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Brunswick Initial Exam 2010-301 Final Simulator Scenarios
	ML101590173
Person / Time
Site:	Brunswick
Issue date:	05/03/2010
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-324/10-301, 50-325/10-301
	Download: ML101590173 (131)
	v • d • e

Appendix D Scenario Outline Form ES-D Facility:

BRUNSWICK Scenario No.: 2010-1 # 2 Op-Test No.: FINAL Examiners:

Operators: (SRO) (RO) (BOP) Initial Conditions:

The plant is operating at 100% power with Condensate Pump 2C and 1A NSW pump out of service for maintenance.

CWIP 2B needs to be removed from service to support motor oil replacement.

Turnover:

Reduce reactor power to 90% to support shifting CWIPs lAW 20P-29. = Event Malt. No. Event Event Description No. Type* 1 N/A R-RO Power reduction to support removal of CWIP 2A R-SRO 2 N/A N-BOP Shift CWIPs to remove 2B from service. N-SRO 3 ZA164 I-SRO CST Level switch failure (TS) 3a Q1108RRL C-RO E41-F004 fails to auto close Q1108LGL C-SRO 4 CF095F I-BOP 2A HDP trip I-SRO 5 RW013F M-AII RWCU leak in reactor building 77 ft. 6 EE030M C-BOP Loss of MCC 2XC C-SRO 7 RW016F C-RO 2-G31-F004 motor overload C-SRO 8 N/A M-AII Manual reactor Scram prior to MSOT/L 9 K4101B C-BOP BOP bus 2D fault fail to transfer C-SRO 10 ES041F I-RO RCIC auto start failure I-SRO 11 ZUA1214 SRHR water level Hi-HI (2 areas above Max Safe Operating Water Level) Emergency Depressurization required 12 RPV depressurized with level in the normal band. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-1 NRC EXAM SCENARIO #2 SCENARIO DESCRIPTION The plant is operating at 100% power with Condensate Pump 2C out of service for maintenance.

CWIP 2B needs to be removed from service to support motor oil replacement.

Event 1 Reduce reactor power to 90% to support CWIP shift lAW 20P-29 (third Condensate Pump is not available, power reduction required).

Event 2 Shift CWIPs lAW 20P-29, Section 8.14 Event 3 HPCI CST level transmitter will fail low causing auto swap of HPCI suction to the Suppression Pool. Event 3a E41-F004 (HPCI CST Suction Valve) will fail to automatically close when both the Suppression Pool Suction valves reach full open position.

Event 4 Heater Drain Pump 2A shaft seizes and trips on overcurrent.

Heater Drain tank level will rise and the crew will throttle HD-V57 to stabilize HD Tank level. If the standby HOP is not started, RFP suction pressure will lower during the transient requiring power reduction to stabilize Condensate/feedwater.

Event 5 A line rupture will develop in the RWCU system in the 77' elevation.

Event 6 MCC 2XC will de-energize due to fault from steam leaking into the Reactor Building (loss of power to G31-F001)

Event 7 G31-F004 will thermally trip. OAOP-05 will be entered and the Reactor Building temperatures and water levels will rise requiring a manual scram. Event 8 Manual Scram prior to reaching the Maximum Safe Operating Temperature or Level. Event 9 When the turbine is tripped, BOP Bus 20 will fail to auto transfer to the SAT. DG3 will auto start and energize E3. DG1 will auto start on Loss BOP Bus 20 with UAT de-energized.

Loss of BOP Bus 20 will require entry into OAOP-36.1 and causes a loss of FW injection.

Reactor water level will drop due to the inventory loss through the leak. Event 10 If level drops to the LL2 initiation, RCIC will fail to auto initiate, but can be manually started. With RCIC injection maximized, LEP-01 alternate coolant injection systems, along with SEP-09 CRD flow maximized (RB inaccessible)

RPV level will be maintained above TAF. Event 11 Area temperatures and water levels will rise. South Core Spray will exceed Max Normal, then Max Safe Operating Water Level. Then South RHR will exceed Max normal then Max Safe Operating Water Level. The crew is directed to consider anticipating emergency depressurization as soon as EOP-03-SCCP directs inserting a manual scram. If the crew does not anticipate emergency depressurization (rapid depressurization to the main condenser) a second area will exceed Max Safe Operating Water Level requiring Emergency Depressurization.

Event 12 Once the reactor is depressurized and RPV level is being maintained

+170-200", the scenario may be terminated.

3 OBJECTIVES SRO 1. 3442278402, Direct Action For Condensate/Feedwater System Failures Per AOP-23.0 2. 3442078502, Direct Actions To Control Secondary Containment Area Temperatures Per EOP-03-SCCP

3. 3442088502, Direct Actions To Control Secondary Containment Area Radiation Levels Per EOP-03-SCCP

4. 3442098502, Direct Actions To Control Secondary Containment Water Level Per EOP-03-SCCP

5. 3442338502, Direct Actions To Anticipate Emergency Depressurization Per EOP-01-RVCP 6. 3442178502, Direct Actions To Control RPV Level Per EOP-01-RVCP

7. 3442278502, Direct Actions To Control An Unmonitored Radioactive Release With The Release Rate Less Than That Requiring An Alert Declaration Per EOP-04-RRCP RO 1. 2590018401, Respond To A Condensate/Feedwater System Failure Per AOP-23 2. 2170038101, Manually Startup the RCIC System Per OP-16 3. 2000658501, Monitor Reactor Water Level Instrumentation Per EOP Caution 1 4. 2006018401, Respond to radioactive spills, high radiation and airborne activity per AOP-5.0 5. 2006038501, Perform immediate actions for a reactor scram 6. 2002198501, Rapidly Depressurize the Reactor Using the 8ypass Valves per EOP-01-RVCP REFERENCES A. OP-29 8. AOP-03.0 C. AOP-05.0 D. AOP-19.0 E. AOP-36.1 F. 01-50 G. EOP-01-RSP H. EOP-01-RVCP I. EOP-02-PCCP J. EOP-03-SCCP K. EOP-04-RRCP L. EOP-LEP-01 M. EOP-01-SEP-09 N. Conduct Of Operations Manual O. Technical Specifications P. Plant Emergency Procedures Q. Annunciator Panel Procedures 4

SIMULATOR SETUP A. Initial Conditions 1.IC 2. Rx Pwr 3. Core Age B. E tT* ven nggers Event 13 100% EOC Trigger Description 0 Normal Operation (Reduce reactor power and shift CWIPs) 1 Manually Initiated (ZA 164 HPCI CST Level Transmitter fails low) 2 Manually Initiated (2A HDP Seized Shaft) 3 Manually Initiated (RWCU Rupture) 4 Auto initiated (Loss of MCC 2XC -G31-F001) 5 Auto Initiated (G31-F004 Green = TRUE, overrides on F004) Auto Initiated (Loss of BOP bus 2D fail to transfer)

Auto Initiated (S RHR Flood Hi-Hi Alarm) C. Malfunctions Malfunctions Summary MalflD Mult Description Current Target Rmptime Actime ID Value Value CF095F A HEATER DRAIN PUMP SHAFT SEIZURE FALSE TRUE RW013F RWCU BRK TRIANGLE ROOM 77' 50% 10 MIN EE030M 2XC INDIVIDUAL BUS FAILURE FALSE TRUE ES041F RCIC FAILURE TO AUTO START TRUE TRUE RW015F 2-G31-F001 FAILS TO ISOLATE TRUE TRUE RW016F 2-G31-F004 FAILS TO ISOLATE TRUE TRUE Remotes Summary Remf ID Mult Description Current Target Rmptime ID Value Value ZVRW004M G31-F004 SW_IATRVER INTAKE CANAL TEMPERATURE 65.64 65.64 SW_IALRVER INTAKE CANAL LEVEL 1.0000 1.0000 5 Dactime Trig 2 3 4 Actime Trig 5 SIMULATOR SETUP D. Overrides Switches Tag 10 Description K4101B SAT INC LINE TO BUS 20 ON K4101B SAT INC LINE TO BUS 20 ON K4101B SAT INC LINE TO BUS 20 ON K1123A SUPP POOL SUCT VLV E41-F041 K1123A SUPP POOL SUCT VLV E41-F041 K1123A SUPP POOL SUCT VLV E41-F041 K1124A SUPP POOL SUCT VLV E41-F042 K1124A SUPP POOL SUCTVLV E41-F042 K1124A SUPP POOL SUCT VLV E41-F042 Lamps Tag 10 Description Q1410RRK RWCU VLV G31-F004 RED Q1410LGK RWCU VLV G31-F004 GREEN Q1108RRL CST SUCT VLV E41-F004 RED Q1108LGL CST SUCT VLV E41-F004 GREEN Q44202GY COND PMP C PMP OFF G Q44201GY COND PMP C DISCH VLV (GREEN) Q44201HY COND PMP C RECIRC VLV (GREEN) Q1124RRL TORUS SUCTVLV E41-F042 RED Q1124LGL TORUS SUCT VL V E41-F042 GREEN Annunciator Summary Event Panel Tag Position/

Actual Target Value NORMAL ON CLOSE OFF TRIP OFF AUTO ON CLOSE OFF OPEN OFF AUTO ON CLOSE OFF OPEN OFF Position/

Actual Target Value ON/OFF ON ON/OFF OFF ON/OFF ON ON/OFF OFF ON/OFF ON ON/OFF OFF ON/OFF ON ON/OFF OFF ON/OFF ON Title P601 ZA164 HPCICONDSTORAGETNK WTR LVL LO P601 ZA255 OUTBD NSSS Vlv Ovid XU-3 ZUA1214 S RHR Flood Hi-Hi E. Materials ENP-24 for IC-13 6 Override Rmptime Actime Dactime Trig Value OFF OFF ON OFF 1 OFF 1 ON 1 OFF 11 OFF 11 ON 11 Override Rmptime Actime Dactime Trig Value ON ON 2 ON OFF OFF OFF OFF ON 1 OFF 10 Value Activate Deactivate Trig (ramp Time (sec) Time (sec) rate) ON o SEC NA 1 ON OSEC NA 5 ON OSEC NA 6 F. Special Instructions

1. Ensure "Exam In Progress" Stop Signs posted at all simulator entrances.

2. Advance all chart recorders to indicate steady state conditions.

3. Place all SPDS displays to the Critical Plant Variable display (#100). 4. Ensure appropriate keys have blanks in switches.

5. Exit shutdown screen on RWM and place the RWM key in the key locker. 6. Reset alarms on SJAE, MSL, and RWM NUMACs. 7. Ensure reference material is in appropriate location.

8. Verify all log books have blank sheets only. 9. Place red cap on Condensate Pump 2C and ensure Unit Trip Load Shed plaque is updated for the current line-up. 10. Ensure LOCA Load Shed plaque reflects 2A CWIP enabled (2C Disabled).

11. Ensure CWIP Screens identifier on XU-2 represents fine mesh (green magnet) for 2A and 20 Traveling Screens. 12. Ensure ENP-24 for IC-13 @ P603. 13. Ensure Hotwell Temperature is below 115°F (C099) to allow 2 Condensate pump operation. (OP-32 P&L) 14. Load scenario file, 2010 Scenario 2.scn, if required.

7 SHIFT BRIEFING Plant Status Unit 2 is operating at 100% power, Middle of Cycle. A severe thunderstorm warning has been issued for Brunswick County for the next 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Equipment Out of Service Condensate Pump 2C is under clearance for pump impeller replacement and is expected to remain out of service for the next five days. NSW Pump 1 A is under clearance breaker refurbishment and is expected to be returned to service in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . No other equipment is out of service Plan of the Day Reduce reactor power to 90% to support shifting CWIPs. CWIP 2B needs to be removed from service to support motor oil replacement.

Another operator will perform 20P-29, Section 8.29 (NPDES Permit Flow Limit Verification) actions as required before, during, and following CWIP shift. The Circ Isol Valves Mode Selector Switch is required to be returned to the original position after the pump shift has been completed.

SCENARIO TRAINING INFORMATION A. Instructor Notes 1. This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Revision 9, ES-301 and Appendix D. 2. During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-303. B. Common Student Problems/Errors None C. Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.

D. CREW CRITICAL TASKS (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)

1. Manually Scram the Reactor before an area reaches Maximum Safe Operating value. 2. Depressurize the RPV by performing or anticipating Emergency Depressurization.

9 EVENT 1 SHIFT TURNOVER, REDUCE POWER Reduce reactor power to 90% to support CWIP shift lAW 20P-29 (third Condensate Pump is not available, power reduction required).

Objectives:

SCO -Directs power to be reduced in order to shift CWIPs. RO -Performs power reduction in accordance with ENP-24.5.

Success Path: Power reduced to less than or equal to 90% 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 Unit 2 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 90% to support CWIP shift. SRO Time Action Notes Directs power to be reduced in accordance with ENP-24.5 using recirculation flow in order to swap CWIPs. Directs RO to insert control rods to get below the MELL line. May direct OGP-12 reference due to control rod movements.

10 EVENT 1 SHIFT TURNOVER, REDUCE POWER RO Time Action Notes May reference 20P-02, Section 7.1 Request peer checker / reactivity team. Reduces power lAW ENP-24.5 using recirculation flow to 90% 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 speed reductions until 90% 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 22-19) Turns control rod power on. Selects control rod (22-19) in accordance with ENP-24.5 sheet. May also insert 30-35,30-19, or 22-35. (in this order in order to establish a margin to the MELLL line) Continuously drives selected rod full in using RMCS. BOP I Time Monitors the plant. I Action I Notes 11 EVENT 2 CWIP SHIFT Shift CWIPs lAW 20P-29, Section 8.14 Objectives:

SCO -Directs shifting CWIPs. BOP -Performs CWIP shift in accordance with 20P-29, Section 8.14. Success Path: 2C CWIP in service and 2B CWIP shutdown with the CW ISOL VALVES MODE SELECTOR in position C. Simulator Operator Actions: D If contacted as E&RC, acknowledge CWIP pump shift. D If contacted as Radwaste, acknowledge CWIP pump shift. D If contacted as Outside AO, report prestart checks satisfactory for CWIP 2C. D If contacted as Outside AO to monitor circulating water traveling screen differential pressure, acknowledge request. D If contacted as Unit One, report 3 CWIP and 3 CWOD pumps in service on U1. D When 2C CWIP is started, contact BOP as Outside AO to report 2C CWIP satisfactory start and normal traveling screen differential pressures.

D When directed by the lead examiner, proceed to the next event. Required Operator Actions Normal Operation

-20P-29, Section 8.14 (Shifting Circulating Water Intake Pumps). SRO Time Action Notes Directs placing 2C CWIP in service and shutting down 2B CWIP. Directs RO to monitor the plant. RO Time Action Notes Monitors the plant. Monitors reactor recirculation pump speed during CWIP start. 12 EVENT 2 CWIP SHIFT BOP Time Action Notes Obtains 20P-29, Section 8.14 (Shifting Circulating Water Intake Pumps). Reviews 20P-29 precautions and limitations:

Change in CWIP combination and circulating pump mode switch shall be recorded in the log. (P&L 3.9) The time four CWIPs are in operation during pump swaps should be limited to approximately two minutes. (P&L 3.20) Verifies Circulating Water System operation 3 sets of intake and discharge pumps operating. (May call U1 to verify U1 Circ Water alignment)

Verifies mean sea level greater than 0 feet indicated on INTAKE/DISCHARGE CANAL LEVEL recorder, SCW-LR-285/CW-LR-761 , or Computer Point, L 125. Notifies Radwaste of pending CWIP shift to ensure proper operation of Chlorination System. Recognizes power reduction to 90% is required and is met. Ensures RW Radioactive Release is not occurring and that routine CWIP shift will not impact release. Dispatches an AO to monitor circulating water traveling screen differential pressure.

13 EVENT 2 CWIP SHIFT BOP Time Action Ensures RO monitors reactor recirculation pump speeds during CWIP start. Places CW ISOL VAL VES MODE SELECTOR switch in position D. Monitors water box outlet valve positions.

(4 Pump Only light lit) Starts 2C CWIP. Makes PA announcement Contact OS AO for proper start Stops 2B CWIP Makes PA announcement Contact OS AO for proper stop LOCA Load Shed should already be enabled on 2A CWIP and was not Enabled for 2C CWIP Ensures condenser vacuum is being maintained in the normal operating range. Places CW ISOL VAL VES MODE SELECTOR switch in position C. Monitors water box outlet valve positions (April requires "C") May use PPC Screen # 405 Informs SRO CWIP shift is complete, 2B CWIP is shutdown.

14 Notes 4 CWIP operation should be limited to 2 minutes.

EVENT 3 HPCI CST LEVEL TRANSMITTER FAILS LOW I E41-F004 FAILURE HPCI Condensate Storage Tank Level Switch E41-LSL-N002 will fail low causing HPCI suction to shift to the Suppression Pool. The crew will respond per APP A-1 6-4 and align HPCI suction to the Suppression Pool. Objectives:

SCO -Address Technical Specifications for HPCI CST level transmitter inoperability RO -Diagnose HPCI CST low level and failure of E41-F004.

Success Path: HPCI suction aligned to the Suppression Pool only and TS addressed Simulator Operator Actions: o When directed by lead examiner, initiate Trigger 1 to initiate HPCI CST level transmitter failure. o If contacted as I&C to investigate, wait 2 minutes and report E41-LSL-N002 has failed downscale and need replaced.

o If contacted as I&C to investigate E41-F004 auto closure failure, acknowledge request. o If contacted as Ops Center SRO to initiate an impairment lAW OPLP-01.5 and establish compensatory measures for ASSD and Station Blackout procedures with HPCI aligned to the Suppression Pool, acknowledge the request. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Instrument

/ Component Failure -Align HPCI suction to the Suppression Pool SRO Time Action Notes Direct annunciator response for A-1 6-4 HPCI COND STORAGE TNK WTRLVLLO Identify requirement to initiate an impairment lAW OPLP-01.5 and establish compensatory measures for ASSD and Station Blackout procedures with HPCI aligned to the Suppression Pool. (These actions may be directed to Ops Center SRO) Directs BOP to monitor the plant. Directs closure of E41-FOO4 15 EVENT 3 HPCI CST LEVEL TRANSMITTER FAILS LOW I E41-F004 FAILURE SRO Time Action Notes Contact I&C to investigate HPCI CST level transmitter failure and E41-F004 auto closure failure. Refer to Tech Spec 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation and Determine Function 3.d requires 2 Channels.

CONDITION A. One or more channels inoperable.

REQUIRED ACTION A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel ("0")-Immediately.

CONDITION 0 REQUIRED ACTION 0.1 Declare HPCI System inoperable (Only applicable if HPCI pump suction is not aligned to the suppression pool) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI initiation capability.

AND 0.2.1 Place channel in trip. OR 0.2.2 Align the HPCI pump suction to the suppression pool Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . May reference 001-18 to place channel in trip -requires aligning suction to Suppression Pool. 16 EVENT 3 HPCI CST LEVEL TRANSMITTER FAILS LOW I E41-F004 FAILURE RO Time Action Notes Acknowledge and report annunciator A-1 6-4HPCI COND STORAGE TNK WTR LVL LO Verifies Auto Actions Torus Suction Valve, E41-F041, open. Torus Suction Valve, E41-F042, open. CST suction Valve, E41-F004, closed. Recognize and report E41-F004 auto closure failure. Manually closes E41-FOO4 Notifies SRO HPCI suction is aligned to the Suppression Pool Notifies SRO of APP requirement to initiate an impairment lAW OPLP-01.5 and establish compensatory measures for ASSD and Station Blackout procedures with HPCI aligned to the Suppression Pool. BOP Time Action Notes Monitors the plant and reports CST at normal level 17 EVENT 4 2A HEATER DRAIN PUMP TRIP Heater Drain Pump 2A shaft seizes and trips on overcurrent.

Heater Drain tank level will rise and the crew will throttle HD-V57 to stabilize HD Tank level. If the standby HDP is not started, RFP suction pressure will lower during the transient requiring power reduction to stabilize Condensate/feedwater.

Objectives:

SCO -Directs AOP-23 and possible AOP-03.0 entry BOP -Diagnose HDP pump trip and start the standby HDP. Success Path: 2C HDP started with HDD level recovered in the normal band. Simulator Operator Actions: o When directed by lead examiner, initiate Trigger 2 to initiate 2A HDP trip. o If contacted as AO to investigate, wait 2 minutes and report over-current flags for all phases of 2A HDP 4KV breaker on Bus 2D. o If requested as I&C to investigate Heater Drain Pump malfunctions, acknowledge the request. o If contacted as RE for reduced FW Temp, acknowledge request. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Instrument I Component Failure -Start standby Heater Drain Pump SRO Time Action Notes Direct annunciator response for UA-04 4-10 HD PUMP A TRIP 2-10 HD DEAERATOR LEVEL HIGH-LOW 3-10 HD DEAERATOR LEVEL HIGH TRIP Start standby HDP. May direct AOP-3.0 entry if power rises due to the HDD Ext Trip. May direct monitoring of final feedwater temperature.

18 EVENT 4 2A HEATER DRAIN PUMP TRIP RO Time Action Notes Monitors the plant May reduce power lAW AOP-23 to stabilize reactor water level. BOP Time Action Notes Recognize and report annunciators:

UA-04 4-10 HO PUMP A TRIP 2-10 HO OEAERATOR LEVEL HIGH-LOW 3-10 HO OEAERATOR LEVEL HIGH TRIP UA-06 1-7 BUS 20 4 KV MOTOR OVLO Manually starts 2C HOP lAW APP or AOP. Enter and announce AOP-23 entry Monitors final feedwater temperature (FFWT) lAW 201-03.2 May open the HD-V57 to assist in HOD level recovery.

Directs an AO to 4.16 KV Switchgear Bus 20 to investigate 2A HOP trip Verifies auto actions for HO OEAERA TOR LEVEL HIGH TRIP 1. Nonreturn valves (EX-VII and EX-Vl2)to deaerator close. 2. HOD Extraction Line B moisture removal valves (MVD-LV-266 and MVD-LV-267) open. May reference 20P-35 to recover MRVs following HOD level restoration.

19 EVENT 5/617 RWCU Leak -77' RB, MCC 2XC LOSS, G31-F004 FAILURE A line rupture will develop in the RWCU system in the 77' elevation.

MCC 2XC will de-energize due to fault (loss of power to G31-F001) and G31-F004 will thermally trip. OAOP-05 will be entered and the 77' elevation temperature and radiation levels will rise requiring a manual scram. (SOUTH CS RM FLOOD LEVEL HI alarms 10 minutes, followed by SOUTH CS RM FLOOD LEVEL HI-HI at 14 minutes, and SOUTH RHR RM FLOOD LEVEL HI at 17 minutes without cooling down.) Objectives:

SCO Directs OAOP-5.0 entry Directs EOP-03-SCCP entry Directs Reactor Scram with Unisolable Primary leak in Secondary Containment BOP Perform AOP-05 actions RO Diagnose RWCU rupture and isolation failure Success Path: Manual reactor scram inserted prior to reaching Max Safe Operating Temp or Level Simulator Operator Actions: o When the crew has stabilized the plant after the CSW failure and directed by lead examiner, initiate Trigger 3 to start the RWCU rupture o When Rx Bldg ARM alarms, report as RBAO steam on 50' elevation and you have left the building o If requested to close PIV-33, wait 3 minutes and report closed o If contacted as Engineering, Chem, HP, Maintenance, I&C, OSAO, acknowledge report o When directed by the lead examiner, proceed to the next event. Required Operator Actions Major -Enter OAOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity and upon recognition of RWCU isolation not available insert reactor scram. SRO Time Action Notes Direct entry into AOP-05.0 Enter and direct EOP-03-SCCP Direct verification of auto actions RB Vent Exh rise above 4mr/hr -RB HVAC isolations and SBGT auto start. Direct evacuation of the reactor building Diagnose leak from RWCU and direct RWCU isolation 20 EVENT 5/6/7 Rweu Leak -77' RB, Mee 2Xe LOSS, G31-F004 FAILURE SRO Time Action Notes Direct RHR room coolers be started Direct service water aligned to the vital header Evaluate Level instrument operability using Caution 1 (Wide Range -N026s inop with Temperature on the Reactor Building 50' above 140°F) Contact engineering to perform EQ evaluation Direct manual Scram prior to Max Safe **CRITICAL STEP** Temperature or Level. SCRAM prior to UA-12 1-3 SOUTH CS RM FLOOD LEVEL HI-HI RO Time Action Notes Monitors the plant Diagnose RWCU leak and attempt to manually isolate, Recognize and report RWCU inboard valve failure -Loss of MCC 2XC inability to isolate RWCU Recognize and report RWCU outboard valve failure and inability to isolate RWCU A-2 5-5 OTaD NSSS VALVES MTR OVERLOAD Align service water to the vital header (SW-V117 or SW-V111) if not already done BOP Time Action Notes Acknowledge and report UA-03 2-7 AREA RAD RX BLDG HIGH 21 EVENT 5/6/7 Rweu Leak -77' RB, Mee 2Xe LOSS, G31-F004 FAILURE BOP Time Action Notes Enters and announce AOP-05.0 entry Evacuates the U2 Reactor building.

Sounds RB evacuation alarm Verifies Secondary Containment and Group 6 isolation and SBGT initiation if Rx Bldg Vent exhaust Hi-Hi rad alarms Directs PIV-33 to be closed Ensures the RHR room coolers are running May Align service water to the vital header (SW-V117 or SW-V111) if not already done due to FAN CLG UNIT CS PUMP RM A INL PRESS LO annunciator Monitors Reactor Building pressure, reports if pressure goes positive. (Blue bar annunciator RX BLDG STATIC PRESS DIFF-LOW)

Acknowledges

& reports UA-17 3-2 SUB E7 FOR TO MCC-2XC BKR TRIP 1. May refer to 001-50.3 for loss of loads. 2. Should not direct Auxiliary Operator to the Reactor Building to check for fault(s) in MCC-2XC. 3. May direct Auxiliary Operator to Substation E7, Breaker AYO, to check for fault(s).

4. May contact maintenance to investigate.

Notifies E&RC to perform the following as necessary:

-Area radiation survey -Air sampling -Smear survey -Post the affected area as necessary

-Control access to reduce exposure and contamination.

Recognize and report to SRO alarms A-26-8 RB 50120 ft Temp Hi. UA-122-3 SOUTH CS RM FLOOD LEVEL HI UA-121-3 SOUTH CS RM FLOOD LEVEL HI-HI (MAX SAFE LEVEL) 22 EVENT 8/9/10 REACTOR SCRAM, RCIC Failure, 20 Bus A Manual Scram is inserted prior to reaching the Maximum Safe Operating Level in South Core Spray. When the turbine is tripped, BOP Bus 20 will fail to auto transfer to the SAT. DG3 will auto start and energize E3. DG1 will auto start on Loss BOP Bus 20 with UAT de-energized.

Loss of BOP Bus 20 will require entry into OAOP-36.1 and causes a loss of FW injection.

Reactor water level will drop due to the inventory loss through the leak. If level drops to the LL2 initiation, RCIC will fail to auto initiate, but can be manually started. With HPCI, RCIC and very limited FW injection, LEP-01 alternate coolant injection systems, along with SEP-09 CRD flow maximized (RB inaccessible) will maintain RPV level above TAF. Objectives:

SCO -Directs manual Reactor Scram Enters RSP, RVCP BOP -Diagnose Bus 20 fails to transfer Enters AOP-36.1.

RO -Diagnose RCIC auto start failure Execute AOP and EOP actions as directed by SRO Perform SCRAM actions Control reactor parameters post SCRAM Success Path: Maintain RPV water level above TAF and depressurizing the RPV. Simulator Operator Actions: D If contacted as I&C, Maintenance, or OS AO to investigate, acknowledge the request D If contacted as AO for SEP-09 or LEP-01, wait 2 minutes and report Reactor Building is inaccessible per RP. D If contacted as AO to restart RPS A, wait 2 minutes and initiate batch file to restart RPSA D If contacted as Unit 1 SRO to perform PEP-3.4.7, acknowledge request. D When directed by the lead examiner, proceed to the next event. Required Operator Actions Major -Enter RSP and RVCP, cooldown at normal rates, anticipate and/or ED. SRO Time Action Notes Before South Core Spray reaches Max **Critical Step** Safe Operating Level, directs a manual reactor scram Enters and directs EOP-01-RSP If reactor building loses negative pressure, enter and execute RRCP for unmonitored release, and request field surveys 23 EVENT 8/9/10 REACTOR SCRAM, RCIC Failure, 2D Bus SRO Time Action Notes Directs entry into OAOP-36.1 for loss of Bus 20 Determines entry into EOP-01-RVCP is required Directs verification

Group Isolations

ECCS Initiations

Diesel Generator Auto Starts Directs restoring and maintaining reactor water level between +170 and +200 inches with one or more of the systems listed in Table 1

CRD (SEP-09)

RCIC May direct pressure control using EHC and pressure band of 800-1000#

Directs starting RCIC to maintain level May direct utilizing SLC aligned to Demin Water (LEP-01).

May direct restoring RBHVAC per SEP-04 Directs commencing normal cooldown not to exceed 100 0 F / hr Directs Anticipating Emergency

- CRITICAL STEP** Depressurization Cautions not to close MSIVs (Gp1) 24 EVENT 8/9/10 RO REACTOR SCRAM, RCIC Failure, 20 Bus Time Action Notes Inserts a manual scram as directed by SRO Performs scram immediate actions: 1. Unit 2 Only: After steam flow is less than 3 x 106 Ib/hr, PLACE the reactor mode switch to SHUTDOWN.

2. IF reactor power is below 2% (APRM downscale trip), THEN TRIP the main turbine. 3. ENSURE the master reactor level controller setpoint is +170". 4. IF two reactor feed pumps are running, and reactor vessel level is above +160" and rising, then trip one. Maintains RPV level 170-200" Reports when out of band and actions to address recovery.

Diagnoses loss of Feedwater flow to RPV Diagnoses RCIC failure to auto start Manually starts RCIC to maintain RPV level Performs SEP-09, CRD Flow Maximization with procedure or Hardcard.

May request SLC aligned for DW injection lAW LEP-01. Rx Bldg is inaccessible.

Recognizes and reports no direct RPV level indication available below 150" wi RR pumps operating.

Trips Recirc pumps if directed by SCO Should have tripped at LL2 if LL2 is reached during the scram. Commences normal cooldown not to exceed 100° F I hr Utilizing BPVs Anticipates ED Opens BPVs with the BPV Opening Jack maintaining Steam Flow below isolation setpoint.

Avoids inadvertent Gp 1 due to high steam flow 25 EVENT 8/9/10 REACTOR SCRAM, RCIC Failure, 20 Bus BOP Time Action Notes Diagnoses loss of Feedwater flow to RPV and potential for uncontrolled injection (loss of Bus 2D power) Enters and announces AOP-36.1 Dispatches an AO to monitor DGs Dispatches an AO to investigate Bus 2D Verifies air compressor alignment May place 2C TBCCW pump in service on U2. May direct AO to restart RPS MG set 2A or Transfer RPS Alt power to the Alternate power supply. Verifies CWIPs in service and maintains main condenser available.

SPE and steam seals Recognize and report to SRO alarms A-26-8 RB 50120 ft Temp Hi. UA-122-3 SOUTH CS RM FLOOD LEVEL HI UA-121-3 SOUTH CS RM FLOOD LEVEL HI-HI May perform SCRAM Hardcard actions. 1. Ensure Scram Valves Are Open By Manual Scram or ARI Initiation

2. Control Reactor Pressure Between 800 and 1000 psig 3. Control Reactor Water Level Between +170 and +200 Inches 4. Place SULCV in Service 5. Insert Nuclear Instrumentation

6. Ensure Turbine Oil System Operating

7. Place Recirc Pump Speed Controllers to 10% and Ensure Pump Speed Lowers 8. Ensure Heater Drain Pumps Tripped 26 EVENT 11 REACTOR DEPRESSURIZATION Area temperatures and water levels will rise. South Core Spray will exceed Max Normal, then Max Safe Operating Water Level. Then South RHR will exceed Max normal then Max Safe Operating Water Level. The crew is directed to consider anticipating emergency depressurization as soon as EOP-03-SCCP directs inserting a manual scram. If the crew does not anticipate emergency depressurization (rapid depressurization to the main condenser) a second area will exceed Max Safe Operating Water Level requiring Emergency Depressurization.

Depressurization may be Anticipated or manually performed when two area exceed Max Safe. Objectives:

SCO Directs actions Emergency Depressurization and restoration of reactor water level. RO Performs actions for emergency Depressurization and restoration of reactor water level. BOP Monitors and reports RB Flood level alarms. Success Path: Restore reactor water level to 170-200 inches. Simulator Operator Actions: Instructor Activities D If crew decides not to anticipate ED, after S RHR Flood Hi has alarmed, 3 minutes later verify Trigger 6 activates to override S RHR Flood Hi-Hi alarm D When RPV level is being controlled above 170", the scenario may be terminated D When directed by the lead evaluator, place the simulator in FREEZE. Required Operator Actions SRO Time Depressurize the RPV by performing or anticipating Emergency Depressurization Action Notes If two areas exceed MSOWL, direct **CRITICAL STEP** Emergency Depressurization Directs controlling condensate injection when RPV pressure is less than 440 psig. (may require closing FW isolations of securing condensate due to power loss) Directs controlling Low Pressure ECCS injection when RPV pressure is less than 400 psig 27 EVENT 11 REACTOR DEPRESSURIZATION SRO Time Action Notes Directs opening 7 ADS valves (ED) Directs restoring and maintaining RPV level 170-200 inches. RO/BOP Time Action Notes Recognize/report S RHR Flood level Hi (and Hi-Hi if alarms) Places 7 ADS valve control switches Operates LP ECCS to restore and maintain RPV level 170-200 inches. Maintains RPV water level below the Main Steam Lines <<254 inches). Termination Cue When RPV water level is being maintained above 170 inches (controlled below the MSLs) with the reactor depressurized, by direction of the Lead examiner, the scenario may be terminated.

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 29 Appendix D Scenario Outline Form ES-D-1 Facility:

Brunswick Scenario No.: 2010-1 #1 Op-Test No.: Final Examiners:

Operators:

Initial Conditions:

Plant is operating max power. PT-02.3.1A has been completed due to the Torus-DW Vacuum Breaker D indication unavailable.

RHR SW Pump 2A is under clearance.

Turnover:

Vent the drywell in accordance with 20P-10, Section 8.2, Venting Containment via the SBGT. Event Malf. No. Event Event No. Type* Description 1 N-BOP Venting DW lAW 20P-10 Section 8.2 N-SRO 2 ES022F I-RO Inadvertent RCIC initiation (TS) I-SRO 3 EE043F R-RO Switchyard Line trip requiring Power reduction R-SRO 4 K4521A C-BOP RBCCW pump trip with failure of standby to auto start Off C-SRO 5 ES013F C-SRO HPCI FIC Power Supply Failure (TS) 6 EE020F C-RO SAT trip; manual scram fails requiring ARI C-SRO 6 DG005F I-BOP DG 4 failures (Con't) I-SRO 7 NB009F M-AII Small break LOCA 7 ES044F ES045F C-RO LP ECCS initiation logic failure (Con't) ES046F C-SRO 8 NA Emergency depressurization

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 37 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-1 NRC Exam Scenario #1 SCENARIO DESCRIPTION The plant is operating at maximum power, Middle of Cycle. Event 1 RHR SW Pump 2A is under clearance.

Suppression Chamber to Drywell Vacuum Breaker D indication is unavailable.

PT-02.3.1A, Vacuum Breaker Position Check Alternate Method has been completed.

The crew will vent the DrywelllAW 20P-10 Section 8.2. Event 2 RCIC will inadvertently initiate.

The crew should respond per OAOP-03.0 and trip RCIC. Event 3 230 kV Line 30 will trip. The Load Dispatcher will request power be reduced to <800 MWe. Power must be reduced using ENP-24.5.

Event 4 The B RBCCW pump will trip with the standby pump failing to auto start. OAOP-16.0 should be entered and the standby pump started to recover system pressure.

Event 5 The HPCI logic power fuse will blow requiring HPCI AOP to be secured per the APP and declared Inoperable.

With RCIC also Inoperable, Tech Specs requires a plant shutdown.

Event 6 The SAT will trip resulting in loss of Recirculation Pumps requiring a manual scram. Manual scram push button B will fail. Rods can be inserted using ARI. Off-site power is lost when the turbine trips. Diesel Generator

3 will start, tie to E3, then trip on over current. Diesel Generator

4 will fail to auto start and tie, but can be manually auto started and manually tied to energize E4. The crew will respond per AOP-36.1 and EOP-01-RSP.

Bus E3 cannot be cross-tied due to the electrical fault, but 480V E7 can be cross-tied to E8. SRVs will be available for pressure control. RCIC can be restarted with an initiation signal following trip to provide inventory makeup to the RPV. CRD flow can be maximized (1 pump) and SLC can be aligned for demin water injection (1 pump until E7 is cross-tied, then both). Event 7 A small Recirculation line break will occur. Available injection sources will be unable to stabilize RPV level. RPV level will drop to LL3 resulting in actuation of ADS timers. The crew may allow ADS to automatically initiate, or manually initiate ADS when level drops below TAF. Low pressure ECCS initiation logic will fail at LL3 requiring manual actions to start available pumps and align injection when RPV pressure drops below 400 psig. Event 8 When the RPV has been depressurized and RPV level restored to the normal band, the scenario may be terminated.

Page 3 of 37 OBJECTIVES SRO 344205B402, Direct Shift Response To A Moderator Temperature Decrease Per AOP-03.0 344237B402, Direct Actions For A Loss of Any 4KV Buses Per AOP-36.1 344231 B502, Direct Actions For A Reactor Scram With MSIVs Closed And Reactor Power Less Than 4% Per EOP-01-RSP 344217B502, Direct Actions To Control RPV Level Per EOP-01-RVCP 344218B502, Direct Actions To Control Reactor Pressure Per EOP-01-RVCP 344220B502, Direct Actions To Emergency Depressurize The RPV Per EOP-01-RVCP 344214B502, Direct Actions To Control Primary Containment Pressure Per EOP-02-PCCP 344215B502, Direct Actions To Control Primary Containment Temperature Per EOP-02-PCCP 344216B502, Direct Actions To Control Suppression Pool Temperature Per EOP-02-PCCP RO 202202B101, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 217200B401, Restart The RCIC System After Auto Initiation And Turbine Trip Per OP-16 217204B401, Shutdown The RCIC System with an Automatic Initiation signal present Per OP-16 262002B401, Respond To A Loss Of Off-Site Power Per AOP-36.1 262007B401, Crosstie Emergency 480 VAC Buses Per AOP-36.1 264009B401, Manually Start A DG With An Auto Start Signal Present With A Failure Of The DG To Start 209007B501, Manually Operate Core Spray To Maintain Reactor Water Level 203006B501, Manually Operate LPCI To Control Reactor Water Level 200049B501, Spray The Drywell Per EOP-01-SEP-02 200062B501, Spray The Suppression Pool Per EOP-01-SEP-03 205014B101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 Page 4 of 37 SIMULATOR SETUP Initial Conditions IC-13 E tT* ven riggers Event Trigger Description 0 Normal Ops (Vacuum Breaker PT) 1 Manually Initiated (Inadvertent RCIC Initiation) 2 Manually Initiated (230 kV Line Trip) 3 Manually Initiated (2B RCC Pump Trip) 4 Manually Initiated (HPCI Bus A Logic Fails) 5 Manually Initiated (SAT Trip) 6 Manually Initiated (Small Break LOCA) 7 Auto Initiated (DG4 Auto Mode Start Depressed, deletes DG005F)(K4G14ABS)

S Auto Initiated (DG3 to E3 Breaker Red=True, activates DG# Trip)(Q4226URS)

Malfunctions Event Sys Tag Title Value Activate Deactivate (Ramp) Time Time A DG DG005F DG4 Auto Start Fail NA OSEC NA A ES ES044F Core Spray B Auto Start Fail NA OSEC NA A ES ES045F RHR A Auto Start Fail NA OSEC NA A ES ES046F RHR B Auto Start Fail NA OSEC NA E1 ES ES022F Inadvertent RCIC Start NA o SEC NA E2 EE EE043F 230 kV Line 30 Trip NA OSEC NA E4 ES ES015F HPCI Power Supply Failure NA OSEC NA E5 EE EE020F SAT Relay Failure NA OSEC NA E6 NB NB009F Small Recirc Line Rupture 10% o SEC NA 5 MIN E8 DG DG026F DG3 Differential Fault NA 5SEC NA Page 5 of 37 Switch Event Panel Tag Title Value Activate Deactivate A XU-2 K2503A Rx Manual Scram B OFF o SEC NA A XU2 K4522A RBCCW Pump C Auto Off o Sec NA E3 XU2 K4521A RBCCW Pump B Off On o Sec NA L amps Event Panel Tag Title Value Activate Deactivate (Ramp) Time Time A XU-2 Q4B212R4 NSW Pump B On Red ON 3 XU2 Q4521LG4 RBCCW Pump B Off G Off A P601 Q1D23SWN RHR A Init Sig White OFF A P601 Q1J39SWN RHR 2 Init Sig White OFF A XU-2 Q4804DGP SP-DW Vac Bkr D Grn OFF A XU-2 Q4804URP SP-DW Vac Bkr D Red OFF A P601 Q1C22SWL Init Sig Seal In -White OFF A P601 Q1J32SWL Init Sig Seal In -White OFF Remote Functions Event System Tag Title Status Act.lRamp A ED IABKCF15 DC Control Fuses RHR SW 2A OUT A ED IABKCF13 DC Control Fuses NSW 2B OUT 10 CA IABSG02A RB Purge Fan 2A Bkr In 11 RD RDVF034 Charging Water Isol Valve F034 1.0 Over 5 sec 12 SW VHSW146L CSW to RBCCW Hxs V146 Open 13 ED ZIEDH08 Pnl 2AB to Alternate Alt 1 min 13 ED ZIEDHXO Pnl 32AB to Alternate Alt 2 min 13 ED ZIEDH11 Pnl 2AB-RX to Alternate Alt 3 min 14 RP IAEPAMGA RPS MG Set AEPA Bkrs Set 14 RP IARPSA Restart RPS MG Set A Reset 5 sec. 15 ED IARKA10 X-Tie Bkr E8-E7 A10 In 2.5 min 15 ED IARKAX5 X-Tie Bkr E7 -E8 AX5 In 5 min 16 EP IACS993P DW Clr ND Override Stop 16 EP IACS994P DW Clr B/C Override Stop Page 6 of 37 SPECIAL INSTRUCTIONS Ensure simulator exam security measures in place. Perform actions of OPT-02.3.1A as necessary to increase drywell pressure to between 0.5 and 1.0 psig using nitrogen injection with the suppression chamber being vented. Secure nitrogen injection and mark up OPT-02.3.1A to last drywell pressure check (@ 60 minutes).

Ensure CAC 4409/4410 in service. Advance all chart recorders to indicate steady state conditions.

Place all SPDS displays to the Critical Plant Variable display (#100). Ensure appropriate keys have blanks in switches.

Exit shutdown screen on RWM and place the RWM key in the key locker. Reset alarms on SJAE, MSL, and RWM NUMACs. Ensure reference material is in appropriate location.

Verify any log books have blank sheets only and procedures are not marked. Load scenario file if available.

Load malfunctions/overrides if scenario file is unavailable.

In command line type trc:7, mfd:dg005f (if scenario file is unavailable)

Place red cap on RHR SW Pump A. Verify U2CO_C099, Avg Hotwell Temp <115°F, or start the third condensate pump. Ensure OENP-24.5 for IC-13 @ P603. Page 7 of 37 SHIFT BRIEFING Plant Status The plant is operating at maximum power. A severe thunderstorm warning has been issued for Brunswick County for the next 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Equipment Out of Service RHR SW Pump 2A is under clearance for breaker repair and is expected to be returned to service in two hours. Suppression Chamber to Drywell Vacuum Breaker D position indication is unavailable.

OPT-02.3.1A, Suppression Chamber to Drywell Vacuum Breaker Position Check Alternate Method, has been completed SAT to comply with LCO 3.6.1.6. No other equipment is out of service. Plan of the Day Maintain maximum power. When the shift turnover is complete vent the drywell in accordance with 20P-10, Section 8.2, Venting Containment via the SBGT. (It is NOT desired to vent the suppression chamber) Page 8 of 37 SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1 021, Rev.9, Supp.1 ES-301 and Appendix D. During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1021, ES-302. Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.

Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)

Insert control rods

Manually start and tie Diesel generator

4

Restore and maintain RPV level by starting LP ECCS Pumps manually before reaching LL4 or LL5 without a Core Spray Pump running. Page 9 of 37 EVENT 1 VENTING THE DRYWELL The crew will complete shift turnover and perform 20P-10, Section 8.2. Objectives:

SCO -Directs performance of 20P-10, Section 8.2. RO -Completes 20P-1 0, Section 8.2. Success Path: Venting of the Drywelilined up lAW 20P-1 0, Section 8.2. Simulator Operator Actions: D If asked as I&C, spare limit switches for vacuum breaker D are unavailable.

D When requested, initiate Trigger 10 to turn Purge Fan A breaker ON. D Once venting has been established, with concurrence from the lead examiner, proceed to the next event. Required Operator Actions Normal Ops -Perform 20P-10, Section 8.2 to vent the drywell. SRO Time Action Notes Direct 20P-10, Section 8.2 to be performed from the DW only. Establishes a target for DW pressure of psig. RO Time Action Notes Plant Monitor May be asked to perform IV for steps from the operating procedure.

Page 10 of 37 EVENT 1 (Cont'd) VACUUM BREAKER TEST BOP Time Action Verifies Initial conditions in 20P-10, Section 8.2. Record 2-D12-RR-R600B, STACK RAD MONITOR, digital point display of 1.06. Records 1.06 and adds 0.17 and records result 1.23. Determines step 3 is N/A. Records 1.23 in the value space provided Close REACTOR BUILDING SBGT TRAIN 2A INLET VALVE, 2-VA-2D-BFV-RB. Close REACTOR BUILDING SBGT TRAIN 2B INLET VALVE, 2-VA-2H-BFV-RB. Open SBGT OW SUCT DAMPER, 2-VA-2F-BFV-RB Determines step 8 is N/A. Open DW PURGE EXH VLV, 2-CAC-V9 Open DW PURGE EXH VL V, 2-CAC-V23 Determines steps 9c and 9d are N/A. Monitor STACK RAD MONITOR, 2-D 12-RR-R600B, on Panel XU-3 for an increase in activity.

Notifies the Unit SCO that OW vent path has been established Notes Page 11 of 37 EVENT 2 INADVERTENT RCIC INITIATION The crew will respond to an inadvertent RCIC initiation.

Objectives:

SCO -Direct shift response to a moderator temperature decrease.

RO -Shutdown the RCIC system with an automatic initiation signal present. Success Path: RCIC shutdown and Technical Specifications reviewed.

Simulator Operator Actions: o When the directed by the lead examiner, initiate Trigger 1 to inadvertently start RCIC. o If RCIC has been running for >5 minutes, and crew has not recognized RCIC running, call control room as AO and ask why RCIC is running. o If asked as I&C to investigate, acknowledge the request o If asked as RE to monitor thermal limits, acknowledge the request. o If asked as chemistry for Rx Coolant Sample, acknowledge the request. o When directed by the lead examiner, proceed to the next event. Required Operator Actions SRO Time Tech Specs -3.5.3 RCIC System Condition A Verify HPCI is OPERABLE and restore RCIC to OPERABLE status within 14 days. Action Notes Direct entry into OAOP-03.0.

May direct RCIC operation to be terminated if the RO has not already performed this task. May contact RE to monitor thermal limits due to the cold water injection from RCIC. Contacts I&C to investigate RCIC logic. May, or may not, review Attachment 5, SRO Checklist For Equipment Status Changes, from OPS-NGGC-1000 and/or Attachment 13, Emergent Item Checklist, from 001-01.03 Page 12 of 37 EVENT 2 (Cont'd) INADVERTENT RCIC INITIATION SRO (Cont'd) Time Action Notes Tech Spec 3.5.3 RCIC System Determine Condition A applies Required Action A.1, Immediately verify HPCI is OPERABLE Required Action A.2, Restore RCIC to OPERABLE within 14 days RO Time Action Notes Recognize and report RCIC injection Enter and announce OAOP-03.0 Verify inadvertent initiation by two independent indications and trip RCIC. Depress TURBINE TRIP, E51-S17, push button to trip the RCIC turbine Monitor reactor power and thermal limits. May monitor SRM Periods or select a control rod to monitor for THI conditions lAW OAOP-03.0.

A-03 3-5, RCIC TURBINE STM LINE DRN POT LEVEL HI will annunciate the operator to perform the following if it has been in for 5 minutes: Ensure that the TURBINE TRIP & THROTTLE VLV, E51-VB, is closed. The valve is closed but the examinee may close the actuator also. BOP I Action I Notes Page 13 of 37 EVENT 3 SWITCHYARD TRANSMISSION LINE 30 TRIP The crew will respond to a trip of Transmission Line 30 and reduce power to less than 800 MWe as directed by the Load Dispatcher.

Objectives:

SCO -Direct power reduction in accordance with ENP-24.5 to 800 MWe using recirc. RO -Decrease reactor recirculation pump speed/reactor power. Success Path: Power is reduced to less than 800 MWe. Simulator Operator Actions: D When the directed by the lead examiner, initiate Trigger 2 to trip transmission line 30. D If asked as Outside AO, acknowledge request to investigate switchyard alarms and report that you will inform the LD directly of your findings.

D If asked as TB AO, inform crew that the PSS system is in service. D Call Brunswick U2 or respond if called as the Load Dispatcher, inform the crew that there is a problem on the line and that Unit 2 should be reduced to <710 MWe (Net). No estimate at this time of the duration of the down power. Ask for the RO to talk on the phone to perform the following operator actions: Place Auto Reclose switches for the following in MAN: 1. Bus 2B Delco West Line 230 KV Breaker, 30B. 2. Bus 2A Delco West Line 230 KV Breaker, 30A. D If contacted as the RE for power reduction guidance, Ask for the SRO's recommendation for the power reduction and then concur with the recommendation given. D If contacted as the RE to monitor power reduction, inform crew that you will monitor core performance on the computer.

D If contacted as the RE for guidance on operation above the MELL line, concur with the recommendation given by the SRO. (Should be to use OENP-24.5 to get below or on the MELLL). D When directed by the lead examiner, proceed to the next event. Required Operator Actions SRO Time Reactivity

-Reduces reactor recirculation pump speeds to reduce to power less than 710 MWe (Net). Action Notes Notify Load Dispatcher of transmission line failure. Direct power reduction to <710 MWe lAW OENP-24.5.

May direct the removal of a condensate pump lAW OGP-12. Page 14 of 37 EVENT 3 (Cont'd) SWITCHYARD TRANSMISSION LINE 30 TRIP BOP Time Action Notes Informs SRO that Delco West Line has tripped. May request Outside AO to investigate alarms in the switchyard.

Places Auto Reclose switches for Delco West Line 230 KV Breaker, 30A and 30B, to MAN per the Load Dispatchers orders. May remove a condensate pump from service lAW OGP-12. May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 O'clock. (May have to perform this several times) RO Time Action Notes Perform power reduction using reactor recirculation pump speed controller to less than 710 MWe. May reference 20P-02 section 7.1 Request peer checker I reactivity team. Reduces power using ENP-24.5 using recirculation flow to <710 MWe. 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 710 MWe. Verifies operation on the Power to Flow map. Page 15 of 37 EVENT 3 (Cont'd) SWITCHYARD TRANSMISSION LINE 30 TRIP RO (Cont'd) Time Action Notes May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 O'clock. (May have to perform this several times) Recognizes operation above the MELLL line and informs SCO. Inserts control rods using OENP-24.5 to get below the MELLL line. Turns control rod power on. Selects control rod (22-19) in accordance with OENP-24.5 sheet. May also insert 30-35,30-19, or 22-35. (in this order in order to establish a margin to the MELLL line) Continuously drives selected rod in using RMCS. Page 16 of 37 EVENT 4 RBCCW PUMP TRIP The crew will respond to a trip of the 2B RCC pump 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 will restore pressure to normal. 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: Starting the 2C RCC pump will restore pressure to normal. Simulator Operator Actions: D At the discretion of the lead evaluator, initiate Trigger 3 to trip the 2B RCC Pump. D If directed as the RB AO to investigate RCC low pressure, report RCC Pump 2B Motor is hot to the touch, breaker is tripped. D If contacted as the RB AO, inform the control room prestart checks of the 2C RCC pump are complete.

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 Component failure -starting 2C RCC pump. SRO Time Action Notes Directs BOP operator to enter Annunciator response for 2-UA-3 2-5, RBCCW PUMP DISCH HEADER PRESS LOW, and refers to OAOP-16.0.

Directs start of 2C RCC pump if BOP fails to recognize auto start failure. Directs Maintenance to investigate 2C RBCCW pump auto start failure. Notifies Maintenance of 2B RBCCW Pump trip. May direct the 2B RCC pump to be placed in OFF. Page 17 of 37 EVENT 4 (Cont'd) RBCCW PUMP TRIP RO I Time I Action BOP Time Action Recognize the failure of the C RCC pump to auto start at 65 psig. Manually starts 2C RBCCW Pump. Refers to Annunciator Response UA-3 2-5, RBCCW PUMP DISCH HEADER PRESS LOW. May Reference OAOP-16.0 Dispatches AO to investigate cause of 2B Pump trip. Places 2B RBCCW Pump switch to OFF. Verifies RBCCW System is operating normally.

I Notes Notes Page 18 of 37 EVENT 5 HPCI FIC POWER SUPPLY FAILURE The crew will respond to a HPCI Controller power supply failure which will require HPCI AOP to be secured per the APP and declared Inoperable.

With RCIC also Inoperable, Tech Specs will require a plant shutdown.

Objectives:

SCO -Determines HPCI Tech Spec call. BOP -Securing of HPCI AOP. Success Path: Securing of HPCI AOP and TS 3.5.1 declaration.

Simulator Operator Actions: D When directed by the lead evaluator, initiate Trigger 4 to activate HPCI controller power supply failure. D If asked as AO to investigate, report all circuit breakers in DC Panel 4A are closed and/or Supply breaker to Panel 4A is closed. D If asked as I&C to investigate, report fuse E41-F25 in panel P601 is blown (blows again if replaced).

D If asked as the NE, acknowledge request to come to the control room for Unit Shutdown.

D When directed by the lead examiner, proceed to the next event. Required Operator Actions Tech Specs -3.5.1 ECCS Operating Condition D Verify RCIC is OPERABLE and restore HPCI to OPERABLE status within 14 days Condition I Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to <150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Tech Specs -3.5.3 RCIC System Condition A Verify HPCI is OPERABLE and restore RCIC to OPERABLE status within 14 days Condition B Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to <150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Page 19 of 37 EVENT 5 (Cont'd) HPCI POWER SUPPLY FUSE SRO Time Action Notes Direct actions of 2APP-A-01 (2-5) HPGI FIG POWER LOSS. Direct HPCI AOP to be placed in pUIl-to-lock per A-01 2-5, HPGI FIG POWER LOSS. Contact I&C to investigate HPCI power supply failure. Tech Spec 3.5.1 ECCS Operating Determine Condition D applies Required Action D.1, Immediately verify RCIC is OPERABLE Required Action D.2, Restore HPCI to OPERABLE within 14 days. Determine condition I applies, Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to <150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Tech Spec 3.5.3 RCIC System Determine Condition A applies Required Action A.1, Immediately verify HPCI is OPERABLE Required Action A.2, Restore RCIC to OPERABLE within 14 days Determine condition B applies, Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to <150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Directs to commence a Unit Shutdown in accordance with OGP-05. Page 20 of 37 EVENT 5 (Cont'd) HPCI POWER SUPPLY FUSE BOP I Action I Notes RO Time Action Notes Diagnose and report HPCI power supply failure Perform actions for A-01 2-5, HPGI FIG POWER LOSS Place HPCI AOP in pull-to-Iock.

Page 21 of 37 EVENT 6 LOSS OF SATISCRAM The SAT will trip resulting in loss of Recirculation Pumps requiring a manual scram. This will start all DGs except DG4. Manual scram push button B will fail. Rods can be inserted using ARI. Off-site power is lost when the turbine trips. Diesel Generator

3 will tie to E3, then trip on over current. Diesel Generator

4 will fail to auto start and tie, but can be manually auto started (control room manual mode) and manually tied to energize E4. The crew will respond per OAOP-36.1 and EOP-01-RSP.

SRVs will be available for pressure control. RCIC can be restarted with an initiation signal following trip to provide inventory makeup to the RPV. CRD flow can be maximized (1 pump) and SLC can be aligned for demin water injection (1 pump until E7 is cross-tied, then both). Objectives:

SCO -Directs actions for a Reactor Scram, LPC, and OAOP-36.1.

RO -Insert a reactor scram with no recirc pumps running. BOP -Start DG4, tie to E4 and perform OAOP-36.1 actions. Success Path: Start and tie DG4 to E4. Rods inserted with ARI. Simulator Operator Actions: D When directed by the lead evaluator, initiate Trigger 5 to activate SAT failure. D Acknowledge Fireworks alarm. D If contacted as load dispatcher, report line crews are being dispatched to investigate.

D If asked as Outside AO, acknowledge request to monitor DGs. D If requested to transfer SLC suction to demin water, initiate Trigger 9, wait two minutes and report actions complete.

D If asked to perform actions to maximize CRD flow with 1 pump per SEP-09, wait 4 minutes and report the actions complete.

D If requested to open CRD charging header isolation valve, initiate Trigger 11, wait 2 minutes and report actions complete.

D If asked as Unit 1 for status of the air system, report 1 D is carrying the load. D If asked to transfer RCC to CSW, initiate Trigger 12, wait 5 minutes and report actions complete.

D If requested to transfer 2AB, 32AB and 2AB-RX, initiate Trigger 13 and after 3 minutes report transfers complete (each one will sequence on every 1 minute). D If asked to restart RPS, initiate Trigger 14, wait 3 minutes and report actions complete.

D If requested to perform field actions for UAT back-feed, acknowledge the request. D When directed by the lead examiner, proceed to the next event. Required Operator Actions Insert control rods. (critical task) Start DG4 and tie to E4. (critical task) Page 22 of 37 EVENT 6 (Cont'd) LOSS OF SAT I SCRAM SRO Time Action Direct insertion of manual scram due to loss of the recirc pumps. Enter and direct EOP-01-RSP.

May enter LPC. May direct Initiation of ARI. (critical task) Direct entry into OAOP-36.1 for loss of Off-Site Power and loss of E3/E7 Directs a pressure band of 800-1000#

Direct reactor water level band of 170-200 inches. CRD (SEP-09) RCIC SLC with Demin Water When suppression pool temperature reaches 95°F or OW temperature reaches 150°F, enter EOP-02-PCCP.

Direct RHR Loop B to be placed in suppression pool cooling. Notes Page 23 of 37 EVENT 6 (Cont'd) LOSS OF SAT I SCRAM RO Time Action Recognize failure of manual scram channel B Initiates ARI per the Scram Hard Card. (critical task) Perform immediate actions for Reactor scram After steam flow is less than 3 x 10 6 Ib/hr, place the reactor mode switch to shutdown When APRM downscale trip, then Trip the main turbine Ensure the master reactor level controller setpoint is +170 inches Operate SRVs as directed to stabilize pressure and control pressure as directed by the SCO. Start RCIC following turbine trip with initiation signal per the OP. Ensure the E51-V8 (valve position) and E51-V8 (motor operator) are closed Place RCIC flow control in MANUAL (m) and adjust output to 0%. Jog open E51-V8 until the turbine speed is controlled by the governor Fully open E51-V8 Slowly increase turbine speed until flow rate of at least 120 gpm Ensure E51-F019 is closed with flow above 80 gpm Notes Page 24 of 37 EVENT 6 (Cont'd) LOSS OF SAT I SCRAM RO (Cont'd) Slowly adjust flow rate using RCIC flow control in Auto (A) Ensure Barometric Cndsr Vacuum Pump has started Start CRD per SEP-09 (RO should perform Hard Card then dispatch an AO for procedure actions. SEP-09 Hard Card Actions Ensure CRD Flow Control, C12-FC-R600, in MAN Close in-service Flow Control Vlv, C 12-F002A(F002B)

Start a CRD pump. Throttle the following valves to maintain charging water header pressure greater than or equal to 1000 psig but as low as possible:

In-service Flow Control Vlv, C12-F002A(F002B)

Drive Pressure Vlv, C12-PCV-F003 SEP-09 Procedure Actions Dispatch AO to perform SEP-09 for one CRD with the Reactor Building Accessible.

Throttle the following valves to maintain charging water header pressure greater than or equal to 800 psig but as low as possible:

In-service Flow Control Vlv, C12-F002A(F002B)

Drive Pressure Vlv, C12-PCV-F003

Charging Water Header Throttle Valve, C12-F034 Page 25 of 37 EVENT 6 (Cont'd) LOSS OF SAT I SCRAM RO (Cant'd) Time Action Notes Perform LEP-01 for SLC injection with demin water Dispatch an AO to perform infield actions. When in field actions complete, starts B SLC Pump. Operate RCIC/CRD/SLC to restore/maintain Reactor water level +170-200 inches. Place RHR Loop B into suppression pool cooling. Open SW-V105 Close SW-V143 If LOCA signal is present place RHR SW Booster Pumps B & D LOCA override switch to manual override Start RHR SW Pmp Adjust E11-PDV-F068B (1 pump 2000 -4000 gpm) (2 pumps 5000 -8000 gpm) Supply Clg Wtr to Vital Hdr Verify spray logic is made up Start Loop B RHR Pmp Open E 11-F028B Throttle E 11-F024B (1 pump 6000 -10000 gpm) (2 pumps 6000 -11500 gpm) Throttle E11-F048B Page 26 af 37 EVENT 6 (Cont'd) LOSS OF SAT 1 SCRAM BOP Time Action Diagnose failure of DG4 to auto start Start and manually tie DG4 to E4. (critical task) Depresses the AUTO Start pushbutton.

Places the DG4 to E4 control switch to close. Determine trip of DG3 is due to electrical fault. Announce and enter OAOP-36.1.

Determine UA T back-feed available and direct field actions. Ensure NSW 2B running, start CSW 2B and 2C. Start Control Room and Battery Room HVAC. Dispatch an AO to shift the Manual Bus Transfer (MBT) devices for the following panels to the alternate power source: 2AB 32AB 2AB-RX Restore Drywell cooling (Dispatch an AO to transfer RCC to CSW header). Direct RPS to be restarted.

Close SW-V3 for suppression pool cooling when required.

Notes Page 27 of 37 EVENT 7 SMALL BREAK LOCA A small Recirculation line break will occur. Available injection sources will be unable to stabilize RPV level. RPV level will drop to LL3 resulting in actuation of ADS timers. The crew may allow ADS to automatically initiate, or manually initiate ADS when level drops below TAF. Low pressure ECCS initiation logic will fail at LL3 requiring manual actions to start available pumps and align injection when RPV pressure drops below 400 psig. Bus E3 cannot be cross-tied due to the electrical fault, but 480V E7 can be cross-tied to E8. Objectives:

SCO -Directs actions for a Reactor Scram, LPC, and OAOP-36.1.

RO -Insert a reactor scram with no recirc pumps running. BOP -Start DG4, tie to E4 and perform OAOP-36.1 actions. Success Path: Start and tie DG4 to E4. Rods inserted with ARI. Simulator Operator Actions: o After the crew has stabilized RPV level using CRD/SLC/RCIC and when directed by the lead evaluator, initiate Trigger 6 to activate small break LOCA. o If requested to perform actions for E7 -E8 cross-tie per OAOP-36.1, Initiate Trigger 15 and wait 5 minutes and report breakers are racked in. o If requested to stop drywell coolers, initiate Trigger 16. o If asked as I&C to investigate ECCS logics, acknowledge request o When directed by the lead examiner, proceed to the next event. Required Operator Actions Page 28 of 37 EVENT 7 (Cont'd) SMALL BREAK LOCA SRO Time Action Recognize rising drywell temperature and pressure, diagnose as LOCA. Enter and direct EOP-01-RVCP, if not already in. Direct reactor water level band of 170-200 inches. CRD (SEP-09) RCIC SLC (LEP-01) Direct initiation of suppression chamber spray. (SEP-03 or Hardcard)

Direct drywell spray when suppression chamber pressure >11.5 psig. (SEP-02) Direct E7-E8 cross-tied.

Informs crew on decision of inhibiting or not inhibiting ADS. Inhibit ADS -when all injection sources are not yet lined up or are thought to be able to maintain or turn level before LL4. Not Inhibiting ADS -when all injection sources are injecting and cannot maintain level above TAF. Direct LL3 actuations verified Directs Low Pressure ECCS pumps be started Notes Page 29 of 37 EVENT 7 (Cont'd) SMALL BREAK LOCA RO Time Action Recognize rising drywell temperature and pressure, diagnose as LOCA Initiate suppression chamber spray per SEP-03. If necessary, then place Loop B 2/3 CORE HEIGHT LPCIINITIATION OVERRIDE SWITCH, E11-CS-S18B, in Manual Overrd. If the CTMT SPR OVRD light for the Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, E 11-CS-S 17B is not on, then momentarily place Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, E11-CS-S17B, to Manual Ensure at least one RHR Loop B Pump is operating Ensure TORUS DISCHARGE ISOL VLV, E11-F028B, is open Open TORUS SPRAY ISOL VLV, E11-F027B.

Notes Page 30 of 37 EVENT 7 (Cont'd) SMALL BREAK LOCA RO (Cont'd) Initiate drywell spray per SEP-02 Ensure WELL WATER TO VITAL HEADER VLV, SW-V141, is closed Ensure both reactor recirculation pumps are tripped Place all drywell cooler control switches to OFF (LlO) May request Drywell Cooler override switches to STOP. Confirm the following:

Drywell pressure and drywell temperature are in the "SAFE" region of the DSIL graph.

Suppression pool water level is below +21 inches. Open Loop B DRYWELL SPRAY INBD ISOL VLV, E11-F021 B Throttle open Loop B DRYWELL SPRAY OTBD ISOL VLV, E11-F016B, to obtain between 8,000-10,000 gpm flow Inhibits ADS if directed by SCO Start all available low pressure ECCS pumps at 400 psig in reactor or when reaching LL3 (ADS Timer Initiated alarm A-03, 5-1): 2B CS 2B RHR 2CRHR 2D RHR Page 31 of 37 EVENT 7 (Cont'd) SMALL BREAK LOCA BOP Time Action Cross-tie E7-E8 when directed by SCO. Obtain permission from both Units' SCO to close the 480V E bus cross-tie breakers Dispatch AO to Rack in the 480V Crosstie breakers.

Place SUB E7 480V Main Breaker, breaker AZ1, in trip. Place BUS E3 TO SUB E7, breaker AJO in trip. Place and hold BUS E7 TIE TO BUS E8, breaker AX5 and A 10 in close until both cross-tie breakers indicate closed. May start available low pressure ECCS pumps at 400 psig in reactor or when reaching LL3 (ADS Timer Initiated alarm A-03,5-1):

2B CS 2B RHR 2C RHR 2D RHR Notes Page 32 of 37 EVENT 8 REACTOR DEPRESSURIZATION Depressurization may be automatic or manually performed when level drops below TAF. Objectives:

SCO -Directs actions Emergency Depressurization and restoration of reactor water level. RO -Performs action for emergency Depressurization and restoration of reactor water level. Success Path: Restore reactor water level to 170-200 inches. Simulator Operator Actions: D If requested to re-align SLC to the boron tank, wait 4 minutes and modify Remote Function SL_IASLCTST, NORM D When RPV level is raised to +170 inches and Alternate Source Term actions are recognized as needed, the scenario may be terminated D When directed by the lead evaluator place the simulator in FREEZE. Required Operator Actions SRO Time Restore and maintain RPV level by starting LP ECCS Pumps manually before reaching LL4 or LL5 without a Core Spray Pump running (critical task) Action Notes Determine ED is required.

Direct placing 7 ADS valve switches to open. Direct re-alignment of RHR for LPCI injection Direct low pressure ECCS injection valves opened Direct RPV level be restored and maintained

+170-200 inches Direct Alternative Source Term actions (SLC, CREV, SEP-11) Page 33 of 37 EVENT 8 (Cont'd) REACTOR DEPRESSURIZATION RO/BOP Time Action Notes Places 7 ADS valve control switches Re-align RHR for LPCI injection.

Ensures Drywell Sprays I SP Sprays I Torus Cooling removed from service Manually perform any failed LPCI initiation actions Open 2B CS injection valve Open 2A RHR Loop Injection Valve Open 2B RHR Loop Injection Valve Close Recirc Discharge and Discharge Bypass valves Operate LP ECCS to restore and maintain RPV level 170-200 inches. (critical task) Re-align SLC for SLC Tank Injection (Alternate Source Term Action) Start CREV (Alternate Source Term Action) Perform SEP-11 (Alternate Source Term Action) Page 34 of 37 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 Page 35 of 37 0 20 U) W ::I:

30 (J Z ....... --40 -I W :> .. 50 W -I 0 -60 W -70 2 CI Z 90 -100 ATTACHMENT 6 Page '13 of 19 FIGURE 17A Unit 2 Reactor Water Level at T AF 700 900 1,100 60 600 800 1 1 000 REACTOR PRESSURE (PSIG) WHEN REACTOR PRESSURE IS LESS THAN 60 PSIG, USE INDICATED LEVEL TAF IS -7.5 INCHES. Page 36 of 37 REf lEG . TEMP ABOVE 20{)'F REF LEG TEMP BELOW OR EQUAL TO 20Q"F 0 -20 CIJ W :r: -30 U Z --40 ....J W > -50 W ....J C -60 W 70 U -Cl Z 90 ATTACHtv1ENT 6 Page '15 of '19 FIGURE'18A Unit 2 Reactor Water Level at LL-4 (Minimum Steam Cooling Level) 00 300 60 200 400 600 800 1,000 REACTOR PRESSURE (PSIG) WHEN REACTOR PRESSURE IS LESS THAN 60 PSIG, USE INDICATED LEVEL. LL-4 IS -30.0 INCHES, Page 37 of 37 I REF LEG TEMP ABOVE: 200'F REF LEG TEMP BELOW OR EQUAL TO Appendix D Scenario Outline Form ES-D-1 Facility:

Brunswick Scenario #: 2010-1 #3 OP-Test No.: Final Examiners:

Operators:

Initial Conditions:

The plant is operating at -50% power during startup following a refuel outage. No equipment is out of service Turnover:

Following shift turnover, raise power to 60%, perform alternate power verification and prepare to place the second feed pump in service. Event Malf. No. Event Event No. Type* Description 1 N/A R-RO Raise power to 60% R-SRO 2 N/A N-SRO Place the second reactor feed pump in service N-BOP 2a ZA411 C-RO Failure of DWEDT Sump Pump to start C-SRO 3 EE030M C-BOP Main Stack Rad Monitor power failure with failure of SBGT C-SRO to auto start. (TS) 4 K4517A C-BOP 2B TCC Pump trip C-SRO 5 MS031F M-ALL MTLO controller failure leads to Event 6 6 MS017F M-ALL Turbine high vibration requiring turbine trip and scram resulting in an ATWS condition requiring entry to LPC. 7 K2119A C-RO SLC pumps will not start due to switch failure. Off C-SRO 8 RD036F C-RO Scram discharge volume vents and drains fail closed. C-SRO 9 All Rods In .. * (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Page 2 of 31 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-1 NRC Exam Scenario #3 SCENARIO DESCRIPTION Unit 2 is operating at -50% power during startup following a refuel outage. Event 1 Continue with startup to -62% power using recirc flow. Event 2 Places the second reactor feed pump in service. Event 2a Annunciator A-04 1-1, Drywell Equip Drain Sump Lvi Hi, will annunciate and the sumps will not auto start. One of the sump pumps will need to be manually started. Event 3 Power to the Main Stack Rad Monitor will be lost. The power results in Group 6 isolation and Secondary containment isolation.

Event 4 TCC Pump 2B will trip and TBCCW low header pressure will alarm. The crew will respond per OAOP-17.0 and place 2C TBCCW pump in service. Event 5 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.

Event 6 Most control rods will fail to insert on the scram. The crew will respond to the A TWS per EOP-01-LPC.

Event 7 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 8 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 9 When level has been lowered and level band has been established, the scram discharge volume vents and drains will be repaired.

Control rods can then be inserted by manual scram. When all control rods are inserted and level is being maintained 170 to 200 inches the scenario may be terminated.

Page 3 of 31 Simulator Setup Initial Conditions:

IC ENP-24.5 for IC 9 Rx Power 60% Core Age EOC Events: ent # Trigger Description 3 1 Manual Main Stack Rad Monitor Power Failure 4 2 Manual Trip 2B TBCCW Pump 5 3 Manual MTLO controller failure 6 4 Auto Turbine high vibration causing the crew to scram the plant with an A TWS condition 8 NA SLC switch failure 9 5 Auto Scram Discharge Vents and Drains fail closed Malfunctions Summary Shaded entr"ies'are ACtiVe Malf.ID Mult Description Current ID Value RP010F ATWS3 True RD036F Scram Disc Vol Drn Fails Closed False MS031F MTLO Temp Cntrlr Fails False MS017F 4 Turbine Bearing Vibration 0 MS017F 5 Turbine Bearing Vibration 0 MS017F 6 Turbine Bearing Vibration 0 MS008F Main Turbine Trip False RP005F Auto Scram Defeat False R S emotes ummary Remote ID Mult. Description ID EP IAEOPJP1 Bypass LL3 Group I Isol MS VMS5005D MVD-5005 Mn Stm Drn Hdr Isolation EP IACS993U DW CLR A&D Overide -Normal/Run EP IACS994U DW CLR B&C Overide -Normal/Run EP IASW5997 SW-V106 LOCA Override EP IASW5998 SW-V103 LOCA Override ED IAUPB2A6 UPS 2A to Sample Detection Skid SL IALEP03 Alt = Sub Pump / Hose Lineup ZA411 Drywell Equip Drain Sump Lvi Hi ZA431 Drywell Equip Drain Sump Leak Hi Page 4 of 31 Target Ramp Value Time True True True 5 5min 5 5min 5 5 min True True Current Value Off 0 Normal Normal Normal Normal Closed Normal Act. Deact Trig Time Time 5 -on Scram 3 Auto on UA231-6 Auto on UA231-6 Auto on UA231-6 6 7 Target Trig Value T On 1 9 Run 10 Run 10 Bypass 10 Bypass 10 Open 1 Alt 11 On 12 OFF S *t h S WI C es ummary I Switch ID Description Target Position K4517A TBCCW Pump B On Q4517LG4 TBCCW Pump B Green OnlOff K2119A SIB Liq Pump A-B Stop K2119A SIB Liq Pump A-B Pump A K2119A SIB Liq Pump A-B PumpAB K2119A SIB Liq Pump A-B Pump B K6103B SBGT SyS B Pref K4313A RFP A Recirc Vlv Auto Close K4307A RFP B Recirc Vlv Auto Close Special Instructions:

Ensure ENP-24.5 for IC-9 at P603 panel. Reduce power to -50% using recirc flow. Place 28 TCC pump in service. Verify APRM GAFs are.::: 1.00 FWLC setpoint at 190 inches Page 5 of 31 Override Trig Value Off 2 Off 2 On Off Off Off Off Off Auto on RFP A Trip (Q43164WY

= true) Off Auto on RFP B Trip (Q43104WY

= true)

Shift Briefing Plant Status The plant is operating at -50% power during startup following a refuel outage. GP-04 is complete up to step 5.2.22. Alternate Power verifications lAW OGP-04 are being performed by the Reactor Engineer.

A severe thunderstorm warning has been issued for Brunswick County for the next 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Equipment Out of Service 1A NSW Pump is under clearance for breaker refurbishment, expected to be returned to service in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Plan of the Day Raise power to 60%, perform alternate power verification and prepare to place the second feed pump in service. Page 6 of 31 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. Page 7 of 31 EVENT 1 SHIFT TURNOVER, RAISE REACTOR POWER TO 62% The crew will complete shift turnover and raise reactor power to -62%. Malfunctions required:

None. Objectives:

SCO -Directs reactor power to be raised using Recirc pump speed control. RO -Performs power increase using recirc flow control. Success Path: Power is raised to -62% power. Simulator Operator Actions: o If contacted as the RE for power increase guidance, inform crew to raise power using Reactor Recirc flow. o If contacted as the RE to monitor power increase, inform crew that you will monitor core performance and when plant is at 60% power inform crew Alt Power at is SAT. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Reactivity Manipulation

-Raise power -10% using recirc pump speed controls.

SRO Time Action Notes Directs Power to be raised to -62% power. RO Time Action Notes Raises power using recirculation flow to -62% power. Raise flow on one RR Pump (-2%) at a time to stay within mismatch criteria (7 .5x1 0 6 Mlbs jet pump flow if < than 58 Mlbs or 3.5x1 0 6 Mlbs if> than 58 Mlbs). Continues alternating Recirc pump increases until power is -60%. Verifies operation on the Power to Flow map. BOP I Time I Action I Notes Page 8 of 31 EVENT 2/2a PLACE THE SECOND REACTOR FEED PUMP IN SERVICE I FAILURE OF DWEDT SUMP PUMP BOP -Places the second reactor feed pump in service. RO -Annunciator A-04 1-1, Drywell Equip Drain Sump Lvi Hi, will annunciate and the sumps will not auto start. One of the sump pumps will need to be manually started. Malfunctions required:

ZA411. Objectives:

SCO -Directs placing the second RFP in service lAW 20P-32 Section 5.7. RO -Manually starts one of the DWEDT Sump Pumps. BOP -Places the second reactor feed pump in service lAW 20P-32 Section 5.7. Success Path: Second RFP in service. DWEDT pumped down. Simulator Operator Actions: If contacted as the RE to monitor core performance, inform crew that you will monitor core performance on the computer.

While the BOP is placing the RFP in service, Initiate Trigger 12 to activate the OWED Sump Lvi Hi Annunciator.

Acknowledge requests for the Radwaste Operator.

Acknowledge requests as I&C for troubleshooting OWED Sump Pump auto start failure. After RFP B RECIRC VLV, FW-FV-V47, has been closed and when directed by the lead examiner, proceed to the next event. Required Operator Actions SRO Time Normal Operations

-Places Second RFP in service. Component Failure of the OWED Sump Pumps to auto start. Action Notes Directs Second RFP be placed in service lAW 20P-32. Acknowledges alarm condition for OWED Sump Level High May direct RO to start one of the OWED Sump Pumps if not performed by the RO. Page 9 of 31 EVENT 2/2a PLACE THE SECOND REACTOR FEED PUMP IN SERVICE 1 FAILURE OF DWEDT SUMP PUMP RO Time Action Notes Plant Monitoring Announces OWED Sump Lvi Hi Annunciator.

Diagnose failure of the OWED Sump Pumps to auto start and manually starts one of the pumps. Verifies that the manually started pump shuts off after pumping down the sump. BOP Time Action Notes Performs 20P-32, Section 5.7 Determines initial conditions met. Notify Radwaste Operator to monitor COD flows and place additional demineralizers in service as necessary.

Ensure RFP B LP SUPPL Y VL V, RHS-V1, is open Slowly raise RFPT B speed by placing RFPT B LOWER fRAISE speed control switch in RAISE until speed is greater than approximately 2550 rpm When RFPT B speed is greater than approximately 2550 rpm, then raise RFPT B SP CTL, C32-SIC-R601 B, output to match DFCS STPT and SPEED STPT on Panel P603 to within 100 rpm. Notify Radwaste Operator to monitor COD effluent conductivity for each demineralizers in service Page 10 of 31 EVENT 2/2a PLACE THE SECOND REACTOR FEED PUMP IN SERVICE 1 FAILURE OF DWEDT SUMP PUMP BOP (Cont'd) Time Action Notes Confirm the following RFPT B speed signals on Panel P603 agree within approximately 100 rpm:

DFCS STPT (speed demand from DFCS).

SPEED STPT (speed demand from 5009 control)

ACT SPD (actual RFPT speed) Place MANIDFCS control switch in DFCS. Slowly raise RFPT B speed by depressing the raise pushbutton on C32-SIC-R601 B until RFP discharge pressure is approximately equal to reactor pressure.

Open RFP B DISCH VLV, FW-V4 Slowly raise RFPT B speed, using RFPT B SP CTL, C32-SIC-R601 B, until B OEM is approximately equal to A OEM of the on line RFP. DEPRESS AIM pushbutton on RFPT B SP CTL, C32-SIC-R601 B, AND CHECK AIM indicator changes to A (automatic).

When pump suction flow is greater than 3.9 X 106 Ibm/hr, and heater drains are forward pumping, then close RFP B RECIRC VL V, FW-FV-V47, by momentarily placing control switch in CLOSE. When RFP B RECIRC VL V closes, then adjust level setpoint on MSTR RFPT SPIRX L VL CTL, C32-SIC-R600, to 187 inches. Page 11 of 31 EVENT 3 MAIN STACK RAD MONITOR FAILURE Power to the Main Stack Rad Monitor will be lost. The power results in Group 6 isolation, Secondary containment Isolation but SBGT fails to auto start. The crew must manually start SBGT to maintain Secondary Containment integrity.

Malfunctions required:

UPS 2A to Sample Detection Skid breaker open. Objectives:

SCO -Determine actions required for LCO per Technical Specifications.

BOP -Respond to a process radiation monitoring downscaleiinop annunciator.

Success Path: Technical Specification i TRM

3.3.6.1 PCIS Instrumentation, determine Function 2c is inoperable, determine condition A 1, Place in trip condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

TRM 3.4 Post Accident Monitoring, determine Function 5 is inoperable and condition B applies, Restore one required channel in 7 days.

ODCM 7.3.2 Gaseous Effluent Monitoring, determine function 1 is inoperable

A.1, Enter the Condition referenced in Table 7.3.2-1 for the channel

B.1, Take a grab sample once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

B.2, Analyze the grab sample for gross noble gas activity within 24 hrs

B.3, Restore the channel in 30 days

C.1, C.1.1, Initiate actions to establish auxiliary sampling equipment to continuously collect samples from the associated effluent release pathway as required by Table 7.3.7-1 -OR-C.1.2, Initiate continuous sample collection from associated release pathway as required by Table 7.3.7-1 with auxiliary sampling equipment.

C.2, Restore the channel in 30 days

0.1, Estimate the flow rate through the associated pathway

0.2, Restore the channel in 30 days Simulator Operator Actions: D Insert Trigger 1 at the discretion of the lead evaluator.

D Ensure SBGT start when switches are taken to ON. D If asked to investigate, report UPS Panel 2A to the Stack Rad Monitor is tripped. D If contacted as I&C to investigate, acknowledge the request, if asked do not recommend transfer to the alternate power supply until the cause of the trip is investigated.

D When directed by the lead examiner, proceed to the next event. Required Operator Actions Tech Spec Declaration

-3.3.6.1 condition A 1, TRM 3.4 condition B, and ODCM 7.3.2, A1, B, C and D. Page 12 of 31 EVENT 3 (cont'd) MAIN STACK RAD MONITOR FAILURE SRO Time Action Notes Direct actions of the APPS for the Main Stack Rad Monitor Direct manual start of SSGT. Direct lie to investigate loss of UPS 2A. Refer to Tech Specs. See success path on page 12. RO Time Action Notes Plant Monitoring.

May open the SW-V111 or V117 to supply cooling water to the vital header lAW 2APP-UA-05 1-9 or 2-9. Page 13 of 31 EVENT 3 (cont'd) MAIN STACK RAD MONITOR FAILURE BOP Time Action Notes Report loss of Main Stack Rad Monitor. UA-03 5-4, PROCESS OG VENT PIPE RAD HI-HI 6-3, PROCESS SMPL OG VENT PIPE DNSC/INOP 6-4, PROCESS OG VENT PIPE RAD -HI UA-05 3-5, SBGT SYS B FAILURE 4-6, SBGT SYS A FAILURE 6-10, RX BLDG ISOLATED Report TS review for the SCO from the Annunciator reviews.

3.6.4.3

3.3.6.1 Table 3.3.6.1-1, Function 2C

ODCM 7.3.2 Table 7.3.2-1 Function 1,7.3.7, and 7.3.13

TRM 3.4, Table 3.4.2 Function 5 Determine SBGT did not auto start and manually starts both trains Dispatch AO to investigate UPS 2A condition.

May open the SW-V111 or V117 to supply cooling water to the vital header lAW 2APP-UA-05 1-9 or 2-9. Page 14 of 31 EVENT 4 TBCCW PUMP B TRIP TCC Pump 2B will trip and TBCCW low header pressure will alarm. The crew will respond per OAOP-17.0 and place a TBCCW pump in service Malfunctions required:

Trip of 2B TCC pump Objectives:

SCO -Direct entry into OAOP-17.0.

RO -Restoration of TCC pressure Success Path: 2C TBCCW pump started and TCC pressures restored to normal. Simulator Operator Actions: o Insert Trigger 2 at the discretion of the lead evaluator.

o If contact as the TB AO, wait one minute and report that 2B TCC pump is hot to the touch and the breaker is tripped. o If contacted as Unit One CRS, report Unit One is not using the 2C TCC Pump. o Acknowledge request as I&C to do troubleshooting/repair for the 2B TCC Pump. o When directed by the lead examiner, proceed to the next event. Required Operator Actions SRO Time Action Notes Direct entry into OAOP-17.0.

Direct start of a TCC Pump. Direct IIC to investigate loss of 2B TCC pump. RO I Time Plant Monitoring . I Action I Notes Page 15 of 31 EVENT 4 (Cont'd) TBCCW PUMP B TRIP BOP Time Action Notes Report loss of 2B TCC Pump and refer to APPs. 2APP-UA-03 (2-4) TBCCW PUMP DISCH HEADER PRESS LOW Enter OAOP-17.0.

Dispatch AO to investigate 2B TCC Pump condition.

May dispatch AO to perform prestart checks for 2A or 2C TCC Pump. Starts a TCC pump. (May start two pumps) (Depending on the amount of time that no TCC pump is operating, one pump may not immediately restore TCC pressure due to the system loads TCC temperature control valves being wide open.) If needed, Verify Unit One is not using 2C TCC pump and start pump. Page 16 of 31 EVENT 5/6 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 3 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 Verify turbine vibrations on 4, 5, and 6 begin to rise after receiving UA-23 1-6. 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. When vibrations rise to above the TSI setpoint, direct manual scram and turbine trip per the vibration APP. (12 mils on bearings 1-8, 10 mils on bearings 9-10) (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. Page 17 of 31 EVENT 5/6 (Cont'd) 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 UA-23 1-6 TURB OR RFP BRG TEMP HIGH 6-1 TURBINE VIBRATION HIGH 6-3 TSI HIGH VIBRATION TRIP 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. Page 18 of 31 EVENT 7/8 ATWS ACTIONS Most control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-LPC. 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 Malfunctions Required:

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 per EOP-01-RSP.

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

RO/BOP -Perform immediate actions for a reactor scram. Perform actions for 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 6 to trip the main turbine. D If requested to perform alternate boron injection using CRD, acknowledge the request. (will be performed after RPV injection is re-started)

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 Performs LEP-03, Alternate Boron Injection Performs LEP-02, Alternate Rod Insertion SRO Time Action Enter RSP and transition to LPC. Direct mode switch to shutdown when steam flow < 3 Mlbs/hr. Direct ARI initiation.

Direct Recirc Pump speeds reduced to 10%. Direct Recirc Pumps Tripped. Page 19 of 31 Notes EVENT 7/8 ATWS ACTIONS SRO Continued Time Action Notes Direct SLC initiation.

Direct LEP-03, Alternate boron injection. (Critical task) Direct ADS inhibited.

Direct RWCU isolation.

Direct LEP-02, Alternate Rod Insertion. (Critical task) BOP Time Action Notes Places ADS in inhibit. Identifies RWCU fails to isolate. Closes RWCU Outboard Isol Valve G31-F004.

Trips the Main Turbine due to the high vibrations and loss of cooling. 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. Page 20 of 31 EVENT 7/8 ATWS ACTIONS RO (cont'd) Time Action Notes Recognizes failure of SLC and reports to SCO. Performs LEP-03, Alternate Boron Injection. (Critical task) Direct AO to perform LEP-03, Section 1, Alternate Boron Injection using CRD. Performs LEP-02, Alternate Rod Insertion. (RMCS Section) (Critical task) 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. 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. Page 21 of 31 EVENT 8/9 ATWS ACTIONS -CONTINUED The crew will terminate and prevent injection, re-injection will start when level is at 90 inches due to table 3 conditions not met. If RFPs are tripped they will be unavailable for level control as the Recirc Valves will fail in the closed position not allowing the RFPs to be restarted.

HPCI will be available for level control. Objectives:

SCO -Direct actions to lower reactor vessel level when the conditions of Table 3 are not met per EOP-01-LPC.

RO/BOP -Control reactor level during an ATWS per EOP-01 LPC. Success Path: Continues actions in the LPC procedure, terminate and prevent injection, drive rods using RMCS. Simulator Operator Actions: D If requested to defeat Group I LL3, wait 2 minutes, initiate Trigger 8 and inform the SCO that the jumpers are installed.

D If requested to install LEP-02, Section 3 jumpers, wait until level has been terminated and prevented or 5 minutes whichever is longer, insert Trigger 7 and inform the SCO that the jumpers are installed.

D If requested as I&C to investigate the failure of the scram discharge volume vents and drains, acknowledge the request. D If requested to open the MVD-5005, wait 5 minutes, initiate Trigger 9 and inform the control room that the valve is open. D If requested to defeat Drywell Cooler LOCA Lockout, wait three minutes, initiate Trigger 10 and inform the SCO that the jumpers are installed.

D When injection to the RPV has been re-established and if requested to line up boron to the CRD system initiate Trigger 11. D When directed by the lead examiner, proceed to the next event. Page 22 of 31 EVENT 8/9 ATWS ACTIONS -CONTINUED Required Operator Actions Terminate and prevent HPCIIFeedwater (CSIRHR when LOCA signal received).

SRO Time Action Notes Direct Group 10 switches to override reset. Direct terminate and prevent HPCIIFeedwater (CSIRHR when LOCA signal received). (Critical task) When level reaches +90 inches, evaluate Table 3:

If not met, establishes a level band of LL4 to +90 inches. Directs Drywell cooling restored per SEP-10. Evaluate TAF and LL4 indicated levels using Caution 1 graphs. Direct injection established to maintain If level is lowered to less than 45 inches (LL3) RPV level LL4 to 90 inches then the LP ECCS pumps will start and will (should try to keep level above the LL3 need to be terminated and prevented.

setpoint, most likely will establish a level band of 60-90 inches) Page 23 of 31 EVENT 8/9 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.

Inhibit ARI Places ARllnitiation 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 Recognize/report failure of scram discharge volume vents and drains. Page 24 of 31 EVENT 8/9 ATWS ACTIONS -CONTINUED BOP Time Action Notes Places Group 10 switches to override I reset Terminate and prevent injection to RPV. (Critical task) HPCI -Places HPCI Aux Oil Pump to Pull to Lock. FW-Can be performed a couple of If RFP are tripped they will not be able to be ways. restarted.

The preferred method would be to lower discharge pressure.

Trip RFP Turbines OR Trip one RFP and adjust discharge pressure of the running pump down to below RPV pressure to prevent injection.

Then Ensures SULCV lineup with MSTR RFPT SP/RX LVL CTL in manual and SULCV closed. ECCS -Turns OFF low pressure ECCS pumps if they start. May place Feedwater in service for level control when directed by the SCO. Raise RFP discharge pressure above RPV pressure Open SULCV to obtain desired level Page 25 of 31 EVENT 8/9 ATWS ACTIONS -CONTINUED BOP Continued Time Action Notes May place HPCI in service for level control during A TWS 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 Page 26 of 31 EVENT 10 ALL RODS IN When level has been lowered and level band has been established, the scram discharge volume vents and drains will be repaired.

Control rods can then be inserted by manual scram. When all control rods are inserted and level is being maintained 170 to 200 inches the scenario may be terminated Malfunctions Required:

Success Path: When actions are taken to control reactor water level during the A TWS 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 170 -200 inches 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

-RP01 OF, A TWS 3 (Make sure RPS is reset before deleting)

Inform the SCQ that a loose wire was found on the SDV vent and drain logic and have been fixed. o If contacted as the RB AQ to secure Alternate Boron Injection delete remote SL IALEP03. o When directed by the lead examiner, proceed to the next event. Required Operator Actions SRQ 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. Page 27 of 31 EVENT 10 ALL RODS 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.

BOP Time Action Notes Maintains reactor pressure as determined by the SCO. 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. Raises feedwater flow to raise reactor water level, if RFPs were not tripped. Page 28 of 31 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 Page 29 of 31 0 -20 <n W ::c -30 () Z ---40 ...J w > -50 W ...J C -60 W -70 () C Z 90 -100 ATTACHMENT 6 Page '13 of 19 FIGURE FA Unit 2 Reactor Water Level at TAF 700 900 60 600 800 REACTOR PRESSURE (PSIG) vVHEN REACTOR PRESSURE IS LESS THAN 60 PSIG, USE INDICATED LEVEL TAF IS -7.5 INCHES. Page 30 of 31 /. REf lEG TEMP ABOVE 200'F .rREFLEG ,. TEMP BELOW OR EQUAL TO 200"F 1,150 0 -20 CI) W :::I: -30 () Z --....J W > -50 W ....J C -60 W -70 U -C Z 90 100 ATTACHf*,.1ENT

!3 Page 15 of '19 FIGURE 'l8A Unit. 2 Reactor Water Level at LL-4 (Minimum Steam Cooling Level) 900 1,100 60 400 600 REACTOR PRESSURE (PSIG) WHEN REACTOR PRESSURE IS LESS THAN 60 PSIG, USE INDICATED LEVEL. LL-4 IS -30.0 INCHES. Page 31 of 31 REF LEG TEMP BELOW OR EQUAL TO 200"F 1 1 150 rA Scenario Outline Form ES-D-1 Facility:

Brunswick Scenario No.: 2010-1 #4 Op-Test No.: Final Examiners:

Operators:

Initial Conditions:

Unit Two (2) is operating at 6% power. Reactor startup is in progress per GP-03. GP-10 sequence A2X is complete up to Step 10 Item 166. 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 NI018F I-RO IRM C fails upscale (TS) I-SRO 2 N/A N-BOP Shift Steam Packing Exhausters (SPE) N-SRO 3 N/A R-RO Raise reactor power by pulling control rods R-SRO 4 RD032M, 26-23 C-RO Difficult to move control rod C-SRO 5 Q2BXPUAD HCU 30-07 Accumulator low pressure (TS) 5a CF063F C-BOP RFP TM-25 Actuator Failure C-SRO 6 MS005F M-ALL Inadvertent MSIV closure 7 ES004F C-RO SRV F failing open C-SRO 8 CA020F M-ALL Tailpipe rupture (LOCA) 9 K1227A I-BOP RHR A Spray logic failure I-SRO 10 RH_ZVRH28BM C-BOP E 11-F028B failure C-SRO 11 Drywell & Suppression Pool Spray and Reactor water level being maintained.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 34 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-1 NRC EXAM SCENARIO #4 Page 1 of 34 SCENARIO DESCRIPTION Unit Two is operating at -6% power. Reactor startup is in progress per GP-03. GP-10 sequence A2X is complete up to Step 10 Item 166. 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 166 (10-23 @ 12) of the A2X sequence.

While withdrawing control rod 10-23 from position 12, IRM C will fail upscale causing a rod block and half scram. SRO will address IRM A and C inoperability lAW TS 3.3.1.1. Once addressed, I&C will report IRM A is ready to be returned to service following proper channel check. The crew will take the actions of the APP and bypass IRM C and reset the half scram. Event 2 Maintenance will contact the control room and request SPEs be swapped due to low oil level. Shift Steam Packing Exhausters (SPE) lAW 20P-26.1, Section 8. Event 3 Following SPE shift, control rods will continue to be withdrawn raising power. Event 4 When control rod 26-23 is selected for withdrawal, it will be stuck at position 12. AOP-02 may be entered and 20P-07, Section 8.2 actions are required to withdraw a difficult intermediate control rod. Event 5 When control rod 26-23 is fully withdrawn, HCU 30-07 accumulator light and annunciator will alarm. AO will be dispatched to investigate and determine accumulator alarm is due to low pressure and requires charging.

TS 3.1.5 evaluation will be required.

Event 5a When HCU 30-07 accumulator is re-pressurized and TS addressed, The TM-25 actuator will fail on 2A RFP. The crew will raise the discharge pressure of the idling RFP and open the discharge valve to maintain level lAW OAOP-23.0.

Event 6 After the TM-25 Actuator failure a spurious Group 1 isolation (MSIV closure) causes reactor pressure and power rise. Manual SRV opening or Scram may be performed.

HPCI and/or RCIC may be manually started to control RPV water level due to loss of RFPTs. Event 7 2 minutes following MSIV closure, SRV F will fail open requiring entry into OAOP-30.0 to attempt to close. Event 8 With SRV F failed open, PCCP will be entered and as reactor pressure falls below 700 psig, the tail pipe will rupture causing direct pressurization of the Suppression Pool air space (loss of PSP). Event 9 When containment spray is attempted with RHR Loop A, the Spray logic will fail to actuate, making sprays unavailable.

Emergency depressurization will be required due to pressure suppression pressure limit. Logic will be available following ED. Event 10 When containment spray is attempted with the B RHR Loop, the E11-F028B will trip on thermal overload.

RHR Loop B will be the only loop available to provide OW Spray lAW SEP-02. Emergency depressurization will be required due to pressure suppression pressure limit. Valve will be available following ED. Event 11 Once the reactor is depressurized with OW & SP Sprays in service and RPV water level being maintained in the normal band, the scenario may be terminated.

Page 3 of 34 OBJECTIVES SRO 1. 3442318402, Direct Actions For Safety/Relief Valve Failures Per AOP-30.0 2. 3442438402, Direct Shift Response To High Suppression Pool Temperature Per AOP-14.0 3. 3442178502, Direct Actions To Control RPV Level Per EOP-01-RVCP

4. 3442188502, Direct Actions To Control Reactor Pressure Per EOP-01-RVCP

5. 3442208502, Direct Actions To Emergency Depressurize The RPV Per EOP-01-RVCP 6. 3442148502, Direct Actions To Control Primary Containment Pressure Per EOP-02-PCCP 7. 3442158502, Direct Actions To Control Primary Containment Temperature Per EOP-02-PCCP 8. 3442168502, Direct Actions To Control Suppression Pool Temperature Per EOP-02-PCCP RO 1. 2006038501, Perform immediate actions for a reactor scram 2. 2236018401, Respond to High Suppression Pool Temperature per AOP-14.0 3. 2390088401, Respond To An SRV Failure Per AOP-30.0 4. 2000498501, Spray The Drywell Per EOP-01-SEP-02

5. 2000628501, Spray The Suppression Pool Per EOP-01-SEP-03

6. 2050148101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 REFERENCES A. OP-07 8. OP-08 C. OP-26.1 D. GP-03 E. GP-10 F. AOP-02.0 G. AOP-30.0 H. AOP-39 I. 01-50 J. EOP-01-RSP K. EOP-01-RVCP L. EOP-02-PCCP M. EOP-LEP-01 N. EOP-01-SEP-02 O. EOP-01-SEP-03 P. EOP-01-SEP-09 Q. Conduct Of Operations Manual R. Technical Specifications S. Plant Emergency Procedures T. Annunciator Panel Procedures Page 4 of 34 SIMULATOR SETUP Initial Conditions IC-6 Rx Pwr 6% Event Triggers Event Trigger Description 0 Normal Ops (Shift SPEs) 1 Auto Initiated (IRM C Fails Upscale) 2 Auto Initiated (Control Rod 26-23 Stuck) 3 Manually Initiated (HCU 30-07 Low Pressure) 4 Manually Initiated (MSIV closure) 5 Auto Initiated (SRV F Fail Open) 6 Auto Initiated (SRV F Tailpipe ruture) 7 Auto Initiated (RHR Loop A Spray Logic Failure) 8 Auto Initiated (E11-F028B Overload)

Event Trigger Trigger Description Number 1 1 NI018F Withdraw override SRM C failure (K2324JGD) 2 SPE shift 3 Raise reactor power by pulling control rods 4 RD032M Control Rod 26-23 stuck at position "12" 2 K2324JVD EMERG IN deletes RD012M 26-23 5 3 Q2BXPUAD HCU 30-07 low pressure 5a 12 CF063F TM-25 Actuator Failure 6 5 MS005F Inadvertent MSIV closure 7 6 ES004F SRV F fails open 8 7 CA020F SRV F tail pipe rupture 9 K1227A A RHR Containment Spray Logic failure 10 8 Q1717RGN E 11-F028B Overload 11 Delete K 1227 A 11 Delete E11-F028B Overload 11 Pull SRV F Backpanel fuses Page 5 of 34 SIMULATOR SETUP Malfunctions Summary MalflD Mult Description 10 NI018F IRM C FAILURE RD012M 30-07 STUCK CONTROL ROD MS005F MSIV closure ES004F ADS VALVE fail open CA020F SRV F tail pipe rupture

CF063F A TM-25 Actuator Failure Remotes Summary Remf 10 Mult Description 10 K2324JGD OVERRIDE Q2BXPUAD 30-07 ACCUM-ROD DISPLAY K2324JVD EMER IN Current Target Value Value FALSE TRUE TRUE TRUE FALSE TRUE FALSE TRUE FALSE TRUE 1 0 Current Value OFF G1HZ1G1H REACTOR PRESSURE < 700 psig Q1303LGH SCRAM PUSH BUTTON Override Summary Tag 10 Description Position/

Actual Override Target Value Value K1227A CONT SPRAY VLV CONT NORM ON ON K1227A CONT SPRAY VLV CONT MANUAL OFF OFF K1227A CONT SPRAY VLV CONT RESET OFF OFF Q1717LGN TORUS ISOL E11-F0028B GREEN ON/OFF ON ON Q1717RRN TORUS ISOL E11-F0028B RED ON/OFF OFF ON Q1508RRJ SRVVLV B21-F013F RED ON/OFF OFF OFF Q1508LGJ SRVVLV B21-F013F GREEN ON/OFF ON OFF Annunciator Summary Rmptime Actime Dactime 40 sec 4min Target Rmptime Actime Value ON 2min Rmptime Actime Dactime Window Description Tagname Override Type Oval AVal Actime Dactime 6-1 CRD ACCUM LO PRESS/HI LEVEL ZA761 ON/OFF ON OFF 5-8 RHR B VALVES OVERLOAD ZA358 ON/OFF ON OFF 2-2 AUTO DEPRESS CONTROL PWR ZA322 ON/OFF ON OFF FAILUE Page 6 of 34 Trig 1 5 6 7 12 Trig 1 3 2 7 6 Trig 9 9 11 11 Trig 3 9 11 Special Instructions

1. Ensure "Exam In Progress" Stop Signs posted at all simulator entrances.

2. Advance all chart recorders to indicate steady state conditions.

3. Place all SPDS displays to the Critical Plant Variable display (#100). 4. Ensure appropriate keys have blanks in switches.

5. Exit shutdown screen on RWM and place the RWM key in the key locker. 6. Reset alarms on SJAE, MSL, and RWM NUMACs. 7. Ensure reference materials are in appropriate location.

8. Verify all log books have blank sheets only. 9. Reset to IC-6 and place in run. 10. Insert control rods to get back to Step 10 Item 166 11. Bypass IRM A and place off normal tag. 12. Verify SPE A is in service 13. Ensure GP-1 0 is completed up to Step 10 Item 166 of A2X sequence.

14. Ensure OGP-03 is completed up to Step 5.1.5. 15. Ensure Reactor pressure is 925 psig and #1 BPV open at least 20%. 16. Transfer RFP & Master level controllers to Auto and fully open SULCV in Manual. 17.Verify APRM GAFs are

18. Load scenario file, 2010 Scenario 4.scn, if required.

19. Provide turnover sheet along with IRM A Troubleshooting Form (Attachment 5). 20. Throttle V177 to maintain RFP demand stable. Page 7 of 34 SHIFT BRIEFING Plant Status Unit startup is in progress per OGP-03 following a refueling outage. Reactor power is approximately 5%. Control rod withdraw is in progress per Step 5.1.5 of OGP-03. Reactor pressure is 925 psig with one bypass valve open to approx. 20%. OGP-10, sequence A2X, is being used and is complete up to Step 10 Item 166. Equipment Out of Service IRM A was declared inoperable early last shift due to spiking and is bypassed.

I&C Troubleshooting has determined that the instrument loop is functioning satisfactorily and that the spiking was due to welding near the pre-amp at that time. Stable operation has been observed for the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The Ops Center SRO is evaluating IRM Operability.

Plan of the Day Continue with OGP-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.

Page 8 of 34 SCENARIO TRAINING INFORMATION Instructor Notes 1. This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1 021, Revision 9, ES-301 and Appendix D. 2. During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1021, ES-303. B.Common Student Problems/Errors None C.Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.

D.CREW CRITICAL TASKS (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)

1. Emergency Depressurize the RPV when PSP has been exceeded.

2. Establish Containment Sprays Page 9 of 34 EVENT 1 SHIFT TURNOVER, RAISE REACTOR POWER, IRM C FAILURE 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 166 (10-23 @ 12) of the A2X sequence.

While withdrawing control rod 10-23 from position 12, IRM C will fail upscale causing a rod block and half scram. Unit SRO will address IRM A and C inoperability lAW TS 3.3.1.1. Once addressed, Ops Center SRO will report IRM A is ready to be returned to service following proper channel check. The crew will take the actions of the APP and bypass IRM C and reset the half scram. Objectives:

SRO Directs and monitor reactor power ascension with control rods Direct actions for IRM C failure. Address IRM C TS 3.3.1.1 RO Withdraw control rods to raise reactor power Monitor plant parameters during power ascension Perform actions for IRM C failure Success Path: Technical Specification

/ TRM

3.3.1.1* Reactor Protection System (RPS) Instrumentation Determines with IRMs A & C inoperable, Condition A. One or more required channels inoperable for Function 1 a (IRM Neutron Flux-High.

Required Action A.1 (Place channel in trip) within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Declare IRM A operable by channel check and bypass IRM C with tracking LCO for IRM C. Simulator Operator Actions: o While continuously withdrawing control rods, verify Trigger #1 initiates to fail IRM C upscale. o If contacted as the RE for IRM C inoperability, acknowledge request. o When IRM C inoperability has been addressed and by lead examiners direction, contact the control room as Ops Center SRO and report IRM A can be declared Operable following a satisfactory channel check. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Instrument Failure -IRM C upscale rod block and half scram. Technical Specification

-IRM C inoperability and restore IRM A operability.

SRO Time Action Notes Ensures no other distracting evolutions are in progress while reactivity controls are being manipulated.

Directs RO to raise reactor power by withdrawing control rods lAW OGP-1 0 Item 10 Step 166. (Continuous withdrawal allowed).

Page 10 of 34 EVENT 1 cont'd SHIFT TURNOVER, RAISE REACTOR POWER, IRM C FAILURE SRO (Cont'd) Time Action Notes Directs BOP to continue monitoring plant. Directs APP reference.

Contacts I&C for IRM C failure. May contact Shift Manager also. References TS 3.3.1.1 and determines with IRMs A & C inoperable:

Condition A is applicable for Function 1 a Required Action A.1 is required within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . May enter TRM 3.3 (Control Rod Block May conservatively declare an active LCO, Instrumentation)

Function 3 Condition A, Required Action A.1 Restore channel to Tracking LCO. OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Evaluates IRM A operability following satisfactory channel check. 20P-09, Attachment 4, 2.3.4 (Operability Guidance)

-Channel Checks are a sufficient WO PMT for SRMs and IRMs at power unless a component failure is suspected in which case an IN curve and TDR trace is desirable.

Directs IRM A channel check be performed.

Determines IRM A is operable Directs removing IRM A from Bypass Directs bypassing IRM C Directs resetting half scram Page 11 of 34 EVENT 1 cont'd SHIFT TURNOVER, RAISE REACTOR POWER, IRM C FAILURE RO Time Action Notes Commence rod withdrawal at step 166 of GP-10 per guidance of 01-01.02 20P-07 Continuous Rod Withdraw 1. ENSURE ROD SELECT POWER control switch is in ON. 2. SELECT desired control rod by depressing its CONTROL ROD SELECT push button. 3. ENSURE the backlighted CONTROL ROD SELECT push button is brightly illuminated AND the white indicating light on the full core display is also illuminated.

4. ENSURE ROD WITHDRAWAL PERMISSIVE indication has illuminated.

5. CONTINUOUSLY WITHDRAW control rod to position designated on GP pull sheets by holding EMERGENCY ROD IN NOTCH OVERRIDE switch to OVERRIDE, while simultaneously holding ROD MOVEMENT switch to NOTCH OUT. 6. MONITOR control rod position AND nuclear instrumentation while withdrawing the control rod. 7. PERFORM the following for control rods to be fully withdrawn:

a. WHEN control rod reaches position 48, THEN PERFORM either of the following:

-MAINTAIN the continuous withdraw signal for the desired time -APPLY a separate notch withdraw signal. b. ENSURE control rod does NOT retract beyond position 48. (ref. SR 3.1.3.4) c. RELEASE ROD MOVEMENT and EMERGENCY ROD IN NOTCH OVERRIDE switches, if used. d. ENSURE control rod settles at position 48 AND rod settle light extinguishes.

e. ENSURE control rod reed switch position indicators agree with FULL OUT indication on full core display. Stops withdrawing control rods when IRM C fails upscale. ROD OUT BLOCK Determines IRM C failed upscale. Page 12 of 34 EVENT 1 cont'd SHIFT TURNOVER, RAISE REACTOR POWER, IRM C FAILURE RO (Cont'd) Time Action Notes Responds and reports applicable alarms for IRM C failing upscale. A-5 1-7 REACTOR AUTO SCRAM SYS A 4-7 NEUT MON SYS TRIP 2-4 IRM UPSCALE 2-2 ROD OUT BLOCK 3-4 IRM A UPSCALE//NOP A-5 IRM A UPSCALE/INOP actions: May Reposition range switch for I RM C to bring indicated power to between 15 and 50 on the 0-125 scale. May verify I RM C Drawer Selector switch (Control Panel H12-P606) is in OPERATE. May notify SRO of Tech Spec applicability May inform SRO IRM C cannot be bypassed and half scram cannot be reset due to IRM A being bypassed.

Performs channel check of IRM A for operability.

RO DSR Item # 9 (IRM channel check) 201-03.2, Definition

5.1. Removes

I RM A from Bypass Bypasses IRM C per APP guidance.

Resets half scram per APP guidance.

BOP Time Action Notes Monitors reactor plant parameters during evolution.

Page 13 of 34 EVENT 2 SHIFT STEAM PACKING EXHAUSTERS Maintenance will contact the control room and request SPEs be swapped due to low oil level in SPE A. Shift SPE lAW 20P-26.1, Section 8. Objectives:

SRO Directs SPE shift A to B. BOP Shift SPEs lAW 20P-26.1, Section 8 Success Path: SPE B placed in service and SPE A shutdown lAW 20P-26.1, Section 8. Simulator Operator Actions: o Following half scram reset and by direction of the Lead examiner, Contact the control room as Maintenance and request SPE A be shutdown due to low oil level to prevent equipment failure. o As AO, when requested, report MVD-V52 is open, o As AO, when requested, report MVD-V51 is closed. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Normal Operation

-Shift SPEs lAW 20P-26.1.

SRO Time Action Notes Direct RO to stop power maneuver and monitor plant while shifting SPEs. Directs BOP to shift SPEs to remove A from service. May direct continuing control rod withdrawal following SPE shift. RO Time Action Notes Monitors plant while shifting SPEs. BOP Time Action Notes Communicates maintenance request for shutting down SPE A to SRO. Identifies 20P-26.1, Section 8.1 (Shifting Steam Packing Exhausters) is required.

Page 14 of 34 EVENT 2 cont'd SHIFT STEAM PACKING EXHAUSTERS BOP (Cont'd) Time Action Notes Shifts SPEs Directs AO to OPEN FLOA T TRAP OUTLET VAL VE, MVD-V52. Makes plant PA announcement and Starts SPE B Ensures STEAM SEAL SPE 28 MO INLET VL V, OG-MOV-E2, is open. Throttles closed STEAM SEAL SPE 2A MO DISCH VLV, OG-MOV-D1, AND Throttles open STEAM SEAL SPE 28 MO DISCH VL V, OG-MOV-D2, while maintaining GLAND EXHAUST HEADER, OG-PI-EPT-9, located on Panel XU-2, between 10 and 20 inches water vacuum. May get annunciator UA-02 4-5 GLAND SEAL VACUUM LOSS If Gland seal vacuum on OG-PI-EPT9-SPE drops below 5 inches of water. Ensures STEAM SEAL SPE 2A MO DISCH VL V, OG-MOV-D1, is closed. Makes plant PA announcement and Stops SPE A Directs AO to close FLOA T TRAP OUTLET VALVE, MVD-V51 Ensures STEAM SEAL SPE 2A MO INLET VALVE, OG-MOV-E1, is closed. Informs SRO SPE shift is complete.

Notifies maintenance SPE A is shutdown.

Page 15 of 34 EVENT 3/4 RAISE REACTOR POWER ISTUCK CONTROL ROD Following SPE shift, control rods will continue to be withdrawn until control rod 26-23 which is difficult to move at position 12, requires OP-07 actions to move. Objectives:

SRO Directs and monitor reactor power ascension with control rods Direct actions for a stuck control rod. RO Withdraw control rods to raise reactor power Perform 20P-07 actions for stuck control rod Monitor plant parameters during power ascension BOP Monitor plant parameters during power ascension Success Path: Control rod 26-23 withdrawn to position 48 by use of increase drive water DP and double clutch. Simulator Operator Actions: o If contacted as the RE for Control Rod 26-23 stuck, concur with 20P-07 guidance and double clutch withdrawal if requested.

o When drive water DP has been raised to 300 psid and RE concurrence, ensure Trigger 2 deletes RD032M when EMERGENCY ROD IN NOTCH OVERRIDE is placed in the EMERGENCY ROD IN position.

o When directed by the lead examiner, proceed to the next event. Required Operator Actions Reactivity Manipulation

-Raise reactor power by control rod withdrawal.

Component Failure -Control Rod 26-23 stuck at position 12. SRO Time Action Notes Directs RO to continue to raise reactor power by withdrawing control rods. (Continuous withdrawal allowed).

Directs RO to perform 20P-07. May direct AOP-02 (Control Rod malfunction)

-Provides notifying RE and Using 20P-07 to move rod. Page 16 of 34 EVENT 3/4 cont'd RAISE REACTOR POWER ISTUCK CONTROL ROD SRO (Cont'd) Time Action Notes May evaluate Tech Spec 3.1.3 Control Rod Operability Condition A. One withdrawn control rod stuck Required Action A.1 Verify stuck control rod separation criteria are met (Immediately)

AND Required Action A.2 Disarm the associated control rod drive (CRD). (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) AND Required Action A.4 Perform SR 3.1.1.1.(72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) May evaluate TS 3.1.3, Control Rod Conservatively may declare the control rod Operability, AND 3.3.2.1, Control Rod inoperable.

Block Instrumentation before performing procedure.

Should not declare control rod stuck until actions of 20P-07 have been attempted.

Separation criteria is met (no identified slow rods) Obtains RE concurrence for double clutching control rod with elevated drive water DP. RO Time Action Notes Continues rod withdrawal per GP-10 lAW guidance of 01-01.02 and 20P-07. Report A-6 2-7 APRM DOWNSCALE annunciator clears. Recognizes control rod 26-23 is stuck. Notifies SRO control rod 26-23 is stuck. Identifies 20P-07, Reactor Manual Control System Operating Procedure, Section 8.2 (Control Rod Difficult to Withdraw, Control Rod NOT at Position 00) is required.

Page 17 of 34 EVENT 3/4 cont'd RAISE REACTOR POWER ISTUCK CONTROL ROD RO (Cont'd) Time Action Notes Notifies SRO to consult TS 3.1.3 & 3.3.2.1. Verifies no Rod Blocks. Raises drive water DP to 300 psid. May use 20P-08, Section 8.29 (Adjusting CRDHS Parameters)

Maintains CRD flow rate 30 to 60 gpm

May raise CRD flow and/or throttle closed DRIVE PRESSURE VLV, C12-PCV-F003 Attempts to withdraw control rod 26-23 Normal withdraw attempts may be repeated at elevated drive water DP. Notifies SRO double clutching is required.

Verifies RE concurrence.

Momentarily places EMERGENCY Deletes malfunction Trigger 2 ROD IN NOTCH OVERRIDE in EMERGENCY ROD IN. Simultaneously places EMERGENCY ROD IN NOTCH OVERRIDE in OVERRIDE AND ROD MOVEMENT in NOTCH OUT. Recognizes control rod withdraw and stops to return drive water DP back to normal (260 -275 psid) Once fully withdrawn, control rod is inserted to 46 and withdrawn to 48 under normal drive water DP. Performs coupling check following fully withdrawing control rod to position 48. BOP Time Action Notes Monitors plant while control rods are being withdrawn.

Page 18 of 34 EVENT 5 HCU 30-07 ACCUMULATOR LOW PRESSURE When directed by Lead examiner, HCU 30-07 accumulator light and annunciator will alarm. AO will be dispatched to investigate and determine accumulator alarm is due to low pressure and requires charging.

TS 3.1.5 evaluation will be required.

Objectives:

SRO Direct actions for inoperable CRD accumulator.

Address TS 3.1.5 ROIBOP Perform actions for HCU accumulator alarm Success Path: Technical Specification

/ TRM

3.1.5 Control Rod Scram Accumulators Determines Condition C. One or more control rod scram accumulators inoperable with reactor steam dome pressure < 950 psig. Required Action C.1 Verify all control rods associated with inoperable accumulators are fully inserted Immediately.

AND C.2 Declare the associated control rod inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Simulator Operator Actions: D When directed by the Lead examiner, activate Trigger 3 to cause accumulator alarm and annunciator for HCU 30-07. D If contacted as AO to investigate, acknowledge request, wait 1 minute and report the accumulator alarm is low pressure.

Accumulator pressure is at 930 psig. D After Tech Spec declaration is made, delete CRD ACCUM LO PRESS/HI LEVEL (ZA761) and ACCUM-ROD DISPLAY (Q2BXPUAD ) and report HCU 30-07 has been re-charged with final accumulator pressure equal to 1140 psig. D When directed by the lead examiner, proceed to the next event. Required Operator Actions Component Failure -HCU accumulator low pressure Technical Specification

-3.1.5 SRO Time Action Directs APP actions Direct contingency plans to monitor the other accumulator alarms due to masking. Directs charging the accumulator per 20P-OB. Notes Page 19 of 34 EVENT 5 cont'd HCU 30-07 ACCUMULATOR LOW PRESSURE SRO (Cont'd) Time Action Notes Determines TS 3.1.5 applicability Determines reactor pressure <950 psig. Determines Condition C. One or more control rod scram accumulators inoperable with reactor steam dome pressure < 950 psig. Required Action C.1 Verify all control rods associated with inoperable accumulators are fully inserted Immediately.

AND C.2 Declare the associated control rod inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . RO Time Action Notes Acknowledges and reports to SRO annunciator A-7 6-1 CRD ACCUM LO PRESS/HI LEVEL Directs AO to investigate.

Directs AO to determine if alarm is due to low pressure or high water level in the HCU by depressing the lighted indication on the local HCU panel and observing the status of the light (light out indicates water). Directs charging the accumulator per 20P-08 Reports to SRO annunciator A-7 6-1 CRD ACCUM LO PRESS/HI LEVEL is clear. BOP I Time I Action I Notes Page 20 of 34 EVENT 5a RFP TM-25 ACTUATOR FAILURE When directed by Lead examiner, the 2A Reactor Feed Pump TM-25 Actuator will fail. This will cause the speed to decay away and level to lower. The crew will raise the discharge pressure on the idling 28 RFP and then open the discharge valve to control level. Objectives:

SRO Direct actions to control RPV water level lAW OAOP-23.0.

ROIBOP Perform actions lAW OAOP-23.0 to control RPV water level. Success Path: 2B RFP discharge pressure increased and discharge valve opened to control RPV water level. Simulator Operator Actions: o When directed by the Lead examiner, activate Trigger 12 to cause the 2A RFP TM-25 to fail closed. o When directed by the lead examiner, proceed to the next event. Required Operator Actions Raise RFP discharge pressure, open the discharge valve, and control RPV eater level. SRO Time Action Notes Directs OAOP-23.0 entry May direct 2B RFP to be placed in service from an idling condition.

Directs the 2A RFP to be shutdown.

Page 21 of 34 EVENT 5a cont'd RFP TM-25 ACTUATOR FAILURE RO Time Action Notes Monitors plant Announces lowering RPV water level May announce entry into OAOP-23.0 BOP Time Action Notes Performs Immediate Operator Actions associated with OAOP-23.0 to place an idling RFP in service. Slowly adjust RFPT speed LOWER/RAISE speed control switch to maintain discharge pressure at least 100 psig greater than reactor pressure.

Open RFP B DISCH VLV, FW-V4. Control reactor feed pump turbine speed as necessary using the LOWER/RAISE speed control switch. Obtains procedure for shutting down the After RPV water level is stable can proceed to 2A RFP. the next event. Page 22 of 34 EVENT 6/7 MSIV CLOSURE, REACTOR SCRAM, SRV F FAILS OPEN When RPV water level is stable after placing 28 RFP in service, a spurious Group 1 isolation (MSIV closure) causes reactor pressure and power rise. Manual SRV opening or Scram may be performed.

HPCI and/or RCIC may be manually started to control RPV water level due to loss of RFPTs. Objectives:

SRO Direct manual scram and pressure control Directs entry to AOP-14 Enters RSP, RVCP, PCCP ROIBOP Diagnose loss of pressure control Diagnose SRV F failing open Perform SCRAM actions Control reactor parameters post SCRAM Success Path: Manual reactor scram inserted with pressure being controlled Simulator Operator Actions: o When HCU 30-07 accumulator is re-pressurized and TS addressed and by direction of the Lead examiner, activate Trigger 5. o If contacted as I&C to investigate MSIV closure, Acknowledge request. o Ensure Trigger 6 automatically actuates 2 minutes after MSIV closure. o If contacted as Ops Center SRO to pull fuses for SRV F, acknowledge request and activate Trigger 11 one minute later and report fuses pulled. o If contacted as I&C to investigate SRV F opening, Acknowledge request. Required Operator Actions Major -Reactor scram Component Failure -SRV F fails open SRO Time Action Notes Direct manual scram insertion.

Conservative decision before power oscillations cause automatic scram Direct manual pressure control. Enters and directs EOP-01-RSP Determines entry into EOP-01-RVCP is required Directs AOP-30 entry Directs LEP-02 to reset scram. Page 23 of 34 EVENT 6/7 cont'd MSIV CLOSURE, REACTOR SCRAM, SRV F FAILS OPEN SRO (Cont'd) Time Action Notes Directs verification

Group Isolations

ECCS Initiations

Diesel Generator Auto Starts Directs restoring and maintaining reactor water level between +170 and +200 inches with one or more of the systems listed in Table 1

CRD (SEP-09)

RCIC Directs AOP-14 on rising Suppression Pool temperature.

Direct RHR be placed in suppression pool cooling Directs starting RCIC to maintain level May direct starting HPCI to maintain level May direct utilizing SLC aligned to Demin Water (LEP-01).

RO Time Action Notes Inserts a manual scram as directed by SRO Performs scram immediate actions: 1. Unit 2 Only: After steam flow is less than 3 x 106 Ib/hr, PLACE the reactor mode switch to SHUTDOWN.

2. IF reactor power is below 2% (APRM downscale trip), THEN TRIP the main turbine. 3. ENSURE the master reactor level controller setpoint is +170". 4. IF two reactor feed pumps are running, and reactor vessel level is above +160" and rising, then trip one. Reports Scram immediate actions complete All rods in, Mode Switch in shutdown Page 24 of 34 EVENT 6/7 cont'd MSIV CLOSURE, REACTOR SCRAM, SRV F FAILS OPEN RO (Cont'd) Time Action Notes Maintains RPV level 170-200" Reports when out of band and actions to address recovery.

Diagnoses loss of Feedwater flow to RPV Recognize SRV F failed opened. Enter and announce AOP-30.0 Performs AOP-30 immediate actions: 1. Cycles the control switch of the affected safety/relief valve to OPEN and CLOSE OR OPEN and AUTO several times. 2. Ensures the affected safety/relief valve control switch is left in CLOSE OR AUTO. 3. Contacts Ops Center SRO to pull fuses for SRV FlAW OAOP-30, Attachment 1 Recognizes SRV control power fuses pulled (no position indication and AUTO DEPRESS CONTROL PWR FAILURE) Manually starts RCIC to maintain RPV level May perform SEP-09, CRD Flow Maximization with procedure or Hardcard.

May start HPCI to maintain level or pressure.

Page 25 of 34 EVENT 6/7 cont'd MSIV CLOSURE, REACTOR SCRAM, SRV F FAILS OPEN BOP Time Action Notes Diagnoses loss of Feedwater flow to RPV Announces Unit Two reactor scram May perform SCRAM Hard card actions. 1. Ensure Scram Valves Are Open By Manual Scram or ARllnitiation

2. Control Reactor Pressure Between 800 and 1000 psig 3. Control Reactor Water Level Between +170 and +200 Inches 4. Place SULCV in Service 5. Insert Nuclear Instrumentation

6. Ensure Turbine Oil System Operating Enter and announce AOP-14.0 Place RHR in suppression pool cooling Page 26 of 34 EVENT 8/9/10 SRV TAIL PIPE RUPTURE, SPRAY FAILURES With SRV F failed open and reactor pressure approaching 700psig, the tail pipe will rupture causing direct pressurization of the Suppression Pool air space (loss of PSP). Suppression chamber and drywell pressure rapidly rise. Suppression chamber pressure leads drywell pressure and torus-drywell vacuum breakers lifting indicate broken SRV tailpipe When containment spray is attempted with the A RHR Loop, the Spray logic will fail to actuate, making sprays unavailable.

Emergency depressurization will be required due to pressure suppression pressure limit. Logic will be available following ED. When containment spray is attempted with the B RHR Loop, the E11-F028B will trip on thermal overload.

RHR Loop B will be the only loop available to provide OW Spray lAW SEP-02. Emergency depressurization will be required due to pressure suppression pressure limit. Valve will be available following ED. Objectives:

SRO Direct entry into PCCP Direct Emergency Depressurization when loss of PSP is recognized.

ROIBOP Diagnose and report rapidly rising containment pressures Determine leak is in suppression chamber based on higher suppression chamber pressure Attempt to initiate spray per SEP-02 and/or SEP-03 Diagnose and report failure of Loop B spray logic Success Path: Emergency depressurize the RPV and restore RPV water level followed by aligning RHR for SP Spray. Simulator Operator Actions: o Monitor RPV pressure and ensure Trigger 7 activates when RPV pressure drops below 700 psig. o If contacted as I&C for RHR A Spray logic failure, acknowledge request. o If contacted as I&C for RHR B E11-F028B overload, acknowledge request. o If contacted as AO for RHR B E11-F028B overload, acknowledge and request breaker location MCC (2XB-2) Required Operator Actions Place Containment Sprays in service (Critical Task) Emergency Depressurize the RPV when PSP exceeded (Critical Task) Page 27 of 34 EVENT 8/9/10 cont'd SRV TAIL PIPE RUPTURE, SPRAY FAILURES SRO Time Action Notes Enters and Directs PCCP Directs SP Spray lAW SEP-03 before Suppression Chamber pressure reaches 11.5 psig (Critical Task) Directs DW Spray lAW SEP-02 when Suppression Chamber exceeds 11.5 psig (Critical Task) Determine leak is in suppression chamber based on higher suppression chamber pressure Directs I&C for RHR A Spray logic failure. Directs I&C for RHR E11-F028B failure When PSPL exceeded, determine emergency depressurization is required Directs Emergency Depressurization (Critical Task) Page 28 of 34 EVENT 8/9/10 cont'd SRV TAIL PIPE RUPTURE, SPRAY FAILURES RO/BOP Time Action Notes Diagnose and report rising containment pressures.

Diagnose SRV F tailpipe rupture

SP to DW vacuum breakers open

SP pressure>

DW pressure Place RHR Loop A into suppression pool RHR Loop A remains available for SPC only cooling. until a LOCA signal is recieved.

Open SW-V101

Close SW-V143

If LOCA signal is present place RHR SW Booster Pumps A & C LOCA override switch to manual override

Start RHRSW Pump

Adjust E11-PDV-F06BA (1 pump 2000 -4000 gpm) (2 pumps 5000 -BOOO gpm)

Supply Clg Wtr to Vital Hdr

Verify spray logic is made up

Start Loop A RHR Pmp

Open E11-F028A

Throttle E 11-F024A (1 pump 6000 -10000 gpm) (2 pumps 6000 -11500 gpm)

Throttle E 11-F048A Diagnose and report RHR Loop A Spray Logic failure Initiate suppression chamber spray per SEP-03. (Critical Task)

If necessary, then place Loop B 2/3 CORE HEIGHT LPCIINITIATION OVERRIDE SWITCH, E11-CS-S1BB, in Manual Overrd.

If the CTMT SPR OVRD light for the Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, E11-CS-S17B is not on, then momentarily place Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, E11-CS-S17B, to Manual

Ensure at least one RHR Loop B Pump is operating

Ensure TORUS DISCHARGE ISOL VLV, E11-F02BB, is open

Open TORUS SPRAY ISOL VLV, E11-F027B.

Page 29 of 34 EVENT 8/9/10 cont'd SRV TAIL PIPE RUPTURE, SPRAY FAILURES RO/BOP (Cont'd) Time Action Notes Diagnose and report RHR Loop B E11-A-03 5-8, RHR B Valves Overload F028B overload.

Dispatch AO to RB Mee 2XB-2 to attempt thermal reset for E 11-F028B overload.

Report RHR Loop B is only available for DW Spray operation.

Initiate Drywel/ Spray per SEP-02. (Critical Task)

Ensure WELL WATER TO VITAL HEADER VLV, SW-V141, is closed

Ensure both reactor recirculation pumps are tripped

Place all drywell cooler control switches to OFF (LlO)

Request Drywell Cooler override switches to STOP.

Confirms the following:

Drywell pressure and drywell temperature are in the "SAFE" region of the DSIL graph.

Suppression pool water level is below +21 inches.

Open Loop B DRYWELL SPRAY INBD ISOL VLV, E11-F021B

Throttle open Loop B DRYWELL SPRAY OTBD ISOL VLV, E11-F016B, to obtain between 8,000-10,000 gpm flow Page 30 of 34 EVENT 11 EMERGENCY DEPRESSURIZATION, CONTAINMENT SPRAY Once the reactor is depressurized and DW & SP Sprays are in service, with RPV water level being maintained in the normal band, the scenario may be terminated.

Objectives:

seo Directs actions Emergency Depressurization and restoration of reactor water level. Direct drywell and torus spray per SEP-02 and SEP-03 following level restoration.

ROIBOP Performs actions for emergency Depressurization and restoration of reactor water level. Places RHR Loop A in Suppression Chamber and DW spray Success Path: Restore reactor water level to 170-200 inches. RHR Loop has been placed in SP & DW Sprays Simulator Operator Actions: Instructor Activities o Following emergency depressurization actions and by direction of the Lead examiner, DELETE K1227A overrides and contact the control room as I&C to report RHR A Spray logic has been repaired.

o Following emergency depressurization actions and by direction of the Lead examiner, DELETE Q1717LGN, RRN,& ZA358 overrides and report as AO the thermal overload has been reset for the E 11-F028B.

o When RPV level is being controlled above170" with DW & SP spray in service, the scenario may be terminated o When directed by the lead evaluator, place the simulator in FREEZE. Required Operator Actions Emergency Depressurize the RPV (Critical Task) SRO Time Action Notes Determine Emergency Depressurization is required.

Direct placing 7 ADS valve switches to open. (Critical Task) Direct RPV level be restored and maintained

+170-200 inches Evaluate level instruments lAW Caution 1. Page 31 of 34 EVENT 11 cont'd EMERGENCY DEPRESSURIZATION, CONTAINMENT SPRAY SRO (Cont'd) Time Action Notes Directs controlling condensate injection when RPV pressure is less than 440 psig. Directs controlling Low Pressure EGGS injection when RPV pressure is less than 400 psig Directs OW and SP spray when level is being controlled.

RO/BOP Time Action Notes Places 7 ADS valve control switches (Critical Task) Operates LP EGGS to restore and maintain RPV level 170-200 inches. Re-align RHR for LPGI injection.

Ensures Drywell Sprays / SP Sprays / Torus Gooling removed from service Low Pressure EGGS systems may be overridden to prevent uncontrolled injection.

Termination Cue When RPV water level is being maintained above 170 inches with a Loop of RHR spraying the OW and Suppression Pool, by direction of the Lead examiner, the scenario may be terminated.

Page 32 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 Page 33 of 34

1. 2. 3. ATTACHMENT 5 Page 1 of 1 Neutron Monitoring Spiking Troubleshooting Form Initiator's name Unit Two SRO Check all instruments that are spiking and the associated Unit D Unit 1 D SRMA [lJIRM A D IRME III Unit2 D SRMB D IRMB D IRMF D SRMC D IRMC D IRMG D SRMD D IRMD D !RMH Time and date of event Todav* Previous Shift R Reference Use 4. What is the duration of the spiking (duration of individual spike)? Add additional information below to characterize spiking event. D Seconds III Minutes o Hours 5. Ensure all required observations to support operability are appropriately documented.

6. Has a WO or AR been initiated?

If yes, list number(s):

00345765 \lIYes DNo 7. Has a log entry been made?

nNo 8. Is there any welding occurring in the plant? Q'lYes DNo 9. Afe there any personnel under-vessel?

nYes V'I No 10. Are there any plant evolutions in progress?

Q'lYes DNo 11. Is there any electrical switching occurring?

nYes !7lNo 12. Are any control rods being moved or selected?

DNo 13. Has there been a recent change in the mode switch? nYes IJiNo 14. Is there any major equipment being started? bZjYes DNo 15. Has there been any observed relay chatter? DYes 16. Is there any refuel bridge movement?

nYes 17. Are the rod interlocks being affected?

DNo 18. Completed copy of this attachment sent to engineer Y'lYes nNo Please note below any additional information that may aid troubleshooting (such as 2 instruments spiking but not in the same manner): Multiple upscale and downscale alarms during startup over a 15 minute period. All other I RMs responded normally.

120P-09 Rev. 28 Page 38 of 391 Page 34 of 34

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