Text

302 Final Simulator Scenarios
	ML090270043
Person / Time
Site:	Brunswick
Issue date:	11/10/2008
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-324/08-302, 50-325/08-302
	Download: ML090270043 (136)
	v • d • e

Final Submittal (Blue Paper)

FINAL SIMULATOR SCENARIOS

Brunswick 2008 NRC Scenario 1 Page 10(34 Facility: BRUNSWICK Scenario No.: 1 Op Test No.: Final Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is operating at 100% power, End of Cycle.

No equipment is out of service Turnover: Following shift turnover, Reduce power and place the 2C Condensate Pump in service and remove the 2A Condensate Pump. The 2A Condensate pump is experiencing high vibrations and will be placed under clearance by the WCC for maintenance.

Critical Task: See Scenario Summary Event Malf. No. Event Event Description No. Type*

1 N/A R-SRO Reduce power to <92% power in order to swap Condensate Pumps.

R-RO 2 N/A N-SRO Swap Condensate Pumps per 20P-32 section 8.5.

N-BOP 3 EE030M C-SRO 2XB power failure. (TS) 4 IAFWATRP C-SRO RFP trip with failure of Limiter #2 C-RO 5 K4522A Off C-BOP RBCCW Shaft shear with failure of standby to auto start C-SRO 6 MS031F I-BOP MTLO controller failure I-SRO 7 MS017F M-ALL Turbine high vibration requiring turbine trip and scram resulting in an ATWS condition requiring entry to LPC.

8 K5416A Off C-ALL EHC pump trip and failure of standby pump causing bypass valve failure.

9 K2119A Off C-RO SLC pumps will not start due to switch failure. (TS)

C-SRO 10 RD036F C-RO Scram discharge volume drains fail closed.

C-SRO 11 K1208A Off C-BOP .E11-F024A will initially trip on thermal overload when opened.

C-SRO

Brunswick 2008 NRC Scenario 1 Page 2 of 34 SCENARIO DESCRIPTION Unit 2 is operating at maximum power, End Of Cycle.

Event 1 - Direction in the turnover has the crew remove the A condensate pump from service which requires a power reduction to less than 92% power in accordance with ENP-24.

Event 2 - Swap condensate pumps in accordance with 20P-32.

Event 3 - 2XB will fail. The crew will respond per APPs and refer to TS to declare RHR BLoop inoperable (3.5.1 Action A) and PCIV's 3.6.1.3 Action A (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affect flowpath) and B (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to isolate the affected flowpath).

Event 4 - Reactor Feed Pump will trip with a failure to runback to limiter #2. Crew should enter AOP-23. Immediate operator action to reduce Recirc controllers to 40% if a RFP trips and a run back does not occur.

Event 5 - The A RBCCW pump shaft will shear with the standby pump failing to auto start. AOP-16 should be entered and the standby pump started to recover system pressure.

Event 6/7/8 - The main turbine lube oil controller will fail closed causing the lube oil to heat up and vibrations to occur on the main turbine. This will require the main turbine to be tripped (>12 mils on bearing 1-8 and >10 mils on bearings 9/10) and the reactor to be scrammed. Most control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-LPC.

When the scram occurs, the running EHC pump will trip and the standby EHC pump will also trip thus causing a failure of bypass valves.

Event 9 - When SLC initiation is attempted, neither SLC pump will start due to switch failure.

The crew will enter LEP-03 and align for alternate boron injection using CRD.

Event 10 - When scram jumpers are installed the scram discharge vents and drains will fail to open which will result in inability to insert control rods by resetting RPS and inserting additional manual scrams.

Event 11 - Suppression pool temperature will rise requiring entry into EOP-02-PCCP and lowering water level per LPC Table 3. When RPV level is lowered to TAF, reactor power will still be above the APRM downscale set point. Suppression pool cooling is required due to elevated suppression pool temperature. Suppression pool cooling is limited to RHR A. The E11-F024A will initially trip on thermal overload when opened. If the crew requests, the thermal overload can be reset and the valve can then be opened, after actions are taken to reduce reactor pressure.

Event 12 - When level has been lowered and injection re-established, the scram discharge volume vents and drains will be repaired. Control rods can then be inserted by manual scram.

When level is restored above TAF, RHR Loop A can be placed in suppression pool cooling.

When all control rods are inserted and suppression pool cooling initiated, the scenario may be terminated.

Brunswick 2008 NRC Scenario 1 Page 3 0'34 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2008 NRC EXAM SCENARIO #1

Brunswick 2008 NRC Scenario 1 Page 4 of 34 Simulator Setup Initial Conditions:

IC ENP-24 for IC 14 Rx Power 100%

Core Age EOC Events*

Event # Trigger Description 1 NA Reduce power from 100% to 92% using recirc 2 1 Manual Swap Condensate pumps (Start 2C, Secure 2A).

3 2 Manual 2XB power failure 4 3 Manual RFPA trip 5 4 Manual RBCCW pump trip 6 5 Manual MTLO controller failure Turbine high vibration causing the crew to scram the plant with an 7 6 Auto ATWS condition 8 7 Auto EHC pump trip with failure of standby to auto start 9 NA SLC switch failure 10 7 Auto Scram Discharge Vents and Drains fail closed 11 8 Auto Thermal overload on RHR 24 valve 12 NA ED I Depressurize the Reactor 16 Auto RCC Pump 2C to on 17 Auto RCC Pump 2A to off Malfunctions Summary MS017F 4 Turbine Bearing Vibration 0 S Smin 60n MS017F S Turbine Bearing Vibration 0 S Smin UA231 60n MS017F 6 Turbine Bearing Vibration 0 S Smin UA231-6 MSOO8F RPOOSF Auto Scram Defeat False True 13

Brunswick 2008 NRC Scenario 1 Page 5 0'34 Remotes Summary Mult. Current Target Remote 10 Description Trig 10 Value Value LOCA Load Shed Sel Sw, 2C Condensate EE_LSHED3 Enabled Disabled 1 Pump Unit Trip Load Shed Sel Sw, 2C EE_UTSHED3 Enabled Disabled 1 Condensate Pump RH ZVRH24AT E11-F024A Full Flow Test ON OFF 8 LOCA Load Shed Sel Sw, 2A Condensate EE_LSHED1 Disabled Enabled 10 Pump Unit Trip Load Shed Sel Sw, 2A EE_UTSHED1 Disabled Enabled 10 Condensate Pump EP IAEOPJP1 Bypass LL3 Group I Isol Off On 12 MS VMS5005D MVD-5005 Mn Stm Drn Hdr Isolation 0 1 14 EP IACS993U OW CLR A&D Overide - Normal/Run Normal Run 15 EP IACS994U OW CLR B&C Overide - Normal/Run Normal Run 15 EP IASW5997 SW-V106 LOCA Override Normal Bypass 15 EP IASW5998 SW-V103 LOCA Override Normal Bypass 15 CF IAFWATRP Local RFP A Trip Normal Tripped 3 SWIC't hes S ummary Target Override Switch 10 Description Trig Position Value K4521 A RBCCW Pmp B Auto Auto Off 4 Q4521LG4 RBCCW Pmp B Off G Off Off Q4521RR4 RBCCW Pmp B On R On On K4522A RBCCW Pmp C Auto Auto Off 78 over 5 G4H12G14 RBCCW Disch Pressure 78 16 on starting RCC 2C seconds 7 on Scram button A K5416A Hyd Fluid Pmp A HFPM-A Off On (K2501A=True) 7 on Scram button A K5416A Hyd Fluid Pmp A HFPM-A Auto Off JK2501A=True) 7 on Scram button A K5416A Hyd Fluid Pmp A HFPM-A On Off (K2501A=True) 7 on Scram button A K5417A Hyd Fluid Pmp A HFPM-B Off On (K2501A=True) 7 on Scram button A K5417A Hyd Fluid Pmp A HFPM-B Auto Off (K2501 A=True) 7 on Scram button A K5417A Hyd Fluid Pmp A HFPM-B On Off (K2501A=True)

~1j9A 's~a;ljtfPlirnl'.A~a . "~' *. ; ,; 'Sfop On ' ; ,'. .'

\~1.1~A SIB LlQpump;,t\fB .'

PampA Off >

~1;1SA SIB J..jClPump;.4i~B, .... PUmpAB Off: ..*....... :.. .>

~1;19A SIB WQl?ump"'A'~B" ~/.; ;';$ '. ". PompB' Off" .' .'

.:: .. ,.' .'

Q~207LGN: Full flow..E11-F024 Grlen. .. On/Off '.

06"; .::/; '8/;i .":.; . i',

Gt1~O: ZRRN Full flowE11-F024 ,Red ': . ;,' <'N

... On/Off :()6~;; 8***** . !. "/ ;

Annunciators' Current Target Remote 10 Description Trig Value Value 8 on 24 valve to open A-01 5-9 RHR A Valves Overload Off On (Q1207RRN=True)

UA-32-5 RBCCW Pump Disch Header Press Lo Off Off 17 removed after 30 sec.

Special Instructions:

Load Scenario file, 2008 Scenario 1.scn, if required.

Ensure ENP-24 for IC-14 at P603 panel.

Brunswick 2008 NRC Scenario 1 Page 6 0(34 Shift Briefing Plant Status The plant is operating at -100% power, End of Cycle.

Equipment Out of Service No equipment is out of service Plan of the Day Following shift turnover, Reduce power to 92% and place the 2C Condensate Pump in service and remove the 2A Condensate Pump. The 2A Condensate pump is experiencing high vibrations and will be placed under clearance by the WCC for maintenance.

Brunswick 2008 NRC Scenario 1 Page 7 of 34 Scenario Information Critical Tasks (bolded/italicized in the required operator action statements)

Terminate and prevent HPCI/Feedwater during the ATWS (CS/RHR when LOCA signal received)

Direct LEP-03, Alternate Boron Injection, using CRD.

Perform LEP-02, Alternate Rod Insertion using RMCS.

Brunswick 2008 NRC Scenario 1 Page 8 of 34 EVENT 1 SHIFT TURNOVER, REDUCE POWER The crew will have to reduce power to less than or equal to 92% power.

Malfunctions required: None.

Objectives:

SCQ - Directs power to be reduced in order to swap Condensate Pumps.

RQ - Performs power reduction in accordance with ENP-24.

Success Path:

Power reduced to less than or equal to 92% power.

Simulator Operator Actions:

o If contacted as the NE for power reduction guidance, inform crew to use ENP-24.5 guidance.

o If contacted as the NE to monitor power reduction, inform crew that you will monitor core performance on the computer.

o If contacted as the Load Dispatcher, acknowledge report that Brunswick U2 will be lowering power.

o If contacted as the NE for guidance on operation above the MELL line, inform crew to take the appropriate actions per ENP-24.5 to get below or on the MELLL.

o When directed by the lead examiner, proceed to the next event.

Required Operator Actions Reactivity Manipulation - Reduce Power to 92% to be able to swap Condensate pumps.

SRQ Time Action Notes Directs power to be reduced in accordance with ENP-24.5 using recirculation flow in order to swap Condensate Pumps.

Directs RO to insert control rods to get below the MELL line.

Brunswick 2008 NRC Scenario 1 Page 9 of 34 EVENT 1 SHIFT TURNOVER, REDUCE POWER RO Time Action Notes ..

May reference 20P-02 section 7.1 Request peer checker / reactivity team.

Reduces power using ENP-24.5 using recirculation flow to 92% power.

Reduce flow on one RR Pump

(-2%) at a time to stay within mismatch criteria (3.5x10 6 Mlbs jet pump flow).

Continues alternating Recirc pump reductions until 92% power.

Verifies operation on the Power to Flow map.

Recognizes operation above the MELLL line and informs SCO.

Inserts control rods using ENP-24.5 to get below the MELLL line. (Should only need to insert one control rod 10-43)

Turns control rod power on.

Selects control rod (10-43) in accordance with ENP-24.5 sheet.

May also insert 42-43, 42-11, or 10-11. (in this order in order to establish a margin to the MELLL line)

Continuously drives selected rod in using RMCS.

BOP ITime IAction .

Monitor the plant.

I Notes

Brunswick 200B NRC Scenario 1 Page 100(34 EVENT 2 SWAP CONDENSATE PUMPS After power has been reduced to less than 92% the crew will swap condensate pumps.

Malfunctions required: None Objectives:

SCO - Directs starting of the 2C Condensate Pump and securing the 2A Condensate Pump.

BOP - Starts the 2C Condensate Pump and secures the 2A Condensate Pump.

Success Path:

2C condensate pump running and the 2A condensate pump shutdown.

Simulator Operator Actions:

D When contacted as RW to place an additional CFD and/or COD in service report that this had already been completed.

D If contacted as the TB AO report that the prestart checks for the 2C Condensate pump are complete.

D When contacted as the TB AO to disable the LOCA and Unit Trip Load Shed switches acknowledge request, initiate trigger 1 and inform control room that the LOCA Load Shed and Unit Trip Load Shed switches are disabled for the 2C Condensate pump.

D When contacted as the TB AO to enable the LOCA and Unit Trip Load Shed switches acknowledge request, initiate trigger 10 and inform control room that the LOCA Load Shed and Unit Trip Load Shed switches are enabled for the 2A Condensate pump.

D When contacted as the RW operator to secure CFD and/or COD from service, acknowledge the request.

D When directed by the lead examiner, proceed to the next event.

Required Operator Actions Normal Ops -Swap Condensate pumps in accordance with 20P-32 Section B.S.

SRO Time Action Notes Directs BOP to swap Condensate Pumps in accordance with 20P-32.

RO Time Action Notes Performs plant monitoring.

Brunswick 2008 NRC Scenario 1 Page 11 of34 EVENT 2 SWAP CONDENSATE PUMPS BOP Time Action Notes Swaps condensate pumps in accordance with 20P-32, Section 8.5.

Notifies RW operator to place an additional CFO in service.

Notifies RW operator to place an additional COO in service, if needed.

Notifies TB AO to perform prestart checks for the 2C Condensate pump (ensures proper motor oil level and motor cooling).

Place 2C condensate pump mode selector switch in MAN.

Notifies TB AO to place Unit Trip Load Shed and LOCA Load Shed selector switches to DISABLED for the 2C Condensate Pump.

Makes a PA announcement for starting 2C condensate Pump.

Starts the 2C Condensate Pump.

Observes discharge valve opens for the 2C Condensate Pump.

Observes condensate discharge pressure has stabilized.

Stops the 2A condensate Pump.

Places 2A condensate pump mode selector switch in AUTO.

Notifies TB AO to place Unit Trip Load Shed and LOCA Load Shed selector switches to ENABLED for the 2A Condensate Pump.

Brunswick 2008 NRC Scenario 1 Page 12 of 34 EVENT 2 SWAP CONDENSATE PUMPS BOP Continued Time Action N()tes Notifies RW operator to remove the additional CFO and/or COO from service.

Informs SCO that Attachment 8 needs to be completed.

Brunswick 2008 NRC Scenario 1 Page 130'34 EVENT 3 2XB POWER FAILURE The main feeder breaker to 2XB will trip. The crew will respond per APPs and refer to 001-50.4 to determine TS. Should declare RHR B Loop inoperable (3.5.1 Condition A), RHRSW BLoop Inop (3.7.1 Condition B), RHR BLoop SPC Inop (3.6.2.3 Condition A), PAM Instrumentation for PC IV Position Indication (Condition A - 30 days), PCIV's 3.6.1.3 Condition A (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affected flowpath that has one of two isolation valves Inop), Condition B (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to isolate the affected flowpath that has two out of two valves Inop), and Condition C (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affected flowpath that has one out of one valves Inop). Primary containment atmosphere particulate monitor (CAC-1260) will be lost per TRM 3.4 Condition A requires it to be restored in 31 days.

Malfunctions required:

2XB feeder breaker over current trip causing a loss of all loads on MCC 2XB.

Objectives:

SCO - Determine actions required for LCO per Technical Specifications.

Success Path:

Technical Specification / TRM

3.7.1, Declare One RHR SW subsystem Inop (Condition B, 7 days)

3.5.1, Declare RHR B Loop inoperable (Condition A, 7 days)

3.6.2.3, Declare One RHR SPC subsystem Inop (Condition A, 7 days)

TRM 3.4 One drywell radiation monitor inoperable (Condition A, 31 days)

3.3.3.1, PAM Instrumentation - PC IV Position Indication (Condition A - 30 days)

3.6.1.3, PCIV's

Condition A - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affect flowpath (E11-F024B, E11-F027B, E41-F079, E51-F066, and B32-V30). Valves F024 and 27 are closed.

Condition B-2 hours to isolate the affected flowpath (E11-F016B and F021 B).

Valves are closed.

Condition C - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affect flowpath (E 11-F007B, FO 11 B, F020B, and F103B). Valves F007, 11, and 103 are closed.

Simulator Operator Actions:

D Insert trigger 2 at the discretion of the lead evaluator.

D If contact as the RB AO, wait one minute and report that MCC 2XB looks normal except that there is no power at the MCC.

D If contacted as the Outside AO, report that the 480V MCC 2XB Feeder Breaker A02 at E8 is tripped on over current. (white trip flag protruding from the breaker)

D If contacted as Chemistry, wait two minutes and report that the CAC-1260 Analyzer has lost power.

D Acknowledge request as I&C to do troubleshooting/repair for the electrical failure.

D When directed by the lead examiner, proceed to the next event.

Brunswick 2008 NRC Scenario 1 Page 14 of 34 EVENT 3 2XB POWER FAILURE Required Operator Actions SRO Time Action Notes Refer to OOI-SO.4load list to assess effects of loss of MCC 2XB.

Direct IIC to investigate loss of MCC 2XB.

Refer to Tech Specs.

3.7.1, Declare One RHR SW subsystem Inop (Condition B, 7 days) 3.S.1, Declare RHR B Loop inoperable (Condition A, 7 days) 3.6.2.3, Declare One RHR SPC subsystem Inop (Condition A, 7 days)

TRM 3.4 One drywell radiation monitor inoperable (Condition A, 31 days) 3.3.3.1, PAM Instrumentation - PCIV Position Indication (Condition A -

30 days) 3.6.1.3, PC IV's

Condition A - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affect flowpath (E11-F024B, E11-F027B, E41-F079, ES1-F066, and B32-V30). Valves F024 and 27 are closed.

Condition B-2 hours to isolate the affected flowpath (E11-F016B and F021 B). Valves are closed.

Condition C - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the affect flowpath (E11-F007B, F011 B, F020B, and F103B).

Valves F007, 11, and 103 are closed.

Brunswick 2008 NRC Scenario 1 Page 15 of 34 EVENT 3 2XB POWER FAILURE RO IAction > I Not~

BOP Time Action Notes Report loss of MCC 2XB and refer to APPs.

2APP-UA-18 2-2, Sub E8 Fdr to MCC-2XB Bkr Trip 2APP-UA-25 1-8, Ctmt Atmos Rad Mon Dnsc/lnop Dispatch AO to investigate MCC 2XB condition.

Dispatch AO to investigate MCC 2XB feeder breaker at E8.

Brunswick 2008 NRC Scenario 1 Page 16 of 34 EVENT 4 REACTOR FEED PUMP TRIP WITH FAILURE TO RUNBACK Malfunctions Required:

Failure of Runback signal #2.

Trip of the A RFP Objectives:

SCO - Direct actions to respond To A Condensate/Feedwater System Failure Per AOP-23.

RO - Respond To A Condensate/Feedwater System Failure Per AOP-23.

Success Path:

The crew will respond per AOP and lower recirc pump speeds to 40%.

Simulator Operator Actions:

o At the discretion of the lead evaluator insert trigger 3 to trip the A RFP.

o If contacted as the AO to acknowledge local woodward alarms, wait 1 minute, acknowledge the local alarm.

o If contacted as I&C to investigate, acknowledge the request.

o When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Action Notes Direct Recirc to be lowered to maintain level. (If AOP immediate actions were not performed will direct recirc to be lowered to 40%)

Direct entry of OAOP-23, Condensate/Feedwater System Failures.

Direct entry of 2AOP-04.0, Low Core Flow.

Contact IIC for the RFP trip and Failure of Limiter #2.

Direct RO to insert rods per OENP-24.5 to get on or below the MELLL Line.

Direct chemistry to sample RCS activity due to power change greater than 15%.

Brunswick 2008 NRC Scenario 1 Page 170(34 EVENT 4 REACTOR FEED PUMP TRIP WITH FAILURE TO RUNBACK RO Time Action Notes Report level decreasing, but recovering.

Performs immediate operator action of OAOP-23,

Determines a runback signal did not occur

Reduces Recirc flow to 40% .

Inserts control rods using ENP-24 to get below the MELL line. (Will use rods from Group 1, 42-43, 42-11, and 10-11) Will continue with rods not inserted in the power reductions earlier.

Turns control rod power on.

Selects control rod (42-43) in accordance with ENP-24 sheet. May also insert 42-11 or 10-11. (in this order)

Continuously drives selected rod in using RMCS.

BOP Time Action .. Notes References 2APP-A-07 4-2, FW Ctl Sys Trbl Announce and enter AOP-23.

Announce and enter 2AOP-04.0.

Dispatch an AO to acknowledge the local alarm panel for the RFP (Woodward).

Dispatches personnel to determine the cause of the RFP trip.

Brunswick 2008 NRC Scenario 1 Page 18 of 34 EVENT 5 RBCCW PUMP TRIP Malfunctions Required:

Trip of the 2B ReC pump and override of lights.

Objectives:

SCO - Directs BOP to enter and execute OAOP-16.0: RBCCW System Failure BOP - Refers to 2-UA-3 2-5 and OAOP-16.0 to respond to the 2C Pump failure to start Success Path:

The A RCC pump shaft will shear and pressure will lower. C RCC Pump will fail to auto start and the low pressure alarm will be received. Starting the 2C RCC pump on will restore pressure to normal.

Simulator Operator Actions:

D At the discretion of the lead evaluator, initiate trigger 4 to shear the shaft on 2A RCC Pump. (trigger actually trips the 2B pump)

D If directed as the RB AO to investigate RCC low pressure, wait 2 minutes and report RCC Pump 2A appears to have a broken coupling. Motor is running but pump is not turning.

D If contacted as the RB AO, inform the control room prestart checks of the 2C RCC pump are complete.

D After the 2A pump is tripped delete override on the RCC pressure gauge.

D If directed to investigate as I&C acknowledge the request.

D When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Action Notes Directs BOP operator to enter Annunciator response and refers to OAOP-16.0.

Directs start of 2C RBCCW pump.

Directs Maintenance to investigate 2C RBCCW pump auto start failure.

Notifies Maintenance of 2A RBCCW Pump coupling failure.

Directs BOP to remove 2A RBCCW Pump from service.

Brunswick 2008 NRC Scenario 1 Page 19 of34 EVENT 5 RBCCW PUMP TRIP RO I Time IAction Plant Monitoring.

I Notes BOP Time Action Notes Manually starts 2C RBCCW Pump.

Refers to Annunciator Response 2-UA-3 2-5 (RBCCW Disch Header Press Lo).

May Reference OAOP-16.0 Dispatches AO to investigate cause of RBCCW low pressure.

Places 2A RBCCW Pump switch to OFF.

Verifies RBCCW System is operating normally.

Brunswick 2008 NRC Scenario 1 Page 20 of34 EVENT 617 MTLO CONTROLLER FAILURE/TURBINE VIBRATIONS HIGH Malfunctions Required:

Main Turbine lube oil cooler controller fails closed. When high temperature alarm annunciates activate trigger to accelerate turbine vibrations.

Objectives:

Respond to an abnormal turbine vibration per UA-23 6-1 and UA-23 6-3.

Success Path:

The MTLO controller on XU-2 indicates 100% output (full closed) and turbine lube oil temperature will rise. Dispatch AO and I&C to investigate.

Simulator Operator Actions:

o At the discretion of the lead evaluator, insert trigger 5 to fail the MTLO controller closed.

o If asked as the TB AO to investigate, report that the temperature control valve to the MTLO is closed. (There is no bypass valve).

o If asked as I&C to investigate acknowledge the request.

o When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Action Notes Direct actions of APP's, UA-236-1 and UA-236-3.

When vibrations rise to above the TSI setpoint, direct manual scram and turbine trip per the vibration APP. (As conservative decision making may insert before setpoint).

RO Time Action Notes Plant Monitoring .

When directed by the SRO, insert a manual scram and trip the main turbine.

Recognize and report an ATWS.

Brunswick 2008 NRC Scenario 1 Page 210'34 EVENT 617 MTLO CONTROLLER FAILURE/TURBINE VIBRATIONS HIGH BOP Time Action Notes ..

Recognize and report rising lube oil temperatures.

Dispatch TB AO to investigate TCV.

Perform actions of APPs 2APP-UA-23 1-6, Turb or RFP Brg Temp High 2APP-UA-23 6-1, Turb or RFP Vibration High Monitor turbine bearing temperatures and vibrations (PC display 630).

May place the Main Turbine Lube Oil controller in manual and attempt to operate the valve.

Recognize failure of the bypass valves on the scram.

Brunswick 2008 NRC Scenario 1 Page 22 of 34 EVENT 8/9 ATWS ACTIONS Malfunctions Required:

EHC pump trips with a failure of the standby pump which causes bypass valve failure, Scram discharge volume vents and drain fail closed on the scram, SLC switch is failed in the off position.

Objectives:

SCO - Direct actions for a reactor scram with MSIV's closed per EOP-01-RSP.

Direct actions to control reactor power per EOP-01-LPC.

RO/BOP - Perform immediate actions for a reactor scram.

Control reactor pressure during an ATWS per EOP-01-LPC.

Success Path:

Controls reactor pressure using the SRV's. Performs actions of LPC, recognizes failure of SLC and performs alternate boron injection.

Simulator Operator Actions:

D If crew does not trip the main turbine by the time SLC initiation is directed, initiate trigger 9 to trip the main turbine.

D If requested to perform alternate boron injection using CRD, acknowledge the request. (boron will not be injected during this scenario)

D Acknowledge request as I&C to investigate failure of EHC pumps.

D Acknowledge request as I&C to investigate failure of SLC.

D When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Action Notes Enter RSP and transition to LPC.

Direct mode switch to shutdown when steam flow < 3 Mlbs/hr.

Direct use of SRV's to stabilize, then control pressure (800 - 1000#).

Direct ARI initiation.

Direct Recirc Pump speeds reduced to 10%.

Direct Recirc Pumps Tripped.

Brunswick 2008 NRC Scenario 1 Page 23 of 34 EVENT 8/9 ATWS ACTIONS SRO Continued Time Action Notes Direct SLC initiation.

Direct LEP-03, Alternate boron injection.

Direct ADS inhibited.

Direct RWCU isolation.

Direct LEP-02, Alternate Rod Insertion.

Follow-up question for the SRO:

Determine initial SLC TS LCO for the A TWS conditions:

3.1 .7 - with two pum ps inoperable in Mode 1 or 2, restore to operable status in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in Mode 3 in the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

BOP Time Action Notes Operates SRV's to stabilize, then control pressure (800 - 1000#).

Places ADS in inhibit.

Isolates RWCU.

Closes RWCU Outboard Isol Valve G31-F004.

Brunswick 2008 NRC Scenario 1 Page 24 of 34 EVENT 8/9 A TWS ACTIONS RO Time Action Notes Place mode switch to shutdown when steam flow < 3x10 6 Ib/hr.

Initiates ARI.

Places Recirc Pump speeds reduced to 10%.

Trips Recirc Pumps.

Initiates SLC.

Recognizes failure of SLC and reports to SCO.

Performs LEP-03, Alternate Boron Injection.

Direct AO to perform LEP-03, Section 1, Alternate Boron Injection using CRD.

Performs LEP-02, Alternate Rod Insertion. (RMCS Section)

Insert IRMs.

When < range 3 on IRMs insert SRMs.

Start both CRD pumps.

Place CRD Flow Controller to Manual.

Throttle open flow controller to establish ~ 260 drive water psid.

Bypass RWM.

Brunswick 2008 NRC Scenario 1 Page 25 0(34 EVENT 8/9 ATWS ACTIONS RO Actions Continued Time Action Notes ..

Selects control rods and drives in using Emerg rod in notch override.

Performs alternate rod insertion per LEP-02 Section 3.

Request jumpers for LEP-02 Section 3.

Brunswick 2008 NRC Scenario 1 Page 26 of 34 EVENT 10/11 A TWS ACTIONS - CONTINUED Objectives:

SCO - Direct actions to lower reactor vessel level when the conditions of Table 3 are met per EOP-01-lPC.

RO/BOP - Control reactor level during an ATWS per EOP-01 lPC.

Start up RHR in Suppression Pool Cooling mode per OP-17.

Success Path:

Continues actions in the lPC procedure, terminate and prevent injection, drive rods using RMCS. Establish suppression pool cooling.

Simulator Operator Actions:

o If requested to defeat Group I ll3, wait 2 minutes, initiate trigger 12 and inform the SCO that the jumpers are installed.

o If requested to install lEP-02, Section 3 jumpers, wait 5 minutes, insert trigger 13 and inform the SCO that the jumpers are installed.

o If requested as I&C to investigate the failure of the scram discharge volume vents and drains, acknowledge the request.

o If requested to open the MVD-5005, wait 5 minutes, initiate trigger 14 and inform the control room that the valve is open.

o If requested to defeat Drywell Cooler lOCA lockout, wait three minutes, initiate trigger 15 and inform the SCO that the jumpers are installed.

o If directed as the AD to investigate the E11-F048A breaker, wait until reactor pressure is being lowered because of HCTl and then report nothing appears wrong at the breaker except that the position indicating lights are off.

o If requested as maintenance to inspect the E11-F024A valve, wait until reactor pressure is being lowered because of HCTl and report it is tripped on thermals.

o If directed as the AD/Maintenance to attempt to reset the thermals for the E11-F024A, then delete the following commands:

o Malfunction - E11-F048A Full Flow Test o Lights - Red and Green lights for E11-F024A o Annunciator - RHR Valves Overload o When directed by the lead examiner, proceed to the next event.

Brunswick 2008 NRC Scenario 1 Page 27 of 34 EVENT 10/11 ATWS ACTIONS - CONTINUED Required Operator Actions SRO Time Action Notes Direct Group 10 switches to override reset.

Direct terminate and prevent HPCIIFeedwater (CSIRHR when LOCA signal received).

When level reaches +90 inches, evaluate Table 3:

If not met, establishes a level band of LL4 to +90 inches.

When met, direct injection be or remain terminated.

When Suppression Pool is greater than 95° F, enters PCCP and directs Suppression Pool Cooling.

Directs Drywell cooling restored per SEP-10.

Evaluate T AF and LL4 indicated levels using Caution 1 graphs.

Direct injection established to maintain RPV level LL4 to TAF (or the level at which APRMs indicate downscale)

Direct attempt to reset breaker for E11-F024A valve.

Brunswick 2008 NRC Scenario 1 Page 28 0'34 EVENT 10/11 ATWS ACTIONS* CONTINUED RO Time Action Notes Continues to select control rods and drive in using Emerg rod in notch override.

Monitor APRMs for downscale.

Performs LEP-02 Section 3 after jumpers are installed.

InhibitARI Places ARI Initiation Switch to INOP Places ARI Reset Switch to RESET and maintains for 5 seconds.

Verifies red TRIP light above ARI Initiation is OFF Reset RPS when scram jumpers installed.

Ensures Dish Vol Vent & Drain Test switch is in Isolate.

Confirms Disch Vol Vent Valves V139 and CV-F010 are closed Confirms Disch Vol Drain valves V140 and CV-F011 are closed.

Resets RPS.

Place Disch Vol Vent & Drain Test switch to Normal Recognizelreport failure of scram discharge volume vents and drains.

Brunswick 2008 NRC Scenario 1 Page 29 of 34 EVENT 10/11 ATWS ACTIONS - CONTINUED BOP Time Action Notes Places Group 10 switches to override I reset Terminate and prevent injection to RPV.

Places HPCI Aux Oil Pump to Pull to Lock.

May trip the RFPs OR May adjust discharge pressure of pump down to prevent injection.

Closes FW-V6 and VB.

Opens FW-V10.

Ensures MSTR RFPT SPIRX L VL CTL in manual and SULCV closed.

Turns OFF low pressure ECCS pumps if they start.

Continue to control RPV pressure using SRV's, steam line drains.

Brunswick 2008 NRC Scenario 1 Page 30 of 34 EVENT 10/11 ATWS ACTIONS - CONTINUED BOP Continued Places suppression pool cooling in service on A Loop.

Opens SW-V101.

Closes SW-V143.

May verify adequate suction source and start a CSW Pump.

Starts RHR SW Pump(s)

Adjusts E11-PDV-F068A to achieve

-4000 gpm per RHR SW pump running.

Supplies cooling water to vital header ensures open either SW-V111 or SW-V117.

Operates THINK switch to make up spray logic.

Starts RHR pump Attempts to open E11-F028A.

Recognizes/reports failure of E11-F024A.

2APP-A-01 5-9, RHR A Valves Overload May direct AO to reset the thermals for the E11-F024A breaker.

When reset, throttles open E11-F024A (establishes flow in green band for 1 pump or ~11500 gpm for 2 pump operation)

Closes E11-F048A.

Brunswick 2008 NRC Scenario 1 Page 310'34 EVENT 10/11 ATWS ACTIONS* CONTINUED BOP Continued Places HPCI in service for level control during ATWS when directed by the SCO.

Place HPCI in manual (M) and adjust output demand to approximately 40% using the manual lever.

Adjust HPCI setpoint to approximately 1000 GPM.

Start auxiliary oil pump.

When HPCI turbine speed stops increasing, then raise HPCI pump flow to approximately 1000 GPM using the manual lever on HPCI.

Ensure E41-F012 is closed when flow has increased above 800 GPM.

Transfer HPCI from Manual (M) TO Auto (A).

Adjust HPCI setpoint to maintain desired reactor water level

Brunswick 2008 NRC Scenario 1 Page 32 0'34 EVENT 12 ALL RODS IN Malfunctions Required:

Success Path:

When actions are taken to control reactor water level during the ATWS after terminating and preventing, the SDV vents and drains will be repaired and rods can be inserted.

When all rods are inserted and level is being controlled above TAF the scenario may be terminated.

Simulator Operator Actions:

o When directed by the lead evaluator, delete the following commands:

o Malfunction - RD036F, Scram Disc Vol Drn Fails Closed o Malfunction - RP010F, ATWS 3 (Make sure RPS is reset before deleting)

Inform the SCO that a loose wire was found on the SDV vent and drain logic and have been fixed.

o If contacted as the RB AO, acknowledge request to secure Alternate Boron Injection.

o When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Action Notes Exit LPC and enter RVCP when all rods are in.

Direct securing Alternate Boron Injection.

Direct level restored to 170 - 200 inches after rods are all in.

RO Time Action Notes Continues to drive rods using RMCS Confirms Disch Vol Vent & Drains are open when reported fixed.

Inserts a scram after discharge volume has drained for -2 minutes.

Reports all rods in.

Directs AO to secure Alternate Boron Injection.

Brunswick 2008 NRC Scenario 1 Page 33 of 34 EVENT 12 ALL RODS IN BOP Time Action Notes Maintains reactor pressure as determined by the SCQ.

Maintains level as directed by the SCO.

Restores level to 170 - 200 inches after all rod inserted.

Increases RCIC controller to 500 gpm.

Increases HPCI controller to raise reactor water level.

Brunswick 2008 NRC Scenario 1 Page 34 of 34 Simulator Operator Activities:

WHEN directed by the lead examiner, place the simulator in FREEZE.

CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER

Facility: BRUNSWICK Scenario No.: 2 Op Test No.: Final Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is operating at 100% power, Middle of Cycle.

APRM 2 is INOP and Bypassed.

Turnover: Transfer 2A SJAE Train to FULL LOAD and secure 2B SJAE Train lAW 20P-30.

Event Malf. No. Event Event Description No. Type*

1 N/A N-SRO Transfer 2A SJAE Train to FULL LOAD, secure 2B SJAE Train N-BOP 2 NI032F I-SRO APRM 3 fails downscale (TS)

I-RO 3 CN001F R-RO Small condenser leak causes lowering vacuum. (AOP)

RO reduces reactor power with recirc flow to stabilize vacuum >25".

4 ZUA125 C-SRO Large debris causes "B" Circ. Water Screen to stop; C-BOP "CIRC SCREEN Hi DP or STOPPED" alarm; Swap Circ. Pumps per OP 5 CW023F C-SRO NSW Pump Trip, failure of STBY pump to auto start, manual start req'd; (TS)

(AOP-18)

C-BOP 6 ES002F C-SRO SRV "E" fails open. (AOP-30) Pull fuses to close SRV; C-RO Possible PCCP entry; Place torus cooling in service.

7 RW013F/15FI M-ALL Un-isolable RWCU leak, SCRAM, Loss of Vacuum; 16F (AOPs, EOPs) 8 ES028F C-SRO HPCI injection valve fails to auto open C-RO 9 N/A M-ALL Emergency Depressurization (EOPs) 10 K1507A C-BOP Failure of two ADS valves to open, manually open two additional SRV's; K1512A Scenario ends when reactor pressure reaches 50#

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2008 NRC Examination Scenario #2

Scenario Description Event 1 - BOP operator will transfer SJAE 2A to FULL load using 20P-30 Section 8.1.

Task requires some component manipulations and parameter monitoring.

Event 2 - APRM 3 will fail downscale. With APRM 2 already bypassed requires placing in trip by placing Module in INOP and T.S. evaluation.

Event 3 - A small condenser leak which will cause condenser vacuum to slowly lower. Crew should enter AOP-37. SRO should direct RO to lower reactor power to stabilize vacuum. Once power has been reduced at least 5%, vacuum will stabilize.

Event 4 - Large piece of debris will lodge in 2B CW traveling screen. "CIRC SCREEN A HIGH DP or STOPPED" will alarm on panel UA-1. Crew will reference APP and dispatch AO to investigate. AO will report that screen is jammed and will not move. Per the direction of the APP, crew will start an available CW pump and secure 2B CW pump.

Event 5 - The running NSW pump will TRIP on motor overload. The STBY NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the STBY NSW pump.

System parameters will return to normal. SRO should address T.S. implications. AOP-18 entry.

Event 6 - SRV "E" will fail full open. Crew will enter AOP-30. Immediate operator actions are unsuccessful in closing the SRV; pulling fuses per supplementary actions will close SRV.

Event 7 - A large un-isolable RWCU leak will occur. Crew will enter AOP-5.0 and SCCP. SRO should direct a SCRAM. Original vacuum leak will worsen causing a complete loss of vacuum.

Group 1 isolation will occur due to loss of vacuum.

Event 8 - HPCI injection valve will fail to open if HPCI AUTO initiation is received. Manual operation will open injection valve.

Event 9 - Secondary containment conditions will worsen, forcing the SRO to direct an Emergency Depressurization due to high water levels.

Event 10 - Two ADS SRV's will fail to manually open. SRO should direct opening two additional SRV's. Scenario will end when reactor pressure reaches 100#.

2008 NRC Examination Scenario #2 2

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2008 NRC EXAM SCENARIO #2 2008 NRC Examination Scenario #2 3

SIMULATOR SETUP Initial Conditions IC ENP-24 for IC 13 Rx Pwr 100%

Core Age MOC EVENTS Event Trigger Trigger Description Number 1 N/A Transfer 2A SJAE to Full Load, Secure 2B SJAE 2 1 Manual APRM 3 fails downscale 3 2 Manual Small condenser leak, lowering vacuum, power reduction 4 3 Manual Circ. Screen Stopped, Swap Circ. water pumps 5 4 Manual NSW pump trip, failure of STBY NSW pump to start 6 5 Manual 'E' SRV stuck open 7 6 Manual Unisolable RWCU leak, SCRAM, Loss of vacuum, Gp.1 isolation 8 N/A HPCI Injection valve fails to open 9 N/A Emergency Depress 10 N/A Failure of 2 ADS valves to open 2008 NRC Examination Scenario #2 4

SIMULATOR SETUP Malfunctions Summary MalflD Mult Description Current Target Rmptime Actime Dactime Trig ID Value Value CN001F LOSS OF CONDENSER VACUUM 0.00 825.00 00:03:00 2 ES002F ADS VALVE E FAILS OPEN FALSE TRUE 4 CW023F B NSW PUMP SHAFT SEIZURE FALSE TRUE 5 RW013F RWCU BRK IN TRIANGLE ROOM 70' 0.00 100.0000 00:10:00 6 NI032F 3 APRM FAILS LO FALSE TRUE Remotes Summary RemflD Mult Description Current Target Rmptime Actime Trig ID Value Value RW_ZVRW004M G31-F004 OUTBOARD ISOL VALVE ON OFF 8 RW_ZVRW001M G31-F004 OUTBOARD ISOL VALVE ON OFF 00:00:02 9 2008 NRC Examination Scenario #2 5

SIMULATOR SETUP Override Summary TaglD Description Position! Actual Override Rmptime Actime Dactime Trig Value Value K1504A MAN DEPRESS VLV B21-F013E ON ON 7 K1504A MAN DEPRESS VLV B21-F013E OFF OFF 7 Annunciator Summary Window Description Tagname Override Type Oval AVal Actime Dactime Trig 2-5 CW SCREEN B DIFF HIGH ZUA125 ON ON OFF 3 5-5 OTBD NSS VALVES MTR OVLD ZA255 ON ON OFF 8 Special Instructions Load scenario file, 2008 Scenario 2.scn, if required.

Ensure ENP-24 for IC-13 at P603 panel.

2008 NRC Examination Scenario #2 6

SHIFT BRIEFING Plant Status The plant is operating at 100% power, Middle of Cycle.

Equipment Out of Service APRM 2 (Bypassed)

Plan of the Day Maintain current power.

APRM 2 is bypassed for erratic behavior, IIC is investigating.

Following shift turnover, place 2A SJAE in full load and remove 2B SJAE from service per the direction of 20P-30 Section 8.1.

The 2B SJAE is being removed from service for periodic maintenance and will be unavailable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

2008 NRC Examination Scenario #2 7

SCENARIO INFORMATION Critical Tasks (bolded and italicized in the required operator actions)

Recognize failure of HPCI injection valve to auto open and take manual action to open valve before level reaches top of active fuel.

Perform Emergency Depressurization when two plant areas exceed max safe water level.

2008 NRC Examination Scenario #2 8

EVENT 1 SHIFT TURNOVER I SJAE TRAIN MANIPULATIONS The crew places 2A SJAE in full load per SCO direction Malfunctions required: None Objectives:

Directs BOP to place 2A SJAE in full load and remove 2B SJAE from service per 20P-30 section 8.1.

RO/BOP

Places 2A SJAE in full load and removes 2B SJAE from service per 20P-30 section 8.1.

Monitors reactor plant during evolution Success Path:

2A SJAE in full load, 2B SJAE secured, vacuum steady Simulator Operator Actions:

D If contacted as the Auxiliary Operator, respond that you are standing by and ready to assist during the evolution.

D When directed by the lead examiner, proceed to the next event.

Required Operator Actions SRO Time Required Actions Notes Direct BOP operator to place 2A SJAE in full load and secure 2B SJAE I

2008 NRC Examination Scenario #2 9

EVENT 1 SHIFT TURNOVER I SJAE TRAIN MANIPULATIONS BOP Time Required Actions Notes Place 2A SJAE in full load and removes 2B SJAE from service per 20P-30, section 8.1 as follows Verify Auxiliary Operator available to respond to valve or breaker problems that could be encountered during the transfer Depress OFFGAS TRAIN A(B)

MASTER SWITCH, FULL LOAD pushbutton.

Verify the following valves auto open:

SJE-V11 HTOG-V1 SJE-V4 OG-V10 Alarms expected for this evolution.

2APP-UA-45 (6-3) ICNDSR COND OUTLET VL V CO-V17 OPEN 2APP-UA-45 (4-3) AFTER CNDSR COND LVL HIGH/LO 2APP-UA-45 (3-2) RECOMBINER INLET TEMP LOW Check SJAE Off Gas Rad Monitors A&B Depress OFFGAS TRAIN B(A)

MASTER SWITCH, OFF/RESET pushbutton.

Verify the following valves close:

SJE-V12 OG-V13 MVD-V56 2008 NRC Examination Scenario #2 10

EVENT 1 SHIFT TURNOVER I SJAE TRAIN MANIPULATIONS BOP Continued Time Required* Actions Notes After three minutes, verify the following valves have closed:

SJE-V1 SJE-V17 HTOG-V4 Confirms intercondenser condensate drain level MVD-U-4332 on the 2B SJAE train is stable.

Steps 8.1.2.5 - 7 are N/A.

Level is less than 80 inches.

Verifies that 2A SPE is in service and N/A's step 8.

Close the following condensate system valves:

CO-V16, SPE COND INL VALVE CO-V182, AFTERCONDSR COND OUTLET VALVE CO-V17, SJAE INTERCONDSR COND OUTLET VALVE Ensures condenser vacuum is stable.

Informs SCO to initiate a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months tracking LCO on ODCM table 7.3.2-1.

Place recombiner electric strip heaters to OFF.

RO Time Required Actions Notes .

Monitor reactor plant parameters during evolution.

2008 NRC Examination Scenario #2 11

EVENT 2 APRM 3 FAILS DOWNSCALE I TECH SPEC The crew responds to Annunciator "APRM DOWNSCALE".

Malfunctions required:

APRM 3 fails downscale Objectives:

Direct actions in response to an APRM failure

Evaluates Tech Spec 3.3.1.1 Reactor Protection System Instrumentation BOP/RO

Respond to APRM failure

Execute applicable APP's Success Path:

Place APRM 3 in trip per the 001-18.

Simulator Operator Actions:

o WHEN directed by the lead examiner, activate TRIGGER 1 (APRM 3 fails downscale) o If contacted as I&C to assist with APRM troubleshooting, report indicating downscale and troubleshooting is in progress.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 12

EVENT 2 APRM 3 FAILS DOWNSCALE I TECH SPEC Required Operator Actions SRO Time Required Actions Notes Direct RO/BOP to enter and execute 2APP-A-06 (3-8) APRM UPSCALE TRIP/INOP.

Direct RO to trip APRM 3 by placing mode switch in INOP per 001-18.

Refers to T.S. 3.3.1.1.

Determine APRM 3 is inoperable Determine 2 of 4 channels are inoperable (3 required) for Function 2.

Determine condition A 1 applies to place in a trip condition in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .(With A 1 not met be in Mode 2 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months )

Determines condition A2 does not apply due to note.

Refer to TRMS 3.3 Determines that condition A applies to restore channel to operable status in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(With condition A not met place one channel in trip in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

Contacts I&C for support.

2008 NRC Examination Scenario #2 13

EVENT 2 APRM 3 FAILS DOWNSCALE I TECH SPEC BOP Time Required Actions Notes Monitor reactor plant parameters during evolution.

RO Time Required Actions Notes Execute APPs on A-5:

(2-7) APRM DOWNSCALE.

(3-7) APRM TROUBLE (2-2) ROD OUT BLOCK Execute APPs on A-6:

(3-8) APRM UPSCALE TRIP/INOP Monitor APRM indications.

Recognize APRM 3 downscale.

Verify APRM DNSC light ON.

Verify ROD OUT BLOCK Annunciator illuminated.

Compare APRM 3 indication to other APRMs.

Notify Unit SRO.

Place the APRM mode switch in INOP per 001-18. (Key needed from SRO key locker) 2008 NRC Examination Scenario #2 14

EVENT 3 SMALL CONDENSER LEAK / LOWERING VACUUM/POWER REDUCTION The crew responds to lowering condenser vacuum.

NOTE: Vacuum will stabilize as crew lowers power.

Malfunctions required:

Condenser leak Objectives:

Direct actions in response to lowering condenser vacuum ROIBOP

Respond to lowering condenser vacuum

Reduce reactor power, as directed by SRO, to stabilize vacuum above 25" Success Path:

Reduce reactor power approx. 10% to stabilize condenser vacuum above 25" Hg Simulator Operator Actions:

D WHEN directed by lead examiner, activate TRIGGER 2 (Condenser Leak)

D IF asked as the Rad Waste Operator to maintain hotwellievel using manual hotwell level control, respond in the affirmative.

D IF contacted as Ops Center to assist with vacuum leak search, acknowledge request.

D IF contacted as chemistry to perform actions for 15% power reduction, acknowledge.

D IF contacted as HP to assist in SJAE room entry, acknowledge request.

D IF contacted as AO to check closed MVD-5023, acknowledge request.

D IF crew fails to lower power, increase vacuum leak until reactor scram occurs, as instructed by the lead evaluator.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 15

EVENT 3 SMALL CONDENSER LEAK / LOWERING VACUUM/POWER REDUCTION Required Operator Actions SRO Time Required Actions Notes Direct crew to enter and execute AOP-37 Low Condenser Vacuum.

Direct RO to reduce reactor power per ENP-24.5 to maintain vacuum greater than 25" Hg.

Refer to ODCM LCO 7.3.10 if AOG Bypass occurs (2APP-UA-48 (5-4)

AOG SYSTEM BYPASS).

Condition A 1 applies to place AOG in service in 7 days.

BOP Time Required Actions Notes Enter and execute AOP-37 Low Condenser Vacuum.

Direct Radwaste to maintain hotwell level between -7 and +7 inches in manual hotwell level control Verify proper SJAE operation.

Respond to Alarms.

2APP-UA-48 (5-4) AOG SYSTEM BYPASS 2APP-UA-48 (5-3) AOG SYSTEM OUTLET FLOWITEMP HIGH 2APP-UA-23 (2-1) EXH HOOD A VACCUM LOW 2APP-UA-23 (3-1) EXH HOOD B VACUUM LOW 2008 NRC Examination Scenario #2 16

EVENT 3 SMALL CONDENSER LEAK / LOWERING VACUUM/POWER REDUCTION RQ Time . Req uired. Actions Notes ..

Enter and execute AQP-37, Low Condenser Vacuum.

Reduce reactor power as required to maintain condenser vacuum greater than 25" Hg per OENP-24.5.

Reduce flow on one RR Pump

(-2%) at a time to stay within mismatch criteria (3.5x10 6 Mlbs jet pump flow).

Continues alternating Recirc pump reductions until vacuum is steady and greater than 25 inches HG.

Verifies operation on the Power to Flow map.

Recognizes operation above the MELLL line and informs SeQ.

Inserts control rods using ENP-24 to get below the MELLL line.

(Should only need to insert one control rod 10-43)

Turns control rod power on.

Selects control rod (10-43) in accordance with ENP-24 sheet.

May also insert 42-43, 42-11, or 10-11. (in this order to establish margin to MELLL line).

Continuously drives selected rod in using RMCS.

2008 NRC Examination Scenario #2 17

EVENT 4 LARGE DEBRIS IN CIRC SCREEN 2A I SWAP CIRC WATER PUMPS The crew responds to a jammed circ water traveling screen and swaps CW pumps Malfunctions required:

Annunciator UA-01 (2-5) CW Screen B Diff-High or Stopped Objectives:

Supervises the swapping of circ water pumps RO/BOP

Recognizes the requirement to swap circ water pumps and takes action to do so.

Monitors reactor plant parameters Success Path:

Circ water pump 2B removed from service and another available circ pump placed in service.

Simulator Operator Actions:

D WHEN directed by the lead examiner, activate TRIGGER 3 (Annunciator - CW Screen A Diff-Hi or Stopped UA-01 12-5)

D IF contacted as the Outside Operator to check the status of the 2A CW Screen, report the screen is stopped and jammed with a large immovable piece of debris.

Report all other screens are operating and free of debris.

D IF contacted as maintenance to assist with screens, acknowledge request.

D IF contacted as Radwaste, acknowledge report of pending swap CWIPs and to ensure proper operation of chlorination operating.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 18

EVENT 4 LARGE DEBRIS IN CIRC SCREEN 2A I SWAP CIRC WATER PUMPS Required Operator Actions SRO Time Required Actions Notes Direct RO/BOP to enter and execute Annunciator Panel Procedure.

Direct RO/BOP to enter and execute AOP-37.1 Intake Structure Blockages.

BOP Time Required Actions Notes Execute APP UA-01 (2-5) CW Screen B Diff-Hi or Stopped.

Direct RO/BOP to enter and execute AOP-37.1 Intake Structure Blockages.

Direct aux operator to check status of 2B CW screen.

When informed of CW screen status:

Swap Circ. Water Pumps.

(May use OP-29 or since the APP since it directs starting without referencing a procedure number)

Place CW Isol Valves Mode Selector in position D.

Start the desired non-operating CWIP.

Stop 2B CWIP RO Time Required*Actions Notes Monitor reactor plant parameters during evolution.

2008 NRC Examination Scenario #2 19

EVENT 5 NSW PUMP TRIP I FAILURE OF STBY PUMP TO START The crew responds to the trip of a NSW pump and the failure of the auto pump to start.

Malfunctions required:

'B' NSW Pump shaft seizure

Failure of STBY NSW pump to start Objectives:

Direct actions for loss of NSW

Evaluates Tech Specs 3.7.2 Service Water System and Ultimate Heat Sink RO/BOP

Respond to the trip of a NSW pump

Respond to the failure of an automatic start of the C NSW pump Success Path:

STBY NSW pump started and NSW system pressure returned to normal band Simulator Operator Activities:

D WHEN directed by lead examiner, activate TRIGGER 4.

(NSW pump trip)

D IF contacted as Outside AO to investigate NSW pump and breaker, acknowledge request.

D IF contacted as maintenance or I&C to investigate trip, acknowledge request.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 20

EVENT 5 NSW PUMP TRIP I FAILURE OF STBY PUMP TO START Required Operator Actions SRO Time Required Actions Notes Direct entry into AOP-18 NSW System Failure.

Evaluate Tech Spec 3.7.2 Service Water System and Ultimate Heat Sink.

Determine 2B NSW pump inoperable Determine 2A NSW Pump INOP due to failure of auto-start.

Per the Bases, 3 required site wide.

3.7.2 Condition B. One required NSW pump inoperable for reasons other than condition A. Required Action B.1 Restore required NSW pump to Operable status in 7 days RO Time Required Actions Notes Monitor reactor plant parameters during evolution.

2008 NRC Examination Scenario #2 21

EVENT 5 NSW PUMP TRIP I FAILURE OF STBY PUMP TO START BOP Time Required Actions Notes Monitor NSW system parameters.

Recognize lowering NSW system pressure.

Enter and execute AOP-18 NSW System Failure.

Recognize trip of B NSW pump.

Recognize the failure of the STBY NSW pump to start and starts standby pump.

Refer to alarms.

2APP-UA-01 (4-10) NUCLEAR HDR SW PUMP B TRIP 2APP-UA-01 (1-10) NUCLEAR HEADER SERV WTR PRESS-LOW 2APP-UA-03 (1-5) RBCCW HEAD TANK LEVEL HI/LO 2008 NRC Examination Scenario #2 22

EVENT 6 SRV IE' FAILS OPEN The crew responds to an inadvertent stuck open SRV Malfunctions required:

ADS valve 'E' fails open Objectives:

Direct actions in response to a stuck open SRV BOP/RO

Respond to a stuck open SRV Success Path:

'E' SRV is closed by pulling fuses per the supplementary actions of AOP-30.

Simulator Operator Actions:

o WHEN directed by the lead examiner, activate TRIGGER 5.

(ADS valve E fails open) o If contacted as operator to pull fuses, wait until torus temperature reaches 95° F and then activate TRIGGER 7and immediately DELETE the malfunction from TRIGGERS o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 23

EVENT 6 SRV 'E' FAILS OPEN Required Operator Actions SRO Time Required Actions Notes Direct entry into AOP-30 Safety/Relief Valve Failure.

Direct support personnel to pull applicable fuses per Attachment 1 of AOP-30.0.

Enter PCCP when torus temp reaches 95° F.

Determine TS 3.6.2.1 applies for Torus greater than 95° F.

Condition A 1 requires verifying the Torus temperature ~ 110° F once per hour.

Condition A2 requires Torus to be ~ 95° F in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Direct BOP to place torus cooling in service per PCCP (Hard Card or OP-17).

BOP Time Required Actions Notes Respond to alarms.

2APP-A-03 (1-10)

SAFETY/RELIEF VALVE OPEN 2APP-A-03 (1-1) SAFETY OR DEPRESS VALVE LEAKING 2APP-UA-12 (5-4) SPTMOS DIV I 2APP-UA-12 (5-5) SPTMOS DIV II 2APP-A-2 (3-2) RHR PUMP 2A SEAL CLR FLOW LOW 2APP-A-2 (4-2) RHR PUMP 2C SEAL CLR FLOW LOW 2APP-A-3 (2-1) CS OR RHR PUMPS RUNNING 2008 NRC Examination Scenario #2 24

EVENT 6 SRV 'E' FAILS OPEN RO Time Required Actions Notes Cycle "E' SRV control switch several times leaving control switch in CLOSE or AUTO per immediate operator actions of OAOP-30.

Request fuses for the SRV be pulled per Attachment 1 of AOP-30.0.

When informed that fuses have been pulled, verify SRV is closed.

Places suppression pool cooling in service on A Loop. (Actions in parenthesis for BLoop)

Opens SW-V101 (V105).

Closes SW-V143.

May verify adequate suction source and start a CSW (NSW)

Pump.

Starts RHR SW Pump(s)

Adjusts E11-PDV-F068A(8) to achieve -4000 gpm per RHR SW pump running.

Supplies cooling water to vital header ensures open either SW-V111orSW-V117.

Starts RHR pump(s)

Open E11-F028A(8).

Throttles open E11-F024A(8)

(establishes flow in green band for 1 pump or ~11500 gpm for 2 pump operation)

Closes E11-F048A(8).

2008 NRC Examination Scenario #2 25

EVENT 7 &8 UNISOLABLE RWCU LEAK I SCRAM I LOSS OF VACUUM The crew will respond to an un-isolable RWCU leak in secondary containment.

Malfunctions required:

RWCU leak Triangle Room 77ft

RWCU isolation valve failures

Vacuum Loss

HPCI Injection valve failure to open Objectives:

Direct response to un-isolable primary system breach in secondary containment

Direct execution of applicable AOPs & EOPs BOP/RO

Respond to un-isolable primary system breach in secondary containment

Recognize and respond to component malfunctions

Execute AOP and EOP actions as directed by SRO

Perform SCRAM actions

Control reactor parameters post SCRAM Success Path:

Crew enters and executes AOP-5.0 and SCCP, attempts to isolate RWCU, inserts reactor scram, recognizes Gp.1 isolation, recognizes failure of HPCI injection valve, maintains reactor water level above LL3, controls reactor pressure with SRVs.

Simulator Operator Actions:

D WHEN directed by lead examiner, activate TRIGGER 6 D WHEN crew inserts a SCRAM, increase TRIGGER 2 malfunction setting (vacuum leak) to maximum.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 26

EVENTS 7 &8 UNISOLABLE RWCU LEAK I SCRAM I LOSS OF VACUUM Required Operator Actions SRO Time Required Actions Notes Direct entry into AOP-5.0 High Radiation Direct RO to trip and isolate RWCU.

Enter and execute SCCP.

Direct a reactor scram.

Direct cool down at normal cool down rates.

Enter and execute RVCP.

Direct RO/BOP to stabilize reactor pressure below 1050 psig.

Verify Instrument operability per Caution 1.

Direct crew to not use N026A1B due to 50' temperatures after 50' alarm reported.

Direct verification of group isolations, ECCS initiations and DG starts as appropriate.

Direct RO/BOP to restore and maintain reactor water level 170"-200" using systems available in Table 1.

Direct HPCI injection valve to be opened.

Contact support personnel for assistance with RWCU isolation valve failures.

2008 NRC Examination Scenario #2 27

EVENTS 7 & 8 UNISOLABLE RWCU LEAK 1 SCRAM 1 LOSS OF VACUUM RO Time Required Actions Notes ..

Enter and execute AOP-5.0 High Radiation.

Diagnose source of radiation as RWCU leak.

Trip and isolate RWCU as directed by SRO.

Recognize RWCU isolation valve failures and report to SRO.

(F001 - Breaker trip)

(F004 - Overload trip)

Insert Reactor scram as directed by SRO.

Complete scram actions Recognize Grp.llsolation (vacuum loss) and report to crew.

Maintain reactor pressure with SRVs as directed by SRO.

Maintain reactor water level as directed by SRO.

Perform reactor cooldown as directed by SRO.

Recognize failure of HPCI injection valve to open and open manually.

Recognize and report to SRO alarm A-2 RB 50120 ft Temp Hi.

2008 NRC Examination Scenario #2 28

EVENTS 7 & 8 UNISOLABLE RWCU LEAK I SCRAM I LOSS OF VACUUM BOP Time Required Actions Notes Respond to alarm UA-03, 2-7 Area Rad Rx Bldg Hi.

Enter and execute AOP-5.0.

Evacuate Unit 2 Reactor Bldg.

Direct AO to close PIV-33 RB Sprinkler Shutoff Valve.

Direct E&RC to take applicable AOP-5.0 actions.

Check area radiation readings at back panels.

Diagnose source of radiation as RWCU leak.

Recognize Grp.1 Isolation (vacuum loss) and report to crew.

2APP-UA-23 (2-1, 3-1) EXH HOOD AlB LOW VACCUUM 2APP-UA-23 (1-1) TURB VACCUUM TRIP 2APP-A-5 (5-4,5-3) GP.IISOL LOGIC TRIPPED Maintain reactor pressure with SRVs as directed by SRO.

Maintain reactor water level as directed by SRO.

Perform reactor cooldown as directed by SRO.

2008 NRC Examination Scenario #2 29

EVENTS 7 & 8 UNISOLABLE RWCU LEAK I SCRAM I LOSS OF VACUUM BOP Continued Time Required Actions Notes Recognize failure of HPCI injection valve to open and open manually.

Recognize and report to SRO alarm A-2 RB 50/20 ft Temp Hi.

Recognize and report to SRO alarm UA-12 South Core Spray Flood Level Hi.

2008 NRC Examination Scenario #2 30

EVENT 9 & 10 EMERGENCY DEPRESSURIZATION I ADS VALVE FAILURES The crew will perform and respond to a manual emergency depressurization with ADS valve failures.

Malfunctions required:

"C' and "K' ADS valves fail to open manually Objectives:

Evaluate plant conditions and direct an Emergency Depressurization BOP/RO

Perform Emergency Depressurization

Recognize and respond to component malfunctions Success Path:

Emergency depressurization performed as required by SCCP Simulator Operator Actions:

D 2 minutes after receiving annunciator UA-12 (2-4) SOUTH RHR RM FLOOD HI, initiate TRIGGER 12 (South RHR RM Flood HI-HI)

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #2 31

EVENT 9 & 10 EMERGENCY DEPRESSURIZATION I ADS VALVE FAILURES Required Operator Actions:

SRO Time Required Actions Notes Continue reactor cooldown per secp direction.

Direct Emergency Depressurization when RHR RM FLOOD LEVEL HI-HI alarm (Two plant areas with radiation levels above Max Safe - South CS andRHR)

Direct RO/BOP to open 7 ADS valves.

If informed by RP/BOP that 2 SRVs failed to open, direct opening additional SRVs until 7 SRVs are open.

RO/BOP Time Required Actions Notes Continue reactor cool down as directed by SRO.

Recognize and report South CS and South RHR Room Flood Hi-Hi alarms.

Open seven ADS valves as directed bySRO.

Recognize failure of 2 ADS valves to OPEN and report to SRO.

Open 2 additional SRVs as directed bySRO.

Maintain reactor water level as directed by SRO.

2008 NRC Examination Scenario #2 32

Simulator Operator Activities:

WHEN directed by the lead examiner, place the simulator in FREEZE.

CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER 2008 NRC Examination Scenario #2 33

Facility: BRUNSWICK Scenario No.: 3 Op Test No.: Final Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: Reactor power is 60% with power ascension in progress per GP-04 Turnover: GP-04 is complete thru step 5.2.21. Continue with step 5.2.22 to place the second reactor feed pump is service in accordance with 20P-32.

Event Malf. No. Event Event Description No. Type*

1 N/A N-BOP Place second reactor feed pump in service SRO 2 N/A R-RO Raise reactor power to 70% with recirc.

SRO 3 RD001M C-RO Control rod drift TS - SRO (TS) 4 ES022F I-BOP Inadvertent HPCI Initiation TS - SRO (TS) 5 RD187F C-RO CRD pump trip; start STBY CRD pump SRO 6 IAUPB2A6 C-BOP Power loss to Main Stack Rad Monitor; SBGT system failure to start SRO 7 NB006F M-AII Main steam line leak in primary containment I SCRAM I ATWS RP008F 8 K1227A C-BOP Drywell Spray required; spray valve failures prevent sprays K1J36A SRO 9 N/A M-AII Emergency Depressurization with low power ATWS

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2008 NRC Examination Scenario #3

Scenario Description Event 1 - Following shift turnover the BOP operator will place the second reactor feed pump in service.

Event 2 - When the second reactor feed pump is in service, the RO will be directed to raise reactor power to 70% using recirc. per the nuclear engineers direction.

Event 3 - A fully withdrawn control rod will drift full in. The crew will enter AOP-2.0 Control Rod Malfunction/Misposition. AOP-2.0 will direct response per 2APP-A-05 (3-2) ROD DRIFT. The RO should attempt to arrest the drifting control rod.

Event 4 - An inadvertent HPCI initiation will occur. The crew will respond by verifying no initiation signal is present and securing HPCI. The HPCI trip pushbutton will fail to operate requiring HPCI shutdown by other means. If injection occurs, crew will enter AOP-3.0 Positive Reactivity Addition.

Event 5 - The running CRD pump will trip. The crew should respond by placing the STBY CRD pump in service in accordance with the OP.

Event 6 - Power to the Main Stack Radiation Monitor will be lost resulting in a Gp. 6 Isolation.

SBGT system will fail to start as required. The crew must diagnose the failure of SBGT and start manually to maintain secondary containment integrity.

Event 7 - A main steam line leak inside primary containment will cause drywell pressure and temperature to rise. The crew should scram the reactor before 1.7 psig or an auto scram will occur.

Five control rods will fail to insert following the scram requiring entry into LPC and PCCP.

Event 8 - Containment parameters will worsen requiring drywell and torus sprays. A combination of failures will prevent drywell sprays from occurring.

Event 9 - Drywell temperature will approach or exceed 300F with no drywell sprays available.

SRO will direct an Emergency depressurization. Only 6 SRVs will open requiring depressurization to 140 psig prior to reestablishing injection. When reactor water level is restored, the scenario will terminate.

2008 NRC Examination Scenario #3 2

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2008 NRC EXAM SCENARIO #3 2008 NRC Examination Scenario #3 3

SIMULATOR SETUP Initial Conditions IC ENP-24 for IC 9 Rx Pwr 60%

Core Age BOC EVENTS Event Trigger Trigger Description Number 1 N/A Place second reactor feed pump in service 2 N/A Raise reactor power to 70% with recirc.

3 1 Manual Control Rod drift 4 2 Manual Inadvertent HPCI initiation 5 3 Manual CRD pump trip; start STBY CRD pump 6 4 Manual Loss of power to Mn Stack Rad Mon I SBGT system failure 7 5 Manual Main steam leak in primary containment I Scram I ATWS 8 N/A Drywell sprays required; spray valve failures 9 N/A Emergency depressurization required; ATWS conditions 2008 NRC Examination Scenario #3 4

SIMULATOR SETUP Malfunctions Summary MalflD MultlD Description Current Target Rmptime Actime Dactime Trig Value RD001M 30-119 CONTROL ROD DRIFT FALSE TRUE ES014F HCIC INADVERTANT START FALSE TRUE 2 RD187F A CRD PUMP SHAFT SEIZURE FALSE TRUE 3 NB006F B MSLBREAK 0.00 1.0000 00:20:00 5 Remotes Summary RemflD Mult Description Current Target Rmptime Actime Trig ID Value Value RH_ZVRH16BT DW SPRAY VLV E11-F016B ON OFF 8 RD_RDELDIS 30-19 ELECTRIC DISARM ROD ARM DISARM 5 RD_RDELDIS 30-19 HYDRAULIC DISARM ROD ARM DISARM 5 EP_IAEOPJP1 BYPASS LL3 GP.1 ISOL (SEP-10) OFF ON 7 ED-IAUPB2A6 UPS LOAD BKR PNL 2A SMPL SKD CLOSE OPEN 4 Override Summary 2008 NRC Examination Scenario #3 5

Annunciator Summary Window Description Tagname Override Type Oval AVal Actime Dactime Trig 5-8 RHR B VALVES OVERLOAD ZA358 ON ON OFF 8 1-2 CRD HYD TEMP HIGH ZA512 OFF OFF OFF 1 Special Instructions Load scenario file 2008 Scenario 3.scn, if required.

Ensure ENP-24 for IC-9 at P603 panel.

Ensure GP-04 open and signed off through step 5.2.21 Ensure GP-04 alternate power verifications signed off through 60% power Critical Task(s)

Perform Emergency Depressurization when it is recognized that drywell temperature cannot be restored and maintained below 300 0 F.

2008 NRC Examination Scenario #3 6

SHIFT BRIEFING Plant Status Reactor power is 60% with power ascension in progress per GP-04.

GP-04 is complete thru step 5.2.21.

Alternate power verification for 60% power is complete.

"8" RFP is idling in accordance with Section 5.12 of 20P-32 Equipment Out of Service None Plan of the Day Following shift turnover, place the second reactor feed pump in service per 20P-32, Section 5.7 Reactor Feed Pump Startup From Idle Speed to Injection - Second Pump Operation After second feed pump is in service, raise reactor power to 70% with recirc. per the Reactor Engineer recommendation.

2008 NRC Examination Scenario #3 7

EVENT 1 PLACE SECOND REACTOR FEED PUMP IN SERVICE The BOP operator places the second feed pump in service per OP-32.

Malfunctions required:

None Objectives:

Direct BOP operator to place the second RFP is service per OP-32.

Place a second RFP is service per the direction of OP-32 RO

Monitor reactor plant parameters during RFP startup.

Success Path:

Two RFPs in service with balanced injection flows.

Simulator Operator Actions:

D If asked as the RW operator to monitor COD flows and place additional demins in service as needed, acknowledge request.

D If asked as the RW operator to monitor COD effluent conductivity, acknowledge request.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 8

EVENT 1 PLACE SECOND REACTOR FEED PUMP IN SERVICE Required Operator Actions Normal Operations - Placing a second RFP is service.

SRO Direct BOP operator to place the second RFP is service per OP-32.

BOP Place the second RFP in service per 20P-32 Section 5.7. as follows:

0 Notify Radwaste operator to monitor COD flows 0 Ensure RFP B LP SUPPLY VL V 'V1' is open 0 Slowly raise RFPT B speed until speed is > 2550 rpm 0 When RFPT B speed is > 2550 rpm, match DFCS and SPEED outputs to within 100 rpm 0 Notify Radwaste operator to monitor COD effluent conductivity 0 Verify speed signals within 100 rpm and place MAN/DFCS control switch to DFCS 0 Slowly raise RFPT speed until RFP discharge pressure is approx. equal to reactor pressure 0 Open RFP B DISCH VLV 'V4' 2008 NRC Examination Scenario #3 9

EVENT 1 PLACE SECOND REACTOR FEED PUMP IN SERVICE Required Operator Actions D Slowly raise speed on RFP B to match demand signal of RFP A D Depress RFP B AIM pushbutton to place RFP B in AUTO D When RFP B flow is greater than 3.3E6, place RFP B RECIRC VLV 'V47' to close D When RFP B RECIRC VLV closes, adjust level setpoint to 187 inches D If desired, balance RFP flows by adjusting flow BIAS settings RO Monitor reactor plant parameters during evolution 2008 NRC Examination Scenario #3 10

EVENT 2 RAISE REACTOR POWER TO 70% WITH RECIRC SYSTEM The crew will increase recirc flow to raise reactor power to 70%.

Malfunctions required:

None Objectives:

SCO

Direct RO to raise reactor power to 70% per guidance of the Reactor Engineer.

BOP

Monitor plant parameters during evolution RO

Raise reactor power by increasing recirc flow lAW OP-02 Reactor Recirc System Success Path:

Reactor power raised to 70% using recirc flow.

Simulator Operator Actions:

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 11

EVENT 2 RAISE REACTOR POWER TO 70% WITH RECIRC SYSTEM Required Operator Actions Reactivity Manipulation - Raise reactor power by adjusting recirculation flow SRO Direct the RO to raise reactor power to 70% per RE guidance BOP Monitor plant parameters during the evolution RO Raise reactor power by increasing reactor recirculation flow lAW OP-02 as follows:

D Request peer checker D Increase flow (2-4%) on one RR pump at a time to stay within mismatch criteria.

(With core flow less than 58e6 Ibs/hr jet pump loop flows are required to be within 10%. With core flow greater than or equal to 58e6 Ibs/hr jet pump loop flows are required to be within 5%.)

D Continue alternating RR pump speed increases until reactor power is 70%

D Monitor power/flow map 2008 NRC Examination Scenario #3 12

EVENT 3 CONTROL ROD DRIFT The crew responds to a drifting control rod.

Malfunctions required:

o Drifting control rod Objectives:

o Direct actions in response to a drifting control rod o Evaluate Tech Specs

Respond to a drifting control

Respond to a drifting control rod Success Path:

The drifting control rod is fully inserted, valved out of service and electrically disarmed.

Simulator Operator Actions:

o WHEN directed by the lead examiner, activate TRIGGER 1 (Control Rod Drift) o WHEN HCU clearance has been requested, REMOVE drift malfunction.

o If asked as the RBAO to investigate HCU for control 30-19, wait 2 minutes and report that the HCU scram outlet riser is hot to the touch.

o If asked as the aux operator to valve out accumulator and disarm control rod, wait 2 minutes and activate TRIGGER 6.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 13

EVENT 3 CONTROL ROD DRIFT Required Operator Actions SRO Direct entry into AOP-2.0 Control Rod Malfunction/Misposition Evaluate Tech Spec 3.1.3 Control Rod Operability D Condition C. One or more control rods inoperable for reasons other than Condition A or B D Required Action C.1 Fully insert inoperable control rod (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months )

D Required Action C.2 Disarm the associated CRD (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

BOP Monitor plant parameters Acknowledge and ROD OUT BLOCK alarm RO (RO actions continued on next page) 2008 NRC Examination Scenario #3 14

EVENT 3 CONTROL ROD DRIFT Required Operator Actions Perform the actions of APP-A-05 (3-2)

ROD DRIFT as follows:

D Determine which control rod is drifting D Select the drifting control rod and determine direction of drift D Attempt to arrest the drift by giving a withdraw signal D If rod continues to drift in, apply an RMCS insert signal and fully insert to position 00.

D Attempt to locate and correct the cause of the rod malfunction as follows:

Check and adjust cooling water header ressure if uired

Direct AO to check for leaking scram valve

With the rod full in, individually scram the control rod and attempt to reseat the scram valves

Contact I&C to check for possible directional control valve failure D Monitor core parameters, main steam line radiation and off-gas activity 2008 NRC Examination Scenario #3 15

EVENT 4 INADVERTENT HPCIINITIATION The crew responds to an inadvertent HPCI initiation and possible injection.

Malfunctions required:

o Inadvertent HPCI initiation Objectives:

o Direct actions in response to an inadvertent HPCI initiation and potential positive reactivity addition o Respond to an inadvertent HPCI intiation and potential positive reactivity addition o Respond to an inadvertent HPCI intiation and potential positive reactivity addition Success Path:

Verify HPCI initiation signal not present and trip HPCI.

Simulator Operator Actions:

o WHEN directed by the lead examiner, activate TRIGGER 2.

(HPCI Initiation) o If contacted as I&C to assist with troubleshooting, acknowledge request.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 16

EVENT 4 INADVERTENT HPCIINITIATION Required Operator Actions SRO Direct crew to verify no HPCI initiation signal is present Direct crew to trip HPCI following verification offalse initiation Direct crew to isolate HPCI on failure of trip pushbutton (May use isolation pushbutton or direct steam supply valves to be closed).

Direct crew to enter and execute AOP-3.0 Positive Reactivity Addition, if injection has occurred.

Evaluate Tech Spec 3.5.3 ECCS -

Operating D Condition D. HPCI System Inoperable D Required Action 0.1 Verify by Administrative means RCIC is OPERABLE immediately D Required Action 0.2 Restore HPCI to OPERABLE status within 14 days 2008 NRC Examination Scenario #3 17

EVENT 4 INADVERTENT HPCIINITIATION BOP Verify false HPCI initiation signal (No LL2 signal present)

Trip HPCI by pushing the HPCI trip pushbutton, recognize failure of trip May depress Manual Isolation System A pushbutton to isolate HPCI.

OR May isolate the steam supply valves to HPCI to isolate system.

Enter and execute AOP-3.0 Positive Addition Respond to the following alarms:

HPCI LOW FLOW

HPCI ISOLATION TRIP SIG A INITIATED

HPCI TURBINE TRIP SOLENOID ENERGIZED

HPCU TURBINE TRIP

HPCI VACUUM TANK LVL HI RO Monitor for HPCI injection Enter and execute AOP-3.0 Positive Reactivity Addition, if injection has occurred.

o If necessary to prevent a scram, reduce reactor power per ENP-24 o Determine current operating point on the power-to-flow map o Notify Reactor Engineer o Restore power to ~1 00%

2008 NRC Examination Scenario #3 18

EVENT 5 CRD PUMP TRIP The crew responds to a CRD pump trip.

Malfunctions required:

o 2A CRD pump shaft seizure Objectives:

o Direct response to a loss of CRD pump o Respond to a loss of CRD pump o Respond to loss of CRD pump Success Path:

Crew places STBY CRD pump in service lAW OP-B.O, section B.17 Simulator Operator Activities:

o WHEN directed by the lead examiner, activate TRIGGER 3 (CRD pump shaft seizure) o If asked as the aux operator to close SEAL INJECTION FLOW CONTROLLER UPSTREAM ISOLATION VALVE and BYPASS VALVE, wait 1 minutes and report closed.

o If asked as the aux operator to open SEAL INJECTION FLOW CONTROLLER UPSTREAM ISOLATION VALVE or BYPASS VALVE, wait 1 minutes and report open.

o If contacted as RBAO to perform prestart checks on the STBY CRD Pp, wait 1 minutes and report complete and SAT.

o When directed by the lead examiner, proceed to the next event.

200B NRC Examination Scenario #3 19

EVENT 5 CRD PUMP TRIP Required Operator Actions:

SCO Direct crew to enter and execute AOP-2.0 Control Rod Malfunction/Misposition Request assistance from support personnel for assistance with troubleshooting the trip of 2A CRD pump BOP Respond to BUS E3 4KV MOTOR OVLD alarm Enter and execute AOP-2.0 Monitor plant parameters RO actions on next page 2008 NRC Examination Scenario #3 20

EVENT 5 CRD PUMP TRIP RO Enter and execute AOP-2.0 Place STBY CRD pump in service lAW OP-B.O Section B.17 as follows:

o Close SEAL INJ VLV 'V22' for RR pump 2A o Close SEAL INJ VLV 'V30' for RR pump 2B o Place CRD FLOW CNTRL in MAN and reduce setting to minimum 0 Ensure DRIVE PRESS VL V 'F003' is fully open 0 Ensure RBCCW system in operation 0 Start non-operating CRD pump 0 Raise CRD flow rate to 30-60 gpm by adjusting CRD FLOW CNTRL 0 Restore Seal Purge Flow to Recirc slAW 20P-2.0 Section B.7 0 Null CRD FLOW CNTRL by adjusting setpoint tape 0 Shift CRD FLOW CNTRL to AUTO 0 Adjust setpoint tatpe to maintain cooling water DP 10-26 psid 0 Ensure CRD flow rate 30-60 gpm 0 Establish drive water header DP 260-275 psid by throttling DRIVE PRESS VL V 'F003' 200B NRC Examination Scenario #3 21

EVENT 6 LOSS OF POWER TO MAIN STACK RAD MONITOR The crew responds to a loss of power to the main stack radiation monitor with a failure of the SBGT system to auto start.

Malfunctions required:

D Power loss to Main Stack Radiation Monitor Objectives:

D Direct response to a loss of Main Stack Radiation Monitor D Respond to a loss of Main Stack Radiation Monitor D Respond to a failure of SBGT to auto start D Respond to loss of Main Stack Radiation Monitor Success Path:

Crew recognizes SBGT failure and manually starts SBGT Simulator Operator Activities:

D WHEN directed by the lead examiner, activate TRIGGER 4 (Power loss to Main Stack Rad Monitor)

D If dispatched as AO to check UPS Panel 2A, wait 2 minutes and report circuit breaker #6 has tripped.

D If asked as I&C to investigate tripped circuit breaker, wait 2 minutes and report that the problem is isolated to the breaker. No apparent problems exist with the circuits loads.

D If asked to transfer power supplies to the Stack Rad Monitor, wait 1 minute and restore malfunction ED_1AUPB2A6 to ON. Report actions to control room.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 22

EVENT 6 LOSS OF POWER TO MAIN STACK RAD MONITOR Required Operator Actions:

SCO Direct Alarm Panel Procedure actions for loss of Main Stack Rad Monitor Diagnose alarms as indication of loss of UPS to the Main Stack Rad Mon Recognize failure of SBGT to start and direct manual start Contact support personnel for troubleshooti assistance Reference AOP-12 Loss of UPS o Consider transferring Stack Radiation Monitor power supply per OP-52 o Refer to 01-50.5 UPS Load List SCO Tech Spec Actions on next page 2008 NRC Examination Scenario #3 23

EVENT 6 LOSS OF POWER TO MAIN STACK RAD MONITOR Evaluate Tech Spec 3.3.6.1 Primary Containment Isolation Instrumentation Function 2C Main Stack Radiation High D Condition A. One or more required channels inoperable D Required Action A.1 Place Channel in tri within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Evaluate TRM 3.4 Accident Monitoring Instrumentation Function 5 Off-gas Stack Vent Monitor D Condition A. One or more Functions with one required channel inoperable D Required Action A.1 Restore required channel to OPERABLE status 1 d Evaluate ODCM 7.3.2 Function 1 Main Stack Monitoring System Evaluate Tech Spec 3.6.4.3 Standby Gas Treatment D Condition B. Two SGT subsystems inoperable in Mode 1,2 or 3 D Required Action B.1 Be in Mode 3 (12 hrs)

D Required Action B.2 Be in Mode 4 hrs 2008 NRC Examination Scenario #3 24

EVENT 6 LOSS OF POWER TO MAIN STACK RAD MONITOR BOP Report and respond to the following alarms o PROCESS OG VENT PIPE RAD HI o PROCESS OG VENT PIPE RAD HI HI o PROCESS OG VENT PIPE DNSC/INOP o RX BLDG ISOLATED o SBGT A FAILURE o SBGT B FAILURE o RX BLDG STATIC PRESS DIFF LOW Recognize and report loss of Main Stack Radiation Monitor Verify auto actions occur as described in Alarm Panel Procedure o Secondary Containment Isolation o SBGT system start Recognize a failure of SBGT to start o Manually start SBGT RO 2008 NRC Examination Scenario #3 25

EVENT 7 MAIN STEAM SYSTEM LEAK IN THE DRYWELL I SCRAM I ATWS The crew responds to a steam leak in the drywell.

Malfunctions required:

Main Steam leak upstream of flow restrictors

Auto SCRAM failure

ATWS 1

Rod select switch failure Objectives:

Direct response to rising drywell pressure per AOP-14 and PCCP

Direct SCRAM / ATWS response per Reactor Scram Procedure, Reactor Vessel Control Procedure and Level/Power Control Procedure

Respond to steam leak in primary containment

Respond to low power ATWS condition

Respond to steam leak in primary containment

Respond to low power ATWS condition Success Path:

Recognize 4 rod ATWS; Execute RVCP, LPC and PCCP to address plant conditions.

Simulator Operator Actions:

o WHEN directed by lead examiner, activate TRIGGER 4. (steam leak upstream of flow restrictors) o After the scram is inserted, modify malfunction (NB006F, MSL Break) to 5%.

o If asked as additional operator to install jumpers per LEP-02 Section 3, acknowledge request.

o If asked as I&C to investigate failure of Rod Select switch, acknowledge request.

o If requested to install jumpers to bypass LL3 Gp.1 Isol per SEP-1 0, wait 2 minutes and initiate TRIGGER 7.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #3 26

EVENT 7 MAIN STEAM SYSTEM LEAK IN THE DRYWELL I SCRAM I ATWS Required Operator Actions SRO Recognize failure of AUTO scram on Hi ressure and direct manual scram Enter and execute Level/Power Control Procedure D Direct RO initiate ARI D Direct RO place RR pumps to 10%

D Request RO report reactor power D Direct RO perform LEP-02 Alternate Rod Insertion D Direct BOP Inhibit ADS D Direct BOP perform SEP-10 Bypass Gp.1 Isolation D Direct BOP place RNA switches to OVERRIDE/RESET D Direct BOP maintain reactor water level 170-200 inches D Direct BOP maintain reactor pressure 800-1000 psig Enter and execute Primary Containment Control Procedure next 2008 NRC Examination Scenario #3 27

EVENT 7 MAIN STEAM SYSTEM LEAK IN THE DRYWELL I SCRAM I ATWS BOP Enter and execute AOP-14 o Ensure drywell coolers are running o Ensure RBCCW correctly aligned o Vent the drywell per OP-1 0 if time allows Stabilize reactor pressure below 1050 psig as directed by SRO Inhibit ADS as directed by SRO Perform SEP-10 Bypass Gp1 Low Level Isolation as directed by SRO Place Div 1&2 RNA switches to OVERIDE/RESET as directed by SRO Maintain reactor water level as directed by SRO 2008 NRC Examination Scenario #3 28

EVENT 7 MAIN STEAM SYSTEM LEAK IN THE DRYWELL I SCRAM I ATWS RO Perform Scram actions D After steam flow is less than 3E6 Ibm/hr, PLACE the mode switch to SHUTDOWN D If reactor power is below 2%, trip the main turbine D Ensure level setpoint at 170 inches D If two RFPs are running and reactor water level is above 160 inches, then trip one.

D Insert Nls D Recognize ATWS and report to SRO D Initiate ARI as directed by SRO D Place RR pump speed controllers to 10% as directed by SRO D Report reactor power is <2% as requested from SRO D Perform LEP-02 Alternate Control Rod Insertion as directed bySRO D Recognize failure of Rod Select switch and report to SRO 2008 NRC Examination Scenario #3 29

EVENT 8 DRYWELL SPRAYS WITH SPRAY VALVE FAILURES The crew will attempt to spray the drywell; spray valve failures will prevent spraying.

Malfunctions required:

'A' RHR Loop THINK switch failure

'8' RHR loop Orywell Spray valve failure Objectives:

SRO

Execute PCCP to combat degrading drywell conditions

Execute LlPC to combat ATWS conditions

Execute PCCP actions as directed by SRO

Execute LlPC actions as directed by SRO

Execute PCCP actions as directed by SRO

Execute LlPC actions as directed by SRO Success Path:

Enter and execute LlPC and Primary Containment Control Procedure; Recognize equipment failures and take corrective actions.

Simulator Operator Actions:

D If contacted as I&C to investigate failure of THINK switch, acknowledge request.

D If contacted as I&C or operator to investigate failure of Orywell Spray valve, acknowledge request.

2008 NRC Examination Scenario #3 30

EVENT 8 DRYWELL SPRAYS WITH SPRAY VALVE FAILURES Required Operator Actions:

SRO Execute Level/Power Control Procedure Execute Primary Containment Control Procedure o Evaluate level instrument operability using Caution 1 o Direct BOP start all available drywell coolers o Direct BOP Spray the suppression pool per SEP-03 o Direct BOP Spray the drywell per SEP-02 o Direct BOP to place torus cooling in service per hard card If informed by BOP/RO of THINK switch failure, contact I&C for troubleshooting assistance.

If informed by BOP/RO of Drywell Spray valve failure, contact I&C and/or Ops for troubleshooting assistance.

2008 NRC Examination Scenario #3 31

EVENT 8 DRYWELL SPRAYS WITH SPRAY VALVE FAILURES BOP/RO Maintain reactor pressure and level as directed by SRO Place Suppression Pool cooling in service as directed by SRO Spray the suppression pool per SEP-03 as directed by SRO Spray the drywell per SEP-02 as directed bySRO o Ensure WELL WTR TO VITAL HDR

'V141' is closed o Ensure 'V111' or 'V117' is OPEN o Ensure RR pumps are tripped o Place drywell cooler switches to OFF o If coolers continue to run, request LOCA lockout switches o Place LPCIINITIATION OVERRIDE switch in Manual/Override o Place CNT SPRAY CNTRL switch to Manual o "A" Loop RHR - recognize failure of THINK SWITCH and report to SRO 2008 NRC Examination Scenario #3 32

EVENT 8 DRYWELL SPRAYS WITH SPRAY VALVE FAILURES D Ensure at least one RHR pump running D Ensure TORUS CLG ISOL VL V

'F024' is closed D Confirm SAFE region of Drywell Spray Initiation graph D Verify torus level less than +21 inches D Open DRYWELL SPRAY INBD ISOL VLV 'F021' D Throttle open DRYWELL SPRAY OUTBD ISOL VLV 'F016' D "B" Loop RHR - Recognize failure of spray valve E11-F016B and report toSRO 2008 NRC Examination Scenario #3 33

EVENT 9 EMERGENCY DEPRESSURIZATION WITH ATWS CONDITIONS The crew will initiate emergency depressurization under ATWS conditions.

Malfunctions required:

SRVs K,G,E,B and F fail to open Objectives:

Execute EOPs to combat Emergency Depressurization conditions

Execute PCCP actions as directed by SRO

Execute LlPC actions as directed by SRO

Execute PCCP actions as directed by SRO

Execute LlPC actions as directed by SRO Success Path:

Terminate and prevent injection to the reactor vessel and perform emergency depressurization Simulator Operator Actions:

None 2008 NRC Examination Scenario #3 34

EVENT 9 EMERGENCY DEPRESSURIZATION WITH ATWS CONDITIONS Required Operator Actions SRO Execute Primary Containment Control Procedure Recognize the inability to restore and Critical Task maintain drywell average air temperature

<300° F Direct Emergency Depressurization from Critical Task Level Power Control o Direct BOP terminate and prevent injection to the reactor vessel o Direct BOP Open Seven ADS valves o Direct opening additional SRVs until 7 are n

o Direct BOP, when reactor pressure is below the minimum alternate flooding pressure (140 psig for 6 SRVs) direct slowly increase injection to the reactor vessel Direct establish water level 170-200 inches 2008 NRC Examination Scenario #3 35

EVENT 9 EMERGENCY DEPRESSURIZATION WITH ATWS CONDITIONS BOP/RO Maintain reactor pressure and level as directed by SRO Terminate and prevent injection into the reactor vessel as directed by SRO Open 7 ADS valves as directed by SRO o Report "K" SRV failed to open o As directed by SRO, attempt to open additional SRVs until 7 SRVs are open o Report only 6 SRVs can be opened When reactor pressure reaches 140 psig, reestablish level control as directed by SRO Scenario Termination -

When reactor water level has been restored to the band directed by the SRO after the emergency depressurization, the scenario will be terminated Simulator Operator Activities:

WHEN directed by the lead examiner, place the simulator in FREEZE.

2008 NRC Examination Scenario #3 36

CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER 2008 NRC Examination Scenario #3 37

Facility: BRUNSWICK Scenario No.: 4 Op Test No.: Final Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: Unit Two (2) is operating at 6% power. Reactor startup is in progress per GP-03.

GP-10 sequence A2X is complete through step 278.

Turnover: Continue with GP-03 actions to raise reactor power to 10% in preparation for placing the Mode switch to RUN.

Event Malf. No. Event Event Description No. Type*

1 R-RO Raise reactor power by pulling control rods SRO 2 RD012M C-RO Stuck control rod SRO 3 RD191F I-RO RWM critical self test fault / Bypass RWM (TS) 4 RD016M C-RO Uncoupled control rod (TS) 5 ZUA343 C-BOP Clogged Off-gas filter / Swap filters SRO 6 CW036F C-BOP CSW pump overload / Swap pumps (TS) 7 CF035F C-BOP SULCV fails closed / lowering reactor water level SRO 8 EE020F M-ALL Loss of SAT / DG4 trip / DG3 frequency drift / AOP-36.1 I-BOP 9 DGOO8F M-ALL DG3 output breaker trip / Station Blackout / AOP-36.2

(N)ormal, (R)eactivity, (I)nstrument, (C)om ponent, (M)ajor 2008 NRC Examination Scenario #4

SCENARIO DESCRIPTION Event 1 - The crew will continue raising power by pulling control rods in preparation for placing the Mode switch to RUN. Rods pulls will commence at step 279 of the A2X sequence.

Event 2 - When the RO attempts to pull Control rod 06-15, it will stick at the full in position. The crew will respond per the direction of OP-07 RMCS Operating Procedure.

The rod will unseat on the second sequence of step 8.1.2.2 of OP-07.

Event 3 - The RWM will fail requiring the SRO to address Tech Specs and implement contingency rod manipulation actions.

Event 4 - When control rod 26-51 is withdrawn to position 48 a "rod over travel" alarm will be received. The crew will take the actions of the APP and drive the control rod full in.

Event 5 - The clogging of the in-service Off-gas Filter will cause the "Off-gas Filter Hi DP" alarm. The crew will respond per the APP and swap off-gas filters per the OP-30.

Event 6 - An overload alarm will be received on CSW pump 2B. The crew will respond by starting the 2C CSW pump and shutting down the 2B CSW pump.

Event 7 - The SULCV will fail closed stopping feed flow to the vessel. Reactor water level will drop requiring action to re-establish flow to the vessel.

Event 8 - The SAT will trip and lockout resulting in a loss of off-site power. DG4 will auto start and trip on differential overcurrent. DG3 will fail to auto start. Auto start pushbutton in control room will also not work. Manual control room start will be successful in starting DG3. AOP-36.1 is entered and executed.

Event 9 - DG3 frequency will drift requiring the operator to take action to correct. Four minutes after DG3 starts the DG3 output breaker will trip. Station Blackout conditions exist. AOP-36.2 will be entered and executed.

2008 NRC Examination Scenario #4 2

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2008 NRC EXAM SCENARIO #4 2008 NRC Examination Scenario #4 3

SIMULATOR SETUP Initial Conditions IC-6 Rx Pwr 6%

EVENTS Event Trigger Trigger Description Number 1 Raise reactor power by pulling control rods 2 Control Rod 06-15 stuck at postion "00" 3 1 Manual RWM failure 4 Uncoupled control rod 26-51 5 2 Manual Clogged Off-gas filter 6 3 Manual CSW Pump 2A overload 7 4 Manual SULCV fails closed; lowering reactor water level 8 5 Manual Loss of SAT / DG4 trip / DG3 available / AOP-36.1 9 DG3 output Bkr trip / Station Blackout / AOP-36.2 2008 NRC Examination Scenario #4 4

SIMULATOR SETUP Malfunctions Summary MalflD Mult Description Current Target Rmptime Actime Dactime Trig ID Value Value RD012M STUCK CONTROL ROD FALSE TRUE RD191F RWM CRITICAL SELF TEST FAULT FALSE TRUE 1 RD016M UNCOUPLED CONTROL ROD FALSE TRUE CW036F CSW PUMP OVERLOAD FALSE TRUE 3 CF035F SULCV FAILS CLOSED FALSE TRUE 4 EE020F SAT RELAY FAILURE FALSE TRUE 5 DGOO4F DG3 AUTO START FAILURE FALSE TRUE Remotes Summary Remf ID Mult Description Current Target Rmptime Actime Trig ID Value Value 2008 NRC Examination Scenario #4 5

SIMULATOR SETUP Override Summary TaglD Description Position/ Actual Override Rmptime Actime Dactime Trig Target Value Value Annunciator Summary Window Description Tagname Override Type Oval AVal Actime Dactime Trig 4-3 OFF-GAS FILTER DIFF HIGH ZUAS43' ON 2 Special Instructions Load scenario file, 2008 Scenario 4.scn, if required.

Critical Tasks Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of Station Blackout commencing:

Restore AC power via cross-tie of E1 to E3 or UAT back feed

Commence depressurization of the reactor vessel to less than 300 psig 2008 NRC Examination Scenario #4 6

SHIFT BRIEFING Plant Status Unit startup is in progress per GP-03 following a refueling outage.

Reactor power is approximately 6%. Control rod withdraw is in progress per step 5.1.5 of GP-03.

Reactor pressure is 925 psig with one bypass valve open to approx. 50%.

GP-10, sequence A2X, is being used and is complete through step 278.

Equipment Out of Service No equipment is out of service Plan of the Day Continue with GP-03 actions to raise reactor power to 10% in preparation for placing the Mode switch to RUN.

Continuous control rod withdrawal is allowed per RE recommendation.

2008 NRC Examination Scenario #4 7

EVENT 1/2 RAISE REACTOR POWER 1 STUCK CONTROL ROD The crew pulls rods per GP-1 O. One rod will stick at position '00' requiring OP-07 actions to move.

Malfunctions required: Stuck Rod 06-15 Objectives:

SRO

Directs and monitor reactor power ascension with control rods

Direct actions for a stuck control rod

Perform actions for stuck control rod

Monitor plant parameters during power ascension

Pull control rods to raise reactor power

Monitor plant parameters during power ascension

Perform actions for stuck control rod Success Path:

Control rod 18-03 unstuck and withdrawn to position '12' Simulator Operator Actions:

o On the ROs second attempt to move control rod 06-15, delete stuck rod malfunction to allow rod motion.

o When directed by the lead examiner, proceed to the next event.

(after control rod 14-47, step 286, has been positioned at "12")

2008 NRC Examination Scenario #4 8

EVENT 1/2 RAISE REACTOR POWER 1 STUCK CONTROL ROD Required Operator Actions SRO Direct RO to raise reactor power by pulling control rods.

(Continuous withdrawal allowed)

Direct actions for a stuck control rod RO Control Rod Manipulation Standard per 01-01.02 (see Attachment 1)

Commence rod withdrawal at step 279 of GP-1 0 per guidance of 01-01.02 Pull first 3 rods from position 00-12 Recognize and report 4 rod stuck (06-15)

Take action per OP-07, section 8.1 to unstuck the control rod o Ensure no Rod Block exists for control rod 06-15 o Simultaneously perform the following:

Place and Hold the ROD MOVEMENT switch to NOTCH OUT

Momentarily Place the EMERGENCY ROD IN NOTCH OVERRIDE switch to EMERGENCY ROD IN approx.

8-10 times 2008 NRC Examination Scenario #4 9

EVENT 1/2 RAISE REACTOR POWER 1 STUCK CONTROL ROD Repeat steps above several times Recognize and report that control rod 06-15 has moved from position 00.

Position control rod 06-15 to "12" Pull the next 4 rods to position "12" Monitor reactor plant parameters during evolution.

2008 NRC Examination Scenario #4 10

EVENT 3 RWM FAILURE The crew responds to a Rod Worth Minimizer failure.

Malfunctions required:

Rod Worth Minimizer failure Objectives:

Direct actions for a failed RWM

Evaluates Tech Spec 3.3.2.1 Control Rod Block Instrumentation BOP/RO

Respond to a failed RWM Success Path:

Implement guidance of GP-11 Second Operator Rod Sequence Checkoff Sheets and continue pulling control rods with second rod verifier.

Simulator Operator Actions:

D When directed by the lead examiner, initiate TRIGGER 1 to fail the RWM.

D If contacted as RE for assistance or guidance, recommend following the required Tech Spec actions and GP-11 guidance.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #4 11

EVENT 3 RWM FAILURE Required Operator Actions SRO Direct RO/BOP to enter and execute applicable APPs Evaluate Tech Spec 3.3.2.1 Control Rod Block Instrumentation D Condition C. RWM inoperable during reactor startup D Required Action C.1 Suspend control rod movement except by scram (immediately)

OR D C.2.1.1 Verify> 12 rods withdrawn (immediately)

AND D C.2.2 Verify movement of bypasses bypassed control rods is in compliance with the BPWS by a second licensed operator or other qualified member of the technical staff.

(during rod movement)

Direct RO/BOP Bypass RWM Implement GP-11 Second Operator Once SRO determines GP-11 is Rod Sequence Checkoff Sheet applicable, inform SRO that the STA will be responsible for GP-11 documentation.

2008 NRC Examination Scenario #4 12

EVENT 3 RWM FAILURE RO Respond to ROD BLOCK RWM/RMCS SYS TROUBLE alarm D Check RWM NUMAC for indications of the problem D Diagnose a critical self test fault exists and report to SRO May recommend bypassing the RWM to continue with startu Once the RWM is bypassed and GP-11 has been implemented, continue pulling rods at step 287 of the ull sheet ntrol rod 26-03 BOP Monitor reactor plant parameters during evolution.

2008 NRC Examination Scenario #4 13

EVENT 4 UNCOUPLED CONTROL ROD The crew responds to an uncoupled control rod.

Malfunctions required:

Uncoupled control rod 26-51 Objectives:

Direct actions for an uncoupled control rod per APP

Evaluates Tech Spec 3.1.3 Control Rod Operability BOP/RO

Respond to an uncoupled control rod

Respond to ROD OVERTRAVEL alarm Success Path:

Insert control rod 26-51 Full-In to re-couple Simulator Operator Actions:

o When control rod 26-51 has been fully inserted, delete over travel malfunction to allow resetting of the ROD DRIFT alarm.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #4 14

EVENT 4 UNCOUPLED CONTROL ROD Required Operator Actions SRO Direct RO/BOP to enter and execute applicable APPs Evaluate Tech Spec 3.1.3 Control Rod Operability o Condition C. One or more control rods inoperable for reasons other than Condition A or B o Required Action C.1 Fully insert control rod (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) o Required Action C.2 Disarm the associated CRD Direct RO to ful insert rod to Full In RO Pull next 3 control rods from 12 to 48 and verify coupling as follows:

o Maintain continuous withdraw signal for 3-5 seconds or a separate NOTCH OUT signal o Verify no ROD OVERTRAVEL alarm o Verify no ROD DRIFT alarm o Verify FULL OUT indication o Verify 4-Rod display indicates "48" Respond to ROD OVERTRAVEL alarm when rod 26-51 exceeds "48" Verify ROD DRIFT alarm Fully insert rod 26-51 when directed by SRO and reset ROD DRIFT alarm Notify RE of inserted control rod 2008 NRC Examination Scenario #4 15

EVENT 4 UNCOUPLED CONTROL ROD BOP Monitor plant parameters during evolution 2008 NRC Examination Scenario #4 16

EVENT 5 CLOGGED OFF-GAS FILTER The crew responds to a clogged off-gas filter.

Malfunctions required:

D Clogged off-gas filter Objectives:

Direct actions in response to a Off-gas Filter Diff-Hi alarm BOP/RO

Respond to clogged off-gas filter

Monitor plant parameters Success Path:

Swap Off-gas filters per OP-30 Simulator Operator Actions:

D WHEN directed by lead examiner, activate TRIGGER 2 (Off-gas filter Diff Hi alarm)

D IF contacted as Outside AO to verify Off-gas filter Diff pressure, report local DP indication is reading 13" water.

D IF contacted as AO report 1-0G-CD-V7 is CLOSED D IF contacted as AO report 2-0G-CD-V7 is OPEN D IF contacted as Outside AO to verify Off-gas filter Diff pressure after filter swap, report local DP indication is reading less than 3" water.

D WHEN filter swap is complete, remove TRIGGER 2 annunciator.

D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #4 17

EVENT 5 CLOGGED OFF-GAS FILTER Required Operator Actions SRO Direct crew to perform the actions of OFF GAS FILTER DIFF-HIGH alarm Direct crew to swap Off-gas filters per OP-30 Section 8.3 BOP Respond to OFF GAS FILTER DIFF-HIGH alarm D Dispatch Outside AO to verify Off-gas filter Diff Hi locally Place Off-gas Stby filter in service per Op-30 Section 8.3 as follows:

D Ensure 1-0G-FV-244-4 and 244-5 are closed D Ensure 1-AOG-HCV-1 01 is closed D Ensure 1-0G-CD-V7 is closed D

D OPEN 2-0G-FV-244-4 and 244-5 D OPEN 2-AOG-HCV-101 Remove Off-gas Filter from service as follows:

D CLOSE 2-0G-FV-244-1 ,2,3 Ensure Filter Dipressure less than 10" water Place 2-AOG-HCV-1 01 control switch to OPEN 2008 NRC Examination Scenario #4 18

EVENT 5 CLOGGED OFF-GAS FILTER RO Monitor plant parameters during evolution

. 2008 NRC Examination Scenario #4 19

EVENT 6 CSW PUMP MOTOR OVERLOAD The crew responds to a CSW Pump Overload alarm Malfunctions required:

2A CSW Pump Overload Objectives:

SCO

Direct actions for CSW pump motor overload

Swap CSW pumps

Monitors reactor plant parameters Success Path:

2A CSW removed from service and 2C CSW placed in service.

Simulator Operator Actions:

o WHEN directed by the lead examiner, activate TRIGGER 3 (CSW Pump overload) o If contacted as Outside AO, report 51 device phase B shows target at 2A CSW pump breaker on Bus E4 o IF contacted as Outside AO, report pre-start checks complete SAT on 2C CSW pump.

o If asked as I&C to investigate, acknowledge request.

o When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #4 20

EVENT 5 CSW PUMP MOTOR OVERLOAD Required Operator Actions Direct crew to respond to BUS E3 4KV MOTOR OVLD alarm Evaluate Tech Spec 3.7.2 Service (also reference Ops Standing Order Water and Ultimate Heat Sink # 08-053 and AR #286690)

D Condition C - One required CSW pump inoperable D Required Action C.1 - Verify the one operable CSW and one operable U/2 NSW pump powered from separate 4KV buses (Immediately)

D Restore required pump to operable (7 days and 14 days from d to meet BOP Respond to BUS E3 4KV MOTOR OVLD alarm by checking for tripped loads Dispatch AO to investigate Bus E3 for abnormal conditions Perform OP-43 Section 8.23 to start 2C CSW pump and secure 2A CSW pump as follows:

Place 2C Mode Selector in MAN Start CSW pump 2C Stop CSW pump 2A Leave 2A Mode Selector in MAN RO Monitor plant parameters during evolution 2008 NRC Examination Scenario #4 21

EVENT 7 SULCV FAILS CLOSED The crew responds to SULCV failing closed and reactor water level lowering.

Malfunctions required:

SULCV fail closed Objectives:

Direct actions for failed SULCV and lowering reactor water level

Take action to respond to a failed SULCV and lowering reactor water level

Monitors reactor plant parameters Success Path:

Level restored to normal band by establishing flow through an alternate path Simulator Operator Actions:

D WHEN directed by the lead examiner, activate TRIGGER 4 D When directed by the lead examiner, proceed to the next event.

2008 NRC Examination Scenario #4 22

EVENT 7 SULCV FAILS CLOSED Required Operator Actions SRO nual scram as necessa BOP Recognize lowering reactor water level (may notice before alarm)

Respond to REACTOR WATER LEVEL HIGH/LOW alarm Recognize SULCV has failed closed and attempt to OPEN Attempt to establish flow to the vessel by manually opening one of the following valves:

FW-V120

FW-V118

FW-V119 If direct RO Monitor plant parameters during evolution 2008 NRC Examination Scenario #4 23

EVENT 8 LOSS OF SAT The crew responds to the the loss of SAT and DG3 trip by entering AOP-36.1 Malfunctions required:

DG4 trip on differential overcurrent

DG3 auto start failure

DG3 auto start pushbutton failure

DG3 frequency drift Objectives:

Direct the actions of AOP-36.1 BOP/RO

Perform the actions of AOP-36.1 Success Path:

Control Room manual start DG3 and tie to E3 Simulator Operator Activities:

o WHEN directed by lead examiner, activate TRIGGER 5 (SAT loss) 2008 NRC Examination Scenario #4 24

EVENT 8 LOSS OF SAT Required Operator Actions SRO Recognize loss of SAT and direct crew to enter and execute AOP-36.1 Enter and Execute RVCP D Direct RO to maintain reactor water level 170" to 200" with available Table 1 systems D Direct RO to maintain reactor pressure below 1050 psig using SRVs BOP Recognize Loss of SAT Recognize Trip of DG4 on overcurrent Recognize failure of DG3 to start Manually start DG3 and tie to Bus E3 Recognize DG3 frequency fluctuations and take manual action to adjust to 60 hertz.

RO D Trip the main turbine D Ensure level nt at 170" Maintain reactor pressure and level as directed the SRO 2008 NRC Examination Scenario #4 25

EVENT 9 STATION BLACKOUT The crew responds to a station blackout following the trip of DG3 output breaker.

Malfunctions required:

DG3 output breaker trip Objectives:

SCO

Direct the actions of AOP-36.2 BOP/RO

Perform the actions of AOP-36.2 Success Path:

Crosstie 4KV buses E1 to E3 and depressurize the reactor to less than 300 psig.

Simulator Operator Activities:

o If contacted for assistance with Cross-tying E-buses, reference AOP-36.2 section 3.2.11 and perform requested actions to support cross-tie. This will require many E3 and E1 breakers to be opened and their control power fuses removed. This will require placing the E-bus Control Selector switches to SBO using the cross-tie breaker key. This will require local closing of the E-bus cross-tie breakers.

Termination Cue When Bus E3 has been energized via cross-tie or UAT backfeed and the crew has commenced a cooldown in excess of 1OOf/hr the scenario may be terminated.

2008 NRC Examination Scenario #4 26

EVENT 9 STATION BLACKOUT Required Operator Actions SRO Enter and Execute AOP-36.2 Station Mark initial reactor pressure.

Blackout D Notify other Unit to enter AOP-36.2 D Notify System dispatch that Unit 2 is in Station Blackout D Notify Security to take actions for Station Blackout D Direct UAT Backfeed per OP-50 Enter the applicable Supplementary Action Section per Table 1 (Sect 3.2.9)

D Direct Cross-tie of Bus E1 to E3 per section 3.2.11 D Direct alignment of SAMG DIGs per section 3.2.22 D Direct cool down of Unit 2 to between 150 psig and 300 psig using SRVs at a rate greater than 100F per hour.

D Direct starting U/2 drywell cooling per section 3.2.14 D Direct starting U/2 suppression pool cooling per section 3.2.16 2008 NRC Examination Scenario #4 27

EVENT 9 STATION BLACKOUT BOP Recognize loss of DG3 and report Station Blackout conditions to SRO Perform E1 to E3 cross-tie as directed by SRO OP-36.2 section 3.2.11 RO Perform reactor depressurization to Mark final reactor pressure.

between 150-300 psig with SRVs Maintain reactor water level as directed by the SRO o Place RCIC in service per the hard card o Place HPCI is service per the hard card Termination Cue When Bus E3 has been energized via cross-tie or UAT backfeed and the crew has commenced a cooldown in excess of 1OOf/hr the scenario may be terminated.

2008 NRC Examination Scenario #4 28

Simulator Operator Activities:

WHEN directed by the lead examiner, place the simulator in FREEZE.

CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER 2008 NRC Examination Scenario #4 29

Attachment 1 For Control Rod Manipulations:

1) Manipulates control rods only with SRO permission.

2) Verifies no other reactivity impacting manipulation is occurring.

3) Ensures Concurrent Verifier is available, prepared, and in place.

4) Selects the correct control rod using good self checking techniques.

5) Verifies control rod selection by observing select pushbutton lit.

6) Verifies control rod selection by confirming selection on RWM screen.

7) Verifies control rod selection using full core display.

8) Verifies control rod position using control rod display, confirms it matches expected position.

9) Communicates the following:

a) Control rod selected b) Starting position c) Movement to be taken d) Limitations on movement e) Final position to the Concurrent Verifier NOTE: The following are acceptable methods for ensuring proper control switch manipulation and should be used just prior to control rod motion:

- Placing hands above the movement switches and moving them in the direction of intent

- Placing a finger on the portion of the switch label corresponding to the movement intent (IN or NOTCH OUT)

- Use of different hand positions, depending on the direction of the intended movement of the switch f) Direction control switch manipulation

10) Obtains concurrence (documented by initials) of Concurrent Verifier before beginning the move.

11) Observes plant response to movement commands.

NOTE: The guidance of Steps C.3.i.12 & 13 is waived during emergency conditions or when the Reactor Engineer, with the Shift Superintendent concurrence, has determined that notch operation will result in thermal limits challenges.

12) When moving a control rod four notches or more, stops one notch short, then single notches to final position unless control rod is going to position "48" (full out).

13) When moving a control rod three notch or less, performs separate single notch moves.

2008 NRC Examination Scenario #4 30

Attachment 1 For Control Rod Manipulations: (continued)

14) When control rod movement completed, verifies settle light is extinguished and the control rod is at a settled, latched position.

15) Does NOT select another control rod until three seconds after control rod settle light has extinguished.

16) Periodically checks position on applicable Power to Flow map.

17) Ensures Concurrent Verifier performs duties per OPS-NGGC-1306.

18) Updates and signs documentation as steps are completed.

2008 NRC Examination Scenario #4 31

ML090270043

Text

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