ML14224A564
| ML14224A564 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/27/2013 |
| From: | NRC/RGN-III |
| To: | Exelon Generation Co |
| Bruce Palagi | |
| Shared Package | |
| ML13093A388 | List: |
| References | |
| Download: ML14224A564 (25) | |
Text
Quad Cities 2014 NRC EXAM Scenario 1 Exelon Nuclear 2014 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 1 Revision Number: 00 Date: 10/17/13 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2014 NRC Scenario 1 Op-Test No.: ILT 12-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is operating at 75% power Turnover:
Reverse Main condenser flow and Insert control rods for FCL adjustment.
Event Malf. No. Event Event No. Type* Description 1 None BOP Reverse Main Condenser flow N
2 None ATC Lower Reactor power with control rods for Flow R Control Line adjustment 3 RD02R2619 ATC Recoverable Stuck Rod / Raise CRD Drive C Pressure (QCOA 0300-02) 4 NM10A ATC RBM Channel 7 fails high TS I
5 HP10 BOP Spurious HPCI Initiation TS I (QCOA 2300-01) 6 AIPIC1874011 BOP Drywell N2 controller failure (DW pressure rises)
C 7 ED02 Crew Station Blackout is entered. The SBO diesel will ED03D M be used to reenergize Bus 14-1.
ED04K (QCOA 6100-04)
DG03A 8 RR10A Crew The transient initiates a small LOCA in the HP08 M Drywell; QGA 100 and 200 are performed. RCIC RC01 trips, the SSMP must be manually initiated, and local action is necessary to make HPCI available. When essential bus power is restored, the challenges to the Primary containment will be addressed.
- (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: E1 Malfunction(s) after EOP (1-2): 2 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, 4, 5,& 6 BOP I/C (4 per set): E5 & 6 Major Transient(s) /E-Plan entry (1-2):E7 & 8 ATC I/C (4 per set): E3 & 4 EOPs (1-2): QGA 100 and 200 SRO-I I/C (4 per set inc 2 as ATC): E3-6 EOP Contingencies (0-2): None SRO Tech Spec (2 per set): E4 & 5 Critical Tasks (2-3): 2 ALL Major Transients (2 per set) E7 & 8 Quad Cities 2014 NRC EXAM Scenario 1
SUMMARY
- Initial conditions:
o Unit 1 is operating at 75% power preparing to reverse Main Condenser Flow when Engineering indicates they are ready.
- Event 1: When Engineering is ready, the BOP operator reverses Main Condenser Flow.
- Event 2: Lower Reactor power with control rods for Flow Control Line adjustment.
- Event 3: Recoverable Stuck Rod / Raise CRD Drive Pressure.
- Event 4: RBM Channel 7 fails high. The ATC and SRO Respond per QCAN 901-5 A-7 to bypass the faulty RBM after the SRO references Technical Specifications.
- Event 5: The BOP responds to an inadvertent HPCI Initiation per QCOA 2300-01. When HPCI has been trip-latched to prevent restart, the SRO should reference TS 3.5.1 Condition G.
- Event 6: Drywell N2 controller fails, causing the makeup valve to open fully. The BOP can take manual control of the valve and close it to stabilize Drywell pressure. Without operator action, Drywell pressure will continue to rise and eventually exceed the Drywell High Pressure alarm setpoint.
- Event 7: A Loss of the RAT occurs and Bus 13-1 locks out. The transient initiates a small LOCA in the Drywell requiring a reactor scram. The U1 Diesel cannot be started and Bus 14-1 to Bus 24-1 crosstie fails, Station Blackout is entered. The SBO diesel must be used to reenergize Bus 14-1, which may be used to backfeed Bus 14 and Bus 19.
- Event 8: QGA 100 and 200 are performed due to the LOCA. The crew will attempt to manually initiate RCIC but it will trip on a mechanical overspeed fault that cannot be reset. Local action is necessary to make HPCI available. The crew will start the SSMP to maintain RPV Water level. When essential bus power is restored, the challenges to the Primary containment will be addressed.
- Approximate Run Time: 1.5 Hours CRITICAL TASKS:
Critical task #1: Given an operating reactor plant when a station blackout occurs, take actions to monitor plant parameters and restore electrical power using the emergency DGs, SBO DGs, or unit 4KV crossties in accordance with QCOA 6100-04, QCOA 6100-03 and/or QCOP 6500-08.
Critical task #2: Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with available high-pressure systems IAW with QGA 100 before RPV water level reaches TAF.
(Conditional Critical Task) If RPV water level lowers to less than -59 inches, inhibit ADS in accordance with QGA 100.
Quad Cities 2014 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-4400-P02 Given an operating reactor plant, reverse main condenser circ water flow in accordance with QCOP 4400-09.
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- 0300-P05 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-0700-P10 Given an operating reactor plant with control rod moves occurring to adjust FCL, operate and monitor the RBM in accordance with QCOP 0700-05.
SR-6100-P08 Given an operating reactor plant when a station blackout occurs, take actions to monitor plant parameters and restore electrical power using the emergency DGs, SBO DGs, or unit 4KV crossties in accordance with QCOA 6100-04, QCOA 6100-03 and/or QCOP 6500-08.
SR-0002-P03 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 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-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)
SR-0001-P01 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 E) to attempt to hold RPV water level above -142 inches in accordance with QGA 100.
SR-1000-P02 Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)
SR-1000-P04 Given a reactor plant with rising containment pressures 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 K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays when torus pressure exceeds 5 psig in accordance with QGA 200 and QCOP 1000-30. (Important PRA Operator Action - starting containment sprays has a RAW value of 82.5) 2014 NRC Scenario Scenario 1 ReMA.doc Scenario 1 QCGP Scenario 1 QCOP 1.cae 3-1.pdf 4400-09.pdf Quad Cities 2014 NRC EXAM Scenario 1 Simulator setup:
- 1. Reset to IC-20 (Approximately 75% power).
- 2. Go to RUN.
- 3. Insert rod E-9 to position 14.
- 4. Verify the following RWM Sequence is loaded: PHESU
- a. Mark up the Control Rod Move Sheet to reflect all rods withdrawn up to Step 42.
- b. Markup Step 42 with all Rods withdrawn through FCL step 40. Rod E-9 is at position 14.
(Commands to be utilized during this scenario are contained in the CAEP file:
2014 NRC Scenario 1.cae)
- 5. Insert Commands for setup:
- imf rd02r2619 16 (Control Rod G-5 stuck at position 16)
- trgset 1 rdpdrivedelta > 340 (Set trigger 1 as CRD drive Pressure > 340#)
- trg 1 dmf rd02r2619 (Delete stuck rod on Trigger 1)
- imf ed04k (Bus 14-1 to 24-1 crosstie breaker failure)
- imf dg03a (U1 EDG start failure)
- imf ed03d (3) (On Event Trigger 3, Bus 13-1 Lockout)
- imf ed02 (3) (On Event Trigger 3, Loss of RAT)
- imf rr10a (3 3:) 0.13 7:30 (On Event Trigger 3, Recirc Suction Line Break at 0.13%
severity on a 7.5 min ramp after a 3 minute delay)
- trgset 7 zlohs1130161 (2) (When RCIC Steam to Turbine Valve Red light comes on)
- imf hp08 (3) (HPCI Aux Oil Pump overload on trigger 3)
- 6. Verify the following commands for scenario performance:
- imf nm10a 100 (RBM 7 fails high)
- imf hp10 (HPCI inadvertent initiation)
- trg! 3 (Initiates the Station Blackout and then a LOCA 3 minutes later)
- irf ed34r close (Bus 24-1 to bus 14-1 breaker on U2 as requested)
- irf rp02r mg_set and irf rp29r reset (Restores A RPS to normal power as requested)
- irf rp03r mg_set and irf rp28r reset (Restores B RPS to normal power as requested)
- irf rp02r alt (Restores A RPS to alternate power as requested)
The following two are duplicates because the candidates may need to restore RPS A more than once
- irf rp02r mg_set and irf rp29r reset (Restores A RPS to normal power as requested)
- irf rp02r alt (Restores A RPS to alternate power as requested)
- bat_ sv (silence vacuum breakers when requested)
(Continued)
Quad Cities 2014 NRC EXAM Scenario 1
- None
- 8. Complete the following Control Panel setup items:
- Verify the LOCA TRIP ENABLED labels are above the 1A and 1C Circ Water Pumps.
- Display the Power/Flow Map on Monitor 3.
- Clear all SBO Panel alarms.
- 9. Provide a current revision of the following procedures, signed off as specified:
- QCOP 4400-09 (no steps signed off)
- QCGP 3-1 with the following marked up: Circle all steps up to F.1. N/A step F.2.a. Sign off steps F.3.a, F.3.b (1) through (6)(a)., N/A step F.3. b (6)(b) and (c), Sign off steps F.3.c, d and e(1), leave F.3.e(2) blank, sign off steps F.3.e(3), e(3)(a), F.3.f.(1) through (7), leave F.3.f.(7)(a) blank, N/A step F.3.f.(8), sign off step F.3.g.(1), N/A step F.3.g.(1)(a), sign off steps F.3.g.(2), (2)(a), (2)(b), (3), (4), (5)(a) and (5)(b). All other steps remain blank.
- 10. Provide scenario 1 REMA.
- 11. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.
- 12. Ensure (1) orange ring is available to provide equipment status.
- 13. Ensure 2 ESTs are available to provide equipment status.
Quad Cities 2014 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901-3 A-16, PRI CNMT HIGH PRESSURE, Rev.14 o 901-3 B-9, HPCI MOTOR OVERLOAD, Rev. 4 o 901-3 D-12, HPCI PUMP LOW FLOW, Rev. 7 o 901-4 G-15, RCIC TRIP THROTTLE VALVE CLOSED, Rev. 2 o 901-5 A-7, RBM HIGH OR INOP, Rev. 5 o 901-5 D-13 CHANNEL 4-6 APRM HI-HI OR INOP, Rev. 10 o 901-5 C-3, ROD OUT BLOCK, Rev. 11 o 901-5 C-6 APRM DOWNSCALE, Rev. 5 o 901-8 A-4, DIESEL GEN 1/2 TROUBLE, Rev. 5 o 901-8 A-7, DIESEL GEN 1 TROUBLE, Rev. 5 o 901-8 C-7, DIESEL GEN 1 FAIL TO START, Rev. 3 o 901-8 E-2, RESERVE TRANS 12 TRIP, Rev. 3 o 901-8 G-2, RESERVE AUX TRANS 12 LOW VOLTAGE, Rev. 4 o 901-8 F-3, 4KV BUS OVERCUR TRIP, Rev. 5 QCGP 1-1, Normal Unit Startup, Rev. 94 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 44 QCGP 2-3, Reactor Scram, Rev. 80 QGA 100, RPV Control, Rev. 9 QGA 200, Primary Containment Control, Rev. 9 QCOA 0201-01, Increasing Drywell Pressure, Rev. 23 QCOA 0300-02, Inability to Drive a Control Rod: Control Rod Stuck, Rev. 18 QCOA 0700-03, Loss of Neutron Flux Indication. Rev. 8 QCOA 1000-04, LPCI Automatic Initiation, Rev. 17 QCOA 1300-01, RCIC Turbine Trip/Isolation Recovery, Rev. 15 QCOA 2300-01, HPCI Automatic Initiation, Rev. 21 QCOA 6100-03, Loss of Offsite Power, Rev. 38 QCOA 6100-04, Station Blackout, Rev. 19 QCOP 0280-01, Reactor manual Control Operation, Rev. 18 QCOP 1000-30, Post-Accident RHR Operation, Rev. 26 QCOP 1100-02, Injection of Standby Liquid Control, Rev. 12 QCOP 1300-02, RCIC System Manual Startup, Rev. 29 QCOP 2300-06, HPCI System Manual Startup, Rev. 32 QCOP 2900-02, SSMP System Startup, Rev. 25 QCOP 4400-09, Circulating Water System Flow Reversal, Rev. 25 QCOP 6500-08, 4KV Bus Crosstie Operation, Rev. 26 QCOP 6620-14, Energizing Bus 14-1 From SBO DG 1, Rev. 17 QCOP 7000-01, Reactor Protection System MG Sets, Rev 50 QOP 0700-05, Rod Block Monitor, Rev. 15 Quad Cities 2014 NRC EXAM Scenario 1 CREW TURNOVER
- 1. Plant Conditions:
a.) Unit 1 is at 75% power with a reactor startup in progress.
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.
2.) Significant problems/abnormalities:
a.) None 3.) Evolutions/maintenance for the oncoming shift:
a.) Engineering is doing an evaluation on Circ Water and wants to monitor some parameters during Condenser Flow Reversal. When they report that they are ready, reverse Main Condenser Flow per QCOP 4400-09. Backpressure is not expected to exceed 6 Hg. All involved personnel have been briefed on the evolution.
b.) Lower Reactor power with control rods for Flow Control Line adjustment to 92%.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 1 Page 1 of 1 Event
Description:
Reverse Main Condenser Flow from South to North Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: Contact the Unit Supervisor as the WEC Supervisor (phone 2300):
Engineering is ready to monitor Circ Water, Condenser Flow Reversal may proceed.
SRO Directs Main Condenser flow reversal per QCOP 4400-09.
SIMOP: Role Play the Equipment Operator stationed at MCC 16-3 and the WEC or Engineering as necessary.
BOP Establish communications with the Equipment Operator stationed at MCC 16-3.
BOP (Continuous) Monitors Condenser Backpressure and Condensate Temperatures.
BOP Verifies OFFGAS FLOW TO MAIN CHIMNEY on FR-1-5440-7 (901-54 panel) is >15 scfm.
BOP Verifies Annunciator 901-7 C-1, COND FLOW REV VLVS ON LOCAL CONT, is NOT in alarm.
BOP Opens South SJAE Suction valves using the Test switch on the 901-7 panel by placing the switch to the SOU position.
BOP Places the Circulating Water Flow Selector switch to the NORTH position when the South SJAE valves are fully open.
BOP Verifies the following:
- SJAE Suction valves change over
- Condenser differential pressure has reversed and vacuum is stable ATC Monitors reactor and RPV parameters.
End of Event 1 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 2 Page 1 of 1 Event
Description:
Lower Reactor power with control rods for Flow Control Line adjustment Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: If the crew does not promptly begin the task, call the control room as the Shift Manager and ask them to begin.
LEAD EVALUATOR ROLE PLAY: If the crew decides to verify they are within the thermal limits, role play as the QNE and state thermal limits have been verified.
Qualified Verifier (QV) as necessary.
Directly supervises control rod moves and directs the RO to begin the SRO Flow Control Line adjustment to 92%.
ATC (CONTINUOUS) Monitors reactor parameters.
ATC Selects an in-sequence control rod.
On the RWM verifies proper rod is selected, its current position and ATC bounds.
Communicates to the QV. Ready to Insert Rod L-7 from position 16 ATC to position 14 using single notch.
Replies: Rod L-7 is selected. Understand Inserting L-7 from position QV/BOP 16 to position 14 using single notch.
ATC Replies: That is correct.
ATC Verifies control rod and moves it to the desired position.
ATC/BOP Place keeps rod moves in the rod movement book.
ATC Repeats above steps as necessary.
BOP Monitors balance of plant parameters.
End of Event 2 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 3 Page 1 of 1 Event
Description:
Recoverable Stuck Rod / Raise CRD Drive Pressure Time Position Applicants Actions or Behavior EVALUATOR NOTE: Control Rod G-5 will not move from position 16 with normal drive water pressure; CRD Drive Pressure indication is on 901-5, 1-340-4.
Expected Annunciator(s): None Automatic Actions: None ATC Reports CR G-5 will not move.
SRO Directs RO to perform the actions of QCOA 0300-02.
ATC Verifies no Rod Block exists.
ATC Verifies no RWM select block exists.
ATC Verifies the proper control rod is selected.
Raises CRD drive water pressure in 50 psig increments by throttling ATC closed on the 1-302-8 valve.
SIMOP: When CRD drive water pressure is greater than 340 psid, verify Event Trigger 1 goes active to delete malfunction dmf rd02r2619 Attempts to insert Control Rod G-5 and identifies normal control rod ATC movement.
ATC Continues normal control rod insertion.
ATC Restores drive water pressure to normal.
QV/BOP Provides peer check as required.
BOP Monitors balance of plant parameters.
LEAD EVALUATOR: If the crew does not continue to lower power to adjust the FCL, prompt the crew. This is necessary for moving to the next event.
End of Event 3 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 4 Page 1 of 1 Event
Description:
RBM Channel 7 fails high Time Position Applicants Actions or Behavior SIMOP: When rod J-11, has been inserted to position 14, initiate the RBM Upscale malfunction nm10a at 100% severity: imf nm10a 100 Key Parameter Response: Rod Out Permissive light is OFF; RBM CH 7 indicates upscale Expected Annunciator(s):
901-05 A-7 RBM HIGH OR INOP 901-05 C-3 ROD OUT BLOCK Automatic Actions: Rod Block ATC Responds to unexpected annunciators and informs the Unit Supervisor.
ATC Determines RBM channel 7 is UPSCALE.
ATC Verifies that a ROD BLOCK is in effect.
ATC/BOP May verify RBM 7 is upscale at the 901-37 panel meter.
ATC Verifies the correct rod was being inserted.
ATC May depress the PUSH SETUP button.
May attempt to re-null the RBM by selecting an edge rod and then re-ATC selecting the desired rod.
Contacts Instrument Maintenance to investigate the upscale failure of SRO RBM 7.
SIMOP ROLE PLAY: As Instrument Maintenance, inform the Unit Supervisor 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.
SRO Enters TS 3.3.2.1 Control Rod Block Instrumentation, Condition A for one rod block monitor inoperable.
EVALUATOR NOTE: The crew may return to Event 3 to continue the reactivity manipulation.
End of Event 4 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 5 Page 1 of 1 Event
Description:
Inadvertent HPCI Initiation Time Position Applicants Actions or Behavior SIMOP: At the direction of the Lead Examiner, insert malfunction: imf hp10 (Inadvertent HPCI Initiation.)
Key Parameter Response: HPCI Turbine speed 4000 rpm, Turb Steam Supply 1-2301-3 Valve open, Pump Discharge 1-2301-8 valve open, RPV water level rising Expected Annunciator(s):
901-3 F-9 HPCI OIL FILTER HIGH DP 901-3 D-12 HPCI PUMP LOW FLOW 901-5 D-7 LPRM HIGH 901-5 E-8 RX VESSEL HIGH LEVEL Automatic Actions: HPCI system responds as designed to an Auto Initiation signal.
BOP Responds to Annunciator 901-3 D-12, HPCI PUMP LOW FLOW.
BOP Reports alarm to US; refers to annunciator procedure.
BOP Reports HPCI System initiating.
CREW Determine that HPCI injection is not necessary:
- Report Drywell pressure normal
SRO Directs actions of QCOA 2300-01.
SRO Determines initiation is NOT valid and directs the BOP to trip-latch REMOTE HPCI TURB TRIP pushbutton.
BOP Actuates the trip-latch REMOTE HPCI TURB TRIP pushbutton.
BOP Place MO 1-2301-14 MIN FLOW BYP VLV in P-T-L.
BOP Contacts EMD/IMD to investigate HPCI auto-start.
SRO Enters TS 3.5.1 Cond G, HPCI System Inop. Also enters 14 day ATR LCO for HPCI Inoperable.
SIMOP ROLE PLAY: If contacted as Maintenance to investigate the HPCI start, inform the CR you will start a troubleshooting work package. If dispatched as an EO to investigate the HPCI start, wait 5 minutes and report there is no indication for why HPCI started.
EVALUATOR NOTE: Notifications, event reporting and risk assessment change are not evaluated here.
BOP/SRO (CONTINUOUS) If HPCI operation is subsequently required after it has been trip latched, then release the REMOTE HPCI TURB TRIP pushbutton and place the MIN FLOW BYP VLV in NORMAL.
End of Event 5 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 6 Page 1 of 1 Event
Description:
Drywell N2 controller failure Time Position Applicants Actions or Behavior NOTE: It takes 8 minutes from the time of initiation until the 901-3 A-16 alarms.
SIMOP: When directed by the lead examiner, fail the 1-1640-11 controller using the following command: ior aipic1874011a 100 2:
Key Parameter Response: Containment Pressure Controller Position at 100%
Expected Annunciator(s): 901-3 A-16 PRI CNMT HIGH PRESSURE Automatic Actions: None BOP May identify that Drywell pressure is rising and report to the Unit supervisor.
Announces rising drywell pressure and/or alarm 901-3 A-16 at 1.44 BOP psig. if/ when it alarms.
Directs BOP to perform actions of QCAN 901-3 A-16 and/or QCOA SRO 0201-01, Increasing Drywell Pressure.
SRO May set scram criteria of ~2.0 psig.
CREW May notify Rad Protection of high containment pressure.
IF Drywell pressure reaches 1.5 psig enters TS 3.6.1.4 Condition A.
SRO 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to reduce drywell pressure to <1.5 psig.
BOP May start last Drywell Cooler fan IAW QCOA 0201-01.
BOP Reports drywell pressure controller has failed.
BOP May take manual control of the drywell pressure controller and close it.
BOP Closes the MO 1-1601-57 valve, N2 Makeup Valve.
BOP Contacts IMD to investigate controller failure.
SIMOP ROLE PLAY: If contacted as IMD, inform the CR you will find your supervisor and come to the control room.
SRO IF drywell pressure exceeded 1.5 psig considers venting the drywell.
ATC Monitors DW pressure as BOP investigates and prepares for reactor scram.
Lead Evaluator: Drywell venting is not part of the scenario. Do not wait until it is done to move on.
End of Event 6 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 1 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior SIMOP: When directed by the Lead Evaluator, initiate the Station Blackout using manual Trigger 3: trg! 3 (Note: Initially there is a loss of T12 and bus 13-1, but after 3 minutes a LOCA is inserted leading to a loss of T11 and the Blackout.)
Key Parameter Response: 0 Voltage on 4KV Busses, Transformer 12 Breakers to Busses 11, 12, 13, & 14 indicate OPEN, Loss of lighting in Control Room/Simulator, No output voltage on U1 EDG, 1/2 EDG output breaker open Expected Annunciator(s): (Not a complete list) 901-8 A-7, DIESEL GEN 1 TROUBLE 901-8 C-7, DIESEL GEN 1 FAIL TO START 901-8 E-2, RESERVE TRANS 12 TRIP 901-8 G-2, RESERVE AUX TRANS 12 LOW VOLTAGE 901-8 F-3, 4KV BUS OVERCUR TRIP Automatic Actions: Reactor Scram, Group 1 Isolation, (Note: Faults prevent EDGs from restoring power)
Responds to Annunciators and reports the Loss of T-12, Bus 13-1 and BOP 18.
BOP Dispatches an operator to investigate the loss of T-12 and performs applicable actions of QOA 6100-01, Loss of T-12.
SIMOP ROLE PLAY: The EO dispatched to T-12; Wait 5 minutes and then report that you cannot determine why T-12 tripped and that you have contacted OAD.
BOP May dispatch an EO to investigate the loss of Bus 13-1.
SIMOP ROLE PLAY: As the EO dispatched to Bus 13-1, wait 5 minutes and then report that Bus 13-1 is locked out on an overcurrent trip.
SRO Directs the BOP to crosstie Busses 18 and 19 per the Hard Card.
BOP When directed, crossties Busses 18 and 19 per the Hard Card.
BOP Verifies Bus 19 is energized.
BOP Opens Bus 13-1 to XFMR 18 GCB.
BOP Closes Busses 18 and 19 TIE BKR at Bus 18.
BOP Closes Busses 18 and 19 TIE BKR at Bus 19.
BOP Verifies both Busses 18 and 19 are energized.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 2 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior SIMOP: If RPS restoration is requested, Role Play as necessary. Wait 3 minutes and then use the following commands to restore RPS:
A RPS (normal power): irf 02r mg_set and irf r29r reset A RPS (alternate power): irf rp02r alt Then contact the Control Room to report completion of RPS restoration.
BOP May direct the EO to re-energize RPS A per QCOP 7000-01.
SIMOP: Verify the LOCA malfunction goes active 3 minutes after loss of T12:
imf rr10a 0.13 7:30 (Recirc Suction Line LOCA at 0.13% severity on a 7.5 minute ramp)
BOP Responds to annunciator 901-3, A-16, PRI CNMT HIGH PRESSURE.
SRO Enters and directs QCOA 0201-01 and sets scram criteria.
SRO/ATC Notifies Radiation Protection of elevated containment pressure.
SRO/BOP May make a PA announcement to evacuate the Reactor Building.
Manually scrams the reactor and Places RX MODE switch to ATC SHUTDOWN position.
SRO Directs ATC to Perform QCGP 2-3.
ATC Verifies all Control Rods are fully inserted.
ATC Verifies the SDV vent and drain valves are closed.
QGA 100 ATC When RPV Water Level lowers to less than 0 inches, notifies the US of the QGA 100 entry.
SRO Enters and directs QGA 100 actions (actions in the steps listed below).
SRO Directs ATC/BOP to verify 0 inches isolations and auto-starts.
ATC/BOP Verifies Group 2 Isolation (Containment Auxiliaries).
ATC/BOP Verifies Group 3 Isolation (RWCU).
ATC/BOP Verifies RB vent isolation and SBGT start.
ATC Stabilize RPV Pressure less than 1060 psig with ADS valves.
SRO Directs RPV Water Level be maintained 0 inches to 48 inches with high pressure systems and directs a pressure band.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 3 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior ATC (CONTINUOUS) Monitors and maintains RPV water level using high pressure systems.
ATC (CONTINUOUS) Maintains RPV pressure within the directed pressure band.
Station Blackout BOP Reports the failure of the U1 EDG to start.
BOP Attempts to start U1 EDG from panel 901-8.
SRO/BOP Verifies applicable actions of QCOA 6100-03, Loss of Offsite Power, have been performed.
BOP Dispatches an operator to attempt to start U1 EDG locally.
SIMOP ROLE PLAY: The EO dispatched to the U1 EDG; Wait 3 minutes then report that the U1 EDG is cranking but not starting and it has used up most of its starting air. Mechanical Maintenance has been contacted and they are on the way.
If dispatched as an EO to Bus 14-1, wait 2 minutes and report no flags are up and supply breakers are tripped.
SRO/BOP If Bus 14-1 is not energized and power is available from a non-EDG source on Unit 2, attempt to re-energize the bus per QCOP 6500-08, 4KV Bus Crosstie Operation.
BOP Attempt to crosstie Bus 14-1 to Bus 24-1 as follows:
BOP Take the following Control Switches to PTL:
o U1 EDG to Bus 14-1 GCB o Bus 14-1 & Bus 61 Tie Breaker o Busses 14 and 14-1 Tie GCB o 1B Core Spray Pump o 1C & 1D RHR Pump BOP Request U2 to close the Bus 24-1 to Bus 14-1 Tie Breaker.
SIMOP: Role Play as necessary and use the following Remote function to close the tie breaker between bus 24-1 and 14-1 and then report that it has been closed: irf ed34r close NOTE: This Remote Function is necessary to provide correct indications on Unit 1. However, (Setup) Malfunction ed04k will prevent Bus 14-1 to Bus 24-1 crosstie on Unit 1.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 4 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior BOP Place Synch Switch to ON for Bus 14-1 and Bus 24-1 Tie Breaker.
BOP Attempt to close Bus 14-1 and Bus 24-1 Tie Breaker and recognize the failure.
BOP Inform the Unit supervisor of the Bus 14-1 failure.
SRO/BOP Evaluate status. If Unit is Blacked Out, exit QCOA 6100-03 and perform QCOA 6100-04 Station Blackout.
CT1 SRO Direct starting and loading of the SBO Diesel per the Hard Card to Bus 14-1.
CT1 BOP When directed, energizes Bus 14-1 from the SBO DG per QCOP 6620-14 Hard Card.
BOP Places or verifies the following control switches PTL:
o U1 Diesel Gen to Bus 14-1 GCB o Busses 14-1 and 24-1 Tie GCB o Busses 14 and 14-1 Tie GCB o Bus 13-1 & Bus 61 Tie Breaker o 1B Core Spray Pump o 1C RHR Pump o 1D RHR Pump BOP Place the SBO DG 1 Mode Switch in SBO mode.
BOP Momentarily place SBO DG 1 C/S to START.
BOP Verify Voltage 3900-4580, Freq 58.8-61.2, RPM 900.
BOP Close the DG BKR on the DCS screen.
BOP Close the Bus 14-1 & Bus 61 Tie Breaker.
BOP Close Bus 14-1 Feed from the DCS Screen.
BOP Verify Busses 14-1 and 19 are energized.
BOP Remove ECCS pumps from PTL as directed by the Unit Supervisor, allowing 5 seconds between starts.
BOP Verify proper DCS Panel indications for SBO operation.
SRO May direct the BOP to Backfeed Bus 14 from Bus 14-1.
Note: If buses 18 and 19 were previously crosstied, buses 18 and 19 will be energized when the SBO powers bus 14-1.
SRO May direct the BOP to crosstie Busses 18 and 19 per the Hard Card.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 5 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior BOP May crosstie Busses 18 and 19 per the Hard Card.
BOP Verifies Bus 19 is energized.
BOP Opens Bus 13-1 to XFMR 18 GCB.
BOP Closes Busses 18 and 19 TIE BKR at Bus 18.
BOP Closes Busses 18 and 19 TIE BKR at Bus 19.
BOP Verifies both Busses 18 and 19 are energized.
BOP If directed to backfeed Bus 14:
BOP Place 1B Service Water Pump control switch in PTL.
BOP Place 1C & 1D Condensate Pump control switches in PTL.
BOP Place SYNCHROSCOPE switch for BUSSES 14 AND 14-1 TIE GCB to ON.
BOP Close BUSSES 14 AND 14-1 TIE GCB.
BOP Verifies BUS 14 is energized.
BOP Place SYNCHROSCOPE switch for BUSSES 14 AND 14-1 TIE GCB to OFF.
BOP May direct the EO to re-energize RPS A and RPS B Busses per QCOP 7000-01.
SIMOP: If RPS restoration is requested, Role Play as necessary. Wait 3 minutes and then use the following commands to restore RPS:
A RPS: irf 02r mg_set and irf r29r reset B RPS: irf 03r mg_set and irf r28r reset Then contact the Control Room to report completion of RPS restoration.
SRO May direct the BOP to re-energize Bus 16 and/or Bus 17 per the Hard Card.
BOP When directed, re-energizes Bus 16 per the Hard Card.
BOP Closes the Bus 14 to XFMR 16 GCB.
BOP When directed, re-energizes Bus 17 per the Hard Card.
BOP Closes the Bus 14 to XFMR 17 GCB.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 7 Page 6 of 6 Event
Description:
Station Blackout / Loss of T12 and Bus 13-1 Time Position Applicants Actions or Behavior SRO May direct the BOP to re-energize Bus 15 from Bus 16 or Bus 17 per the Hard Card.
BOP When directed, re-energizes Bus 15 per the Hard Card.
BOP Verifies open transformer main feed to Bus 15.
BOP Verifies open Bus 15 to Bus 17 and Bus 15 to Bus 16 crosstie breakers.
BOP Closes Bus 16 or Bus 17 to Bus 15 crosstie breaker.
End of Event 7 Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 8 Page 1 of 5 Event
Description:
LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior QGA 200 ATC/BOP Reports Drywell pressure above 2.5 psig.
SRO Re-enters QGA 100 and enters QGA 200 on high drywell pressure.
SRO Directs BOP/ATC to verify 2.5 psig isolations/actuations.
BOP/ATC Verifies 2.5 psig isolations/actuations.
ATC/BOP Verifies Core Spray and RHR running when power is restored.
SRO Directs QGA 100 RPV Control actions (actions in steps below).
CT2 SRO Directs ATC to maintain RPV water level with high pressure systems.
CT2 ATC Maintains RPV water level with high pressure systems.
ATC/BOP Attempts to inject with HPCI by removing HPCI from trip-latch.
ATC/BOP Recognizes and reports to US that the HPCI Initiation has failed (Aux Oil Pump lockout).
ATC/BOP Dispatches an EO to troubleshoot HPCI and/or the Aux Oil Pump breaker.
SIMOP: If requested to troubleshoot HPCI failure to start, Role Play as necessary. Wait until the SBO Diesel is providing power and at least 2 minutes, then delete malfunction dmf hp08 and report that the Aux Oil Pump Breaker is reset.
ATC When Aux Oil Pump is restored, restarts HPCI.
If necessary, depresses the HPCI TURB TRIP RESET ATC pushbutton.
Depresses the HPCI MANUAL INITIATION pushbutton and/or ATC verifies HPCI Auto Start .
ATC Adjust HPCI Flow Controller in Manual or AUTO as necessary.
ATC May place HPCI in Trip-Latch if HPCI makeup is unnecessary.
ATC Starts RCIC per QCOP 1300-02.
Depresses the RCIC MANUAL INITIATION pushbutton for at least 30 ATC seconds and recognizes the failure to start.
ATC Responds to Annunciator 901-4 G-15.
ATC/BOP Dispatches an EO to investigate the Trip Throttle Valve failure.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 8 Page 2 of 5 Event
Description:
LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: As the EO dispatched to RCIC: Wait 2 minutes and then report that the RCIC Trip Throttle overspeed mechanism will not reset.
Directs ATC to stabilize RPV Pressure with ADS valves (following SRO LOOP event).
ATC Stabilizes RPV Pressure with ADS valves as directed.
SRO If RPV water level cannot be maintained greater than -59 inches directs ADS inhibited.
BOP/ATC When directed, inhibits ADS.
ATC/BOP May start SSMP per QCOP 2900-02.
Switches power supply to Bus 24-1.
Verify CLOSED the RESERVE FEED CONTROL from Bus 24-1 to Bus 31, GCB 151-2425.
OPEN the NORMAL FEED CONTROL from Bus 14-1 to Bus 31, ACB 151-3101.
CLOSE the RESERVE FEED CONTROL from Bus 24-1 to Bus 31, ACB 151-3102.
Verify Pump suction pressure is available.
OPEN MOV 1/2-2901-7, Throttled Test Valve.
Start the SSMP.
Verify increasing Pump Discharge Pressure.
Place the FCV in AUTO.
Slowly increase flow controller setpoint to 400 gpm.
OPEN MOV 1-2901-8, U1 Reactor Supply Valve.
CLOSE MOV 1/2-2901-7, Throttled Test Valve.
Directs and Equipment Operator to close the Service Water to SSMP Room Cooler Bypass, 1/2-2999-9.
SIMOP ROLE PLAY: As Equipment Operator dispatched to close 1/2-2999-9. After 5 minutes, report that 1/2-2999-9 is CLOSED.
LEAD EVALUATOR/SIMOP: If requested to silence the vacuum breaker alarms, run batch file bat SV to silence alarms and inform the requestor.
SRO May direct use of alternate injection systems.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 8 Page 3 of 5 Event
Description:
LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior May restart the B CRD Pump per QCAN 901-5 B-2 (After power is ATC restored).
ATC Close the Pump Discharge Valve MO 1-301-2A/B.
ATC Start the available CRD Pump.
ATC Throttle open the Pump Discharge Valve MO 1-301-2A/B.
ATC May start available SBLC pump.
EVALUATOR NOTE: The QGA 200 actions will most likely be taken after power has been restored with the SBO Diesel.
(Continuous) Monitors and reports Primary Containment Parameters BOP and trends.
SRO/BOP May dispatch an EO to Aux Electric Room to 2201-5 rack to monitor Reactor water level and Drywell Pressure during the Station Blackout.
Directs the actions of QGA 200 PRIMARY CONTAINMENT CONTROL SRO (actions in the steps below).
SRO Verifies Torus Water level less than 27 ft.
SRO May direct BOP/ATC to monitor SBO loading.
BOP/ATC Monitor SBO loading as directed.
SRO Directs BOP to initiate Torus Sprays.
BOP Uses QCOP 1000-30 to Start RHR.
BOP Takes the available RHR Pumps out of PTL.
Places the Containment Cooling Permissive Switch 17 to ON BOP for the B RHR Loop.
Places the RHR SW Start Permissive Switch 19 to MANUAL BOP OVERRIDE for the B RHR Loop.
BOP Starts Torus Spray.
BOP Opens Torus Test or Spray Valve, MO 1-1001-34B.
BOP Opens Torus Spray Shutoff Valve, MO 1-1001-37B.
Throttles Torus H2O Test Valve MO 1-1001-36B to establish BOP RHR Discharge Pressure of 100-250 psig.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 8 Page 4 of 5 Event
Description:
LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior BOP (If power is restored) Uses QCOP 1000-30 to start RHR Service Water.
Opens The available RHR HX SW Discharge Valve BOP MO 1-1001-5B to approximately 40%.
BOP Starts 1C/D RHR SW Pump(s).
Adjusts MO 1-1001-5B to maintain RHR SW Pressure 15-20 BOP psig higher than RHR and less than 3600 gpm per pump.
BOP Throttles RHR HX Bypass Valve MO 1-1001-16B as necessary.
Verifies Torus level less than 17 ft. and inside DW Spray Initiation Limit SRO curve.
SRO Verifies Recirc pumps and DW coolers tripped.
SRO Directs BOP to initiate DW Sprays.
BOP Initiates Drywell Sprays.
Opens Outboard Spray Isolation, MO 1-1001-23B.
Opens Inboard Spray Isolation, MO 1-1001-26B.
Opens Torus Test or Spray Valve, MO 1-1001-34B.
Adjusts Torus H2O Test Valve MO 1-1001-36B to maintain RHR Discharge Pressure 100-250 psig and RHR SW Pressure 15-20 psig higher than RHR pressure.
SRO May Direct Torus Cooling initiation.
BOP Starts Torus Cooling as directed.
Opens Torus Test or Spray Valve, MO 1-1001-34B.
Opens Torus H2O Test Valve, MO 1-1001-36B.
Adjusts Torus H2O Test Valve MO 1-1001-36B to maintain RHR SW Pressure 15-20 psig higher than RHR pressure and RHR pressure between 100 and 250 psig.
Closes MO 1-1001-16B.
Quad Cities 2014 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 1 Event No.: 8 Page 5 of 5 Event
Description:
LOCA in the Drywell / Initial Actions Time Position Applicants Actions or Behavior (Continuous) Monitors Torus Water level and, if less than -2 inches, BOP notifies US of QGA entry.
SRO If Torus Water Level lowers to less than -2 inches, re-enters QGA 200.
End of Event 8 SIMOP: When Drywell sprays have been initiated and RPV Water level has been restored or as directed by the Lead Evaluator, place the simulator in FREEZE.
(Final)