-301 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 1 Revision Number: 00 Date: 05/28/2019 Developed by:

Instructor Date Validated by:

SME or Instructor Date Reviewed by:

Operations Facility Representative Date Approved by:

Training Department Date Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2019-301 NRC Scenario 1 Op-Test No.: ILT 19-301 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 80% power with Drywell Spray Valve 23A is inoperable, Day 2 of a 7-Day of TLCO 3.6.a Condition a. 2A SW Pump and 1B EHC Pump are OOS.

Turnover: Start the third RFP. Return to full power.

Event Malf. No. Event Event No. Type* Description 1 None BOP Start a third Reactor Feed Pump IAW QOP 3200-03 N

2 None ATC Normal Power up IAW REMA R

3 RM05B SRO B Drywell Rad Monitor Upscale Failure TS TS 4 ED08Q SRO MCC 30 Feed Breaker trip on overcurrent TS TS 5 MC08 ATC Loss of Main Turbine Vacuum/ Emergency Power C Reduction 6 RR10A BOP Slow Recirc Leak resulting in a Scram C

7 RR10A Crew High Drywell Pressure results in entry into QGA 100 M and 200.

8 HP11 BOP HPCI fails to initiate automatically. BOP must start C HPCI manually.

9 DIHS11001S17B Crew Div 2 Drywell Spray valves fail to open, Emergency M Depressurization per QGA 500-1 when PSP exceeded 10 Crew Reference leg flashing results in entry into QGA 500-M 4

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 7 BOP Normal: E1 Malfunction(s) after EOP (1-2): E8, 9 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E5, 6 BOP I/C (4 per set): E6, E8 Major Transient(s) /E-Plan entry (1-2): E7 ATC I/C (4 per set): E5 EOPs (1-2): QGA 100, 200 SRO-I I/C (4 per set inc 2 as ATC):

EOP Contingencies (0-2): QGA 500-1, E5, 6, 8 500-4 SRO Tech Spec (2 per set): E3, 4 Critical Tasks (2-3): 2 ALL Major Transients (2 per set) E6 Quad Cities 2019-301 NRC EXAM Scenario 1

SUMMARY

  • Initial Conditions:

Drywell Spray Valve 23A is inoperable, Day 2 of a 7-Day LCO 2A SW Pump is OOS 1B EHC Pump is OOS

  • Event 1: The BOP will start a third Reactor Feed Pump IAW QOP 3200-03.
  • Event 2: Raise Reactor Power using REMA.
  • Event 4: MCC 30 Feed Breaker trips. Report from EO is that the breaker tripped on overcurrent. SRO enters TS 3.7.9.A.
  • Event 5: An air leak will result in lowering Main Condenser Vacuum. The crew performs QOA 3300-02 and Emergency Power Reduction. Prompt action by Equipment Operators to re-fill a loop seal line will stabilize Main Condenser Vacuum.
  • Event 6: A Recirc leak will develop in the Drywell causing Drywell Pressure to rise resulting in BOP performing actions of QCOA 201-01. Drywell pressure will stabilize when the 7th drywell cooler is started
  • Event 7: Recirc Leak will become larger causing drywell pressure to rise at a greater rate. When Drywell Pressure reaches scram criteria, ATC will SCRAM the Reactor. All three Reactor Feed Pumps will trip when the Scram has been inserted. SRO will enter QGA 100 and 200.
  • Event 8: HPCI will fail to start automatically at 2.5# drywell pressure. BOP must start HPCI manually IAW QCOP 2300-06.
  • Event 9: When Division 2 Containment Spray valves cannot be opened, the crew must Blowdown per QGA 200 and 500-1, in order to avoid exceeding Pressure Suppression Pressure (PSP).
  • After Blowdown has commenced, the drywell will reach saturation conditions. The SRO will enter QGA 500-4 and flood the RPV to the Main Steam Lines.
  • Approximate Run Time: 1.5 Hours Quad Cities 2019-301 NRC EXAM Scenario 1 CRITICAL TASKS:

Critical Task #1 When Drywell temperature CANNOT be maintained < 280 F OR Torus pressure CANNOT be maintained < the Pressure Suppression Pressure Limit, (PSP),

INITIATE an Emergency Depressurization..

Critical Task #2: When RPV Level cannot be determined, flood the RPV to the elevation of the Main Steam Lines.

Quad Cities 2019-301 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-3200-K16 STATE the physical location and DESCRIBE the operation of the following Condensate/Feedwater System controls (local/remote):

g. RFP control switches
h. RFP selector switch
i. RFP motor vent fan control switches
l. Motor/air operated valve control switches (7) RFP discharge valves (MO 3201A/B/C)

(8) RFP recirc valves (AO 3201A/B/C)

SR-0002-P05 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.

SR 2300-P01 Given a reactor plant in an accident condition where HPCI fails to autostart and/or fails to start with auto pushbutton, manually start HPCI for injection in accordance with QCOP 2300-06 SR-0001-P45 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 Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA.

SR-3300-P09 Given a reactor plant at power with a loss of condenser vacuum, take action to attempt to locate and correct the cause for lowering vacuum in accordance with QOA 3300-02 and/or QOA 5450-05.

SR-0001-P23 Given a reactor plant with rising containment pressure and temperature due to a LOCA or steam leak, initiate an emergency depressurization when torus pressure cannot be maintained below the Pressure Suppression Pressure (QGA Figure L) or when drywell temperature cannot be restored and held below 280 degrees in accordance with QGA 200 and QGA 500-1.

Quad Cities 2019-301 NRC EXAM Scenario 1 Simulator Setup:

1. Reset to IC-20 (75% power).
2. Go to RUN.
3. Raise Recirc master controller speed until approximately 80% Rx Power
4. Place the Condensate Pump Selector Switch in OFF and Start the 1D Condensate Pump.
5. On DFWLC OWS, Place Recirc Runback Bypass to activate
6. Place 2A SW Pump in PTL
7. Place 1B EHC Pump in PTL
8. Verify the following RWM Sequence is loaded: 6PESU2 (or current shut down sequence)
9. Place INFO cards as follows:
a. 2A SW Pump
b. 1B EHC Pump
c. 1-1001-23a Valve
d. 1-1001-26a Valve (The following commands to be utilized for this scenario are contained in the CAEP file:

Pham NRC Scenario 1.cae)

10. Insert Commands for setup:
  • Rack out Bkr for RHR 23A Valve o irf RH19AR open
  • Rack out Bkr for RHR 26A Valve o irf RH20AR open
  • 'B' RPS Fails to Auto Trip o imf RP02B o imf RP02D
  • Failure of HPCI to Auto Initiate o imf HP11
  • Failure of RHR S17 Switch 'B' Loop o ior DIHS11001S17B off
  • Trip Feed Pumps on Trigger 2 o imf fw01a (2) o imf fw01b (2) o imf fw01c (2)
11. Verify the following commands for scenario performance:
  • 'A' DW Rad Monitor Fail High (imf rm05a 100 :05)
  • MCC 30 Trips (imf ed08Q)
  • Recirc Suction Leak (imf rr10a .01 15:)
  • Increase Recirct Suction Leak (mmf rr10a .5 15:)
  • Trip 1A EHC Pump (imf tc05a)
  • Open Breakers for 23B and 26B valves (irf rh19br open) (irf rh20br open)
  • Increase Recirct Suction Leak after blowdown starts (mmf rr10a 5 2:)
  • Reference Leg Flashing (bat seqflash5then6)

Quad Cities 2019-301 NRC EXAM Scenario 1 Simulator Setup continued:

12. Install Protected System placards and/or rings on the following equipment:
  • Fuel Pool Cooling Water pumps
13. Provide the following paperwork:
  • QCGP 3-1 signed off for raising power.
  • QCOP 3200-03 signed off ready to start the 1C RFP on Bus 11.
  • QCOP 0600-21, all steps N/A except F.13
  • REMA
14. Place the Zinc Injection placard on 1A RFP.

Quad Cities 2019-301 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3 A-16, Rev 016, PRIMARY CONTAINMENT HIGH PRESSURE o 901(2)-3 D-2, Rev 016, HIGH RADIATION AT SJAE OUTLET 901-5 C-3 ROD OUT BLOCK o 901(2)-5 A-8, Rev 014, GROUP 2 ISOL CH TRIP o 901(2)-5 D-11, Rev 013, HIGH DRYWELL PRESSURE o 901(2)-5 F-5, Rev 008, CONDENSER VACUUM LO o 901(2)-7 H-3, Rev 009, CONDENSER LO VACUUM 24 IN HG o 901-55 A-1, Rev 11 DRYWELL HIGH HIGH RAD CONC o 912-8 A-8, Rev 005, SAFE SHUTDOWN MAKEUP PUMP SYSTEM TROUBLE QCAP 0200-10, Emergency Operating Procedure (QGA) Execution Standards, Rev 56 QOA 3300-02, Loss of Condenser Vacuum, Rev 40 QCOA 0201-01, Increasing Drywell Pressure, Rev 30 QCOP 0202-13, Reactor Recirculation Flow Control Line Determination, Rev 21 QCOP 0203-01, Reactor Pressure Control Using Manual relief Valve Actuation, Rev 17 QCOP 0600-21, Operation of the Feedwater Level Control System, Rev 21 QCOP 1000-30, Post-Accident RHR Operation, Rev 32 QCOP 2300-06, HPCI System Manual Startup, Rev 36 QCOP 5750-19, Drywell Cooler Operation, Rev 11 QOP 3200-03, Start Up of the Second and Third Reactor Feed Pump, rev 51 QCGP 3-1, Reactor Power Operations, Rev 87 QGA 100, RPV Control, Rev 12 QGA 200, Primary Containment Control, Rev 12 QGA 500-1, RPV Blowdown, Rev 16 QGA 500-4, RPV Flooding, Rev 15 Quad Cities 2019-301 NRC EXAM Scenario 1 CREW TURNOVER 1.) Plant Conditions:

a.) Unit 1 is operating at 80% power due to rod pattern adjustment.

b.) Unit 2 is at 100% power.

c.) Technical Specification limitations:

1. Drywell Spray Valve MO 1-1001-23A is inoperable resulting in a 7 Day LCO per TLCO 3.6.a Condition A. On Day 2 of 7.

d.) On Line Risk is GREEN e.) Fire Risk is GREEN f.) Protected Equipment:

(1) RBCCW (2) Fuel Pool Cooling (3) 1A EHC Pump 2.) Significant problems/abnormalities:

a.) 2A SW Pump is OOS for motor bearing replacement.

b.) MO 1-1001-23A is OOS for valve stem replacement. MO 1-1001-26A valve is OOS as a boundary.

c.) 1B EHC Pump is OOS breaker inspection.

3.) Evolutions/maintenance for the oncoming shift:

a.) Start the C RFP per QCOP 3200-03 b.) Return to 100% Power per QCGP 3-1 and REMA Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 1 Page 1 of 1 Event

Description:

Start a third Reactor Feed Pump IAW QOP 3200-03 Time Position Applicants Actions or Behavior SRO Directs BOP to start the 1C RFP on Bus 11 per QOP 3200-03.

BOP Places RFP Selector Switch to OFF BOP Directs EO to perform step F.14 to prepare 1C RFP to be started.

SIMOP ROLE PLAY: After 2 minutes, as EO call the control room and report that step F.14 of QOP 3200-03 is complete and all personnel are clear of the U1 RFP room.

BOP Closes the RFP Discharge Valve, MO 1-3201C.

BOP Opens the RFP Recirc Valve, AO 1-3201C. Informs US of expected 901-6 G-9 alarm when 1C RFP Recirc valve is open.

BOP Starts the 1C RFP from Bus 11.

BOP Verifies that the Auxiliary oil pump auto trips when the RFP starts and oil pressure builds.

BOP When flow stabilizes, returns the RFP Recirc Valve, AO 1-3201C to AUTO.

BOP Verifies the RFP Recirc Valve closes.

BOP Directs the in-plant operator to perform the post-start verifications per QOP 3200-03 Step F.25.

SIMOP ROLE PLAY: After 3 minutes, as EO call the control room and report QOP 3200-03 step F.25 is complete.

Directs EO to verify RFP warming line valves are open per QOP 3200-BOP 03 step F.28.

SIMOP ROLE PLAY: After 2 minutes, as EO call the control room and report QOP 3200-03 step F.28 is complete.

BOP Enables 70% Reactor Recirc runback logic per QCOP 0600-21.

BOP Checks flow control line on power to flow graph (QCOP 0202-13).

End of Event 1 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 2 Page 1 of 1 Event

Description:

Raise Reactor Power Using REMA Time Position Applicants Actions or Behavior SIM OP: At the discretion of the lead examiner, contact the Control Room as the SOS and request to know the status of the power ascension.

Lead Examiner: If QNE is requested to come to the control room, indicate the QNE is in the control room and is monitoring the power change.

SRO Directs ATC operator to begin power ascension.

SRO Provides SRO oversight for reactor power increase using recirc flow.

SRO Verifies compliance with the approved ReMA.

SRO Directs RO to perform load increase IAW QCGP 3-1 step F.3.e.

CREW Announces the power change to the control room.

ATC Monitors plant response and verifies in compliance with REMA.

ATC Depresses RAISE pushbutton on 1-0262-22, MASTER SPEED DEMAND.

ATC Verifies B Recirc loop flow is < 52.92 Mib/hr.

ATC Closely monitors power increase on APRMs.

ATC Monitors Flow Control Line.

BOP Maintains Load set a minimum of 10% above Main Generator load.

BOP Monitors Drywell Pressure and adjusts PIC 1-1640-11 as required.

Monitors A/B Moisture Separator Drain Tank and D1/2/3 Feedwater BOP Heater levels during the load increase.

BOP Provides peer check as requested for power changes.

End of Event 2 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 3 Page 1 of 1 Event

Description:

Drywell Rad Monitor Failure Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead examiner, start the Drywell Rad Monitor Failure event (expert command: imf rm05a 100 5:)

Key Parameter Response: 1-2419A Drywell Radiation Monitor indicating full upscale Expected Annunciator(s):

901-5 A-8, GROUP 2 ISOL CH TRIP 901-55 A-1, DRYWELL HIGH HIGH RAD CONC Automatic Actions: Rod Block 1/2 Group 2 Isolation BOP Acknowledges annunciator 901-55 A-1, DRYWELL HIGH HIGH RAD CONC and reports the 1-2419A Drywell radiation monitor is indicating full upscale.

ATC Acknowledges annunciator 901-5 A-8, GROUP 2 ISOL CH TRIP and refers to annunciator procedure.

SRO Confirms the 1-2419B Drywell radiation monitor is indicating normally (approximately 3-4 R/hr).

EVALUATOR ROLE PLAY: If the BOP goes to confirm the PCI Relays have dropped out:

CUE the following on Panel 901-15 Relay 595-104A dropped out Relay 595-104C dropped out BOP Informs RP of the failed Drywell radiation monitor.

SIMOP ROLE PLAY: As RP, inform the Control Room that you will:

Implement compensatory actions for the Drywell Radiation Monitor.

As IMD, if informed of the failed DW radiation monitor, state you will:

Start a work package.

SRO Enters the following Technical Specifications for an inoperable Drywell Radiation monitor:

  • PCI 3.3.6.1, Condition A, Place the Channel in Trip Within 24 Hours
  • PAM 3.3.3.1, Condition A, Restore Required Channel to Operable Status Within 30 Days End of Event 3 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 4 Page 1 of 1 Event

Description:

MCC 30 Feed Breaker trip on overcurrent Time Position Applicants Actions or Behavior SIM OP: At the Lead Evaluators discretion, trip the MCC 30 Feed Breaker:

imf ed08q Key Parameter Response: MCC 30 Feed Breaker Trip.

Expected Annunciator(s): 912-8 A-8 Automatic Actions: None BOP Acknowledges annunciator 912-8 A-8, Safe Shutdown Makeup Pump System Trouble, and reports that the MCC 30 Feed Breaker has tripped.

SRO Directs actions per QCAN 912-8 A-8 BOP Determines alarm is due to a valid breaker trip.

BOP Directs an EO to verify breaker trip flag at 4160V Bus 31 SIM OP NOTE: As EO sent to SSMP Room, wait 5 minutes and report to the Control Room that the MCC 30 Feed Breaker at Bus 30 has an overcurrent flag up.

BOP Contacts Electrical Maintenance for assistance.

ATC Continuously monitors RPV power, pressure, and water level.

SRO References Tech Specs.

SRO Enters T.S. 3.7.9.A, Restore SSMP system to OPERABLE status within 14 Days.

SIM OP ROLE PLAY: If contacted, as Electrical Supervisor, state that you will:

Prepare a troubleshooting package and dispatch a crew to investigate the MCC 30 Feed Breaker.

End of Event 4 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 5 Page 1 of 2 Event

Description:

Loss of Main Condenser vacuum (Emergency Power Reduction)

Time Position Applicants Actions or Behavior SIM OP: When directed by the Lead Examiner, initiate a 100% loss of Main Condenser vacuum ramped over 25 minutes using malfunction MC08:

imf mc08 100 25:

Key Parameter Response: Main Condenser backpressure rising on PR 1-5640-79; Generator MW(e) lowering, Off gas flow to Main Chimney rising on FI 1-5440-7.

Expected Annunciator(s):

901-3 D-2, OFF GAS HI RADIATION 901-7 H-3, CONDENSER LO VACUUM 24 IN HG 901-5 F-5, CONDENSER VACUUM LO 901-54 C-7, NORMAL PROCESS FLOW HI/LO Automatic Actions: Reactor Scram and Turbine trip BOP Acknowledges 901-3 D-2 alarm and refers to the QCAN.

SRO Directs that reactor power be held constant until the cause of the high radiation is determined.

BOP Monitors SJAE and Main Steam Line radiation levels.

ATC/BOP Report Off Gas Flow as indicated on FI 1-5440-7, OFF GAS FLOW TO MN CHIMNEY, is rising.

ATC/BOP Report Main Condenser backpressure rising.

SRO Enters and directs actions of QOA 3300-02, Loss of Condenser Vacuum.

SRO Directs an Emergency Power Reduction to control Condenser backpressure < 6 in. Hg.

ATC Reduces Recirc Pump speed(s) using the Master/Individual Controllers OR the Manual Runback pushbuttons.

ATC Inserts CRAM rods to maintain FCL within the MELLLA boundary.

BOP Dispatches EOs to verify Condenser vacuum breaker water seal is intact and loop seal are full.

SRO Sets scram criteria at 7.5 in Hg.

BOP Verifies Off-Gas and SJAE suction valves are open.

BOP Verifies Circulating Water System is operating normally.

BOP Verifies Main Condenser Hotwell level is normal.

Event 5 continued Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 5 Page 2 of 2 Event

Description:

Loss of Main Condenser vacuum (Emergency Power Reduction)

Time Position Applicants Actions or Behavior BOP Acknowledges and reports annunciator 901-7 H-3, CONDENSER LO VACUUM 24 IN. HG, is in alarm.

BOP Notifies Chemistry that Condenser vacuum has been lost and to align Unit 1 Reactor Building Sample Panel drains per CY-QC-110-608.

SIMOP ROLE PLAY: If contacted as Chemistry, state you will review CY-QC-110-608.

SIMOP ROLE PLAY: When Emergency Power Reduction has been performed to the satisfaction of the Lead Examiner, AND If an EO/FS has been dispatched, then delete the in-leakage malfunction at 4 inches backpressure: dmf mc08 AND As EO/FS report that the Main Condenser Loop Seals have been re-filled.

BOP Confirms that Condenser Backpressure is returning to normal.

SRO Directs the suspension of Emergency Power Reduction.

ATC Holds Recirc Flow as directed.

SRO Contacts Power Team and informs them of current power level and contacts QNE for assistance in determining thermal limits and recovery actions for control rods.

SIMOP ROLE PLAY: Acknowledge reports from the Unit Supervisor.

End of Event 5 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 6 Page 1 of 2 Event

Description:

Slow Recirc Leak Time Position Applicants Actions or Behavior SIM OP: When directed by the Lead Examiner, slow recirc leak of Imf rr10a .01 15:

Key Parameter Response: Drywell Pressure rising, 901-3 A-16 annunciator.

Expected Annunciator(s):

901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE 901-5 D-11 PRIMARY CNMT HIGH PRESS Automatic Actions: None BOP/ATC Informs the US that alarm 901-3 A-16 is in and reports DW pressure value and trend.

SRO May set Scram Criteria of 2 psig.

SRO Directs BOP to take actions per QCOA 0201-01.

BOP Enters and performs QCOA 0201-01.

BOP Investigate cause of increasing Drywell Pressure ATC/BOP Notify RP of elevated containment pressure.

ATC/BOP Consider evacuating the RB BOP Start 7th Drywell cooler.

BOP Reports 7th Drywell cooler started.

ATC Verifies there is not a failure of the Recirc Pump Seals SRO Notify Shift Manager to classify the event as a possible E-plan condition.

SRO May order the ATC to scram prior to 2.0 psig in the drywell based off trend of drywell pressure.

ATC/BOP After 7th Drywell cooler is started, reports that drywell pressure has stabilized at approximately 1.5 psig.

End of Event 6 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 7/8 Page 1 of 4 Event

Description:

Recirc Leak/HPCI Auto failure Time Position Applicants Actions or Behavior Key Parameter Response: Drywell Pressure Rising Expected Annunciator(s):

901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE 901-5 D-11 PRIMARY CNMT HIGH PRESS Automatic Actions: (Not a complete list) Group 2, 3 Isolation, CR and RB Vents isolate, SBGTS starts, ECCS systems initiate, EDGs start (HPCI will not Auto Start)

SIMOP: When directed by the Lead Evaluator, modify recirc leak with the following malfunction:

mmf rr10a .5 15:

BOP/ATC Reports that drywell pressure is rising at a greater rate.

SRO Orders ATC to manually scram at 2.0 psig Drywell Pressure.

ATC Depresses both manual scram pushbuttons.

SIMOP: After the scram, trip the 1A EHC Pump:

Imf tc05a SRO Enters QGA 100, RPV Control and QGA 200, Primary Containment Control, on 2.5 psig DW pressure SRO Directs ATC/BOP to verify 0 and 2.5 psig isolations and auto-starts Gives Scram Report, reports to the SRO that all Reactor Feed Pumps ATC have tripped.

SRO Orders BOP to start RCIC and to maintain RWL 0- +48 SRO Orders pressure band of 800-1000# using ADS BOP Starts RCIC BOP Reports that HPCI failed to autostart.

Directs EO to investigate the cause of Reactor Feed Pump Trips and BOP HPCI failing to Start.

Events 7/8 continued Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 7/8 Page 2 of 4 Event

Description:

Recirc Leak/HPCI Auto failure Time Position Applicants Actions or Behavior SIM OP ROLE PLAY: As the EO sent to investigate Reactor Feed Pump Trips, wait 5 minutes and report:

All three Reactor Feed Pump Breakers have overcurrent flags up, Electrical Maintenance has been contacted.

As the EO sent to investigate HPCI, wait 3 minutes and report:

There is no apparent cause to why HPCI did not automatically start, Instrument Maintenance is on the scene investigating.

ATC Reports that RWL is dropping.

SRO Directs BOP to start HPCI manually.

BOP Starts HPCI manually per QCOP 2300-06 BOP/ATC Coordinates with HPCI and RCIC to bring RWL to 0- +48 ATC/BOP Verifies Diesels auto started BOP As directed, verifies 1A and 1B CAMs operating SRO May direct actions to start all available drywell cooling ATC/BOP As directed, restores RBCCW and DW coolers per QCOP 5750-19 Verifies Bus 18 and 19 voltage >450 volts Takes the U1 DIV I DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Takes the U1 DIV II DW CLR/RBCCW/FPC TRIP BYPASS switch to BYPASS position Checks Drywell temperature is less than 260 °F Starts 1A and 1B RBCCW pump Starts drywell coolers one at a time Events 7/8 Continued Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 7/8 Page 3 of 4 Event

Description:

Recirc Leak/HPCI Auto failure Time Position Applicants Actions or Behavior Starts Drywell Booster Fan SRO Verifies Torus level <27 ft.

SRO Before Torus Pressure reaches 5 psig, directs BOP to place Torus Sprays on IAW QCOP 1000-30 BOP Maintains the following during Post-Accident RHR Operation:

  • RHR Pressure 100-250 psig BOP Prepares RHR for Operation Verifies RHR Pumps running Places LOOP A/B CONTAINMENT COOLING PERMISSIVE Switch 17 to ON Places LOOP A/B RHR SW START PERMISSIVE Switch 19 to MANUAL OVERRIDE BOP Starts RHR Service Water Opens MO 1-1001-5A/B to approximately 40%

Starts A/B RHR SW Pump Throttles MO 1-1001-5A/B as necessary Throttles MO 1-1001-16A/B as necessary BOP As directed, initiates Torus Sprays per QCOP 1000-30 Opens MO 1-1001-34A Opens MO 1-1001-37A BOP Opens/Throttles MO 1-1001-36A as necessary to maintain RHR Discharge Pressure SRO Directs BOP to secure Torus Sprays before Torus Pressure drops to 0 psig SRO If Torus water temperature cannot be held <95°F, directs start of all available Torus Cooling Quad Cities 2019-301 NRC EXAM Scenario 1 Events 7/8 Continued Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 7/8 Page 4 of 4 Event

Description:

Recirc Leak/HPCI Auto failure Time Position Applicants Actions or Behavior BOP As directed, initiates Torus Cooling per QCOP 1000-30 Opens MO 1-1001-34A/B Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure SIMOP: If PSP Blowdown conditions will not be met and when directed by Lead Examiner, modify the leak to 2%. mmf rr10a 2 BOP Reports Torus pressure >5 psig.

SRO Verifies Torus level <17 ft.

SRO Verifies inside DW Spray Limit Curve SRO Verifies Recirc pumps and DW Coolers are tripped SRO Directs BOP to start DW Sprays BOP As directed, attempts to initiate Drywell Sprays per QCOP 1000-30 Attempts to open MO 1-1001-23B Attempts to open MO 1-1001-26B BOP Recognizes and reports that the B Loop Drywell Sprays will not open SRO/BOP Directs EO investigate 23B & 26B valve breaker and locally open the Containment spray valve(s)

SIMOP ROLE PLAY: If requested to locally operate the B Drywell Spray valves, wait 2 minutes and then open the breakers for MO 1-1001-23B and 26B:

irf rh19br open and irf rh20br open Wait an additional 5 minutes and report that MO 1-1001-23B and 26B cannot be opened.

SIMOP ROLE PLAY: If dispatched to manually open the MO 1-1001-34B and 36B valves, wait 5 minutes then open the breakers using: irf rh23br open and irf rh24br open respectively.

DO NOT OPEN THE VALVES. Report back as necessary that they are stuck OR the declutch lever is broken and you are getting maintenance to assist.

End of Events 7/8 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No.1 Event No. 9 Page 1 of 1 Event

Description:

Emergency Depressurization per QGA 500-1 when PSP exceeded Time Position Applicants Actions or Behavior SRO Enters QGA 500-1 to blowdown the vessel when it is determined drywell temperature cannot be restored below 280ºF or torus pressure cannot be maintained within PSP limits Crew Recognizes that the MSIVs have closed and may begin investigation CT1 SRO Directs actions of QGA 500-1 ATC/BOP Prevent injection from Core Spray and LPCI not needed for Core Cooling by diverting LPCI flow to Torus cooling and/or placing pumps in PTL ATC Maintains Rx water level with RCIC/HPCI SRO Verifies torus level > 5 feet CT1 ATC/BOP Opens all ADS valves, leaves switches in MAN IAW QCOP 0203-01, Manual Relief Valve Actuation, using hard card SIMOP ROLEPLAY: When all 5 ADS Valves are open, increase size of leak:

mmf rr10a 5 2:

ATC/BOP Reports to the SRO Drywell Pressure and Temperature.

End of Event 9 Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 201-301 NRC Scenario No.1 Event No. 10 Page 1 of 1 Event

Description:

QGA 500-04 Time Position Applicants Actions or Behavior SIMOP ROLEPLAY: When Saturation Conditions are met, simulate instrument leg flashing using batch file flashing:

bat seqflash5then6 SRO Determines the Drywell is in saturation conditions.

SRO Determines that RPV level is unknown and exits QGA 100 and 500-1, then enters QGA 500-4 SRO Verifies Torus level above 5 feet.

SRO Verifies all 5 ADS valve switches in MAN SRO ATC/BOP reports RPV pressure <75 psi above Torus pressure.

CT2 SRO Orders RPV flooded to the Main Steam Lines using systems listed in QGA 500-4 and briefs on plant indications to be monitored per QCAP 0200-10.

CT2 ATC/BOP Confirms RPV flooded to MSLs per criteria of QAP 0200-10 SRO Directs BOP/ATC to isolate MSLs, MSL Drains, RCIC, HPCI.

ATC/BOP Isolates MSLs, MSL Drains, RCIC, HPCI.

LEAD EVALUATOR: At the discretion of the Lead Evaluator, Freeze the simulator.

END OF SCENARIO Quad Cities 2019-301 NRC EXAM Scenario 1 END OF SCENARIO Quad Cities 2019-301 NRC EXAM Scenario 2 Exelon Nuclear 2019-301 ILT NRC Exam Scenario Scenario Number:

NRC Scenario 2 Revision Number: 00 Date: 05/28/2019 Developed by:

Instructor Date Validated by:

SME or Instructor Date Reviewed by:

Operations Facility Representative Date Approved by:

Training Department Date Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No. 2019-301 NRC Scenario 2 Op-Test No. ILT 19-301 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

A normal plant shutdown is in progress currently at 75% power.

Turnover: Reduce Recirc Flow to Lower Reactor power.

Event Malf. No. Event Event No. Type* Description 1 None ATC Reduce Recirc Flow to Lower Reactor power.

R 2 SER1494 ATC Feed Pump Vent Fan degraded.

AOTI324087 C

3 FW01A ATC 1A RFP trips with the standby RFP failing to auto-FW02 C start. ATC will start the 1C RFP per QCOA 3200-01 4 AD01D BOP Stuck open relief valve (QCOA 0203-01) and AD07D Reactor Scram C

5 RD13A Crew Hydraulic ATWS. Crew Takes actions per QGA 101 M to control reactor power, level and pressure.

6 RD27C ATC Running CRD pump trips. ATC takes actions to start standby CRD pump C

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 5 BOP Normal:

Malfunction(s) after EOP (1-2): E6 ATC Reactivity (1 per set): E1 Abnormal Events (2-4): E2, 3, 4 BOP I/C (4 per set): E4 Major Transient(s) /E-Plan entry (1-2): E5 ATC I/C (4 per set): E2, 3, 6 EOPs (1-2): QGA 100 SRO-I I/C (4 per set inc 2 as ATC): E2, 3, 4, 6 EOP Contingencies (0-2): QGA 101 SRO Tech Spec (2 per set):

Critical Tasks (2-3): 3 ALL Major Transients (2 per set) E5 Quad Cities 2019-301 NRC EXAM Scenario 2

SUMMARY

  • Initial Conditions:

o The plant is operating at 75%.

o Relief valve 3D Tailpipe Temperature is elevated and rising 1°F/Day.

  • Event 1: The SRO and ATC reduce Recirc Flow to Lower Reactor power.
  • Event 2: A Reactor Feed Pump vent fan will become degraded, requiring a shift to the alternate fan after receiving high temp alarms.
  • Event 3. 1A RFP trips with a failure of 1C RFP auto-starting. ATC will take actions per QCOA 3200-01 to start the 1C RFP and perform Emergency Power Reduction if necessary to maintain RWL.
  • Event 4: The D Relief Valve will actuate and stick open. The crew responds per QCOA 0203-01 and scram the reactor prior to exceeding 95°F Torus Water Temperature. The Relief valve will close after the ATWS.
  • Event 5: When the ATC inserts a manual scram no control rods will insert. The crew will recognize they are in a hydraulic ATWS and enter QGA 100, RPV Control and then they will rapidly transition to QGA 101 RPV Control (ATWS). The crew will attempt to insert control rods per QCOP 0300-28, but they will have little success beyond driving individual driving rods. The SRO will enter the Level/Power Control section of QGA 101 and lower reactor level to control reactor power.
  • Event 6: After entry into QGA 101, the running CRD pump will trip. ATC will take actions per QCOA 0300-01 to start the standby CRD pump.
  • Approximate Run Time: 1 Hour Quad Cities 2019-301 NRC EXAM Scenario 2 CRITICAL TASKS:

Critical task #1: With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110°F torus temperature) 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: With a reactor scram required and the reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)

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 PWR/LVL TERM/PREVENT)

Quad Cities 2019-301 NRC EXAM Scenario 2 EXERCISE PERFORMANCE OBJECTIVES SR-0002-P04 Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCOP 0280-01, QCGP 3-1 and QCGP 4-1.

SR-0002-P05 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.

SR-0203-P02 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-0001-P11 (Freq: LIC=B) Given a reactor plant with an ATWS, take action to reduce heat input into containment in accordance with QGA 101. (SOER 83-8 r11)

((ATWS is a key event in 2 of the top 100 most probable PRA Core Damage Sequences).

SR-0001-P12 (Freq; LIC=B) Given a reactor plant with an ATWS and conditions are met to intentionally lower RPV water level (power/level control), terminate and prevent all RPV injection except for boron, CRD, and RCIC in accordance with QGA 101. (SOER 83-8 r11)

SR-0001-P13 (Freq: LIC=B) Given a reactor plant with an ATWS and conditions are met to re-establish RPV injection during power/level control, use Preferred ATWS Systems (QGA Detail G) to attempt to maintain RPV water level between MSCRWL (Minimum Steam Cooling Reactor Water Level) and the level to where it was lowered in accordance with QGA 101.

SR-0001-P45 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.

Quad Cities 2019-301 NRC EXAM Scenario 2 Simulator Setup:

1. Reset to IC-20 (Approximately 75% power).
2. Go to RUN.
3. Verify the following RWM Sequence is loaded: 6PESU2 (or current shut down sequence)

(The following commands to be utilized for this scenario are contained in the CAEP file:

2018 CERT Scenario 5.cae)

4. Insert Commands for setup:
  • Standby RFP Fails to Auto Start o imf fw02
  • Hydraulic ATWS o imf rd13a 100 o imf rd13b 100
  • Override 'D' ADS Valve Switch o ior DIHS10287303D auto
  • Stick 'D' ADS Valve at 100%

o imf ad07d 100

5. Verify the following commands for scenario performance:
  • Feed Pump Vent Fan Degradation o ior aoti1324087 150 1:

o imf ser1494 (none 1:) on

  • Remove Vent Fan Degradation o ior aoti1324087 103 5:00 o dmf ser1494
  • 'A' RFP Trip o imf fw01a
  • 'D' ADS Valve Setpoint Drift o imf ad01d 0 2:
  • 'D' ADS Valve Remove/Install Fuses o irf ad04r remove o irf ad04r norm
  • After ATWS is recognized delete ADS Malf.

o dor DIHS10287303D o dmf ad01d o dmf ad07d

  • Trip 'A' CRD Pump o imf rd07a
  • Close 1-301-25 o irf rd04r close
  • Install Jumpers o irf qg08r activate
  • Pull ARI fuses o irf qg14r activate
  • Open 1-301-25 o irf rd04r open
6. Take the following components Out of Service:
a. None Quad Cities 2019-301 NRC EXAM Scenario 2
7. Place Protected Equipment rings on the RBCCW pump C/Ss
8. Provide a current revision of the following procedures, signed off as specified:
  • Provide a copy of QCOS 0005-05 (INCREASED MONITORING SURVEILLANCE) for the D relief valve signed off through todays shift
  • Provide a copy of QCGP 3-1 with Steps F.2.a. and F.2.b. signed off.
9. Provide a lowering power REMA signed off to be at 75% power.
10. Need to have blank EST available for use during the scenario.
11. Perform the applicable Post Simulator Exam Security Actions of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.

Quad Cities 2019-301 NRC EXAM Scenario 2 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 E-13 ELECT RELIEF VALVES 3C/3D/3E OPEN o 901(2)-3 E-14, Rev 007, ACOUSTIC MON SAFETY RLF VALVES OPEN o 901-3 E-16 VALVE LEAK DET SYS HIGH TEMP o 901(2)-5 A-1, Rev 009, SCRAM VALVE AIR SUPPLY LOW PRESSURE o 901(2)-5 B-4, Rev 009, GROUP 1 ISOL NOT RESET o 901(2)-5 B-7, Rev 021, GROUP 1 ISOL CH TRIP o 901(2)-6 E-9, Rev 011, REACTOR FEED PUMP VENTILATION EXHAUST AIR HIGH TEMP o 901(2)-6 F-7, Rev 016, REACTOR FEED PUMP AUTO TRIP o QOA 900-6 H-7, Rec 05, RFP 1A(2A) BRG OIL LOW PRESS QCOA 0203-01, Failure of a Relief Valve to Close or Reseat Properly, Rev 13 QCOA 0300-01, Control Rod Drive Pump Failure, Rev 18 QCOA 3200-01, Reactor Feed Pump Auto Trip, Rev 23 QCOP 0250-02, Bypassing MSIV Group I Isolation Signal From Low Low Reactor Water Level, Rev 13 QCOP 0300-28, Alternate Control Rod Insertion, Rev 33 QCOP 1000-09, Torus Cooling Start Up and Operation, Rev 28 QCOP 1000-30, Post Accident RHR Operation, Rev 32 QCOP 5750-15, Reactor Feed Pump Motor Ventilation System, Rev 7 QCOS 0005-05, Increased Monitoring Surveillance, Rev 9 QCGP 2-3, Reactor Scram, rev 92 QCGP 3-1, Reactor Power Operations, Rev 87 QGA 100, RPV Control, Rev 12 QGA 101, RPV Control (ATWS), 16 Quad Cities 2019-301 NRC EXAM Scenario 2 CREW TURNOVER 1.) Plant Conditions:

a.) Unit 1 is at 75% Power.

b.) Unit 2 is at 100% Power.

c.) Technical Specification limitations:

(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.

e.) Protected Equipment:

  • Fuel Pool Cooling 2.) Significant problems/abnormalities:

a.) Relief valve 1-203-3D Tailpipe Temperature is elevated and rising 1°F/Day.

a. QCOS 0005-05, Increased Monitoring Surveillance, being performed once/shift to verify no unexpected torus temperature increase.

3.) Evolutions/maintenance for the oncoming shift:

a. Power reduction for an upcoming weekend outage to repair the 1-203-3D relief valve per QCGP 3-1, Step F.2.c. The Shift Manager will direct the power reduction.

Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 1 Page 1 of 1 Event

Description:

Reduce Recirc Flow to Lower Reactor power.

Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, contact the Control Room as the Shift Manager and inform the US to lower power by 30 MWe using recircs. Inform the US that the SM will make all necessary notifications.

Lead Examiner Role Play: Qualified Verifier (QV) as necessary SRO Provides SRO oversight for lowering reactor power using core flow ATC Depresses LOWER pushbutton on Recirc MASTER SPEED DEMAND ATC Verifies Reactor pressure (Comp Pt C109 or C109_FILT or PI 1-640-25A) in the acceptable region of the CORE Power vs. Reactor Pressure Curve (Att D)

ATC Closely monitors power decrease on APRMs ATC Verifies POWERPLEX is operating and monitors outputs for peaking ATC Verifies Reactor Recirc Pumps remain at approximately equal flows BOP Provides peer check as requested for power changes End of Event 1 Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 2 Page 1 of 2 Event

Description:

Feed Pump Vent Fan Degraded Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Evaluator, initiate this event as follows:

ior aoti1324087 150 1: imf ser1494 (none 1:) on Ramps RFP Vent Temp to 150°F over one minute and provides a high temperature alarm .

Key Parameter Response: RFP AIR EXHAUST TEMP indicator on 901-6 Expected Annunciator(s):

901-6 E-9 RFP VENT EXH AIR HIGH TEMP Automatic Actions: None ATC Responds to annunciator and informs the Unit Supervisor.

SRO Directs the actions of QCAN 901-6 E-9.

ATC Checks the RFP AIR EXHAUST TEMP indicator, TI 1-3240-87, on 901-6 (Reading upscale at 150°F to match the annunciator setpoint).

ATC Verifies the A Vent Fan is running.

ATC Dispatches an operator to investigate high temperature alarm.

ATC/BOP Monitors RFP motor winding temperatures with computer points.

SIMOP ROLE PLAY: As in-plant personnel dispatched to investigate: Wait 2 minutes and then report that the A RFP Vent Fan is very noisy and vibrating like a bearing has failed.

SRO Directs or approves shifting to the B RFP Vent Fan.

ATC Starts the B RFP Vent Fan IAW QCOP 5750-15 ATC Places the B RFP Vent Fan control switch to START and verifies the discharge damper has opened.

SIMOP ROLE PLAY: As the EO dispatched to the RFP room, when asked about the position of the B RFP vent fan damper report the damper is open (QCOP 5750-15 step F.2.b).

ATC Stops the A RFP Vent Fan and verifies its discharge damper has Closed. May place C/S in P-T-L and install an orange ring.

SIMOP ROLE PLAY: As the EO dispatched to the RFP room, when asked about the position of the A RFP vent fan damper report the damper is closed (QCOP 5750-15 step F.3.c.(2)).

Event 2 Continued Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 2 Page 2 of 2 Event

Description:

Feed Pump Vent Fan Degraded SIMOP: When the B Vent Fan has been started and the A Vent Fan has been secured, remove the failures as follows: Modify Override ior aoti324087 103 05 to lower RFP air temp to 103 over 5 minutes then wait 1 minute and delete malfunction dmf ser1494 to clear the high temp alarm.

BOP Provides peer checks and monitors Balance of Plant parameters ATC Reports RFP high Temp alarm cleared and monitors temperature until it returns to normal.

End of Event 2 Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 3 Page 1 of 1 Event

Description:

1A RFP trip with failure of Standby Pump to auto-start.

Time Position Applicants Actions or Behavior SIMOP: At the Lead Evaluators direction, trip the 1A Reactor Feed Pump using malfunction:

imf fw01a Key Parameter Response: 1A RFP trips with failure of Standby Pump to auto-start.

Expected Annunciator(s):

901-6 F-7, RFP AUTO TRIP 901-6 H-7, 1A RFP BRG OIL LOW PRESS Automatic Actions: None (Standby Pump auto-start is defeated)

ATC Reports 1A RFP has tripped and Standby Pump has failed to auto-start.

ATC Manually starts the 1C RFP.

SRO Sets Scram criteria for ATC of RWL +11 lowering and +44 rising.

SRO Directs ATC to perform Emergency Power Reduction to maintain RWL.

ATC Performs Emergency Power Reduction to maintain RWL at +30 inches.

ATC Reports RPV water level is +30 inches and stable.

SRO Directs BOP/ATC to take actions per QCOA 3200-01, Reactor Feed Pump Auto Trip.

ATC/BOP May place the RFP Selector Switch to OFF ATC/BOP Verifies proper operation of the Feed Water Reg Valves.

ATC/BOP Dispatches EO to Bus 11 to check for any red targets on the breaker compartment.

SIMOP: As the EO sent to Bus 11, wait 4 minutes and inform the Control Room that there is an overcurrent target up on the 1A RFP Breaker.

As EMD sent to investigate why 1C RFP did not auto-start, inform the Control Room that a troubleshooting package is being prepared.

End of Event 3 Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 4 Page 1 of 4 Event

Description:

Stuck Open Relief Valve (QCOA 0203-01)

Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Examiner, Fail the 1-203-3D Relief Valve open by inserting the following: imf ad01d 0 2:

Delete Override for 3D high temp: dor aotr1026020L Key Parameter Response: Generator MWe lowering, Torus Water Temperature rising Expected Annunciator(s):

901-3 E-13 ELECT RELIEF VALVES 3C/3D/3E OPEN 901-3 E-14 ACOUSTIC MON SAFETY RLF VALVES OPEN 901-3 E-16 VALVE LEAK DET SYS HIGH TEMP Automatic Actions: None BOP Acknowledges annunciators and reports the D Relief Valve indicates open ATC Reports RPV water level and pressure are stable SRO Directs actions of QCOA 0203-01 BOP Places the D Relief Valve key switch to the OFF position BOP Cycle the key switch between MANUAL and AUTO (because the SRV did not close)

BOP/SRO Recognizes that the D SRV will not close SIMOP: If requested to remove D SRV control power fuses, role-play as necessary.

Wait until AFTER the ATWS occurs, then use fuse removal Remote Function: irf ad04r remove and report the fuses are removed If directed to re-install SRV fuses, re-install using the Remote Function: irf ad04 norm and report the control power fuses are re-installed.

CREW (Continuous) Monitor Torus Water Temperature SRO Enters TS 3.4.3 Cond A, 14 day LCO (May not have time prior to scram)

SRO May set SCRAM CRITERIA based on Torus Water Temperature Event 4 Continued Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 4 Page 2 of 4 Event

Description:

Stuck Open Relief Valve (QCOA 0203-01)

Time Position Applicants Actions or Behavior SRO/ATC Manually Scram the reactor prior to exceeding 95°F Torus Water Temperature SRO Directs the initiation of Torus Cooling per QCOP 1000-09 or per QCOP 1000-30 (Hard Card)

BOP If per QCOP 1000-04, establishes RHRSW flow Verifies RHR HX A/B in either NORMAL or REVERSE FLOW lineup Throttles open MO-1-1001-5A/B RHR SW HX Discharge Valve, to at least 40% open Starts the first RHRSW Pump in each loop Throttles MO-1-1001-5A/B to establish <3600 gpm and <350 psig Discharge Pressure Monitor Process Liquid Monitor 1-1705-12 May start a second RHRSW Pump in each loop Throttles MO-1-1001-5A/B to establish approximately 140 psig Discharge Pressure Starts a second RHRSW Pump in each loop Throttles MO-1-1001-5A/B to establish <7200 gpm and

<350 psig Discharge Pressure in each loop Maintains RHRSW pressure at least 20 psig higher than RHR pressure in each loop BOP If per QCOP 1000-30 Hard Card, establishes RHRSW flow Places RHR LOOP A/B CONTAINMENT CLG permissive switch 17 to the ON position Places RHR LOOP A/B RHR SW START PERMISSIVE SWITCH 19 to the MANUAL OVERRIDE position Throttles open MO-1-1001-5A/B RHR SW HX Discharge Valve, to approximately 40% open Starts the first RHRSW Pump in each loop Throttles MO-1-1001-5A/B to establish <3600 gpm/pump, <350 psig Discharge Pressure and RHRSW pressure at least 20 psig higher than RHR pressure Event 4 Continued Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 4 Page 3 of 4 Event

Description:

Stuck Open Relief Valve (QCOA 0203-01)

Time Position Applicants Actions or Behavior Throttle closed MO 1-1001-16A/B (HX Bypass) on each Loop May start the second RHRSW Pump in each loop and adjusts as necessary BOP If per QCOP 1000-09, establishes RHR flow in both loops Verifies MO 1-1001-19A & B (Loop Crosstie Valves) are OPEN (Not on Hard Card)

Verifies CLOSED on opposite loop: (Not on Hard Card)

MO 1-1001-37A/B (Torus Spray Shutoff)

MO 1-1001-29A/B (LPCI Inject)

MO 1-1001-23A/B & 26B (Drywell Spray Valves)

MO 1-1001-36A/B (Torus Test)

MO 1-1001-34A/B (Torus Test or Spray)

Verifies B Loop RHR discharge pressure is > 57 psig (Not on Hard Card)

Opens MO 1-1001-34A/B Starts the first RHR pump on each loop Throttles open the MO 1-1001-36A/B establishing approx. 3500 gpm flow rate If desired to start a second RHR pump on each loop Throttles the 36A/B valve to establish discharge pressure < 200 psig Starts a second RHR pump and throttles the 36A/B valve to maintain discharge pressure Throttle closed MO 1-1001-16A/B (HX Bypass) on each Loop BOP If per Hard Card, establishes RHR flow in both loops Verifies RHR Pumps running Opens MO 1-1001-34A/B Opens/Throttles MO 1-1001-36A/B as necessary to maintain RHR Discharge Pressure Throttle closed MO 1-1001-16A/B (HX Bypass) on each Loop Event 4 Continued Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 4 Page 4 of 4 Event

Description:

Stuck Open Relief Valve (QCOA 0203-01)

Time Position Applicants Actions or Behavior SRO Directs the actions from QCGP 2-3 Attachment A SRO/ATC May reduce Total Core Flow to not less than 53mlb/hr.

ATC Depresses both RX SCRAM CH A and CH B Pushbuttons prior to Torus Temperature reaching 110°F End of Event 4 Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 5/6 Page 1 of 3 Event

Description:

Hydraulic ATWS/1A CRD Pump Trip SIMOP: After the ATWS is identified, delete the ADS Malfunction: dor DIHS10287303D dmf ad01d dmf ad07d Trip A CRD pump by inserting: imf rd07a Key Parameter Response: RPV pressure/level increase, RFP +48 trip, No control rod movement on manual / auto scrams.

Expected Annunciator(s): 901-5 A-1, 901-5 B-4, 901-5 B-7 Automatic Actions: Group II, III isolations, Time Position Applicants Actions or Behavior SRO Enters QGA 100, then transitions to QGA 101 and directs actions.

CT2 BOP Inhibits ADS and places Core Spray Pumps in PTL.

ATC Actuates the ARI system.

CT1 ATC Injects SBLC by selecting SYS 1 or SYS 2.

ATC Reports SBLC system injection and Tank Level.

ATC Verifies Recirc pumps operating at minimum speed.

SRO Verifies reactor power > 5% and directs ATC to trip the Recirc pumps.

ATC Trips both Recirc pumps by closing discharge valves, using Emergency Stop Pushbutton, or ASD control switches.

SRO Directs ATC to insert control rods per QCOP 0300-28.

ATC Informs the SRO that the 1A CRD Pump has tripped.

SRO Directs ATC to start 1B CRD Pump per QCOA 0300-01.

ATC/BOP Calls EO to investigate trip of the 1A CRD Pump SIMOP ROLEPLAY: As EO sent to investigate CRD Pump trip, wait 3 minutes and inform Control Room that the 1A CRD Pump tripped on overcurrent and EMD is investigating.

ATC Verifies closed MO 1-301-B, 1B PMP DISCH VLV, for the 1B CRD Pump ATC Starts the 1B CRD Pump ATC Throttles MO 1-301-2B to maintain 1400 to 1500 psig discharge pressure.

ATC Informs the SRO that the 1B CRD Pump is running.

Event 5/6 continued.

Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 2 Event No. 5/6 Page 2 of 3 Event

Description:

Hydraulic ATWS/1A CRD Pump Trip Time Position Applicants Actions or Behavior SIM OP ROLE PLAY: If dispatched to close the 1-301-25 valve, wait 3 minutes then insert the command using remote function RD04R and report back:

irf rd04r close CT1 ATC Bypassess the RWM and begins inserting control rods starting from the center and spiraling out.

ATC Adjusts Drive Water pressure as necessary by dispatching an EO to close the 1-301-25 valve and/or manually adjusting the CRD FCV.

ATC Bypasses the SDV high level scram and attempts to reset the scram.

ATC Contacts an EO to place jumpers in the 901-15 and 901-17 panels per QCOP 0300-28 to bypass reactor scram signals.

SIM OP ROLE PLAY: As the EO, directed to install jumpers, wait 2 minutes, then insert the command using remote function QG08R and report back to the ATC:

irf qg08r activate ATC Resets the reactor scram and verifies scram valves are closed.

ATC If necessary, dispatches an EO to the Aux Electric Room to de-energize ARI by pulling fuses in the 2201-70A/B panels per QCOP 0300-28.

SIM OP ROLE PLAY: If dispatched to pull ARI fuses in the Aux Electric Room, wait 2 minutes, then insert remote function QGR14R and report back to the ATC:

irf qg14r activate ATC If desired, directs an EO to re-open the 1-301-25 valve.

SIM OP ROLE PLAY: If dispatched to open the 1-301-25 valve, wait 3 minutes then insert the command using remote function RD04R and report back:

irf rd04r open ATC Directs Shift Supervisor to individually scram control rods from the 901-16 panel when the SDV has drained, (as indicated by alarm 901-5 A-14 resetting).

SIMOP ROLE PLAY: After 3 minutes or at the direction of the Lead Evaluator, report to the ATC:

Individual control rod scramming is NOT successful.

SRO Directs action of QGA 101, Level Leg.

SRO Directs BOP to verify isolations and auto actions for 0 RPV water level.

Event 5/6 continued.

Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2019-301 NRC Scenario No. 1 Event No. 5/6 Page 3 of 3 Event

Description:

Hydraulic ATWS/1A CRD Pump Trip Time Position Applicants Actions or Behavior SRO Orders isolations to be bypassed per QCOP 0250-02 BOP Orders EO to bypass isolations per QCOP 0250-02.

SIM OP ROLE PLAY: As the EO, directed to bypass isolations, wait 2 minutes, then insert the command using remote function QG07R and report back to the ATC:

irf qg07r activate imf ser0736 on CT3 SRO Directs BOP and ATC to terminate and prevent all RPV injection except Boron, CRD, and RCIC.

CT3 ATC Terminates and prevents injection from the 901-5 panel as follows:

  • Places the Low Flow FWRV in MANUAL and reduces output to zero.
  • Places A & B FWRVs in MANUAL and reduces both controller outputs to zero.

Closes A & B FWRV Isolations MO 1-3206A/B.

CT3 BOP Trip-Latches the HPCI turbine.

SRO Directs ATC to lower RPV water level and report at -35 inches.

ATC Reports RPV water level at -35 inches and lowering.

SRO Records RPV water level when one of the following conditions are met:

  • Reactor power < 5%
  • All ADS valves closed and Drywell pressure stays < 2.5 psig SRO Assigns RPV water level band of -162 and the recorded level at which one of the three conditions was met.

SRO Directs ATC to maintain RPV water level in assigned band using Preferred ATWS Systems (Detail G).

ATC Re-establishes injection using Condensate/Feedwater system.

SIM OP NOTE: With concurrence of the Lead Evaluator, the scenario is terminated when RPV water level is being controlled in band, RPV pressure is stable and in band, and reactor power is lowering.

End of Scenario Quad Cities 2019-301 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 END OF SCENARIO

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