ML111020333

Initial Exam 2010-302 Final Simulator Scenarios

ML111020333
Person / Time
Site:	Brunswick
Issue date:	04/06/2011
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
50-324/10-302, 50-325/10-302
Download: ML111020333 (171)

Text

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC EXAM SCENARIO #1

Appendix D Scenario Outline Form ES-D-1 Facility: BRUNSWICK Scenario No.: 2010-2 # 1 Op-Test No.: FINAL Examiners: Operators:

(SRO)

(RO)

(BOP)

Initial Conditions: The plant is operating at ~ 55% power during startup following a refueling outage.

Core Spray Pump 2A out of service.

Turnover: Following shift turnover, raise reactor power to 60% and place the second Reactor Feedwater Pump in service.

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

0 N/A N/A Determine LCO for 2A Core Spray Inoperability (TS) 1 N/A R-RO Raise power to 60%

R-SRO 2 N/A N-BOP Place the second Reactor Feedwater Pump in service.

N-SRO 3 ES022F C-RO Inadvertent RCIC initiation .(TS)(AOP)

C-SRO 4 K4510C C-BOP 2A Steam Packing Exhauster trip.

ZUA215 C-SRO 5 P27391I C-RO 2A Reactor Recirculation pump flow controller slowly fails downscale.

C-SRO (TS)(AOP) 6 ES025M M-All RCIC steam line break ES024F C-RO E51-F007 Magnetic Trip C-SRO E51-F008 Thermal overload Manual reactor Scram prior to MSOT/L 7 K5623A C-BOP North RHR room cooler failure K5623B C-SRO South RHR room cooler trip after start 8 Emergency Depressurization required (2 areas above Max Safe Operating Temperature or EQ envelope exceeded) 8a RPV depressurized with level in the normal band.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 33

SCENARIO DESCRIPTION The plant is operating at ~ 55% power during startup following a refueling outage.

Event 0 While the ROs are walking the control boards, prior to assuming the watch, the SRO will determine TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days of inoperability.

Event 1 Raise reactor power to > 60% using reactor recirculation flow.

Event 2 Place the second reactor feed pump in service IAW 2OP-32.

Event 3 RCIC will inadvertently initiate. The crew should respond per 0AOP-03.0, Positive Reactivity Addition and trip RCIC. RCIC should be declared inoperable per TS 3.5.3.

Event 4 SPE 2A will trip causing a loss of gland sealing header pressure. SPE 2B will be placed in service.

Event 5 2A Reactor Recirculation pump flow controller fails downscale requiring entry into 2AOP-4.0, Low Core Flow and locking the scoop tube. TS 3.4.1, Condition A will require meeting the LCO within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Event 6 A line rupture will develop in the RCIC steam supply which cannot be isolated due to E51-F007 tripping on magnetic and the E51-F008 will thermally trip. 0AOP-05 and SCCP will be entered and the Reactor Building temperatures and radiation levels will rise. The crew should insert a manual scram when they recognize there is an unisolable steam leak in Secondary Containment before SRHR reaches Maximum Safe Operating Temperature. After the scram is inserted the crew should enter EOP-01-RSP and EOP-01-RVCP. Reactor building pressure will go positive requiring entry into RRCP.

Event 7 2B RHR room cooler will auto start and will later trip when SRHR Room temperature reaches 190ºF. The 2A RHR room cooler will not operate. As temperatures in multiple areas of the RB rise the crew may Anticipate Emergency Depressurization.

If Emergency Depressurization is anticipated, the RPV will be rapidly depressurized to the main condenser.

Event 8 If emergency depressurization is not anticipated, secondary containment temperatures will exceed maximum safe operating values in two areas, or EQ Envelopes will be reported as being exceeded, which will require emergency depressurization.

Event 8a Once the reactor is depressurized and RPV level is being maintained +170-200", the scenario may be terminated.

Page 3 of 33

OBJECTIVES SRO

1. 341224B102 Determine Actions Required For Limiting Conditions For Operation

2. 344205B402, Direct Shift Response To A Moderator Temperature Decrease Per AOP-03.0

3. 344206B402 Direct Shift Response To A Recirculation Flow Control Failure Causing A Decreasing Flow Per AOP-04.0

4. 344207B502, Direct Actions To Control Secondary Containment Area Temperatures Per EOP-03-SCCP

5. 344208B502, Direct Actions To Control Secondary Containment Area Radiation Levels Per EOP-03-SCCP

6. 344209B502, Direct Actions To Control Secondary Containment Water Level Per EOP-03-SCCP

7. 344233B502, Direct Actions To Anticipate Emergency Depressurization Per EOP-01-RVCP

8. 344217B502, Direct Actions To Control RPV Level Per EOP-01-RVCP

9. 344227B502, 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. 202014B401 Respond To A Recirc Flow Control Failure Decreasing Per AOP-04.0

2. 217204B401, Shutdown The RCIC System with an Automatic Initiation signal present Per OP-16

3. 272201B401 Respond To An Area Radiation Annunciator Per APP UA-03

4. 200065B501 Monitor Reactor Water Level Instrumentation Per EOP Caution 1

5. 200601B401 Respond to radioactive spills, high radiation and airborne activity per AOP-5.0

6. 200603B501 Perform immediate actions for a reactor scram

7. 200219B501 Rapidly Depressurize the Reactor Using the Bypass Valves per EOP-01-RVCP REFERENCES A. OP-26.1 B. OP-32 C. GP-04 D. AOP-03.0 E. AOP-04.0 F. AOP-05.0 G. OI-50 H. EOP-01-RSP I. EOP-01-RVCP J. EOP-02-PCCP K. EOP-03-SCCP L. EOP-04-RRCP M. Conduct Of Operations Manual N. Technical Specifications O. Plant Emergency Procedures P. Annunciator Panel Procedures Page 4 of 33

SIMULATOR SETUP A. Initial Conditions

1. IC 9

2. Rx Pwr 55%

3. Core Age BOC B. Event Triggers Event Trigger Event / Trigger Description 1 N/A Normal Operation (Raise reactor power and place RFP 2 in-service) 2 1 Manually Initiated (ES022F RCIC Inadvertent Start) 3 2 Manually Initiated (2A SPE trip) 4 3 Manually Initiated (RR 2A Flow control fails low) 4 Auto Initiated (Magnetic Trip of E51-F007) 6 5 Manually Initiated (RCIC Steam Leak in SRHR) 7 6 Auto Initiated (RHR Room Temp > 190ºF trips B RHR room cooler) 8 N/A Emergency Depressurization 7 Maximize Hotwell Makeup C. Malfunctions Malfunctions Summary Malf ID Mult Description Current Target Rmptime Actime Dactime Trig ID Value Value ES022F RCIC INADVERTANT START FALSE TRUE 1 ES025F RCIC STM BRK - SOUTH RHR 0 100% 3 min 5 ES024F RCIC STM ISOL VLV MOTOR OVLD TRUE TRUE RC028F RECIRC PUMP A AUTO TRIP FAILURE TRUE TRUE RC029F RECIRC PUMP B AUTO TRIP FAILURE TRUE TRUE Remotes Summary Remf ID Mult Description Current Target Rmptime Actime Trig ID Value Value ED_IABKCF05 BKR CTL DC FUSES CORE SPRAY OUT OUT PUMP 2A CF_IAHWMUC HOTWELL M/U VLV CONTROLLER AUTO MAN 7 CF_IAHWMUM HW MAN CNTR S.P. FOR M/U 0 1.0 7 CF_IAHWRJC HOTWELL REJECT VLV CONTROLLER MAN MAN 7 CF_IAHWRJM HW MAN CNTR S.P. FOR REJECT .1400 0 7 RI-ZVMS507T E51-F007 INBD STM VLV ON OFF 4 Page 5 of 33

SIMULATOR SETUP D. Overrides Switches Tag ID Description Position/ Actual Override Rmptime Actime Dactime Trig Target Value Value P2739A11 RECIRC A FLOW CONTROL .1 .53 .53 5 SEC 3 K4510C STM PACKING EXHAUSTER NORMAL ON OFF 2 CLOSE D1 K4510C STM PACKING EXHAUSTER START OFF OFF 2 CLOSE D1 K4510C STM PACKING EXHAUSTER STOP OFF ON 2 CLOSE D1 K5623A RHR PMP RM VENT FAN B AUTO ON OFF 6 K5623A RHR PMP RM VENT FAN B OFF OFF OFF 6 K5623A RHR PMP RM VENT FAN B ON OFF OFF 6 K5623A RHR PMP RM VENT FAN A AUTO ON OFF K5623A RHR PMP RM VENT FAN A OFF OFF OFF K5623A RHR PMP RM VENT FAN A ON OFF OFF Lamps Tag ID Description Position/ Actual Override Rmptime Actime Dactime Trig Target Value Value Q1617LG1 RCIC STM LINE VLV F007 GREEN ON/OFF OFF OFF 5 Q1617RR1 RCIC STM LINE VLV F007 RED ON/OFF ON OFF 5 K1617A STEAM LINE VLV E51-F007 AUTO ON OFF 5 K1617A STEAM LINE VLV E51-F007 CLOSE OFF OFF 5 K1617A STEAM LINE VLV E51-F007 OPEN OFF OFF 5 Annunciator Summary Activate Deactivate Trig Event Panel Tag Title Value (ramp Time (sec) Time (sec) rate) 3 XU-3 ZUA215 STM PACKING EXHAUSTER ON 0 SEC NA 2 A OVLD TRIP Page 6 of 33

E. Materials

1. ENP-24 for IC-9 (Sequence 2A)

2. 0GP-04 marked up to Step 5.2.22.

3. Mark-up 0GP-04, Attachment 1, for 30, 40 and 50% power.

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. Ensure ENP-24 for IC-9 @ P603.

10. Verify APRM GAFs are < 1.00 (allow time for stabilization)

11. Have the computer on the Heat Balance page 1.

12. Reduce reactor power to ~ 55% with Recirc Flow.

13. Load scenario file, NRC 1.scn, if required.

14. Place 2B Stator Cooling pump in service.

15. Place red cap on Core Spray Pump 2A.

16. Ensure Master Level Controller setpoint at 190 inches.

Page 7 of 33

SHIFT BRIEFING Plant Status The plant is operating at ~55% power during startup following a refuel outage.

0GP-04 is completed up to step 5.2.22.

Alternate Power verifications IAW 0GP-04, are being performed by the Reactor Engineer.

Equipment Out of Service Core Spray Pump 2A is under clearance for breaker repair and is expected to be returned to service in two hours.

Plan of the Day Determine LCO for Core Spray Pump 2A inoperability effective upon assuming the watch.

Raise power to 60% using Reactor Recirc flow and place the second Reactor Feed Pump in service.

Page 8 of 33

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-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. Manually Scram the Reactor before an area reaches Maximum Safe Operating value.

2. Depressurize the RPV by performing or anticipating Emergency Depressurization.

3. Restore and Maintain RPV level above TAF.

Page 9 of 33

EVENT 0 CORE SPRAY PUMP 2A INOPERABILITY While the ROs are walking the control boards, prior to assuming the watch, the SRO will determine TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days of inoperability.

Objectives:

SCO - Determines TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days.

RO / BOP - Perform control board walk downs Success Path:

LCO 3.5.1, Condition A addressed.

Simulator Operator Actions:

If requested to verify back panel relay positions, report complete IAW 2OP-26.

Required Operator Actions Inform crew Core Spray pump 2A is required to be restored to operable within 7 days.

SRO Time Action Notes References TS 3.5.1 Determines 2A CS is required to be restore to Operable Status within 7 days.

Page 10 of 33

EVENT 1 SHIFT TURNOVER, RAISE REACTOR POWER TO 60%

The crew will complete shift turnover and raise reactor power to ~60%.

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 ~60% power.

Simulator Operator Actions:

If contacted as the RE for power increase guidance, inform crew to raise power using Reactor Recirc flow.

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.

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 ~60%

power.

RO Time Action Notes Raises power using recirculation flow to

~60% power.

Raise flow on one RR Pump (~2%)

at a time to stay within mismatch criteria (7.5x106 Mlbs jet pump flow if < than 58 Mlbs or 3.5x106 Mlbs if > than 58 Mlbs).

Continues alternating Recirc pump increases until power is ~60%.

Verifies operation on the Power to Flow map.

Reports alarm clear as RR flow is raised.

A-5 4-8 OPRM TRIP ENABLED BOP Time Action Notes Plant Monitoring Page 11 of 33

EVENT 2 PLACE THE SECOND REACTOR FEED PUMP IN SERVICE BOP - Places the second reactor feed pump in service.

Objectives:

SCO - Directs placing the second RFP in service IAW 2OP-32 Section 5.7.

BOP - Places the second reactor feed pump in service IAW 2OP-32 Section 5.7.

Success Path:

Place the second RFP in service.

Simulator Operator Actions:

If contacted as the RE to monitor core performance, inform crew that you will monitor core performance on the computer.

Acknowledge requests for the Radwaste Operator.

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 Normal Operations - Places Second RFP in service.

SRO Time Action Notes Directs Second RFP be placed in service IAW 2OP-32.

RO Time Action Notes Plant Monitoring Page 12 of 33

EVENT 2 (CONT) PLACE THE SECOND REACTOR FEED PUMP IN SERVICE BOP Time Action Notes Performs 2OP-32, Section 5.7 Determines initial conditions met.

Notify Radwaste Operator to monitor CDD flows and place additional demineralizers in service as necessary.

Ensure RFP B LP SUPPLY VLV, RHS-V1, is open Slowly raise RFPT B speed by placing RFPT B LOWER /RAISE 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-R601B, output to match DFCS STPT and SPEED STPT on Panel P603 to within 100 rpm.

Notify Radwaste Operator to monitor CDD effluent conductivity for each demineralizers in service 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 MAN/DFCS control switch in DFCS.

Slowly raise RFPT B speed by depressing the raise pushbutton on C32-SIC-R601B until RFP discharge pressure is approximately equal to reactor pressure.

Page 13 of 33

EVENT 2 (CONT) PLACE THE SECOND REACTOR FEED PUMP IN SERVICE BOP Time Action Notes Open RFP B DISCH VLV, FW-V4 Slowly raise RFPT B speed, using RFPT B SP CTL, C32-SIC-R601B, until B DEM is approximately equal to A DEM of the on line RFP.

DEPRESS A/M pushbutton on RFPT B SP CTL,C32-SIC-R601B, AND CHECK A/M indicator changes to A (automatic).

When pump suction flow is greater 6

than 3.9 X 10 lbm/hr, and heater drains are forward pumping, then close RFP B RECIRC VLV, FW-FV-V47, by momentarily placing control switch in CLOSE.

When RFP B RECIRC VLV closes, then adjust level setpoint on MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, to 187 inches.

Notifies Radwaste Operator to monitor CDD effluent conductivity for each demineralizers in service Page 14 of 33

EVENT 3 INADVERTENT RCIC INITIATION RCIC will inadvertently initiate. The crew should respond per 0AOP-03.0, Positive Reactivity Addition and trip RCIC. RCIC should be declared inoperable per TS 3.5.3.

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 Tech Specs - 3.5.3 RCIC System Condition A Verify HPCI is OPERABLE and restore RCIC to OPERABLE status within 14 days.

Simulator Operator Actions:

When the directed by the lead examiner, initiate Trigger 1 to inadvertently start RCIC.

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.

If asked as I&C to investigate, acknowledge the request If asked as RE to monitor thermal limits, acknowledge the request.

If asked as chemistry for Rx Coolant Sample, acknowledge the request.

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

Required Operator Actions Instrument/Component Malfunction - RCIC shutdown Technical Specification - TS 3.5.3 - RCIC System SRO Time Action Notes Direct entry into 0AOP-03.0.

Direct / concur RCIC operation to be terminated.

May contact RE to monitor thermal limits due to the cold water injection from RCIC.

Contact I&C to investigate RCIC logic.

Tech Spec 3.5.3 RCIC System Determine Condition A applies Required Action A.1, Immediately verify HPCI is OPERABLE AND Required Action A.2, Restore RCIC to OPERABLE within 14 days.

Page 15 of 33

EVENT 3 (CONT) INADVERTENT RCIC INITIATION RO Time Action Notes Recognize and report RCIC injection Enter and announce 0AOP-03.0 Verify inadvertent initiation by two HPCI & RCIC auto start on LL2 - RPV independent indications and trip RCIC. Water Level Lo Lo (105 inches) - should have automatically Scrammed prior to this level Depress TURBINE TRIP, E51-S17, push button to trip the RCIC turbine Monitors reactor power and thermal limits.

Acknowledge alarms due to RCIC trip A-3 3-4 RCIC PUMP DISCH FLOW LO 4-5 RCIC BAROM CNDSR VAC TANK LVL HI 5-3 RCIC TURBINE TRIPPED A-03 3-5, RCIC TURBINE STM LINE DRN POT LEVEL HI will annunciate requiring the operator to perform the following if it has been in for 5 minutes:

Close TURBINE TRIP & THROTTLE VLV, E51-V8, motor operator.

BOP Time Action Notes Plant Monitor Page 16 of 33

EVENT 4 STEAM PACKING EXHAUSTER TRIP SPE 2A will trip causing a loss of gland sealing header pressure. SPE 2B will be placed in service.

Objectives:

SCO - Direct shift response to SPE trip.

BOP Place SPE 2B in service.

Success Path:

SPE 2B placed in service.

Simulator Operator Actions:

When the directed by the lead examiner, initiate Trigger 2 to trip SPE 2A.

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

If asked as HP to evaluate TB areas, acknowledge the request.

If asked as TBAO to investigate, acknowledge the request.

If directed to open FLOAT TRAP OUTLET VALVE, MVD-V52 or prestart check 2B SPE, acknowledge request, wait 1 minute and report prestart SAT and MVD-V52 is open.

If directed to close FLOAT TRAP OUTLET VALVE, MVD-V51, wait 1 minute and report MVD-V51 is closed.

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

Required Operator Actions Component Malfunction - SPE 2A trip with discharge valve failure to auto close.

SRO Time Action Notes Acknowledge report of 2A SPE trip alarms UA-02 1-5 STM PACKING EXHAUSTER A OVLD TRIP 4-5 GLAND SEAL VACUUM LOSS Contacts maintenance to investigate.

Directs placing 2B SPE in service IAW 2OP-26.1.

Concurs with 2OP-26.1 NOT APPLICABLE (N/A) steps for section to be performed.

Acknowledges alarm reset UA-02 4-5 GLAND SEAL VACUUM LOSS Page 17 of 33

EVENT 4 (CONT) STEAM PACKING EXHAUSTER TRIP RO Time Action Notes Plant Monitor BOP Time Action Notes Acknowledges & reports 2A SPE trip alarms UA-02 1-5 STM PACKING EXHAUSTER A OVLD TRIP 4-5 GLAND SEAL VACUUM LOSS Identifies & reports Exhauster discharge valve failed to auto close and closes STEAM SEAL SPE 2A MO DISCH VLV, OG-MOV-D1, Identifies 2OP-26.1 section required to Either Section 5.1 or 8.1 may be utilized start 2B SPE. with steps N/Ad to support place SPE in service.

Directs TBAO to perform prestart checks and to open FLOAT TRAP OUTLET VALVE, MVD-V52.

Announces and starts SPE 2B.

Throttles open STEAM SEAL SPE 2B MO DISCH VLV, OG-MOV-D2, to restore GLAND EXHAUST HEADER, OG-PI-EPT-9, located on Panel XU-2, to between 10 and 20 inches water vacuum.

Ensures STEAM SEAL SPE 2A MO DISCH VLV, OG-MOV-D1 and STEAM SEAL SPE 2A MO INLET VALVE,OG-MOV-E1 are closed Directs TBAO to close FLOAT TRAP OUTLET VALVE, MVD-V51.

Reports alarm reset UA-02 4-5 GLAND SEAL VACUUM LOSS Page 18 of 33

EVENT 5 RECIRC FLOW CONTROLLER FAILURE 2A Reactor Recirculation pump flow controller fails downscale requiring entry into 2AOP-4.0, Low Core Flow and locking the scoop tube. TS 3.4.1, Condition A will require meeting the LCO within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Objectives:

SCO - Evaluate TS 3.4.1 applicability RO - Lock 2A RR Scoop tube Success Path: TS 3.4.1 evaluated and entered.

Simulator Operator Actions:

When the directed by the lead examiner, initiate Trigger 3 to fail 2A RR speed controller (RO should not be looking at P603 in activated).

If notified as I&C to investigate, acknowledge request.

If notified as RE of Recirc flow control failure, acknowledge request.

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

Required Operator Actions Instrument/Component Malfunction - 2A RR Flow Controller fails low requiring scoop tube to be locked.

Technical Specification - If Jet pump loop flows are not within 10%, Declare loop with lower flow not in service and meet LCO within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SRO Time Action Notes May direct locking 2A RR scoop tube.

Direct entry into AOP-4.0 Contacts I&C to investigate.

Informs RE of RR pump 2A flow control failure.

Acknowledges report of annunciators A-5 4-8 OPRM TRIP ENABLED A-6 2-4 FLUID DRIVE A SCOOP TUBE LOCK Page 19 of 33

EVENT 5 (CONT) RECIRC FLOW CONTROLLER FAILURE SRO Time Action Notes May Evaluate TS 3.4.1 Jet pump loop flows within 10%

SR 3.4.1.1 - Verify recirculation loop jet (maximum indicated difference pump flow mismatch with both 6 7.5 x10 lbs/hr) with total core flow less recirculation loops in operation a. 10% 6 than 58 x10 lbs/hr of rated core flow when operating at

< 75% of rated core flow.

Page 20 of 33

EVENT 5 (CONT) RECIRC FLOW CONTROLLER FAILURE BOP Time Action Notes Plant Monitor May adjust Main Generator Manual Voltage regulator to null the DVM.

RO Time Action Notes Identifies & reports RR 2A flow control failure.

Locks 2A RR scoop tube by placing the SCOOP TUBE A LOCK switch to TRIP.

Reports scoop tube locked and alarms A-5 4-8 OPRM TRIP ENABLED A-6 2-4 FLUID DRIVE A SCOOP TUBE LOCK Announces AOP-4.0 entry.

Report jet pump loop flow mismatch (either within 10% or not)

Determines current location on the Power-to-Flow Map.

Page 21 of 33

EVENT 6/7 RCIC STEAM BREAK / SCRAM / RHR ROOM CLR FAILURES A line rupture will develop in the RCIC steam supply which cannot be isolated due to E51-F007 tripping on magnetic and the E51-F008 will thermally trip. 0AOP-05 and SCCP will be entered and the Reactor Building temperatures and radiation levels will rise. The crew should insert a manual scram when they recognize there is an unisolable steam leak in Secondary Containment before SRHR reaches Maximum Safe Operating Temperature. After the scram is inserted the crew should enter EOP-01-RSP and EOP-01-RVCP. Reactor building pressure will go positive requiring entry into RRCP.

Objectives:

SCO - Directs manual Reactor Scram Enters RSP, RVCP BOP - Performs AOP-05 & SCCP actions.

RO - Diagnose RCIC steam leak Execute AOP and EOP actions as directed by SRO Perform SCRAM actions Control reactor parameters post SCRAM Success Path:

Insert a manual Scram prior to SRHR room temperature reaching Max Safe.

Simulator Operator Actions:

When the crew has stabilized the plant after the RR Pump 2A flow controller failure and directed by lead examiner, initiate Trigger 5 to initiate RCIC steam leak.

If contacted as I&C, Maintenance, or OS AO to investigate, acknowledge the request When Rx Bldg ARM alarms, report as RBAO steam on 20 elevation and you have left the building If requested to close PIV-33, wait 3 minutes and report closed If contacted as Engineering, Chem, HP, Maintenance, I&C, OSAO, acknowledge report / requests.

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

Required Operator Actions Major - Enter 0AOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity and upon recognition of RCIC isolation not available insert reactor scram.

Major - Enter RSP, SCCP, and RVCP, anticipate and / or ED.

SRO Time Action Notes Acknowledge alarm reports of UA-03 2-7 AREA RAD RX BLDG HIGH 3-5 PROCESS RX BLDG VENT RAD HI-HI 4-5 PROCESS RX BLDG VENT RAD HIGH UA-05 3-9 RHR FAN A FAIL TO START UA-12 3-3 RX BLDG DIFF PRESS HIGH/LOW Page 22 of 33

EVENT 6/7 (CONT) RCIC STEAM BREAK / SCRAM / RHR ROOM CLR FAILURES SRO Time Action Notes Directs entry into AOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity May direct evacuation of the reactor building Enter and directs EOP-03-SCCP Direct verification of auto actions RB Vent Exh rises above 4mr/hr - RB HVAC isolations and SBGT auto start.

Diagnose leak from RCIC and direct RCIC isolation Direct manual Scram prior to SRHR **CRITICAL TASK**

reaching max safe temperature. SCRAM prior to SRHR room temperature exceeding 295ºF.

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 Enters and directs EOP-01-RSP 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 Page 23 of 33

EVENT 7/7A (CONT) RCIC STEAM BREAK / SCRAM / RHR ROOM CLR FAILURES SRO Time Action Notes RVCP Actions continued:

Directs pressure control using EHC and pressure band of 800-1000#

May direct starting HPCI to maintain level Contacts I&C to investigate / help isolate RCIC.

Contacts I&C to investigate RHR room cooler failures.

May direct tripping Recirc Pumps for RPV level instrument indication (if level drops below 150)

Enters RRCP upon report of Reactor Building pressure going positive (un-monitored release entry condition)

Requests Unit One calculate site boundary dose per PEP-3.4.7 Directs CREV be place in service.

Directs commencing normal cooldown not to exceed 100° F / hr Directs Anticipating Emergency **CRITICAL TASK **

Depressurization Cautions not to close MSIVs (Gp1)

RO Time Action Notes Monitors the plant Diagnose RCIC leak and attempt to manually isolate, Page 24 of 33

EVENT 7/7A (CONT) RCIC STEAM BREAK / SCRAM / RHR ROOM CLR FAILURES RO Time Action Notes Recognize and report RCIC inboard valve failure - Loss valve position indication, inability to isolate RCIC Recognize and report RCIC outboard valve failure and inability to isolate RCIC A-2 5-5 OTBD NSSS VALVES MTR OVERLOAD Align service water to the vital header (SW-V117 or SW-V111) if not already done Inserts a manual scram as directed by **CRITICAL TASK **

SRO Performs scram immediate actions: Attachment 3 is a copy of the Hardcard.

1. Unit 2 Only: After steam flow is less than 3 x 106 lb/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.

Places the SULCV in service IAW hard Attachment 4 is a copy of the FW Control card Hardcard.

Recognizes and reports no direct RPV level indication available below 150 w/

RR pumps operating.

Recognizes and reports Recirc pumps Annunciators A-2 (Panel P601) failing to trip at LL2 and TRIPs both RR 5-4 ECCS DIV I RPT/ARI TR pumps. 5-8 ECCS DIV II RPT/ARI TR Commences normal cooldown not to exceed 100° F / hr Utilizing BPVs Anticipates ED **CRITICAL TASK **

Opens BPVs with the BPV Opening Jack maintaining Steam Flow below isolation setpoint.

Does not close MSIVs (Gp1)

Page 25 of 33

EVENT 7/7A (CONT) RCIC STEAM BREAK / SCRAM / RHR ROOM CLR FAILURES BOP Time Action Notes Acknowledge and report alarms UA-03 2-7 AREA RAD RX BLDG HIGH 3-5 PROCESS RX BLDG VENT RAD HI-HI 4-5 PROCESS RX BLDG VENT RAD HIGH UA-05 3-9 RHR FAN A FAIL TO START Enters and announce AOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity, 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 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.

Ensures the RHR room coolers are running Recognizes and reports NRHR room cooler fails to start (Auto or Manual)

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, (Blue bar annunciators) reports if pressure goes positive.

UA-05 6-7 RX BLDG STATIC PRESS DIFF -

LOW UA-12 3-3 RX BLDG DIFF PRESS HIGH/LOW Page 26 of 33

EVENT 8/8A REACTOR DEPRESSURIZATION / SCENARIO TERMINATION If emergency depressurization is not anticipated, secondary containment temperatures will exceed maximum safe operating values in two areas, or EQ Envelopes will be reported as being exceeded, which will require emergency depressurization.

Depressurization may be Anticipated or manually performed if / when two areas exceed Max Safe.

Objectives:

SCO - Directs actions to Anticipate Emergency Depressurization or Emergency Depressurize and restore reactor water level.

RO - Performs actions RPV Depressurization and restoration of reactor water level.

BOP - Monitors and reports SCCP & RRCP parameters.

Success Path:

Depressurize the reactor and restore reactor water level to 170-200 inches.

Simulator Operator Actions:

Instructor Activities If crew decides not to anticipate ED, or if SRHR room temperature lowers below Max Safe (around 450#), wait 3 minutes and report as Engineering that the EQ envelope has been exceeded for NRHR. (NOT Required if RPV pressure is rapidly lowering due to anticipating)

When RPV level is being controlled above 170, the scenario may be terminated When directed by the lead evaluator, place the simulator in FREEZE.

Required Operator Actions Restore and maintain RPV level above LL4 SRO Time Action Notes If two areas exceed MSOWL, direct If anticipating ED is performed, reactor emergency depressurization depressurization with BPVs will reduce building temperatures and ED is not required. (May be critical task)

Directs controlling condensate injection when RPV pressure is less than 440 psig.

Directs controlling Low Pressure ECCS injection when RPV pressure is less than 400 psig Page 27 of 33

EVENT 8/8A (CONT) REACTOR DEPRESSURIZATION / SCENARIO TERMINATION SRO Time Action Notes Directs opening 7 ADS valves (ED) Not required if anticipating ED is performed. (May be critical task)

Directs restoring and maintaining **CRITICAL TASK **

RPV level 170-200 inches.

RO / BOP Time Action Notes Places 7 ADS valve control switches Not required if anticipating ED is performed. (May be critical task)

Operates Condensate or LP ECCS to **CRITICAL TASK **

restore and maintain RPV level 170-200 inches.

Termination Cue When RPV water level is being maintained above 170 inches with the reactor depressurized, by direction of the Lead examiner, the scenario may be terminated.

Page 28 of 33

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 33

Attachment 1 Control Rod Manipulations

1) Manipulates control rods only with CRS/SRO permission.

2) Verifies no other reactivity impacting manipulation is occurring.

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

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

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

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

7) Verifies control rod selection using full core display.

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

9) Communicates the following:

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

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

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

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

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

11) Observes plant response to movement commands.

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

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

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

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

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

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

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

18) Updates and signs documentation as steps are complete.

Page 30 of 33

Attachment 2 Recirculation Speed Manipulations

1) Manipulates recirculation speed only with SRO permission.

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

3) Communicates to Concurrent Verifier direction of movement, component to be manipulated, amount of adjustment, and stopping point.

4) Obtains concurrence of Concurrent Verifier before commencing adjustments.

5) Operates recirculation speed controls one at a time, allows time for plant and machine response.

6) Observes redundant plant indications while performing adjustments.

7) Notifies SRO when recirculation speed adjustments are completed.

8) Periodically checks position on Power to Flow map.

Page 31 of 33

Attachment 3 SCRAM HARD CARD Page 32 of 33

Attachment 4 PLACING SULCV IN SERVICE FOLLOWING SCRAM Page 33 of 33

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #2

Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #2 Op-Test No.: FINAL Examiners: _______________________ Operators: __________________________

Initial Conditions: Unit is operating at ~75% power due to Whiteville Line 31 tripping. 1A NSW Pump is under clearance for breaker refurbishment, expected to be returned to service in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. EHC Pump 2B under clearance.

Turnover: Maintain current power.

Event Malf. No. Event Event No. Type* Description K1H14A C-RO RCIC Suction Pressure Switch Failure (Failure of V8 to 1

ZA343 C-SRO close)(TS)

N-BOP 2a ZUA442 Remove RFP from service due to oil leak N-SRO R-RO 2b Lower power to allow RFP to be removed from service R-SRO C-RO 3 ES003F SRV failure (AOP)(TS)

C-SRO C-BOP RBV Rad Monitor Failure (failure of isolations/actuations) 4 RM003F C-SRO (TS)

C-BOP 5 K4522A RBCCW Pump Failure (standby fails to auto start)(AOP)

C-SRO M-All RP009F EHC Pump trip / ATWS / LEP-02 C-BOP 6 K1H03A Failure of ADS Inhibit Switches C-RO K2322A Rod Select Power failure C-SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 33

SCENARIO DESCRIPTION The plant is operating at ~75 power, Middle of Cycle.

Event 1 The RCIC suction pressure switch will fail causing a trip of the RCIC turbine. The RCIC system should be declared inoperable. TS 3.5.3 condition A1, determines HPCI operable immediately and Condition A2 restore RCIC in 14 days.

Event 2 An oil leak will develop on RFP 2A oil system. A low level alarm will be received. The crew should reduce power and shutdown RFP 2A.

Event 3 SRV B will fail full open. Crew will enter 0AOP-30.0. Immediate operator actions are unsuccessful in closing the SRV; pulling fuses per supplementary actions will close SRV.

TS 3.6.2.1 - Condition A1 requires verifying the Torus temperature < 110°F once per hour. Condition A2 requires Torus to be < 95°F in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Ensure each suppression chamber to drywell vacuum breaker is closed (0PT-02.3.1b for SR 3.6.1.6.1), within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after any discharge of steam to the suppression chamber from any source.

Event 4 RBV Rad Monitor A will fail resulting in a Group 6 isolation. Secondary containment isolation and SBGT initiation will fail to automatically occur requiring manual action.

TS 3.3.6.2 Condition A1 place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3). TS 3.3.6.1 Condition A1 place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d). TS 3.4.5 Condition B1 Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition B2 Restore required primary containment atmosphere radioactivity monitoring system to OPERABLE status in 30 days. TRM 3.4 Condition A Restore required channel to OPERABLE status in 31 days.

Event 5 The A RBCCW pump will trip with the standby pump failing to auto start. 0AOP-16.0 should be entered and the standby pump started to recover system pressure.

Event 6 EHC pump will trip resulting in a reactor scram in which all control rods will not go in.

Bypass valves will not be available to control reactor pressure. SRVs and Main Steam Line Drains are available for pressure control. While the actions for LPC are being taken all but 3-5 rods will inserted. The key lock switches for inhibiting ADS will not work (as indicated by the ADS Inhibit lights not lighting up). Control rods will not be available for insertion using RMCS due to a failure of rod select power. Actions to reset the scram and then manually scramming per EOP-01-LEP-02 should be taken.

When all rods have been inserted then the scenario may be terminated.

Page 3 of 33

OBJECTIVES SRO 341224B102, Determine actions required for Limiting Conditions for Operation per OI-01.8 and Technical Specifications 341219B102, Direct Actions To Lower Reactor Power From Rated to 55% Including Removal Of One Feed Pump From Service Per GP-05 & GP-12 RO 202202B101, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 259204B101, Secure The First Reactor Feed Pump Per OP-32 273002B401, Respond To A Process Radiation Monitoring Downscale/Inop Annunciator Per The Appropriate APP Page 4 of 33

SIMULATOR SETUP Initial Conditions IC-10 Event Triggers Event Trigger Trigger Description 1 1 RCIC Suction Pressure Switch Failure (Failure of V8 to close)(TS) 2 2 Annunciator for 2A RFP oil leak 3 Trips 2A RFP when discharge valve FW-V3 is closed 3 4 SRV B failure 5 Pulls fuses for SRV B 4 6 RBV Rad Monitor Failure (failure of isolations/actuations) (TS) 5 12 RBCCW Pump Failure (standby fails to auto start) 6 13 EHC Pump trip / ATWS / Rod Select Power failure 14 LEP-02 Section 3 Jumpers 15 MSIV LL3 Group I Isolation Jumpers 11 MVD-5005 to open Page 5 of 33

Page 6 of 33 SPECIAL INSTRUCTIONS Ensure simulator exam security measures in place.

Start the 2B Stator Cooling Water Pump and Shutdown the 2A Stator Cooling Water Pump and place control switch in Auto.

Place 2B EHC Pump to off and red cap. Place an annunciator placard on the board.

Place the Auto Reclose and Supervisory control switches in Man and Local.

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.

Ensure 0ENP-24.5 for IC-10 @ P603.

Page 7 of 33

SHIFT BRIEFING Plant Status The plant is at ~75% power.

Whiteville Line 31 has tripped, Load Dispatcher has requested power to remain < 75%

power until Line 31 is restored. Crews have been dispatched to investigate.

Equipment Out of Service 1A NSW Pump.

2B EHC Pump.

No other equipment is out of service.

Plan of the Day Maintain current power.

Page 8 of 33

SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, 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 a control rods IAW LEP-02.

• Direct the SRV fuses to be pulled IAW 0AOP-30.0 before reaching 110°F in the suppression pool.

Page 9 of 33

EVENT 1 RCIC SUCTION PRESSURE SWITCH FAILURE A3 4-3, RCIC Pump Suction Low Pressure, 13 seconds later A-02 2-6, RCIC System Press Low and A3 5-3, RCIC Turbine Tripped, annunciators are received. The RCIC suction pressure switch fails low causing the RCIC turbine to trip. The RCIC E51-V8 will not auto close and the operator should make the auto action occur. RCIC will not be available for the rest of the scenario.

Objectives:

SRO Determines Tech Spec implication.

Directs RCIC auto actions completed.

RO Closes RCIC E51-V8.

BOP Monitor plant parameters Success Path:

Tech Specs addressed and RCIC E51-V8 closed.

Simulator Operator Actions:

When the crew has the watch, initiate Trigger 1 to trip the RCIC turbine.

If contacted as I&C to repair the RCIC suction pressure switch acknowledge and do nothing.

If directed to investigate as AO report that you dont see anything wrong.

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

Required Operator Actions Component Failure - Closure of RCIC V8 Tech Specs 3.5.3 A1, Verify by administrative means High Pressure Coolant Injection System is Operable immediately and Tech Specs 3.5.3 A2, Restore RCIC System to Operable status in 14 days.

Page 10 of 33

EVENT 1 (Contd) RCIC SUCTION PRESSURE SWITCH FAILURE SRO Time Action Notes Acknowledge report of RCIC alarms.

A-03 4-3, RCIC Pump Suction Lo Press.

After a 13 second time delay A-03 5-3, RCIC Turbine Tripped.

A-02 2-6, RCIC System Press Low Direct RO to reference APPs Direct the RO to either:

1. Trip RCIC by depressing the Turbine Trip pushbutton.

OR

2. Close the RCIC E51-V8.

Makes TS determination.

TS 3.5.3 - Condition A1, Verify by administrative means High Pressure Coolant Injection System is Operable immediately, AND Condition A2, Restore RCIC System to Operable status in 14 days.

Page 11 of 33

EVENT 1 (Contd) RCIC SUCTION PRESSURE SWITCH FAILURE RO Time Action Notes Announce and reference APPs.

A-03 4-3, RCIC Pump Suction Lo Press.

After a 13 second time delay A-03 5-3, RCIC Turbine Tripped.

A-02 2-6, RCIC System Press Low Determines that RCIC auto actions failed to occur and either:

1. Trips RCIC by depressing the Turbine Trip pushbutton.

OR

2. Closes the RCIC E51-V8.

BOP Time Action Notes Plant Monitoring Page 12 of 33

EVENT 2 REACTOR FEED PUMP OIL LEAK An oil leak will develop on RFP 2A oil system. A low level alarm will be received. The crew should reduce power and shutdown RFP 2A. The RFP will trip when the discharge valve FW-V3 is closed.

Malfunctions required:

RFP A OIL LEVEL HI/LOW Annunciator and RFP 2A Lube Oil Leak Objectives:

SCO - Determines that 2A RFP needs to be shutdown and directs power to support securing 2A RFP.

RO - Lower power to be able to remove 2A RFP.

BOP - Removes the 2A RFP from Service Success Path:

2A RFP removed from service.

Simulator Operator Actions:

When directed by the lead examiner, initiate Trigger 2, to activate RFP A OIL LEVEL HI/LOW Annunciator.

Verify that the 2A RFP trips when the discharge valve, FW-V3, is closed (red light out).

If contacted as AO report oil tank level is low. Report there is an oil leak on RFP A that appears to be unisolable. The RFP should be shutdown.

When contacted as maintenance, report that the RFP must be shutdown in an expeditiously (per the procedure) and the oil pumps must be shutdown.

If contacted as the Load Dispatcher, acknowledge the power reduction.

If contacted as the NE recommend to lower power per 0ENP-24.5 and thermal limits will be monitored via the computer.

If requested to de-energize seal water solenoids for RFP 2A, report circuits are off (2C-TB1, circuits 8 & 24).

If asked and the AC/DC Pumps are shutdown, report as AO the oil leak has stopped After the RFP trips, contact the control room as MM and request that all oil pumps be shutdown and that people are in place to manually bar the RFP Turbine.

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

Required Operator Actions Reactivity Manipulation - to 60-65% power Normal Operation - Shutdown 2A RFP.

Page 13 of 33

EVENT 2 REACTOR FEED PUMP OIL LEAK SRO Time Action Notes Direct power reduction per 0ENP-24.5 and GP-12 to shutdown RFP A (60-65%).

Direct RFP A to be removed from service per 2OP-32.

May direct RFP A oil pumps secured.

RO Time Action Notes Reduce power per 0ENP-24.5 as directed by the SCO.

Lower flow on one RR Pump (~2%) at a time to stay within mismatch criteria 6

(7.5x10 Mlbs jet pump flow if < than 6

58 Mlbs or 3.5x10 Mlbs if > than 58 Mlbs).

Continues alternating Recirc pump decreases until core flow is ~47 Mlbs.

May Insert control rods using 0ENP-24.5 to get to 60-65% power.

Turns control rod power on.

Selects control rods in the sequence prescribed on the 0ENP-24.5 sheets.

26-35, 26-19, 18-27, and/or 34-27.

Continuously drives selected rod in using RMCS.

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 Oclock.

(May have to perform this several times)

Page 14 of 33

EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP Time Action Notes Report UA-4 (4-2) RFP A OIL LEVEL HI/LOW Annunciator Shutdown RFP A per 2OP-32. (the RFP will trip when the discharge valve is closed)

Adjust level setpoint on MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, to 190 inches.

Notify Radwaste Operator to monitor CDD flows and place demineralizers in service as necessary.

Ensure SJAE Condensate Recirculation Valve, CO-FV-49, is closed.

Place RFP A Recirc Vlv, FW-FV-V46, in OPEN Ensure RFPT A Sp Ctl, C32-SIC-R601A, is selected to BIAS and Adjust, using raise and lower push buttons, until BIAS setting is 0.

Ensure RFPT B Sp Ctl, C32-SIC-R601B, is selected to BIAS AND Adjust, using raise and lower push buttons, until BIAS setting is 0.

Depress SEL pushbutton on both RFPT A and B SP Ctl, C32-SIC-R601A and B, until PMP DEM is displayed on each Depress A/M pushbutton on C32-SIC-R601A Slowly Lower RFPT A speed, using lower pushbutton on C32-SIC-R601A, And Observe RFPT B increases speed to maintain reactor level between 182 and 192 inches.

Page 15 of 33

EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP contd Time Action Notes Slowly Lower RFPT A speed using lower pushbutton on C32-SIC-R601A, until RFP discharge pressure is slightly less than reactor pressure.

De-energize seal water solenoid valves.

Close RFP A Disch Vlv, FW-V3. The RFP will trip when valve is closed.

Return level setpoint on MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, to 187 inches Place RFPT A(B) MAN/DFCS control switch to MAN Place RFP A TURNING GEAR MTR mode selector switch in NORM Place RFP A Recirc Vlv, FW-FV-V46, in AUTO.

Shuts down the Oil Pumps.

Page 16 of 33

EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP contd Time Action Notes OPEN the following drain valves

• RFP A HP Stop Vlv & Ln Drain, MS-V41 and MS-V42

• RFP A HP Stop Below Seat Drn, MS-V40

• RFP A LP Stop Vlv & Ln Drain, RHS-V32 and RHS-V39

• RFP A LP Stop Below Seat Drn, RHS-V31

• RFP A LP Ctl Vlv Chest Drn, RHS-V30 and MS-V51

• RFP A LP Stm Supply Ln Drn, RHS-V40 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 Oclock.

(May have to perform this several times)

Page 17 of 33

EVENT 3 SRV B FAILS OPEN The crew responds to an inadvertent stuck open SRV Malfunctions required:

• SRV B fails open Objectives:

SCO

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

• Respond to a stuck open SRV Success Path:

B SRV is closed by pulling fuses per the supplementary actions of AOP-30, Safety/Relief Valve Failure.

Simulator Operator Actions:

WHEN directed by the lead examiner, activate TRIGGER 4. (SRV B fails open)

If contacted as operator to pull fuses, when torus temperature reaches 95°F initiate TRIGGER 5 and immediately DELETE the SRV malfunction.

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

Page 18 of 33

EVENT 3 SRV B FAILS OPEN Required Operator Actions Critical Task - Close the failed open SRV.

Tech Spec 3.6.2.1 Tech Spec 3.6.1.6 Page 19 of 33

EVENT 3 SRV B FAILS OPEN SRO Time Required Actions Notes Direct entry into AOP-30 Safety/Relief Valve Failure.

Direct support personnel to pull applicable fuses per Attachment 1 of 0AOP-30.0, Safety/Relief Valve Failure.

Enter PCCP when torus temp reaches 95°F.

Determine TS 3.6.2.1 Condition A1 requires verifying the Torus temperature < 110°F once per hour.

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

Ensure each suppression chamber to drywell vacuum breaker is closed (0PT-02.3.1b for SR 3.6.1.6.1),

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after any discharge of steam to the suppression chamber from any source When Torus is greater than 95° F direct BOP to place torus cooling in service per PCCP (Hard Card).

Page 20 of 33

EVENT 3 SRV B FAILS OPEN BOP Time Required Actions Notes Plant Monitoring RO Time Required Actions Notes Respond to alarms.

A-03, 1-10, Safety/Relief Valve Open A-03, 1-1, Safety or Depress Valve Leaking Cycle B SRV control switch several times (leaves switch in CLOSE)

Request fuses for the SRV be pulled Critical Task per Attachment 1 of 0AOP-30.0, Safety/Relief Valve Failure.

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

Page 21 of 33

EVENT 3 SRV B FAILS OPEN RO contd Time Required Actions Notes When Torus is greater than 95°F, Places SPC in service on A Loop.

(Actions in parenthesis for B Loop)

Opens SW-V101 (V105).

Closes SW-V143.

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

Pump.

Performs a PA announcement and Starts RHR SW Pump(s)

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

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

Performs a PA announcement and Starts RHR pump(s)

Open E11-F028A(B).

Throttles open E11-F024A(B)

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

Closes E11-F048A(B).

Page 22 of 33

EVENT 4 REACTOR BUILDING VENT RAD MONITOR FAILS RBV Rad Monitor A will fail upscale then downscale resulting in a Group 6 isolation, Secondary containment isolation and SBGT initiation. The RB HVAC Dampers and SBGT will fail to automatically occur requiring manual action Malfunctions required:

• RBV Rad monitor upscale then downscale.

Objectives:

SCO

• Direct actions to start SBGT and isolate RBV.

• Determine Tech Specs.

BOP/RO

• Isolate RBV and Start SBGT.

Success Path:

RBV is isolated and SBGT started.

Simulator Operator Actions:

WHEN directed by the lead examiner, activate TRIGGER 6 to fail the RBV Rad Monitor.

If asked as I&C to investigate, acknowledge the request When directed by the lead examiner, proceed to the next event.

Required Operator Actions Component Failure - Closure of RBV Dampers and Start SBGT TS 3.3.6.2 Condition A1 place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3).

TS 3.3.6.1 Condition A1 place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d).

TS 3.6.4.2 Condition A1 Isolate the affected penetration flow path in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

TS 3.6.4.2 Condition A2 Verify the affected penetration flow path is isolated once per 92 days.

TS 3.6.4.3 Condition A Restore SGT subsystem to OPERABLE status in 7 days TS 3.6.4.3 Condition B1 Be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and B2 Be in Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

TS 3.4.5 Condition B1 Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition TS 3.4.5 Condition B2 Restore required primary containment atmosphere radioactivity monitoring system to OPERABLE status in 30 days.

TRM 3.4 Condition A Restore required channel to OPERABLE status in 31 days.

Page 23 of 33

EVENT 4 (contd) REACTOR BUILDING VENT RAD MONITOR FAILS SRO Time Required Actions Notes Acknowledge report of alarms for RBV Rad Monitor failure.

UA-3, 3 Process Rx Bldg Vent Rad Hi-Hi UA-3, 3 Process Rx Bldg Vent Dnsc/Inop UA-3, 4 Process Rx Bldg Vent Rad Hi UA-25,1-8 -Ctmt Atmos Rad Mon Dnsc/Inop Direct verification of auto actions for rad monitor failure. Group 6 Isolation, Secondary Containment Isolation and SBGT start.

Direct failed auto action to be manually performed.

Direct I&C to investigate failure of vent rad monitor.

Determine Tech Specs:

TS 3.3.6.2 Condition A1, place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3).

TS 3.3.6.1 Condition A1, place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d).

TS 3.4.5 Condition B1, Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition TS 3.4.5 Condition B2, Restore required primary containment atmosphere radioactivity monitoring system to operable status in 30 days.

TRM 3.4 Condition A, Restore required channel to operable status in 31 days.

Condition B, Restore one required channel to operable status in 7 days.

TS 3.6.4.2 Condition A1, Isolate the affected penetration flow path in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Condition A2, Verify the affected penetration flow path is isolated once per 92 days.

TS 3.6.4.3 Condition A, Restore SGT subsystem to operable status in 7 days Condition B1 Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Condition B2 Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

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EVENT 4 (contd) REACTOR BUILDING VENT RAD MONITOR FAILS RO Time Required Actions Notes Plant Monitoring BOP Time Required Actions Notes Report annunciators for RBV Rad Monitor failure and review to APPs.

UA-3, 3 Process Rx Bldg Vent Rad Hi-Hi UA-3, 3 Process Rx Bldg Vent Dnsc/Inop UA-3, 4 Process Rx Bldg Vent Rad Hi UA-25,1-8 -Ctmt Atmos Rad Mon Dnsc/Inop Recognize and report failure of auto actions for rad monitor failure. Group 6 Isolation, Secondary Containment Isolation and SBGT start.

ENSURE reactor building exhaust and supply fans are off.

Close the following valves:

RB VENT INBD ISOL VALVES, EXHAUST C-BFIV-RB, SUPPLY A-BFIV-RB RB VENT OTBD ISOL VALVES, EXHAUST D-BFIV-RB, SUPPLY B-BFIV-RB Start SBGT System by placing the control switches in Start.

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EVENT 5 RBCCW PUMP TRIP The crew will respond to a trip of the 2A RBCCW pump and pressure will lower. C RBCCW Pump will fail to auto start and the low pressure alarm will be received. Starting the 2C RBCCW pump will restore pressure to normal.

Objectives:

SCO - Directs BOP to enter and execute 0AOP-16.0: RBCCW System Failure BOP - Refers to 2-UA-3 2-5 and 0AOP-16.0 to respond to the 2C Pump failure to start Success Path:

Starting the 2C RBCCW pump will restore pressure to normal.

Simulator Operator Actions:

At the discretion of the lead evaluator, initiate Trigger 12 to trip the 2A RBCCW Pump.

If directed as the RB AO to investigate RBCCW low pressure, report RBCCW Pump 2A Motor is hot to the touch, breaker is tripped.

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

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

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

Required Operator Actions Component failure - starting 2C RBCCW 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 0AOP-16.0.

Directs start of 2C RBCCW pump if BOP fails to recognize auto start failure.

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

Notifies Maintenance of 2A RBCCW Pump trip.

May direct the 2A RBCCW pump to be placed in OFF.

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EVENT 5 (Contd) RBCCW PUMP TRIP RO Time Action Notes Plant Monitoring BOP Time Action Notes Recognize the failure of the C RBCCW 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 0AOP-16.0 Dispatches AO to investigate cause of 2A Pump trip.

Places 2A RBCCW Pump switch to OFF.

Verifies RBCCW System is operating normally.

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EVENT 6 EHC LOSS / ATWS EHC pump will trip resulting in a reactor scram in which all control rods will not go in.

Bypass valves will not be available to control reactor pressure. SRVs and Main Steam Line Drains are available for pressure control.

While the actions for LPC are being taken all but 3-5 rods will inserted. The key lock switches for inhibiting ADS will not work (as indicated by the ADS Inhibit lights not lighting up). Control rods will not be available for insertion using RMCS due to a failure of rod select power. Actions to reset the scram and then manually scramming per EOP-01-LEP-02 should be taken.

When all rods have been inserted and pressure is being controlled then the scenario may be terminated.

Objectives:

SCO - Perform LPC directing LEP-02.

BOP - Control RPV pressure using Main Steam Line drains.

RO - Insert control rods IAW LEP-02.

Success Path:

Inserting control rods.

Simulator Operator Actions:

At the discretion of the lead evaluator, initiate Trigger 13 to trip the 2A EHC Pump.

When the SRO enters LPC delete ATWS 2.

If directed as the TB AO to investigate EHC pump, report Pump Motor is hot to the touch, breaker is tripped, will not reset.

When contacted to perform LEP-02 Section 3 jumpers, Wait 5 minutes and Initiate Trigger 14, then report action completed.

If contacted to place jumpers for MSIVs LL3 Group I Isolation, Wait 1 minute and Initiate Trigger 15, then report action completed.

If contacted as the TBAO to open the MVD-5005, Main Stm Drn Hdr Isolation valve, wait 5 minutes and initiate Trigger 11.

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

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

Required Operator Actions Component failure - Rod select power and ADS logic.

Critical Task - Insert Control Rods IAW LEP-02.

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EVENT 6 contd EHC LOSS / ATWS SRO Time Action Notes 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.

Direct ADS inhibited.

Direct LEP-02, Alternate Rod Insertion.

(Critical task)

Direct Group 10 switches to override reset.

Direct Group 1 LL3 jumpers to prevent closure of MSIVs on low level.

Exit LPC and enter RVCP when all rods are in.

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EVENT 6 (Contd) EHC LOSS / ATWS RO Time Action Notes Recognize and report an ATWS.

Place mode switch to shutdown when steam flow < 3x106 lb/hr.

Verifies Initiation of ARI.

Places Recirc Pump speeds reduced to 10%.

Verifies Recirc Pumps are tripped.

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

Insert IRMs.

When < range 3 on IRMs insert SRMs.

Start both CRD pumps.

Place CRD Flow Controller to Manual.

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

Bypass RWM.

Determines Rod Select Power Failure and informs SRO.

Performs alternate rod insertion per (Critical task)

LEP-02 Section 3.

Request jumpers for LEP-02 Section 3.

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EVENT 6 (Contd) EHC LOSS / ATWS RO contd Time Action Notes Monitor APRMs for downscale.

Performs LEP-02 Section 3 after (Critical task) jumpers are installed.

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

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

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

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

Resets RPS.

Place Disch Vol Vent & Drain Test switch to Normal Inserts a scram after discharge volume (Critical task) has drained for ~2 minutes.

Reports all rods in.

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EVENT 6 (Contd) EHC LOSS / ATWS BOP Time Action Notes Places ADS in inhibit.

Identifies ADS failure.

Reports to SRO.

Places Group 10 switches to override /

reset Controls Reactor pressure using Main Steam Line Drains IAW Hardcard.

Open Main Steam Line Drain Otbd (Inbd) Isol Vlvs, B21-F019 and B21-F016 Throttle Main Steam Line Drain Vlv, MVD-F021 as desired to maintain pressure band.

May open Main Steam Line Drain Vlv, MS-F020 with a combination of Main Steam Line Drain Vlv(S), MS-F038A, F038B, F038C, F038D.

May direct TBAO to open Mn Stm Drn Hdr Isolation, MVD-5005 Page 32 of 33

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 33

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #3

Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario #: 2010-2 #3 OP-Test No.: FINAL Examiners: Operators:

Initial Conditions: The plant is operating at ~75% power following a refueling outage.

1A NSW pump is under clearance for motor replacement.

2C TCC pump is in service on Unit One.

Turnover: Following shift turnover, shift CRD pumps and continue power ascension to rated.

Event Malf. No. Event Event No. Type* Description 1 N/A N-SRO Shift CRD pumps N-BOP 2 NB007F C32-LT-N004A fails Low (TS) 3 K4516A C-BOP 2A TCC pump trip (AOP)

C-SRO 3a N/A R-RO AOP-17 power reduction R-SRO 4 CW021F C-BOP 2B NSW pump shaft shear (TS) (AOP)

C-SRO 5 RD001M R-RO Control Rod 14-35 slow drift in. (AOP)

R-SRO 6 RD041F M-ALL Loss of Scram air header, multiple rod drifts, Scram ATWS 3 ATWS condition requiring entry to LPC.

7 K2119A C-RO SLC pumps will not start due to switch failure.

C-SRO RWCU Fails to Isolate.

8 N/A N/A ATWS Actions - Terminate and Prevent 9 N/A N/A All Rods In with RPV water level restored.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 33

SCENARIO DESCRIPTION Unit 2 is operating at ~75% power during startup following a refuel outage.

Event 1 Shift CRD pumps per 2OP-08.

Event 2 Following CRD pump shift, C32-LT-N004A will fail low. The crew will reference Tech Spec 3.3.2.2 and determine a 7 day LCO exists to place the failed channel in the tripped condition. The crew should select level B per OP-32.

Event 3 TCC Pump 2A will trip and TBCCW low header pressure will alarm. The crew will respond per 0AOP-17.0, Turbine Building Closed Cooling Water System Failure and place 2B TBCCW pump in service.

Event 3a With only the 2B TCC pump in service, header pressure will remain below 42 psig requiring reactor power to be reduced with Recirc flow to the ENP-24.5 flow limit.

System pressure will recover as component TCVs throttle closed.

Event 4 The 2B NSW pump shaft will shear causing a low header pressure. 2A NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the 2A NSW pump. 0AOP-18.0 will be entered and T.S. 3.7.2 will require restoring a required NSW pump to Operable status within 7 days.

Event 5 HCU 14-35 will develop an air leak causing the control rod to slowly drift inwards. The crew will enter AOP-2.0 Control Rod Malfunction/Misposition. AOP-2.0 will direct response per 2APP-A-05 (3-2) ROD DRIFT. The RO should attempt to arrest the drifting control rod.

Event 6 The scram air header leak degrades causing additional control rods to drift inward.

With scram air header low and multiple control rods drifting, a manual Scram will be inserted. Most of the control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-LPC.

Event 7 When SLC initiation is attempted, neither SLC pump will start due to switch failure.

RWCU will not automatically isolate requiring manual isolation of G31-F004. The crew will perform LEP-03 and align for alternate boron injection using CRD.

Event 8 The crew will terminate and prevent injection, re-injection will start when level is at 90 inches due to Table 3 conditions not met. Feedwater and HPCI will be available for level control.

Event 9 When level has been lowered and level band has been established, the scram air header leak will be isolated. 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.

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OBJECTIVES SRO 344203B402, Direct Shift Personnel To Respond To a Control Rod Malfunction/Misposition Per AOP-02.0 344220B402, Direct Shift Response To TBCCW Failures Per AOP-17.0 344221B402, Direct Actions For Nuclear Service Water System Failure Per AOP-18.0 341224B102, Determine actions required for Limiting Conditions for Operation per OI-01.8 and Technical Specifications 344201B502, Direct Actions To Control Reactor Power Per EOP-01-LPC 344214B502, Direct Actions To Control Primary Containment Pressure Per EOP PCCP 344215B502, Direct Actions To Control Primary Containment Temperature Per EOP-02-PCCP 344216B502, Direct Actions To Control Suppression Pool Temperature Per EOP PCCP RO 201044B401, Respond To Control Rod Malfunction/Misposition Per AOP-02.0 274601B401, Respond to a Partial Loss of TBCCW per AOP-17.0 276602B401, Respond to a Partial loss of the Nuclear Service Water System per AOP-18.0.

202202B101, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 200223B501, Control Reactor Level During An ATWS Per EOP-01-LPC 201041B501, Insert Control Rods With Reactor Manual Control System Per EOP LEP-02 203004B501, Terminate And Prevent LPCI Injection 206001B501, Terminate And Prevent HPCI Injection per EOP-01-UG 211005B501, Manually Initiate Standby Liquid Control Per OP-05 218003B501, Inhibit ADS Actuation Per EOP-01 256007B501, Terminate And Prevent Condensate System Injection To Reactor Vessel per EOP-01-LPC 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 33

Simulator Setup Initial Conditions IC 10 (Unit 2)

RWM Sequence A2 Rx Pwr 75%

Core Age BOC Triggers Trigger Description 1 Manual C32-LT-N004B Fails Low 2 Manual 2A TCC pump trip 3 Manual 2B NSW pump shaft shear 4 Manual 1D Air Compressor in service 5 Manual Control Rod 14-35, 22-31, 10-31 slow drift in Scram air header leak 7 Manual LEP-02 Section 3 Jumpers 8 Manual Bypass Group 1 LL3 Isolation per SEP-10 9 Manual MVD-5005 10 Manual DW Clr LOCA Logic bypass 11 Manual LEP-03 aligned to CRD Interventions Summary Note: Shaded entries = Active Malfunctions Summary Mult Current Target Ramp Act. Deact Malf. ID Description Trig ID Value Value Time Time Time RP010F ATWS 3 True True RX LVL TRANSMITTER C32-NOO4A NB007F 61 0 1 FAILS CW021F B NSW PUMP SHAFT SHEAR FALSE TRUE 3 RDOO1M 14-35 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 5 RDOO1M 22-31 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 1 Min 5 RDOO1M 10-31 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 1.5 Min 5 RDO41F LOSS OF CONTROL AIR 0 40 2 Min 2 Min 5 RP005F Auto Scram Defeat False True 7 Page 5 of 33

Remotes Summary Mult. Current Target Remote ID Description Trig ID Value Value CC_IACW4518 2C TBCCW PUMP UNIT ALIGNMENT 1 1 EP_IAEOPJP1 Bypass LL3 Group I Isol Off On 8 MS_VMS5005D MVD-5005 Mn Stm Drn Hdr Isolation 0 1 9 EP_IACS993U DW CLR A&D Overide - Normal/Run Normal Run 10 EP_IACS994U DW CLR B&C Overide - Normal/Run Normal Run 10 EP_IASW5997 SW-V106 LOCA Override Normal Bypass 10 EP_IASW5998 SW-V103 LOCA Override Normal Bypass 10 SL_IALEP03 Alt = Sub Pump / Hose Lineup Normal Alt 11 SL_IASLCCRD SLC DISCH (Norm=CRD/ALT=RCIC/HPCI) Normal Normal 11 SL_IASLCSP Submersible Pump Power Off On 11 1D ON AI_IAIU1CMRSS UNIT 1 AIR COMPRESSER STAT 4 1B STBY Switches Summary Target / Actual Override Switch ID Description Trig Position Value Value K4516A TBCCW Pump A On On Off 2 Q4516LG4 TBCCW Pump A Green On/Off On/Off Off 2 K2119A S/B Liq Pump A-B Stop ON ON K2119A S/B Liq Pump A-B Pump_ A OFF OFF K2119A S/B Liq Pump A-B Pump _A&B OFF OFF K2119A S/B Liq Pump A-B Pump_ B OFF OFF K4B20A NUC HDR SW PUMP A DISCH VLV AUTO ON OFF SPECIAL INSTRUCTIONS

1. Ensure simulator exam security measures in place.

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 any log books have blank sheets only and procedures are not marked.

9. Load scenario file if available.

10. Load malfunctions/overrides if scenario file is unavailable.

11. Ensure 2C TCC pump in service on Unit 1.

12. Place in Run and verify power at ~75%.

13. Ensure 2B Stator Cooling pump is in service.

14. Ensure 0ENP-24.5 for IC-10 @ P603.

15. Provide marked up 0GP-04 to step 5.2.31 and Attachment 1 marked for 70% being complete..

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Shift Briefing Plant Status The plant is operating at ~75% power during startup following a refuel outage.

2C TCC pump is in service on Unit One.

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Plan of the Day Following shift turnover, shift CRD pumps and continue power ascension to rated IAW 0GP-04 to step 5.2.31 using Reactor Recirculation Flow.

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SCENARIO INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Revision 8, 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-303.

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.)

(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.

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EVENT 1 SHIFT CRD PUMPS The crew will complete shift turnover and shift CRD pumps IAW 2OP-08.

Objectives:

SCO - Directs shifting CRD pumps to place 2B CRD pump in service.

BOP - Shifts CRD pumps.

RO - Monitors the plant.

Success Path:

CRD pump 2B placed in service with the flow controller in Auto.

Simulator Operator Actions:

If contacted as RBAO for CRD pump shift, report prestart checks complete SAT.

When directed as RBAO to ensure valve positions for the 2B CRD pump, report Section 8.2, Steps 1,2 & 3 are complete (Suction, Discharge, & Recirc Isolation valves are all locked open.

When directed as RBAO to ensure valve position for the 2A CRD pump, report Section 8.2, Step 10 is complete ( Discharge Isolation valve is locked open) and will get valves independently verified IAW Attachment 33.

If contacted as the RE for power increase guidance, inform crew to raise power using Reactor Recirc flow.

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.

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

Required Operator Actions Normal Operation - Shift CRD pumps.

SRO Time Action Notes Directs 2B CRD pump be placed in service IAW 2OP-08.

Acknowledges report of annunciators A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER P HIGH Acknowledges clearing of annunciators A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER P HIGH RO Time Action Notes Plant Monitoring Page 9 of 33

EVENT 1 (CONT) SHIFT CRD PUMPS BOP Time Action Notes Shifts CRD pumps IAW 2OP-08, Section 8.2.

Directs RBAO to ensure

• CRD PUMP 2B SUCTION ISOLATION VALVE, C12-F013B, is locked open.

• CRD PUMP 2B DISCHARGE ISOLATION VALVE, C12-F014B, is locked open.

• CRD PUMP 2B RECIRCULATION LINE ISOLATION VALVE, C12-F014B, is locked open.

Shifts CRD FLOW CONTROL, C12-FC-R600, to BAL.

Nulls CRD FLOW CONTROL, C12-FC-R600, by adjusting the manual potentiometer.

Shifts CRD FLOW CONTROL, C12-FC-R600, to MAN.

Sets CRD flow rate to 35 gpm.

Announces and starts CRD Pump 2B Announces and stops CRD Pump 2A Directs RBAO to ensure CRD PUMP 2B DISCHARGE ISOLATION VALVE, C12-F014A, is locked open.

Nulls CRD FLOW CONTROL, C12-FC-R600, by adjusting the setpoint tape.

Shifts CRD FLOW CONTROL, C12-FC-R600, to AUTO.

Directs RBAO to complete Attachment 33.

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EVENT 1 (CONT) SHIFT CRD PUMPS BOP Time Action Notes Should verify CRD operating parameters CRD flow was initially 45 gpm, returning IAW Section 8.29 flow to this value should restore the ADJUST cooling water differential remaining parameters to ~ pre-shift pressure, CRD flow rate and drive values.

pressure as follows:

CRD FLOW CONTROL, C12-FC-R600, to maintain cooling water differential pressure between 10 and 26 psid.

CRD flow rate between 30 and 60 gpm.

DRIVE PRESS, C12-PDI-R602, between 260 and 275 psid by throttling DRIVE PRESSURE VLV, C12-PCV-F003.

Acknowledges and reports annunciators of A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER P HIGH Acknowledges and reports clearing of annunciators of A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER P HIGH Page 11 of 33

EVENT 2 C32-LT-N004A FAILS LOW (TS)

Following CRD pump shift, C32-LT-N004A will fail low. The crew will reference Tech Spec 3.3.2.2 and determine a 7 day LCO exists to place the failed channel in the tripped condition.

The crew should select level B per OP-32.

Objectives:

SCO - Determine TS LCO for C32-LT-N004A failing low.

RO -. Transfer DFCS to control to B.

Success Path:

TS LCO 3.3.2.2, Condition A One feedwater and main turbine high water level trip channel inoperable. Required Action A.1 Place channel in trip within 7 days.

DFCS Feedwater Level Select transferred to B.

Simulator Operator Actions:

Following CRD pump shift and at the lead evaluator direction, INITIATE TRIGGER 1 to fail C32-LT-N004A downscale.

If contacted as I&C, acknowledge the request.

If contacted as TB AO to check UPS Panel V10, Ckt #3, acknowledge request, wait 2 minutes and report no tripped breakers.

When directed by the lead examiner, proceed to the next event Required Operator Actions Instrument Failure - C32-LT-N004A failing low requires level selected to Level B.

Technical Specification - LCO 3.3.2.2 entered.

SRO Time Action Notes Acknowledges annunciator report of A-7 4-2 FW CTL SYS TROUBLE Contacts I&C to investigate.

May direct FWCS Level control be selected to Level B.

References TS 3.3.2.2 AND TRM TS Instrument List, Appendix B TRM Table 3.3.2.2-1, Functions 1 & 2.

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EVENT 2 (CONT) C32-LT-N004A FAILS LOW (TS)

Page 13 of 33

EVENT 2 (CONT) C32-LT-N004A FAILS LOW (TS)

RO Time Action Notes Acknowledges and reports annunciator report of A-7 4-2 FW CTL SYS TROUBLE Diagnose failure of the C32-N004A May shift LEVEL A/B select switch to Position B per SRO direction.

BOP Time Action Notes Plant Monitoring Page 14 of 33

EVENT 3/3a 2A TCC PUMP TRIP/ AOP-17 POWER REDUCTION TCC Pump 2A will trip and TBCCW low header pressure will alarm. The crew will respond per 0AOP-17.0, Turbine Building Closed Cooling Water System Failure and place 2B TBCCW pump in service Objectives:

SCO - Direct entry into 0AOP-17.0.

RO - Power reduction with Recirc flow.

BOP - Restoration of TCC pressure.

Success Path:

2B TBCCW pump started and TCC pressures restored to normal with reactor power reduced to ~60%.

Simulator Operator Actions:

Following TS call for LCO 3.3.2.2 and at the lead evaluator direction, initiate TRIGGER 2 to trip the 2A TCC pump.

If contacted as the TB AO, wait one minute and report that 2A TCC pump is hot to the touch and the breaker is tripped (magnetic).

If contacted as Unit One CRS, report Unit One is using the 2C TCC Pump.

If contacted as I&C to investigate 2A TCC Pump, acknowledge request.

If contacted as RE for power reduction or Reactivity Plan, acknowledge request.

If contacted as Unit One for air compressor status, initiate TRIGGER 4.

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

Required Operator Actions Component Failure - 2A TCC pump trip.

Reactivity Manipulation - Reduce Reactor Recirc flow to 47 Mlbm/hr.

SRO Time Action Notes Acknowledge report of annunciator UA-03 2-4 TBCCW PUMP DISCH HEADER PRESS LOW Direct entry into 0AOP-17.0, Turbine Building Closed Cooling Water System Failure.

Direct start of 2B TCC Pump.

Direct power reduction IAW ENP-24.5 to 47 Mlbm/hr the Recirc flow limit.

Directs I&C to investigate loss of 2A TCC pump.

Acknowledge report of annunciator UA-03 4-8 OPRM TRIP ENABLED Briefs crew on reactor scram if TCC pressure is not restored above 42 psig within 4 minutes of reaching 47Mlbm/hr.

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EVENT 3/3a (CONT) 2A TCC PUMP TRIP/ AOP-17 POWER REDUCTION RO Time Action Notes Plant Monitoring.

Reduces reactor power with Recirc Flow See Attachment 1 for power reduction to ENP-24.5 flow limit of 47 Mlbm/hr. with Recirc flow actions.

Acknowledge and report annunciator UA-03 4-8 OPRM TRIP ENABLED BOP Time Action Notes Acknowledge and Report annunciator Depending on the amount of time that no TCC UA-03 pump is operating, one pump will not 2-4 TBCCW PUMP DISCH HEADER immediately restore TCC pressure due to the PRESS LOW system load TCC temperature control valves being wide open.

Diagnose loss of 2A TCC Pump.

Enters 0AOP-17.0 and Starts 2B TCC pump by placing control switch to ON.

Dispatch AO to investigate 2A TCC Pump and look for system leaks.

May dispatch AO to perform prestart checks for 2B Pump.

May place 2A TCC pump control switch to OFF.

May request use of 2C TCC pump from Unit One.

May request Unit One place 1D air compressor in service.

Trips the 2D air compressor if running and Unit One air compressor is in service.

Report annunciator UA-03 2-4 TBCCW PUMP DISCH HEADER PRESS LOW clear.

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EVENT 4 2B NSW PUMP SHAFT SHEAR (TS)

The 2B NSW pump shaft will shear causing a low header pressure. 2A NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the 2A NSW pump. 0AOP-18.0, Nuclear Service Water System Failure, will be entered and T.S. 3.7.2 will require restoring a required NSW pump to Operable status within 7 days.

Objectives:

SCO - Direct AOP-18 actions and Evaluate Tech Specs 3.7.2 Service Water System and Ultimate Heat Sink RO/BOP - Respond to the failure of an automatic start of the 2A NSW pump.

Success Path:

2A NSW pump placed in service and TS LCO 3.7.2, 7 day LCO entry.

Simulator Operator Actions:

When TCC parameters have stabilized and at the discretion of the lead evaluator, insert Trigger 3 to If asked as the OSAO to investigate, acknowledge request.

If asked as the OCSRO to initiate an impairment, acknowledge request.

If asked as I&C to investigate acknowledge the request, wait 3 minutes and report 2A NSW pump auto start failure due to pressure switch ONLY - LOCA logic is operable.

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

Required Operator Actions SRO Time Action Notes Acknowledges report of annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Directs AOP-18, Nuclear Service Water System Failure, entry and may direct placing 2A NSW pump in service or a CSW pump in service on the NSW header.

Acknowledges report of annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Clear.

Contacts I&C / Maint to investigate 2B NSW loss and 2A NSW pump failure to auto start.

Evaluates TS 3.7.2 and determines See Attachment 2 for TS 3.7.2 Condition B requires restoration of 1A or Auto start on header low pressure is not 2B NSW operability within 7 days. required for pump operability.

May direct OCSRO to initiate an impairment IAW PLP-1.2.

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EVENT 4 (CONT) 2B NSW PUMP SHAFT SHEAR (TS)

RO Time Action Notes Plant Monitoring.

May make PA announcement for AOP-18 entry BOP Time Action Notes Acknowledges and reports annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Identifies 2A NSW pump failure to auto start.

Places 2A NSW pump control switch in MANUAL and STARTS 2A NSW pump.

Enters and announces entry into AOP-18.

May acknowledge and report annunciators If standby pump is not started fairly quick, UA-05 vital header pressure will lower causing 1-9 FAN CLG UNIT CS PUMP RM A INL these alarms to come in. Alarms will PRESS LO clear once a SW pump is started on the 2-9 FAN CLG UNIT CS PUMP RM B INL NSW header.

PRESS LO Directs OSAO to investigate 2B NSW pump failure and to look for leaks.

Shuts down 2B NSW pump upon report of shaft shear.

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EVENT 5 SCRAM AIR LEAK / CR DRIFT HCU 14-35 will develop an air leak causing the control rod to slowly drift inwards. The crew will enter AOP-2.0 Control Rod Malfunction/Misposition. AOP-2.0 will direct response per 2APP-A-05 (3-2) ROD DRIFT. The RO should attempt to arrest the drifting control rod. The air leak start impacting surrounding HCUs causing additional control rods to drift inward (1 minute later rod 22-31,1.5 minutes later rod 10-31, and 2 minutes later additional rods begin drifting).

Objectives:

SRO - Direct actions for AOP-02 and Scram RO - Perform rod drift actions, insert Manual Scram.

Success Path:

Manual Scram inserted due to multiple control rods drifting.

Simulator Operator Actions:

At the discretion of the lead evaluator, insert Trigger 5 to cause scram air header leak.

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

If contacted as the RE to address thermal limits, inform crew that you will monitor core performance on the computer.

If asked as RBAO to investigate acknowledge the request.

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

Required Operator Actions Component Failure - control rod drift actions SRO Time Action Notes Acknowledges report of annunciators UA-05 3-2 ROD DRIFT 5-2 ROD BLOCK RWM/RMCS SYS TROUBLE Direct actions of APPs.

May contact I&C to investigate control rod drift.

May contact RE for control rod drift.

Acknowledges report of additional control rods drifting.

Direct manual Scram for multiple control rods drifting.

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EVENT 5 (CONT) SCRAM AIR LEAK / CR DRIFT BOP Time Action Notes Plant Monitoring.

May recognize additional control rods drifting RO Time Action Notes Acknowledge and report annunciators UA-05 3-2 ROD DRIFT 5-2 ROD BLOCK RWM/RMCS SYS TROUBLE Announce and enter AOP-2.0 Perform the actions of APP-A-05 (3-2) ROD DRIFT as follows:

Determines control rod 14-35 is drifting.

Selects control rod 14-35 and determines drifting inward.

May attempt to arrest the drift by giving a withdraw signal Monitors core parameters, main steam line radiation and off-gas activity Recognizes and reports additional control rods drifting (22-31, 10-31)

Inserts a Manual Scram by depressing both manual reactor Scram push buttons.

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EVENT 6/7 ATWS / SLC FAILURE / RWCU FAIL TO ISOLATE The scram air header leak degrades causing additional control rods to drift inward. With scram air header low and multiple control rods drifting, a manual Scram will be inserted. Most of the 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 perform LEP-03 and align for alternate boron injection using CRD and manually isolate RWCU.

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:

Actions of LPC performed. Recognizes failure of SLC and performs alternate boron injection and isolates RWCU. Control rods being inserted IAW LEP-02.

Simulator Operator Actions:

If requested to perform alternate boron injection using CRD, acknowledge the request. (will be performed after RPV injection is re-started following T&P)

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

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

Required Operator Actions Major Event - Reactor Scram / ATWS Component Failure - SLC control switch failure Component Failure - RWCU failure to isolate Performs LEP-03, Alternate Boron Injection Performs LEP-02, Alternate Rod Insertion SRO Time Action Notes Enters RSP and transitions to LPC.

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

Directs ARI initiation.

Directs Recirc Pump speeds reduced to 10%.

Directs tripping Recirc Pumps.

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EVENT 6/7 (CONT) SCRAM AIR HEADER LEAK/ATWS ACTIONS SRO Continued Time Action Notes Directs SLC initiation.

Directs LEP-03, Alternate boron (Critical task) injection.

Directs ADS inhibited.

Directs RWCU isolation.

Directs LEP-02, Alternate Rod (Critical task)

Insertion.

Contacts I&C for SLC control switch failure.

Acknowledges request for LEP-02, Section 3 jumpers.

Directs OCSRO to perform LEP-02, Section 3 to bypass scram signals with jumpers.

RO/BOP Time Action Notes Places mode switch to shutdown when After each action, reactor power level steam flow < 3x106 lb/hr. should be reported along with the action being completed.

Initiates ARI.

Places Recirc Pump speeds reduced to 10%.

Trips Recirc Pumps.

Places ADS in inhibit.

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EVENT 6/7 (CONT) SCRAM AIR HEADER LEAK/ATWS ACTIONS RO/BOP Time Action Notes Initiates SLC by placing control switch to the PUMP A & B RUN position.

Recognizes failure of SLC and reports to All positions of control switch should be SCO. attempted prior to reporting failure.

Identifies RWCU fails to isolate.

Closes RWCU Outboard Isol Valve G31-F004.

May close G31-F001 also.

Performs LEP-03, Alternate Boron (Critical task)

Injection.

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

Performs LEP-02, Alternate Rod (Critical task)

Insertion. (RMCS Section)

Insert IRMs.

When < range 3 on IRMs insert SRMs.

Starts both CRD pumps.

Place CRD Flow Controller to Manual.

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

May report failure of CRD Flow control Scram air header leak also causes loss valve. of control air to the CRD FCVs.

Bypasses RWM. Obtains key from key locker.

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

Requests jumpers for LEP-02, Section 3.

Stabilizes RPV level and pressure.

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EVENT 8 ATWS ACTIONS - TERMINATE AND PREVENT 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. Feedwater and 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 and insert control rods per LEP-02.

Success Path:

Continues LPC actions to shutdown the reactor by terminating & preventing injection and inserting rods using RMCS and cooling water D/P.

Simulator Operator Actions:

If requested to defeat Group I, LL3, wait 2 minutes, initiate Trigger 8 and inform the SCO that the jumpers are installed.

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.

If directed as AO to investigate the failure of the SDV vents & drains or CRD FCV failure, acknowledge the request.

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

If requested to open the MVD-5005, wait 5 minutes, initiate Trigger 9 and inform the control room that the valve is open.

If requested to defeat Drywell Cooler LOCA Lockout, wait three minutes, initiate Trigger 10 and inform the SCO that the jumpers are installed.

When injection to the RPV has been re-established and if requested to line up boron to the CRD system initiate Trigger 11.

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

Required Operator Actions Terminate and prevent HPCI/Feedwater (CS/RHR when LOCA signal received).

SRO Time Action Notes Directs verification of initiations and isolations.

Directs OCSRO to bypass Group 1, LL3 per SEP-10.

Directs Group 10 switches placed in override reset.

Directs terminate and prevent (Critical task)

HPCI/Feedwater (CS/RHR when LOCA signal received).

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EVENT 8 (CONT) ATWS ACTIONS - TERMINATE AND PREVENT SRO Time Action Notes May direct RCIC flow be reduced to support lower level to +90 inches.

When level reaches +90 inches, Normally provides level band of 60-90 inches evaluates Table 3: to prevent reaching LL3 (LOCA signal).

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

Directs injection established to maintain If level lowers to less than 45 inches (LL3)

RPV level LL4 to 90 inches then the LP ECCS pumps will start and will need to be terminated and prevented.

Directs Drywell cooling restored per SEP-10.

Evaluate TAF and LL4 indicated levels using Caution 1 graphs.

RO Time Action Notes Continues to select control rods and drive in using Emerg rod in notch override.

Monitor APRMs for downscale.

Monitors SLC tank level after report of LEP-03 is in progress.

Performs LEP-02, Section 3 after (Critical task) jumpers are installed.

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

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

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

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EVENT 8 (CONT) ATWS ACTIONS - TERMINATE AND PREVENT RO Time Action Notes Performs LEP-02, Section 3 Continued 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 Scram air header leak prevents opening discharge volume vents and of SDV V&Ds.

drains.

May direct OCSRO to coordinate venting CRD over pistons IAW LEP-02.

BOP Time Action Notes Places Group 10 switches to override /

reset Terminate and prevents injection to RPV.

HPCI - Places HPCI Aux Oil Pump to Pull to Lock.

FW - Can be performed a couple of The preferred method would be to lower ways. 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.

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EVENT 8 (CONT) ATWS ACTIONS - TERMINATE AND PREVENT BOP Time Action Notes May place Feedwater in service for level Controllers on P603.

control when directed by the SCO.

Raise RFP discharge pressure above RPV pressure Open SULCV to obtain desired level May place HPCI in service for level control during ATWS when directed by the SCO.

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

Adjust HPCI setpoint to approximately 1000 GPM.

Start auxiliary oil pump.

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

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

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

Adjust HPCI setpoint to maintain desired reactor water level Page 27 of 33

EVENT 9 ALL RODS IN When level has been lowered and level band has been established, the scram air header 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 Success Path:

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

When all rods are inserted and level is being controlled 170 - 200 inches the scenario may be terminated.

Simulator Operator Actions:

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

Malfunction - RD041F, Loss of Control air to the Scram valves.

Malfunction - RP010F, ATWS 3 (Make sure RPS is reset before deleting)

Inform the SCO that scram air header leak was located at HCU 14-35 and has been repaired.

If contacted as the RB AO to secure Alternate Boron Injection delete remote SL_IALEP03.

When directed by the lead evaluator, place the simulator in FREEZE.

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

Direct securing Alternate Boron Injection.

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

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EVENT 9 (CONT) ALL RODS IN RO Time Action Notes Continues to drive rods using RMCS Confirms Disch Vol. Vent & Drains open when scram air header is 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 using any of the following:

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.

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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 30 of 33

Attachment 1 Recirculation Speed Adjustments

1) Manipulates recirculation speed only with SRO permission.

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

3) Communicates to Concurrent Verifier direction of movement, component to be manipulated, amount of adjustment, and stopping point.

4) Obtains concurrence of Concurrent Verifier before commencing adjustments.

5) Operates recirculation speed controls one at a time, allows time for plant and machine response.

6) Observes redundant plant indications while performing adjustments.

7) Notifies SRO when recirculation speed adjustments are completed.

8) Periodically checks position on Power to Flow map.

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Attachment 2 Service Water LCO Page 32 of 33

Attachment 2 Service Water LCO Page 33 of 33

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #5

Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #5 Op-Test No.: FINAL Examiners: _______________________ Operators: __________________________

Initial Conditions: Unit Two is operating at ~94% power, end of cycle power.

2A Core Spray pump is under clearance.

APRM Channel 2 failed downscale and bypassed.

2C TCC pump is in service on Unit One Turnover: Perform Main Turbine Stop Valve Testing.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Main Turbine Stop Valve Test N-SRO 2 ES013F I-RO HPCI Logic Bus A Auto Start Fails (TS)

I-SRO 3 CF039F C-BOP Heater Drain Deaerator Controller Failure (AOP)

C-SRO R-RO AOP-23 Power Reduction 3a N/A R-SRO 4 I-RO APRM 4 Failure (TS)

NI031F I-SRO 5 ZUA13210 C-BOP UAT Ground C-SRO 6 M-All Loss of Offsite Power, Scram EE020F 6a DG005F C-BOP DG 4 Failure to Start (AOP)

C-SRO 7 NB009F M-All Small break LOCA 7a ES044F ES045F C-RO LP ECCS initiation logic failure ES046F C-SRO 8 N/A N/A Emergency depressurization

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 37

SCENARIO DESCRIPTION The plant is operating at ~94% power, end of cycle. Core Spray Pump 2A is out of service and APRM Channel 2 is failed downscale and bypassed. 2C TCC pump is aligned to Unit One.

Event 1 2OP-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.15 with feedwater level control transferred to single element IAW 2OP-32. MTSV Testing will continue testing MSVs 3 and 4. DFCS will be transferred to 3-element when complete.

Event 2 The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable per TS 3.5.1, Condition D and also Condition E (HPCI &

CS Inop) which requires restoration of one of the two within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Event 3 The Heater Drain Deaerator level control system will fail causing the HDP discharge valves to fail full open. The crew will respond per AOP-23.0, lower reactor power, stop 1 HD pump before HDD level goes <24, and then open the HD-V57 to control HDD level.

Event 3a Reactor power will be reduced with Recirc Flow to within the capacity of 1 HDP per AOP-23.

Event 4 APRM 4 will fail upscale resulting in a rod block. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. WCCSRO will request APRM TS Actions be taken in order to troubleshoot which requires the APRM mode selector switch to be place in INOP IAW 0OI-18.

Event 5 A UAT ground alarm will be received. The crew will respond IAW the APP.

Investigation by I&C will indicate the alarm is valid requiring Buses 2C & 2D to be transferred to the SAT.

Event 6 Prior to transferring the second Bus to the SAT, the SAT will trip and lock out. Off-site power will be lost. The crew will respond per AOP-36.1 and EOP-01-RSP. SRVs will be available for pressure control. RCIC and CRD will provide inventory makeup to the RPV.

Event 6a Diesel Generator 4 will fail to auto start. DG4 will be manually started in Control Room Manual and Emergency Bus E4 re-energized.

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.

ADS will not automatically initiate due to ECCS logic failure but may be manually initiated when level drops below TAF.

Event 7a Low pressure ECCS initiation logic will fail at LL3 requiring manually starting available pumps and aligning 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.

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OBJECTIVES SRO 341224B102, Determine actions required for Limiting Conditions for Operation per OI-01.8 and Technical Specifications 344227B402, Direct Action For Condensate/Feedwater System Failures Per AOP-23.0 344237B402, Direct Actions For A Loss of Any 4KV Buses Per AOP-36.1 344231B502, 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 PCCP 344215B502, Direct Actions To Control Primary Containment Temperature Per EOP PCCP 344216B502, Direct Actions To Control Suppression Pool Temperature Per EOP PCCP RO 259001B401, Respond to a Condensate/Feedwater System Failure Per AOP-23.0 202202B101, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 215204B401, Respond To An APRM Failure Per APP A-06 2-7, 2-8, 3-7, And/Or 3-8 262002B401, Respond To A Loss Of Off-Site Power 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-25 Sequence B1 Triggers Trigger Description 1 Manual HPCI Bus A Logic Failure 2 Manual HDD Controller Failure 3 Manual APRM 4 Fail Upscale 4 Manual UAT Ground 5 Auto SAT Trip (K4101B08) 7 Manual Small Break LOCA 8 Manual RCC Aligned to CSW 9 Manual CRD Flow Max - F034 Charging Water Isolation valve 10 Manual DW Cooler Stop 11 Manual E41-F041 Breaker Off 12 Manual E41-F042 Breaker Off 13 Manual SLC to DW (LEP-01) 14 Manual CRD Maximize - 2 pumps (SEP-09) 15 Manual Place 1D Air Compressor in service Interventions Summary Note: Shaded entries = Active Malfunctions Summary Current Target Ramp Act. Deact Malf. ID Mult ID Description Trig Value Value Time Time Time DG005F DG4 AUTO START FAIL TRUE TRUE ES043F CORE SPRAY A AUTO START FAIL TRUE TRUE ES044F CORE SPRAY B AUTO START FAIL TRUE TRUE ES045F RHR A AUTO START FAIL TRUE TRUE ES046F RHR B AUTO START FAIL TRUE TRUE NI032F APRM 2 APRM FAILS LO TRUE TRUE Page 5 of 37

Malfunctions Summary Current Target Ramp Act. Deact Malf. ID Mult ID Description Trig Value Value Time Time Time ES013F HPCI LOGIC BUS A AUTO START FAIL FALSE TRUE 1 ES014F INADVERANT HPCI SYS INITIATION FALSE TRUE 1 CF039F HTR DRN DEAER LVL CNTRLR FAILS FALSE TRUE 2 NI031F APRM 4 APRM FAILS HI FALSE TRUE 3 EE020F SAT RELAY FAILURE FALSE TRUE 5 NB009F SMALL RECIRC LINE RUPTURE 10% 5 Min 7 Remotes Summary Current Target Remote ID Mult. ID Description Trig Value Value CC_IACW4518 2C TBCCW PUMP UNIT ALIGNMENT 1 1 ED_IABKCF05 BKR CTL DC FUSES CORE SPRAY PUMP 2A OUT OUT VHSW146L CSW TO RBCCW HXS V146 SHUT OPEN 8 1.0 over 5 RDVF034 CHARGING WATER ISOL VALVE F034 .25 9 sec IACS993P DW CLR A/D OVERRIDE NORMAL/STOP NORM STOP 10 IACS994P DW CLR B/C OVERRIDE NORMAL/STOP NORM STOP 10 HP_ZVHP041M SUPP SUCTION VLV E41-F041 ON OFF 11 HP_ZVHP042M TORUS SUCTION VLV E41-F042 ON OFF 12 SL_IASLCRCR SLC TST TNK SOURCE (NORM=DW/ALT=FP) NORM NORM 13 SL_IASLCCTST SLC SUCT LINEUP (ALT=TEST TANK) ALT ALT 13 BV707/

RD_RDSUCTF SUCTION FILTER ISOL VALVES OPEN OPEN 14 309 RD_RDSUCTB SUCTION FILTER BYPASS VLV C0-V306 OPEN OPEN 14 F020B/

RD_RDDRIVF DRIVE WATER FILTER ISOL VALVES OPEN OPEN 14 F021 1D OFF 1D ON IA_IAIU1CMPRSS UNIT 1 AIR COMPRESSOR STATUS 15 1B STDBY 1B STDBY Page 6 of 37

Switches Summary Position / Actual Override Switch ID Description Trig Target Position Value Q1D23SWN RHR A Init Sig White ON/OFF OFF OFF Q1J39SWN RHR 2 Init Sig White ON/OFF OFF OFF Q1C22SWL Init Sig Seal In - White ON/OFF OFF OFF Q1J32SWL Init Sig Seal In - White ON/OFF OFF OFF ZUA13210 UAT WINDING Y GRD CURRENT ON/OFF OFF ON 4 SPECIAL INSTRUCTIONS

1. Ensure simulator exam security measures in place.

2. Provide 2OP-26, Section 8.6, marked up completed through Step 8.6.2.14.

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

4. Place all SPDS displays to the Critical Plant Variable display (#100).

5. Ensure appropriate keys have blanks in switches.

6. Exit shutdown screen on RWM and place the RWM key in the key locker.

7. Reset alarms on SJAE, MSL, and RWM NUMACs.

8. Ensure reference material is in appropriate location.

9. Verify any log books have blank sheets only and procedures are not marked.

10. Load scenario file if available.

11. Load malfunctions/overrides if scenario file is unavailable.

12. Ensure 2C TCC pump in service on Unit 1.

13. Place in Run and verify power at ~94%.

14. Place Equipment Control Tag on and Bypass APRM 2.

15. Place red cap on 2A Core Spray pump.

16. Ensure 2B Stator Cooling pump is in service.

17. Place DFCS in 1-element.

18. Ensure SIMULATOR CONTROL ROOM KEY INDEX is next to key locker. (Hide actual CR Index)

19. Ensure 0ENP-24.5 for IC-25 @ P603.

Page 7 of 37

SHIFT BRIEFING Plant Status Unit Two is operating at ~94% power, end of cycle.

Equipment Out of Service Core Spray Pump 2A is under clearance for breaker repair and is expected to be returned to service in two hours.

APRM Channel 2 failed downscale and bypassed.

2C TCC pump is supplying Unit One cooling.

No other equipment is out of service Plan of the Day 2OP-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.15 with feedwater level control transferred to single element IAW 2OP-32.

When shift turnover is complete, perform Main Turbine Stop Valve testing.

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-1021, 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.)

• Emergency Depressurize

• Restore and maintain RPV level above LL4.

Page 9 of 37

EVENT 1 MAIN TURBINE STOP VALVE TESTING 2OP-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.15 with feedwater level control transferred to single element IAW 2OP-32. MTSV Testing will continue testing MSVs 3 and 4. DFCS will be transferred to 3-element when complete.

Objectives:

SCO - Directs completion of Main Turbine Stop valve testing IAW 2OP-26, Section 8.6.

RO - Monitors the plant.

BOP - Performs Main Turbine Stop valve testing IAW 2OP-26, Section 8.6.

Success Path:

Main Turbine Stop valve testing completed.

Simulator Operator Actions:

If requested to verify back panel relay positions, report complete IAW 2OP-26.

If contacted as Load Dispatcher, acknowledge request or information.

If contacted as System Engineer (any discussion about fast closure), inform crew fast closure of MTSVs is satisfactory - matches previous performances.

When 2OP-26, Section 8.6 is complete and when directed by the lead examiner, proceed to the next event.

Required Operator Actions Normal Operations - Main Turbine Stop valve testing.

SRO Time Action Notes Direct performance of Main TSV testing.

Acknowledges Annunciator A-7 4-2 FW CTL SYS TROUBLE during TSV testing May allow discontinuing further reports of expected alarms IAW OPS-NGGC-1000.

May contact System Engineer regarding Stop Valve testing abnormalities.

Page 10 of 37

EVENT 1(Cont) MAIN TURBINE STOP VALVE TESTING RO Time Action Notes Monitors the plant during Stop Valve 5-10 MWE Generator output change and possible standby EHC pump auto start.

testing.

Acknowledges Annunciator A-7 4-2 FW CTL SYS TROUBLE during TSV testing.

May request discontinuing further reports of May place a green placard under Annunciator A-7 expected alarms IAW OPS-NGGC-1000.

on Panel P603.

BOP Time Action Notes Ensures plant parameters are stable before testing stop valve number 3.

ENSURE TURB STOP VLV CLOS TRIP (A-05 5-7) annunciator is clear.

DEPRESS AND HOLDs MSV NO 3 TEST push button AND ENSURE the following:

a. Valve travel is smooth from 100% to 10% open.

b. Valve travel is fast from 10% open to 0% open.

RELEASE MSV NO 3 TEST push button AND ENSURE the valve opens smoothly to the full open position.

ALLOWs plant parameters to stabilize before testing stop valve number 4.

ENSURE TURB STOP VLV CLOS TRIP (A-05 5-7) annunciator is clear.

DEPRESS AND HOLDs MSV NO 4 TEST push button AND ENSURE the following:

a. Valve travel is smooth from 100% to 10% open.

b. Valve travel is fast from 10% open to 0% open.

RELEASE MSV NO 4 TEST push button AND ENSURE the valve opens smoothly to the full open position.

Page 11 of 37

EVENT 1 (Cont) MAIN TURBINE STOP VALVE TESTING BOP Time Action Notes PLACEs feedwater level control in three element in accordance with 2OP-32, Section 8.2.

a. ENSUREs steam flow and feedwater flow Any of the following may be utilized:

have negligible mismatch using multiple C32-FR-R607 (SF/FF Recorder - P603) indications. C32-R603 (SF) to C32-R604A & B (FF)

b. ENSUREs vessel level has been at Plant Process Computer (PPC) or ERFIS steady state for approximately 5 minutes.

C32-R608 (NR Level recorder)

1. Depresses SEL button on SULCV, FW-LIC-3269, until LVL ERROR is displayed AND CHECK level error is less than approximately 2 inches.

2. SHIFTs FEEDWATER CONTROL MODE SELECT control switch to 3-element position.

Reports results of testing and DFCS alignment to SRO.

Page 12 of 37

EVENT 2 HPCI LOGIC BUS A FAILURE The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable per TS 3.5.1.

Objectives:

SCO - Declare HPCI Inoperable RO - Recognize logic failure and Isolate HPCI.

Success Path:

HPCI declared inoperable IAW TS 3.5.1 and isolated IAW APP.

Simulator Operator Actions:

When directed by lead evaluator, INITIATE TRIGGER 1 to activate HPCI fuse failure.

If asked as AO to investigate, report all circuit breakers in DC SWBD 2A & Panel 4A are closed.

If asked as I&C to investigate, wait 2 minutes and report fuse E41A-F1 in panel P620 is blown (blows again if replaced).

If asked as WCC/OC SRO for clearance or Equipment Control tags, acknowledge request.

If requested to open breakers for E41-F041 and F042 (MCC 2XDA) when valves are shut, monitor valve positions on panel mimic (P601 Section A2).

o When E41-F041 indicates closed, INITIATE TRIGGER 11 o When E41-F042 indicates closed, INITIATE TRIGGER 12.

Required Operator Actions Instrument /Component Failure - Isolate HPCI steam supply.

Technical Specification - TS 3.5.1 Conditions D & E.

SRO Time Action Notes Direct annunciator response for A-1 5-5 HPCI LOGIC BUS A PWR FAILURE 6-4 HPCI COND STORAGE TNK WTR LVL LO May identify requirement to initiate an HPCI is considered a Train A system for impairment IAW 0PLP-01.5. ASSD.

(This action may be directed to Ops Center SRO)

Directs BOP to monitor the plant.

Determines depressurization of steam supply is NOT required.

Contacts I&C to investigate HPCI LOGIC BUS A PWR FAILURE Page 13 of 37

EVENT 2 (Cont) HPCI LOGIC BUS A FAILURE SRO Time Action Notes Refers to Tech Spec 3.5.1 ECCS Operating and Determines: Condition A existed at turnover with CONDITION A. One low pressure ECCS Core Spray Pump 2A under clearance.

injection/spray subsystem inoperable.

REQUIRED ACTION A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7 days.

CONDITION D REQUIRED ACTION:

D.1 Verify by administrative means RCIC System is OPERABLE.

Immediately AND D.2. Restore HPCI System to OPERABLE status.

14 days CONDITION E REQUIRED ACTION:

E.1 Restore HPCI System to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> May request equipment control tags to support abnormal HPCI system alignment.

Acknowledge and report annunciators A-1:

5-5 HPCI LOGIC BUS A PWR FAILURE 6-4 HPCI COND STORAGE TNK WTR LVL LO Report HPCI Suction is aligned to both the CST and Suppression Pool.

Page 14 of 37

EVENT 2 (Cont) HPCI LOGIC BUS A FAILURE RO Time Action Notes Performs APP A-1 5-5 (HPCI LOGIC BUS A PWR FAILURE ) actions:

1. Close the Condensate Storage Tank Suction Valve, E41-F004.

2. Isolate the HPCI Steam Supply per OP-19, Section 8.5.

1) CLOSE STEAM SUPPLY INBOARD ISOL VLV, E41-F002.

2) CLOSE STEAM SUPPLY OUTBOARD ISOL VLV, E41-F003.

3) Depressurizing steam supply is NOT required, but if performed will require performance of 0PT-02.3.1b, Suppression Pool to Drywell Vacuum Breaker Position Check, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

3. Close the Turbine Exhaust Vacuum Breaker Valve, E41-F075.

Informs SRO of expected alarm A-1 1-1 HPCI VAC BKR VLV F075/F079 NOT FULL OPEN Contacts RBAO to standby for opening breakers on MCC 2XDA when the following valves indicate Full Closed.

4. Close the Torus Suction Valve, E41-F041.

5. Close the Torus Suction Valve, E41-F042.

Notifies SRO APP actions are complete and No impact to TRM 3.6 BUS POWER to reference TS 3.5.1 and TRM 3.6. MONITORS (alarm worked).

BOP Time Action Notes Monitors the plant and reports CST at normal level.

Page 15 of 37

EVENT 3/3a HDD CONTROLLER FAILURE/ AOP-23 POWER REDUCTION The Heater Drain Deaerator level control system will fail causing the HDP discharge valves to fail full open. The crew will respond per AOP-23.0, Condensate/Feedwater System Failure, lower reactor power, stop 1 HD pump before HDD level goes <24, and then open the HD-V57 to control HDD level. Reactor power will be reduced with Recirc Flow to within the capacity of 1 HDP per AOP-23.

Objectives:

SCO - Direct AOP-23 actions.

RO - Reduce reactor power with Recirc flow.

BOP - Trip a HDP and control HDD level manually.

Success Path:

Reactor power reduced to within the capacity of 1 HDP and HDD level being controlled manually with the HD-V57.

Simulator Operator Actions:

When directed by lead evaluator, INITIATE TRIGGER 2 to activate HDD controller failure.

If asked as AO to investigate, acknowledge request.

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

If contacted as RE to monitor thermal limits, acknowledge request.

When plant conditions have stabilized with HDD level being manually controlled, DELETE HDD malfunction (CF039F) and call the control room as I&C and report Level controller output air line was discovered separated and has been reconnected.

Required Operator Actions Component Failure - HDD Level Controller.

Reactivity Manipulation - Lower reactor power with Recirc flow.

SRO Time Action Notes Direct entry into AOP-23.0, Condensate/Feedwater System Failure.

Direct lowering reactor power 1 HDP should maintain HDD Level with Main Generator output between 200 &

550 MWe.

Direct trip of 1 HD pump and HDD level control with HD-V57 Direct I&C to investigate HDD level control problem Direct 0GP-12, Power Changes, or GP-05, Unit Shutdown, performance May contact RE to monitor thermal limits due to reduced feedwater temperature or a reactivity management plan for recovery.

Page 16 of 37

EVENT 3/3a (Cont) HDD CONTROLLER FAILURE/ AOP-23 POWER REDUCTION RO Time Action Notes Reduce power per 0ENP-24.5 as directed by the SCO.

Lower flow on one RR Pump (~2%) at a time to stay within mismatch criteria (7.5x106 Mlbs jet pump flow if < than 6

58 Mlbs or 3.5x10 Mlbs if > than 58 Mlbs).

Continues alternating Recirc pump decreases until core flow is ~43 Mlbs.

BOP Time Action Notes May Diagnose HD pump discharge valves full open prior to low level alarm.

Acknowledges and reports annunciator UA-4 2-10 HD DEAERATOR LEVEL HIGH -

LOW.

Dispatches an operator to local HDD controller.

Enters and announces AOP-23.0 Trips 1 HD pump prior to HDD level reaching +24 inches.

Opens HD-V57 to control HDD level Monitors main condenser vacuum.

Maintains heater drain deaerator level less than 60 inches indicated on HEATER DRAIN DEAERATOR LEVEL, HD-LI-97 MONITORs final feedwater temperature (FFWT) IAW 2OI-03.2, Reactor Operator Daily Surveillance Report.

Ensures plant is compatible with GP-12 or GP-05 Page 17 of 37

EVENT 4 APRM 4 FAILURE APRM 4 will fail upscale resulting in a rod block. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. WCCSRO will request APRM TS Actions be taken in order to troubleshoot which requires the APRM mode selector switch to be place in INOP IAW 0OI-18.

Objectives:

SCO - Determine LCO for APRM 4 inoperability and direct placing channel in trip.

RO - Diagnose APRM 4 failure and place in INOP.

BOP - Monitor the plant.

Success Path:

ARPM 4 declared inoperable IAW TS 3.3.1.1 and placed in trip condition IAW 0OI-18.

Simulator Operator Actions:

With the HDD level being controlled automatically and directed by lead evaluator, INITIATE TRIGGER 3 to activate APRM 4 failure.

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

If asked to pull fuses (for TRM 3.3 actions) acknowledge the request.

After LCO entries have been determined and SRO is waiting for I&C, call as WCCSRO and request APRM 4 be placed in tripped condition to support I&C trouble shooting.

Required Operator Actions Component Failure - APRM 4 will be required to be placed in INOP.

Technical Specification - TS 3.3.1.1 Condition A, TRM 3.3.

SRO Time Action Notes Direct actions of APPs Direct I&C to investigate Evaluate Tech Spec 3.3.1.1 Reactor Protection System Instrumentation Determine APRM 4 and 2 are inoperable.

Determine 2 of 4 the available channels are operable for Function 2.

Condition A, Required Action with one or more required channels inoperable, place in trip condition in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Evaluate TRM 3.3 Control Rod Block Instrumentation Determine one of the required channels is not operable for Function 1 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore to operable.

Page 18 of 37

EVENT 4 (Cont) APRM 4 FAILURE Page 19 of 37

EVENT 4 (Cont) APRM 4 FAILURE SRO Time Action Notes Refers to 0OI-18 for actions to place APRM 4 in a tripped condition.

Direct APRM 4 mode selector switch placed in INOP to allow I&C troubleshooting.

BOP Time Action Notes Monitors the plant.

May check back panel APRM indications.

Page 20 of 37

EVENT 4 (Cont) APRM 4 FAILURE RO Time Action Notes Acknowledges, refers to & reports annunciators A-6 2-8 APRM UPSCALE 3-7 APRM TROUBLE 3-8 APRM UPSCALE TRIP/INOP A-5 2-2 ROD OUT BLOCK Determines ARPM 4 has a critical fault (CPU Failure) and cannot be bypassed (APRM 2 already bypassed).

Obtains Key #114 from Control room Key locker.

Places APRM 4 in the tripped condition If APRM 1 or 3 is placed in INOP, a Full by placing APRM OPER/INOP mode reactor SCRAM will occur.

selector switch in "INOP" on Panel P608.

Page 21 of 37

EVENT 5 UAT GROUND A UAT ground alarm will be received. The crew will respond IAW the APP. Investigation by I&C will indicate the alarm is valid requiring Buses 2C & 2D to be transferred to the SAT.

Objectives:

SCO - Direct BOP Buses transferred to the SAT.

RO - Monitors the plant.

BOP - Transfers BOP Bus 2C to the SAT.

Success Path:

BOP Bus 2C transferred to the SAT.

Simulator Operator Actions:

When directed by lead evaluator, INITIATE TRIGGER 4 to activate UAT ground alarm.

If asked as AO to investigate, wait 1 minute and report no ground targets visible on Buses 2C or 2D.

If asked as I&C to investigate, wait 2 minutes and report UAT Y winding ground is valid.

Monitor BOP bus transfers and ensure TRIGGER 5 automatically initiates when Bus 2D synch switch is placed to ON (Do not allow the crew to transfer BOTH BOP Buses)

Required Operator Actions Component Failure - Ground fault on UAT Y winding requiring BOP bus transfer to SAT.

SRO Time Action Notes Acknowledges report of UA-13 2-10 UAT WINDING Y GRD CURRENT Informs I&C verify UAT ground alarm is valid.

Directs BOP Buses(2C & 2D) be transferred to the SAT per OP-50 May reference TS 3.8.1 for UAT Degraded but not INOP.

inoperability.

RO Time Action Notes Monitors the plant.

Page 22 of 37

EVENT 5 (Cont) UAT GROUND BOP Time Action Notes Acknowledges, refers to & reports annunciator 2-10 UAT WINDING Y GRD CURRENT Directs TBAO to walk down Buses 2C &

2D looking for ground targets.

May direct OSAO to walk down the UAT.

Notifies SRO that no ground targets If a second ground fault should occur before the present on Buses 2C or 2D and that initial ground fault is cleared, loss of equipment and severe equipment damage may result.

these buses should be transferred to the SAT if valid.

Transfers BOP Bus 2C to the SAT Plant announcements for bus transfers utilizing 2OP-50, Section 7.1 should be made.

1. Places SAT TO BUS 2C SYNCHRONIZING SWITCH in ON.

2. Confirms synchroscope is at "12 o'clock",

AND CLOSEs SAT TO BUS 2C BREAKER, AC6.

3. CONFIRMs SAT TO BUS 2C BREAKER, AC6, has closed using the breaker indicating lights.

4. Confirms UAT TO BUS 2C BREAKER, AC4, has opened using the breaker indicating lights.

5. Places SAT TO BUS 2C SYNCHRONIZING SWITCH in OFF.

6. Places SAT TO BUS 2D SYNCHRONIZING This causes a loss of the SAT SWITCH in ON. Loss of both the RR Pumps Page 23 of 37

EVENT 6/6a LOSS OF SAT / SCRAM / DG4 FAILURE Prior to transferring the second Bus to the SAT, the SAT will trip and lock out. Off-site power will be lost. The crew will respond per AOP-36.1, Loss Of Any 4160V Buses OR 480V E-Buses, and EOP-01-RSP. SRVs will be available for pressure control. RCIC and CRD will provide inventory makeup to the RPV.

Diesel Generator 4 will fail to auto start. DG4 will be manually started in Control Room Manual and Emergency Bus E4 re-energized.

Objectives:

SCO - Directs actions for a Reactor Scram, RVCP, and 0AOP-36.1.

RO - Insert a reactor scram with no recirc pumps running.

BOP - Starts DG4, ties to E4 and perform 0AOP-36.1 actions.

Success Path:

Manual SCRAM inserted with DG4 manually started and tied to E4.

Simulator Operator Actions:

Ensure Trigger 5 automatically initiates prior to Bus 2D transfer to the SAT.

If contacted as load dispatcher, report line crews are being dispatched to investigate.

If asked as Outside AO, acknowledge request to monitor DGs.

If asked to perform actions to maximize CRD flow with 2 pumps per SEP-09, wait 4 minutes, initiate Trigger 14 and report the actions complete.

If requested to open CRD charging header isolation valve, initiate Trigger 9, wait 2 minutes and report actions complete.

If asked as Unit 1 for status of the air system, initiate Trigger 15 and report 1D air compressor is in service.

If asked to transfer RCC to CSW, wait 5 minutes, initiate Trigger 8 and report actions complete.

If requested to perform field actions for UAT back-feed, acknowledge the request.

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

Required Operator Actions Major event - Loss of offsite power, reactor Scram.

Component Failure - DG4 auto start failure requiring manual start.

SRO Time Action Notes Direct insertion of manual scram due to loss of the recirc pumps.

Enter and direct EOP-01-RSP.

Direct entry into 0AOP-36.1, Loss Of Any 4160v Buses or 480v E-Buses, for Loss of Off-Site Power.

Page 24 of 37

EVENT 6/6a (Contd) LOSS OF SAT / SCRAM / DG4 FAILURE SRO Time Action Notes Announces entry into RVCP Directs a pressure band of 800-1000#

Direct reactor water level band of 170-200 inches.

CRD (SEP-09)

RCIC Announces entry into PPCP Suppression Pool Temp Above 95°F OR Drywell Average Air Temp Above 150°F OR Suppression Pool Water Level Above - 27 inches Direct RHR Loops be placed in suppression pool cooling.

RO Time Action Notes Announces Unit 2 reactor SCRAM.

Performs immediate actions for Reactor scram Depresses both manual Scram pushbuttons.

After steam flow is less than 3 x 106 lb/hr, place the reactor mode switch to shutdown When APRM downscale trip, then Tripping the main turbine causes a loss of Trip the main turbine offsite power to Unit Two.

Ensures the master reactor level controller setpoint is +170 inches Operates SRVs as directed to stabilize pressure and control pressure as directed by the SCO (800-1000 psig).

Manually Starts RCIC or maximizes RCIC flow to 500 gpm following auto initiation to maintain reactor water level.

Page 25 of 37

EVENT 6/6a (Contd) LOSS OF SAT / SCRAM / DG4 FAILURE RO Time Action Notes Maximizes CRD flow IAW SEP-09 Hard card 1 CRD pump should be in service and

2. ENSURE CRD FLOW CONTROL, C12-FC- hard card only supports this alignment.

R600, is in MAN position.

3. THROTTLE the following valves, as necessary, to maintain charging water header pressure greater than or equal to 1000 psig but as low as possible.

A. In-service FLOW CONTROL VLV, C12-F002A.

B. DRIVE PRESSURE VLV, C12-PCV-F003.

4. IF the CRD pump trips on low suction pressure due to high CRD suction filter dP, THEN PERFORM the following:

A. CLOSE the in-service FLOW CONTROL VLV, C12-F002A.

B. START a CRD pump.

C. THROTTLE OPEN the in-service FLOW CONTROL VLV, C12-F002A, to maintain charging water header pressure above the pressure at which the CRD pump tripped, but as low as possible.

5. As time permits refer to 0EOP-01-SEP-09 for additional actions.

SEP-09 Procedure Actions Dispatch AO to perform SEP-09 for two CRD pumps with the Reactor Building Accessible.

When AO reports field actions for SEP-09 complete for 2 pump operation, the RO performs the following:

d. STARTs the second CRD pump.

e. ENSUREs CRD FLOW CONTROL, C12-FC-R600, is in MAN.

f. Throttles the following valves to maintain charging water header pressure greater than or equal to 950 psig but as low as possible:

• In-service Flow Control Vlv, C12- F002A

• Drive Pressure Vlv, C12-PCV-F003

• Charging Water Header Throttle Valve, C12-F034 F034 throttling is performed by RBAO in the field.

Operates RCIC/CRD to restore/maintain Reactor water level +170-200 inches Page 26 of 37

EVENT 6/6a (Contd) LOSS OF SAT / SCRAM / DG4 FAILURE RO (Contd)

Time Action Notes Place RHR Loop B into suppression pool cooling.

Open SW-V105 Close SW-V143 If LOCA signal is present place RHR LOCA signal may or may not be present SW Booster Pumps B & D LOCA when aligning this loop for SPC.

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 Opens either SW-V111 or SW-V117 Verify cooling logic is made up Start Loop B RHR Pmp Open E11-F028B Throttle OPEN E11-F024B (1 pump 6000 - 10000 gpm)

(2 pumps 6000 - 11500 gpm)

Throttle E11-F048B CLOSED Places MSIV control switches to CLOSED.

Page 27 of 37

EVENT 6/6a (Contd) LOSS OF SAT / SCRAM / DG4 FAILURE BOP Time Action Notes Diagnose failure of DG4 to auto start Manually Start and tie DG4 to E4. DG4 failure to auto start and control room manual mode of operation should be Depresses the AUTO Start pushbutton. reported to the SRO and may be done utilizing Crew Update.

Depresses the Control Room Manual pushbutton.

Manually starts DG4 Verifies DG4 ties E4 (DG4 output bkr closes, E4 undervoltage clears).

Dispatches OSAO to monitor DG operation locally.

Announce and enter 0AOP-36.1.

Verifies the following systems are DG4 loading should be periodically operating as required for current plant monitored to ensure over load conditions conditions: do not occur.

• CRD System

• CSW System

• NSW System

• RBCCW System

• Service/Instrument Air System Momentarily Places DIV I NON-INTRPT RNA, SV-5262 control switch to OVERRIDE/RESET, THEN to OPEN, AND ENSURE DIV I NON-INTRPT RNA, SV-5262 opens Momentarily Places DIV II NON-INTRPT RNA, SV-5261 control switch to OVERRIDE/RESET, THEN to OPEN, AND ENSURE DIV II NON-INTRPT RNA, SV-5261 opens.

Determines UAT back-feed is NOT available with Y-winding ground and gets SRO concurrence.

Page 28 of 37

EVENT 6/6a (Contd) LOSS OF SAT / SCRAM / DG4 FAILURE BOP Time Action Notes Starts all available NSW & CSW pumps.

Starts Control Room HVAC.

Ensures at least one of the following Control Room A/C and Supply Fan units is operating:

- CTL ROOM A/C & SUPPLY FAN, 1D-CU-CB and 1D-SF-CB

- CTL ROOM A/C & SUPPLY FAN, 2D-CU-CB and 2D-SF-CB

- CTL ROOM A/C SPARE FAN, 2E-SF-CB.

Starts Battery Room HVAC.

- BATTERY ROOM 1A VENT FANS, 1C-SF-CB and 1C-EF-CB

- BATTERY ROOM 1B VENT FANS, 1B-SF-CB and 1B-EF-CB

- BATTERY ROOM 2A VENT FANS, 2C-SF-CB and 2C-EF-CB

- BATTERY ROOM 2B VENT FANS, 2B-SF-CB and 2B-EF-CB.

Restores Drywell cooling Dispatches an AO to transfer RCC to CSW header by Opening SW-V146.

Verifies all available DW Coolers in operation Proper aligns RCC pumps

a. IF three RBCCW pumps are running, THEN STOP one RBCCW pump, AND PLACE its control switch in AUTO.

b. IF only one RBCCW pump is running, THEN START a second RBCCW pump, if available.

c. IF no RBCCW pump is running, THEN PLACE all RBCCW pump control switches in OFF Direct RPS to be restarted.

Verifies Group Isolations Group 1,2,3,6,8 & 10 on LOOP.

Page 29 of 37

EVENT 7/7A SMALL BREAK LOCA / ECCS LOGIC FAILURE 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 (only if Low Pressure ECCS pumps are manually started), 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.

Objectives:

SCO - Directs actions for RVCP and PCCP.

RO - Aligns and maximizes flow from available injection sources (RCIC, CRD, SLC).

BOP - Monitors DG4 loading while continuing 0AOP-36.1 actions.

Success Path:

Align alternate coolant injection from SLC and manually start low pressure ECCS systems when level lowers below 45 inches (LL3).

Simulator Operator Actions:

When RPV level and pressure have been stabilized and as directed by the lead evaluator, initiate Trigger 7 to activate small break LOCA.

If requested to transfer SLC suction to demin water, initiate Trigger 13, wait two minutes and report actions complete.

If requested to stop drywell coolers, initiate Trigger 10.

If asked as I&C to investigate ECCS logics, acknowledge request When directed by the lead examiner, proceed to the next event.

Required Operator Actions Major Event - Small Break LOCA Component Failure - ECCS logic failure requiring manual start of ECCS pumps and manual alignment of injection valves SRO Time Action Notes 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.

Page 30 of 37

EVENT 7/7A (Contd) SMALL BREAK LOCA / ECCS LOGIC FAILURE SRO Time Action Notes Direct drywell spray when suppression chamber pressure >11.5 psig.

Informs crew on decision of inhibiting or not inhibiting ADS Directs verification of Isolations and Actuations for LL1, LL2, LL3, & High DW Pressure Directs Low Pressure ECCS pumps be started RO Time Action Notes Recognize rising drywell temperature and pressure, diagnose as LOCA Perform LEP-01 for SLC injection with demin water Dispatch an AO to perform infield actions.

When in field actions complete, starts Both SLC Pumps.

Page 31 of 37

EVENT 7/7A (Contd) SMALL BREAK LOCA / ECCS LOGIC FAILURE RO Time Action Notes Initiate suppression chamber spray per SEP-03.

If necessary, then place Loop B 2/3 CORE HEIGHT LPCI INITIATION OVERRIDE SWITCH, E11-CS-S18B, 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-F028B, is open Open TORUS SPRAY ISOL VLV, E11-F027B.

Page 32 of 37

EVENT 7/7A (Contd) SMALL BREAK LOCA / ECCS LOGIC FAILURE RO (Contd)

Time Action Notes 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 (L/O)

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-F021B 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:

2B CS 2A RHR 2B RHR 2C RHR 2D RHR Page 33 of 37

EVENT 7/7A (Contd) SMALL BREAK LOCA / ECCS LOGIC FAILURE BOP Time Action Notes Monitors DG loading Performs verification of Group Isolations See attached Group and System actuations for LL1, LL2, LL3 and High Drywell pressure.

Page 34 of 37

EVENT 8 REACTOR DEPRESSURIZATION Depressurization may be automatic or manually performed when level drops below TAF.

Objectives:

SCO - Directs Emergency Depressurization and restoration of reactor water level.

RO - Performs action for emergency Depressurization and restoration of reactor water level.

Success Path:

Emergency depressurize the RPV and restore RPV level to 170 - 200 inches.

Simulator Operator Actions:

If requested to re-align SLC to the boron tank, wait 4 minutes and modify Remote Function SL_IASLCTST, NORM When RPV level is being controlled >+170, the scenario may be terminated When directed by the lead evaluator, place the simulator in FREEZE.

Required Operator Actions Restore and maintain RPV level above LL4 SRO Time Action Notes Determine ED is required.

Direct placing 7 ADS valve ***CRITICAL TASK***

switches to open.

Direct re-alignment of RHR for LPCI injection Direct low pressure ECCS injection valves opened Direct RPV level be restored and ***CRITICAL TASK***

maintained +170-200 inches Direct Alternative Source Term actions (SLC, CREV, SEP-11)

Page 35 of 37

EVENT 8 (Contd) REACTOR DEPRESSURIZATION RO / BOP Time Action Notes Places 7 ADS valve control switches ***CRITICAL TASK***

Re-align RHR for LPCI injection.

Ensures Drywell Sprays / SP Sprays /

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 ***CRITICAL TASK***

maintain RPV level 170-200 inches.

Re-align SLC for SLC Tank Injection (Alternate Source Term Action)

Start CREV (Alternate Source Term Action)

Perform SEP-11 (Alternate Source Term Action)

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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 37 of 37

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #6

Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #6 Op-Test No.: FINAL Examiners: _______________________ Operators: __________________________

Initial Conditions: Plant is operating at ~68% power (IC-10). 2B EHC pump under clearance.

Turnover: Swap Condensate Booster Pumps.

Event Malf. No. Event Event No. Type* Description N-BOP 1 Swap Condensate Booster Pumps N-SRO C-BOP MCC 2TD trip / Standby Stator Water Cooling Pump fails 2 EE030M C-SRO to auto start C-RO MG Lube Oil Pump B3 trips / 2B Recirc Pump fails to trip 3a RC029F C-SRO (TS)(AOP)

R-RO Insert control rods to exit scram avoidance region of the 3b R-SRO power to flow map.

C-BOP 4 ZUA5110 RB Exhaust Fan trip C-SRO RD001M C-RO 5 Rod Drift (TS)(AOP)

(22-11) C-SRO M-All NB005F Fuel Failure / Enter RRCP / SCRAM (failure of Rx Scram 6 C-RO NB010F B Pushbutton)

C-SRO C-BOP 7 PCCP / Initiate SPC (failure of F024A valve)

C-SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 35

SCENARIO DESCRIPTION The plant is operating at ~68 power. 2B EHC pump under clearance.

Event 1 Normal Operations - Swap from 2A CBP to 2C CBP. Unit /LOCA Load Shed switches will have to be swapped also.

Event 2 MCC 2TD will trip and the standby stator cooling water will fail to auto start. The standby stator cooling water pump can be manually started. The 2D air compressor will also be lost and 0AOP-20.0 may be entered. Unit One may be contacted to start the 1D Air Compressor.

Event 3a MG Lube Oil Pump B3 trips and with the loss of 2TD this only leaves 1 oil pump.

Recirc MG Set 2B oil pressure drops below the trip setpoint but fails to trip the 2B Recirc Pump. The MG Set must be manually tripped. Determine TS 3.4.1 condition A1 applies to satisfy the requirements of the LCO in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Event 3b 0AOP-04.0 will be entered. The plant will be in the Scram Avoidance Region of the power to flow map. Recirc flow must be increased or control rods must be inserted to exit this region. With only one recirc pump in operation reactor power must be less than 50% also.

Event 4 RB Exhaust fan will trip on overload. The APP will be addressed which will have the standby fan started. I&C should be contacted before the overload reset and the fan restarted.

Event 5 Control Rod 22-11 will start to drift in. The crew will enter 0AOP-02.0 and take action IAW 2APP-A-05 (3-2). When the high temperature alarm is received Engineering will report that scram times cannot be assured based on past history of the control rod.

Determine TS 3.1.3 condition C1 to insert the control rod in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and C2 to disarm the control rod within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Event 6 Fuel failure will occur. RRCP will be entered and charts executed. When Process Off gas Hi Hi alarm with the Main Stack rising a scram will be inserted and Group I valves closed. Reactor Scram Pushbutton B is failed, other methods are available i.e. mode switch, ARI, etc.

Event 7 With MSIVs isolated and fuel damage indicated SRVs will be used to control pressure thereby adding heat to the suppression pool. PCCP will direct SPC to be placed in service on all available loops.

Event 8 After the reactor scram and MSIV closure, when SPC has been placed in service on B loop, and the failure of the SPC valves on the A loop has been identified then the scenario may be terminated.

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OBJECTIVES SRO 344218B502, Direct Actions To Control Reactor Pressure Per EOP-01-RVCP 344209B402, Direct Shift Response To Recirculation Pump Trip Per 0AOP-04.0 341219B102, Direct Actions To Lower Reactor Power From Rated to 55% Including Removal Of One Feed Pump From Service Per GP-05 & GP-12 344227B502, Direct Actions To Control An Unmonitored Radioactive Release With The Release Rate Less Than That Requiring An Alert Declaration Per EOP RRCP RO 259204B101, Secure The First Reactor Feed Pump Per 2OP-32 202017B401, Respond To Recirc Pump Trip(s) Per 0AOP-04.0 201201B401, Respond To A Control Rod Drift Per APP A-05 3-2 205014B101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 272201B401, Respond To An Area Radiation Annunciator Per APP UA-03 200601B401, Respond to radioactive spills, high radiation and airborne activity per 0AOP-05.0 200603B501, Perform immediate actions for a reactor scram Page 4 of 35

SIMULATOR SETUP Initial Conditions IC-10 Event Triggers Event Trigger Trigger Description 1 1 Normal Ops (Disable Unit/LOCA Load Shed for 2C CBP) 2 Normal Ops (Enable Unit/LOCA Load Shed for 2A CBP) 11 HWCH-SV-5719 to open 2 3 Manually Initiated (2TD trip) 10 Manually Initiated (Start 1D Air Compressor) 3 4 Manually Initiated (B3 Oil Pump trip) 4 5 Manually Initiated (RB Exhaust Fan overload) 5 6 Manually Initiated (Control Rod Drift) 6 7 Manually Initiated (Fuel Failure) 8 Auto Initiated (Gross Fuel Failure)(on manual scram A pushbutton, K2501PP7) 7 9 Auto Initiated (SPC valve failures)(on the F024 switch in auto, K1207JNN)

Page 5 of 35

Page 6 of 35 SPECIAL INSTRUCTIONS Ensure simulator exam security measures in place.

Start the 2B Stator Cooling Water Pump and Shutdown the 2A Stator Cooling Water Pump and place control switch in Auto.

Reduce reactor power to ~68% power using recirc.

Place 2B EHC pump to off and red cap. Place an annunciator placard on the board.

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.

Ensure 0ENP-24.5 for IC-10 @ P603.

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SHIFT BRIEFING Plant Status The plant is operating at ~68% power.

Equipment Out of Service 1A NSW Pump is under clearance for breaker refurbishment.

2B EHC Pump.

No other equipment is out of service.

Plan of the Day When the shift turnover is complete swap the Condensate Booster Pumps for maintenance. (Secure 2A CBP, Start 2C CBP)

Page 8 of 35

SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, 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 a manual reactor scram and close the Group I Isolation Valves when Process Off gas Hi Hi annunciator is received and Main Stack Rad is rising.

• Initiate SPC when the suppression pool is greater than 95°F to remain in the safe region of the HCTL graph.

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EVENT 1 SWAPPING CBPs The crew will complete shift turnover and Swap from 2A CBP to 2C CBP. Unit /LOCA Load Shed switches will have to be swapped also.

Objectives:

SCO - Directs performance of 2OP-32, Section 8.6.

RO - Completes 2OP-32, Section 8.6.

Success Path:

Condensate Booster pumps swapped IAW 2OP-32, Section 8.6.

Simulator Operator Actions:

Acknowledge requests as the RW Operator.

When requested, initiate Trigger 1 to disable the 2C CBP LOCA/Unit Trip Load Shed switches.

When requested to check oil level of 2C CBP, report proper oil levels have been verified.

When requested to perform step 9 (venting the mechanical seals) report that it has been completed.

When requested to open HWCH-SV-5719, initiate Trigger 11, and report that the valve is open.

When requested, initiate Trigger 2 to enable the 2C CBP LOCA/Unit Trip Load Shed switches.

When requested to close the HWC condensate H2 injection isolation solenoid valve report that the valve is closed.

Required Operator Actions Normal Ops - Perform 2OP-32, Section 8.6 to swap CBPs.

SRO Time Action Notes Direct 2OP-32, Section 8.6 to be performed.

RO Time Action Notes Plant Monitor May be asked to perform IV for steps from the operating procedure.

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EVENT 1 (Contd) SWAPPING CBPs BOP Time Action Notes Verifies Initial conditions in 2OP-32, Section 8.6. , Verifies a condensate booster pump is in service.

Per note three condensate pumps must be operation if condensate flow is greater than or equal to 14,400 gpm.

Verifies 3 condensate pumps are not needed.

Flow indication of CO-FV-49 is <14,400 gpm.

NOTIFY Radwaste operator to perform the following:

1. Place an additional CFD in service to prevent override or bypass condition during condensate pump transfer

2. Place an additional CDD in service as necessary.

Determines step 2 & 3 are N/A.

PLACE standby condensate booster pump mode selector switch in MAN AND CHECK its discharge valve closes.

Direct an AO to place the following switches in DISABLED for the 2C Condensate Booster Pump:

• Unit Trip Load Shed Selector Switch

• LOCA Load Shed Selector Switch.

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EVENT 1 (Contd) SWAPPING CBPs BOP Contd Time Action Notes Direct an AO to ensure proper level in associated condensate booster pump oil reservoir Determines step 7 & 8 are N/A.

Directs an AO to perform step 9.

START 2C condensate booster pump AND OBSERVE its discharge valve opens.

NOTE:

The start/stop control switch for a condensate booster pump must be held in START until the recirculation valve is full open.

Direct an AO to OPEN HWC condensate H2 injection isolation solenoid valve at HWC local Panel H2J, for condensate booster pump just started.

CONDENSATE BOOSTER PUMP 2C H2 INJECTION ISOLATION VALVE, HWCH-SV-5719 WHEN condensate booster pump discharge pressure stabilizes, THEN STOP selected condensate booster pump AND PLACE its mode switch in AUTO Direct an AO to place the following switches in ENABLED for the 2A Condensate Booster Pump:

• Unit Trip Load Shed Selector Switch

• LOCA Load Shed Selector Switch.

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EVENT 1 (Contd) SWAPPING CBPs BOP Contd Time Action Notes Determines steps 14, 15 and 16 are N/A.

NOTIFY Radwaste operator to remove the additional CFD or CDD placed in service in Step 8.6.2.1.

Direct an AO to CLOSE HWC condensate H2 injection isolation solenoid valve for the 2A condensate booster pump.

CONDENSATE BOOSTER PUMP 2A H2 INJECTION ISOLATION VALVE, HWCH-SV-5717 NOTIFY Radwaste operator to monitor CDD effluent conductivity for each demin in service.

May update the LOCA / Unit Trip Load Shed placard with the 2A CBP enabled and the 2C CBP disabled.

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EVENT 2 TRIP OF MCC 2TD The crew will respond to a trip of MCC 2TD with the standby stator cooling water pump failure to auto start. The standby stator cooling water pump can be manually started. The 2D air compressor will also be lost and 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures, may be entered.

Objectives:

SCO - Direct the standby Stator Cooling Water pump to be started.

BOP - Start the standby Stator Water Cooling pump with an automatic initiation signal present.

Success Path:

Standby Stator Cooling Water Pump started and actions of 0AOP-20.0 Pneumatic (Air/Nitrogen) System Failures, addressed.

Simulator Operator Actions:

When the directed by the lead examiner, initiate Trigger 3 to trip the feeder breaker to MCC 2TD.

When asked as the TB AO to investigate the 2F feeder breaker trip, report a trip of the feeder breaker to MCC 2TD, (ATO) on 480V Substation 2F is tripped with the white overcurrent indicating flag protruding from the breaker.

If asked as I&C to investigate, acknowledge any requests. If asked do not recommend re-energizing 2TD until an investigation can be completed.

If asked to investigate/acknowledge the 2B RFP alarm, acknowledge the local panel alarm and report that the alarm on the local panel is HPU Pump 2 Running in Stby. If asked the standby pump is operating with no problems noted.

If dispatched to verify proper operation of the standby Stator Water Cooling Water Pump or the 2B air Compressor, report no problems with the operation of the pump/compressor are noted.

If contacted as U1, report that the 1D air compressor is not running. If asked to start the 1D Air Compressor initiate Trigger 10, and report 1D air compressor is running. After air pressure returns to normal the 1B will auto shutdown (go into standby).

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

Required Operator Actions Component Failure - Start the standby Stator Cooling Water pump when the auto action did not occur.

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EVENT 2 (Contd) TRIP OF MCC 2TD SRO Time Action Notes Acknowledges report of alarms received/cleared for the BOP/RO.

Directs BOP operator to start the standby stator water cooling pump.

May ask for I&C to investigate

1) The trip of the feeder breaker to 2TD

2) The failure of the standby Stator Water Cooling pump to auto-start.

May direct entry into 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures,.

May review the load list for MCC 2TD (0OI-50.11).

RO Time Action Notes Plant Monitor Report alarms to the SCO. RFP alarm may be addressed by the BOP.

UA-13, 6 RFP B Control Trouble A-7, 6 Fluid Drive B Lube Oil Press Lo (In and then cleared on standby pump auto starting)

May Dispatch an AO to investigate the RFP alarm may be addressed by the BOP.

alarm on the 2B RFP.

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EVENT 2 (Contd) TRIP OF MCC 2TD BOP Time Action Notes Report alarms to the SCO.

UA-6, 2 Sub 2F 480V Feeder Bkr Trip UA-13, 6 RFP B Control Trouble UA-1, 3 Air Compr D Trip UA-2, 1 Stat coolant Inlet Flow-Low UA-2, 1 Loss of Stat Coolant Trip Ckt Ener UA-2, 2 Stat Coolant Press-Low UA-2, 6 Exciter Coolant Flow-Low Start the standby Stator Water Cooling Action to start the pump is in the APPs, or Pump. an auto action that did not occur.

UA-2, 4 Stator Cool Reserve Pump Running will annunciate on starting of the standby pump and then will clear when the 2A pump is placed in off.

Dispatch an AO to investigate the Sub 2F Feeder Breaker Trip.

May dispatch an AO to investigate the Stator Water Cooling pump that was started.

May enter and announce 0AOP-20.0, Actions for starting the 1D are also in the APP.

Pneumatic (Air/Nitrogen) System Failures, for the trip of 2D Air Compressor.

Verifies that the 2B Air Compressor auto starts. If 1D Air Comp. is started the 2B and 1B air comp.

will go back into a standby condition when the air header pressure is returned to normal.

May ask Unit One to start the 1D Air Compressor and verify 2B returns to standby.

May place the 2D A/C is Stop.

Page 16 of 35

EVENT 3a MG LUBE OIL PMP TRIPS / 2B RECIRC PUMP FAILS TO TRIP The crew will respond to a trip of MG Lube Oil Pump B3 in which the 2B Recirc Pump fails to trip.

Objectives:

SCO - Direct tripping of the 2B Recirc Pump.

RO - Trips the 2B Recirc Pump.

Success Path:

Recirc Pump is tripped.

Simulator Operator Actions:

When the directed by the lead examiner, initiate Trigger 4 to trip the B3 MG Lube Oil Pump.

If asked as I&C to investigate, acknowledge any requests.

If requested as the AO to investigate the MG Set, report that the B3 MG Lube Oil Pump is tripped and lube oil pressure is 15 psig with the Emergency and B2 pumps running.

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

Required Operator Actions Component Failure - Recognizes failure (B3 oil pump) and that the 2B Recirc Pump should have tripped and make the action occur.

Tech Spec 3.4.1 - Condition A, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to comply with the LCO requirements.

SRO Time Action Notes Acknowledge the report of alarms due to the loss of B3 Lube Oil Pump.

Direct tripping of the 2B Recirc Pump.

Direct BOP to enter and announce 2AOP-04.0, Low Core Flow.

Contact I&C to investigate failure of Lube Oil System and Recirc Pump trip failure.

Determines TS 3.4.1, Condition A, Comply with the requirements of the LCO in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Page 17 of 35

EVENT 3a contd MG LUBE OIL PMP TRIPS / 2B RECIRC PUMP FAILS TO TRIP BOP Time Action Notes Plant Monitor RO Time Action Notes Report alarms to the SCO.

A-7, 1-6, Fluid Drive B Scoop Tube Lock A-7, 6-4, Fluid Drive B Lube Oil Press Lo Recognize failure of the B3 Lube Oil Pump.

Recognize failure of the 2B Recirc Pump to trip on low oil pressure.

Trips the 2B Recirc Pump.

A-7, 5-5, Pump B Seal Staging Flow Hi/Lo A-7, 4-6, Recirc Loop B Only Out Of Service A-5, 4-8, OPRM Trip Enabled Announce and enter 2AOP-04.0, Low Core Flow.

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EVENT 3b INSERT CONTROL RODS TO EXIT SCRAM AVOIDANCE REGION The crew will respond to the tripping of the 2B Recirc Pump which puts the Unit in the scram avoidance region of the power to flow map requiring the crew to insert control rods to exit the region.

Objectives:

SCO - Direct the RO to exit the Scram Avoidance Region IAW 2AOP-04.0.

RO - Inserts control rods to exit the Scram Avoidance Region.

Success Path:

Scram avoidance region of the power to flow map exited.

Simulator Operator Actions:

If contacted as the RE for power reduction guidance, Ask for the SROs recommendation for the power reduction and then concur with the recommendation given.

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

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

Required Operator Actions Reactivity - Inserts control rods to exit the scram avoidance region of the power to flow map.

SRO Time Action Notes Notify RE of 2B RR Pump Trip.

Direct power reduction to exit scram avoidance region IAW 2AOP-04.0 and 0ENP-24.5.

BOP Time Action Notes Plant Monitor 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 Oclock.

(May have to perform this several times)

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EVENT 3b (Contd) INSERT CONTROL RODS TO EXIT SCRAM AVOIDANCE REGION RO Time Action Notes Request peer checker / reactivity team.

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 Oclock.

(May have to perform this several times)

Inserts control rods using 0ENP-24.5 to exit the Scram Avoidance Region.

Turns control rod power on.

Selects control rod in accordance with 0ENP-24.5 sheet.

(See attachment 1 for the rods to insert, Page 34)

Continuously drives selected rod in using RMCS.

Repeats steps as needed to insert rods to exit the scram avoidance region.

May Raise recirc flow on the 2A RR Pump to exit the Scram Avoidance Region.

Adjusts the potentiometer clockwise to raise the flow on the A recirc loop.

Must stay below 45 Mlbs/Hr and greater than 30.8 Mlbs/Hr while maintaining power less than 50%.

Page 20 of 35

EVENT 4 RB EXHAUST FAN TRIP The crew will respond to a trip of the 2A Reactor Building Exhaust Fan.

Objectives:

SCO - Directs Standby RB Exhaust Fan to be started BOP - Refers to 2-UA-5 1-10 and starts standby RB Exhaust Fan Success Path:

Starting the 2D RB Exhaust Fan.

Simulator Operator Actions:

At the discretion of the lead evaluator, initiate Trigger 5 to trip the 2A RB Exhaust Fan.

If directed as the RB AO to investigate fan trip, report RB Exhaust fan breaker is tripped on an overload. If asked to attempt to reset report that the breaker will not reset.

If contacted as the RB AO, inform the control room prestart checks of the 2D RB Exhaust Fan are complete.

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

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

Required Operator Actions Component failure - Trip of the 2A RB Exhaust Fan requiring a start of the 2D RB Exhaust Fan.

SRO Time Action Notes Directs BOP operator to enter Annunciator response for 2-UA-5, 1-10.

Directs start of 2D RB Exhaust Fan.

Directs Maintenance to investigate 2A RB Exhaust Fan Trip.

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EVENT 4 (Contd) RB EXHAUST FAN TRIP RO Time Action Notes Plant Monitoring BOP Time Action Notes Recognize the failure of the 2A RB Exhaust Fan.

Reports and refers to Annunciator Response UA-5 1-10.

Manually starts 2D RB Exhaust Fan.

Dispatches AO to investigate cause of fan trip.

Verifies RB pressure is maintained negative during evolution.

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EVENT 5 DRIFTING CONTROL ROD The crew responds to a drifting control rod.

Objectives:

SCO - Direct actions in response to a drifting control rod and evaluate Tech Specs.

BOP - Respond to a drifting control rod Success Path:

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

Simulator Operator Actions:

When directed by the lead evaluator, initiate Trigger 6 to activate the control rod drift of rod 22-11.

If contacted as the RE to address thermal limits, inform crew that you will monitor core performance on the computer.

When the control rod is inserted to 00, initiate Trigger 15 to activate CRD high temperature alarm.

If asked as the RBAO to investigate HCU for control 22-11, report that the HCU scram outlet riser is hot to the touch.

When contacted as the RBAO report that the CRD temperature is 390°F.

When contacted as the System Engineer report that based on past history of this rod (22-11) scram times cannot be guaranteed.

If asked as the RBAO to disarm control rod, activate TRIGGER 12 and delete the rod drift malfunction.

Required Operator Actions Insert and disarm control rod 22-11.

Tech Spec 3.1.3 Control Rod Operability Condition C. One or more control rods inoperable for reasons other than Condition A or B Required Action C.1 Fully insert inoperable control rod (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)

C.2 Disarm the associated CRD (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

Page 23 of 35

EVENT 5 (Contd) DRIFTING CONTROL ROD SRO Time Action Notes Direct actions of 2APP-A-05 (3-2) ROD DRIFT.

Direct entry into 0AOP-02.0, Control Rod Malfunction/Misposition According to Note 2 in TS Table 3.1.4-1 the rod must be declared inoperable.

Tech Spec 3.1.3 Control Rod Operability Condition C. One or more control rods inoperable for reasons other than Condition A or B Required Action C.1 Fully insert inoperable control rod (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)

C.2 Disarm the associated CRD (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

Contact System Engineer on high temperature condition of control rod.

May direct the control rod to be scrammed to attempt to reseat the leaking outlet valve.

BOP Time Action Notes Plant Monitoring Page 24 of 35

EVENT 5 (Contd) DRIFTING CONTROL ROD RO Time Action Notes Acknowledge and ROD OUT BLOCK alarm Announce and enter AOP-2.0, Control Rod Malfunction/Misposition Perform the actions of APP-A-05 (3-2)

ROD DRIFT as follows:

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

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

Check and adjust cooling water header pressure if required Direct AO to check for leaking scram valve Monitor core parameters, main steam line radiation and off-gas activity Page 25 of 35

EVENT 6a FUEL FAILURE / RRCP / SCRAM Fuel failure will occur. When the Main Stack Rad indication is rising then a reactor scram and Group I isolation is inserted. Reactor Scram Pushbutton B is failed, other methods are available (i.e. ARI).

Objectives:

SCO - Directs actions for a Reactor Scram, and RRCP.

RO - Insert a reactor scram when directed IAW RRCP.

BOP - Ensure CREV is initiated.

Success Path:

Rods inserted with ARI.

Simulator Operator Actions:

When directed by the lead evaluator, initiate Trigger 7 to activate Fuel failure.

When the ramp timer for trigger 7 is timed out and the lead evaluator is ready initiate Trigger 8 to activate the Gross Fuel Failure.

When directed as AO to align TB HVAC form once through to recirc alignment wait 15 minutes, initiate Trigger 13 and report alignment to Control Room.

When requested as Unit 1 to stop Unit 1 Cable Spread Vent Fans, initiate Trigger 14.

When requested as Unit 1 to stop CB Mechanical Equipment Room Vent Fan initiate Trigger 16.

Monitor MSL Rad and as power is reduced, adjust Fuel Failure and Gross Fuel Failure to ensure MSL Hi-HI is received. (If NB005F reaches 100, Manually initiate Trigger 8)

If PEP-3.4.7 is requested, acknowledge the request.

If asked as E&RC, acknowledge the request to obtain actual/projected off site dose rates.

If asked as E&RC, acknowledge the request to sample off gas and reactor coolant for potential fuel damage.

If asked as E&RC, acknowledge the request to obtain noble gas dose rates.

When fuel failure reaches 100%, proceed to the next event.

Required Operator Actions Insert control rods. (critical task)

Page 26 of 35

EVENT 6a (Contd) FUEL FAILURE / RRCP / SCRAM SRO Time Action Notes May direct BOP to announce and enter 0AOP-05.0.

(May evacuate areas)

Enters RRCP on report of UA-03 5-2.

Asks Unit One to calculate site boundary dose per PEP-3.4.7.

Direct BOP to place CREV in service Direct alignment of TB HVAC from once through to recirc alignment Ensure AOG in service Notify E&RC to sample off- gas and reactor coolant for potential fuel damage.

When UA-03 4-2 is received:

Verifies Main Stack Rad levels rising.

Ensures AOG bypass valve is closed.

May direct a power reduction When UA-23 3-6 is received, Directs Critical Task the insertion of a manual scram.

(May direct sooner as a conservative decision)

Directs the closure of Group I valves (MSIVs, Steam Line Drains (B21-F016 and F019) and Recirc Sample Valves (B32-F019 and F020)

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EVENT 6a (Contd) FUEL FAILURE / RRCP / SCRAM RO Time Action Notes Recognize failure of manual scram channel B Initiates ARI per the Scram Hard Card. Critical task Perform immediate actions for Reactor scram 6

After steam flow is less than 3 x 10 lb/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 Close Group I Isolation valves. Critical Task Closes MSIVs Closes Main Steam Line Drain valves B21-F016 and F019.

Closes Reactor Recirc Sample Valves B32-F019 and F020 Operate SRVs as directed to stabilize pressure and control pressure as directed by the SCO.

Page 28 of 35

EVENT 6a (Contd) FUEL FAILURE / RRCP / SCRAM BOP Time Action Notes Report Annunciators when received UA-03 5-7 UA-03 5-2 UA-23 2-6 UA-23 3-6 May announce and enter 0AOP-05.0.

May evacuate turbine building Manually start CREV per the Hard Card.

Place one of the CB Emerg Recirc Fans, 2A(B)-ERF-CB, in ON.

Ensure CTL Rm Norm MU Air Dmpr, 2L-D-CB, closes.

Ensure CB Emerg Recirc Damper, VA-2J-D-CB, opens.

Stop CB Washroom Exhaust Fan, 2D-EF-CB, and ensure associated damper closes.

Stop CB Mechanical Equip Room CB Mechanical Equip Room Vent Fans Vent Fans 2F-SF-CB and 2E-EF-CB, can be stopped only by simultaneously and ensure associated supply and placing both Units' control switches in exhaust dampers close. OFF Stop Cable Spread Room 2 Vent Fans 2A-SF-CB-and 2A-EF-CB, and ensure associated supply and exhaust dampers close.

Direct Unit One to Stop Cable Spread Room 1 Vent Fans 1A-SF-CB and 1A-EF-CB, and ensure associated supply and exhaust dampers close Page 29 of 35

EVENT 7 PCCP Entry SRVs will be used to control reactor pressure raising the temperature of the suppression pool. PCCP will be entered and Suppression Pool cooling placed in service. The E11-F024A valve will fail not allowing SPC on A Loop to be placed in service.

Objectives:

SCO - Directs PCCP actions and establish a cooldown.

BOP - Place SPC in service.

Success Path:

Suppression Pool Cooling is in service.

Simulator Operator Actions:

If asked as I&C to investigate E11-F024A failure, acknowledge request When suppression pool cooling has been established and F024A valve failure recognized the scenario may be terminated.

Required Operator Actions Recognize valve failure (E11-F024A)

SRO Time Action Notes Recognize rising suppression pool temperature and enter PCCP.

Direct initiation of suppression pool cooling (Hardcard)

Enter and direct RVCP.

Direct reactor water level band of 170-200 inches.

Direct reactor pressure band of 800 -

1000 psig.

Direct a cooldown, not to exceed 100°F/hr.

Page 30 of 35

EVENT 7 (Contd) PCCP Entry RO Time Action Notes Place RHR Loop A into suppression pool cooling.

• Open SW-V101

• Close SW-V143

• If LOCA signal is present place RHR No LOCA signal present SW Booster Pumps A & C LOCA override switch to manual override

• Start RHRSW Pump (may start both)

• Adjust E11-PDV-F068A (1 pump 2000 - 4000 gpm) (2 pumps 5000 -

8000 gpm)

• Supply Clg Wtr to Vital Hdr

• Verify spray logic is made up

• Start Loop A RHR Pmp (may start both)

• Open E11-F028A

• Throttle E11-F024A (Valve will get a overload when attempted to open)

Place RHR Loop B into suppression pool cooling.

• Open SW-V105

• Close SW-V143

• If LOCA signal is present place RHR No LOCA signal present SW Booster Pumps B & D LOCA override switch to manual override

• Start RHRSW Pump (may start both)

• Adjust E11-PDV-F068B (1 pump 2000 - 4000 gpm) (2 pumps 5000 -

8000 gpm)

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

• Verify spray logic is made up

• Start Loop B RHR Pmp (may start both)

• Open E11-F028B

• Throttle E11-F024B. (Valve will get a overload when attempted to open)

Inform SRO of overload on F024A or B valve Page 31 of 35

EVENT 7 (Contd) PCCP Entry BOP Operate SRVs to maintain reactor pressure in the established pressure band.

Establishes a cooldown not to exceed 100°F/hr Maintain reactor water level 170 - 200 inches.

Page 32 of 35

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 35

Attachment 1 ENP-24.5 Form FORM 2 Immediate Reactor Power Reduction Instructions Sheet _1_ of _2_ (Control Rod Insertions ONLY) SRO ______

Control Correct Rod Control Rod Licensed Second Approximate Rod Selected and Position Operator Licensed  % CTP Verified* Operator 26-35 / 08 to 00 26-19 / 08 to 00 18-27 / 08 to 00 34-27 / 08 to 00 59%

/

18-35 / 12 to 00 34-19 / 12 to 00 34-35 / 12 to 00 18-19 / 12 to 00 56%

/

26-27 / 16 to 00 55%

/

18-43 / 16 to 00 34-11 / 16 to 00 34-43 / 16 to 00 18-11 / 16 to 00 51%

/

10-35 / 16 to 00 42-19 / 16 to 00 42-35 / 16 to 00 10-19 / 16 to 00 48%

/

/

Page 34 of 35

Attachment 1 ENP-24.5 Form FORM 2 Immediate Reactor Power Reduction Instructions Sheet _2_ of _2_ (Control Rod Insertions ONLY) SRO ______

Control Correct Rod Control Rod Licensed Second Approximate Rod Selected and Position Operator Licensed  % CTP Verified* Operator 26-43 / 48 to 00 26-11 / 48 to 00 10-27 / 48 to 00 42-27 / 48 to 00 37%

/

10-43 / 48 to 00 42-11 / 48 to 00 42-43 / 48 to 00 10-11 / 48 to 00 30%

/

/

/

/

Page 35 of 35