ML070310164

Final - Section C Operating Exam (Folder 3)

ML070310164
Person / Time
Site:	Indian Point
Issue date:	11/01/2006
From:	NRC Region 1
To:	Entergy Nuclear Operations
Sykes, Marvin D.
References
ES-D-1
Download: ML070310164 (73)

Text

Appendix D Scenario Outline Form ES-D-I Facility:

Indian Point 3 Scenario No:

1 Op-Test No: 1 Examiners:

Operators:

I Initial Conditions:

Scenario begins at 6% power with turbine close to sync speed. The team will continue with the startup by synchronizing the unit to the grid and increasing power.

Turnover:

Continue with the startup. Synchronize the unit to the grid and increase power at 150 MW per hour.

Event No:

1 2

3 4

5 6

Malf.

No.

N/A XMT-RCS052 MAL-SGN005D MAL-SGN005D MAL-EPSOO6 MAL-S I S004A MAL-SIS004C MAL-SGN004P Event Type*

N (BOP)

N (CRS)

R (CRS)

R (ATC)

I (ATC)

I (CRS)

C (ALL)

M (ALL)

C (BOP)

C (BOP)

C (ATC)

Event Description Sync turbine and raise power Thot fails high. CRS references TS SG Tube Leak. CRS references TS SGTR - Manual reactor trip and manual SI actuation Loss of offsite power when 6.9 KV busses transfer 31 and 33 SI pump auto start failure SG safety fails open on ruptured SG

Scenario Event Description NRC Scenario #I Scenario begins at 6% power with turbine close to synchronous speed. The team has received a turnover and has been allowed to review procedures, reactivity data, and perform a brief prior to entering the simulator. The team will continue with the startup by synchronizing the unit to the grid and increasing power.

After a sufficient power increase has been observed, loop 4 Tave will fail high due to Thot instrument failing high. The team will respond per AOP-INST-I, InstrumentlController Failures. During the AOP-INST-1 actions, a 20 gpm SGTL will develop on 34 SG. The team will respond per AOP-SG-1. The leak will then increase in size and the team will manually trip the reactor and actuate Safety injection.

The Station Auxiliary Transformer will fault when 6.9KV buses transfer from the Unit Aux Transformer to the Station Aux Transformer following the trip. EDGs will start and energize the 480V buses. 31 and 33 SI pumps will fail to auto start and will be manually started later by the BOP operator.

During execution of E-0, a SG safety valve on 34 SG will fail open. The team will diagnose a faulted SG and go to E-2, Faulted SG Isolation. In E-2, the team will isolate steam flow from and feed flow to 34 SG and then transition to E-3 due to secondary radiation. The team will progress through E-3 until directed to transition to ECA-3.1, SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired.

The scenario will be terminated when the team has initiated a controlled cooldown in ECA-3.1.

Procedure Flow Path: POP-I.3, 3-SOP-TG-004, AOP-INST-1, AOP-SG-1, EOP E-0, E-2, E-3, ECA-3.1

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Setup Scenario 1 NRC-1.bat A MAL-SIS004C IMF MAL-SIS004C (-1 0) 1 IMF MAL-SIS004A (-1 0) 1 A XMT-RCSO52 HOT LEG NR MICROPROC LOOP 4 TEMPERATURE IMF XMT-RCS052 (I

0) 640.000000 0 551.284973 A MAL-SGN005D IMF MAL-SGNOOSD (2 0) 1.OOOOOO 0 0.000000 TRG 3 "IMF MAL-SGNOOSD (3 0) 8.000000 0 0.000000" IMF MAL-SGN004P (4 0) 0.000000 0 0.000000

• MAL-EPSOOG IMF MAL-EPSOOG (30 30) TRUE SAFETY INJECTION PUMP 33 FAILURES MAL-SIS004A SAFETY INJECTION PUMP 31 FAILURES STEAM GENERATOR 34 TUBE LEAK MAL-SGN005D STEAM GENERATOR 34 TUBE LEAK MAL-SGN004P STEAM GENERATOR SAFETY VALVE FAILURE (MS-45D)

LOSS OF STATION AUX TRANSFORMER TRGSET 30 I'jpplp4(l).eq.l"

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario 1 I Setup/Event IC Reset SES Setup Batch File t-- Floor Setup Event 1 Role Play Event 2 Role Play Event 3 Role Play L Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS 8

Run setup batch file NRC-l.bat and verify malfunctions and over-rides have been entered Perform setup checklist Role play various personnel contacted during startup activities Actuate Trigger 1 At lead evaluator direction If I&C requested of other personnel outside CCR Actuate Trigger 2 At lead evaluator direction When Chemistry contacted When HP and OM notified When NPOs contacted

____ ~

~~~

EXPECTED RESPONSE/INSTRUCTOR CUES Reset Simulator to IC 8 Plant startup in progress, ready to sync to grid Synchronize the generator to the grid, raise power, transfer 6.9KV buses Perform field action LOAs as requested during the startup.

• XMT-RCS052 HOT LEG NR MICROPROC LOOP 4 TEMPERATURE IMF XMT-RCS052 (1 0) 640.000000 0 551.284973 Acknowledge request or reports. I&C will complete troubleshooting or repairs before scenario ends

• MAL-SGN005D IMF MAL-SGN005D (2 0) 1.OOOOOO 0 0.000000 STEAM GENERATOR 34 TUBE LEAK Wait 15 minutes before reporting leak rate =

30,000 gpd Acknowledge report Perform requested LOAs to isolate secondary side

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario I SetupJEvent Event 4,5, 6

Role Play Event 7 Role Play Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS Actuate Trigger 3 At lead evaluator direction If ConEd contacted regarding status of offsite power Actuate Trigger 4 When the BOP operator starts RO-1 Perform actions as directed by CCR EXPECTED RESPONSE/INSTRUCTOR CUES LEAK TRG 3 "IMF MAL-SGN005D (3 0) 8.000000 0 0.000000" MAL-EPSOOG LOSS OF STATION AUX TRANSFORMER TRGSET 30 "jpplp4(l).eq.l" MAL-SGN005D STEAM GENERATOR 34 TUBE IMF MAL-EPSOOG (30 30) TRUE ConEd responds that offsite power is available to the station and the problem must be with stain equipment. ConEd equipment is not affected.

A MAL-SGNOO4P STEAM GENERATOR SAFETY VALVE FAILURE (MS-45D)

IMF MAL-SGN004P (4 0) 0.000000 0 0.000000 Perform various LOA'S per NPO local task list Locally isolate 34 SG when the NPO is diwatched.

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 1 Watch Team Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

Condition:

% Power:

MW Gross:

Boron Conc:

Control Rods TODAY 550.5 O F 2235 psig 26 %

Mode 1 6%

0 1488 ppm 11 8 steps CBD Plant Status:

Plant is performing startup after refueling:

0 0

POP-1.3 in progress at step 4.42 SOP-TG004 in progress at step 4.2.15

1. No equipment out of service.

2. Continue startup:

0 Synchronize unit to grid 0

Raise power to 45% at 150 MWe per hour

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Sync turbine and raise power Position CRS RO BOP i

o n

s or Behavior Continue Plant Startup per 3-POP-I.3 Plant Startup from Zero to 45%

Power, step 4.42 Direct crew actions to synchronize the generator to the grid and raise reactor power 0

Direct reactivity changes 0

Supervise synchronizing the generator 0

Direct RO to block NIS Rod Stop and Trips when P-10 light illuminates 0

Supervise transfer of 6.9 KV bus power supply Control reactor power using control rods and steam dumps 0

Coordinate with BOP to control SG feed rate during load changes to maintain SG level. Adjust bypass Feedwater regulating valves.

0 Maintain Tavg on program using control rods in manual 0

Block NIS PR and IR Rod Stop and Trips when P-IO light illuminated Synchronize the generator to the grid using SOP-TG-004 Match voltages and frequency (turbine speed) 0 Close generator output breaker 0

Operate turbine controls to load turbine to - 30 MWe 0

Coordinates load changes with RO to control SG feed rate

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Sync turbine and raise power Time 1 Position BOP Lead Evaluator Transfer 6.9 KV buses 1-4 to the Unit Aux Transformer Uses SOP-EL-005 section 4.3 0

Adjust tap changer w

Operate Sync Scope switch Operate Bus 1-4 Normal Feed Breakers Operate Bus 1-4 Tie Breaker Proceed to the next event when sufficient power increase has been evaluated Direct the Booth Instructor to actuate Trigger 1

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Thot fails high.

I Position RO CRS BOP Applicants Actions or Behavior Diagnose Tave Instrument failure 0

From memory performs AOP-INST-I immediate actions (verifies control systems on flight panel are stable and places in manual if necessary) 0 Place charging pump speed control to manual Place rod control to manual 0

Control charging pump speed to maintain pressurizer level in normal band per graph RCS-2 Directs team to perform immediate actions of AOP-INST-1, I nstrument/Control ler Fai I ures 0

Verifies immediate actions performed 0

Verifies rod control and charging pump speed control are in manual 0

Performs procedure section for RCS Temperature Instrument failure Evaluate Technical Specification 3.3.1 - requires placing associated bistables to trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Perform ARP for alarms associated with instrument failure 0

HighTave 0

OP-DeltaT CH Trip or Rod Stop 0

OT-DeltaT CH Trip or Rod Stop 0

Delta-T Deviation 0

Tavg Deviation 0

Tavg Tref Deviation 0

Pressurizer Low Level

Appendix D Required Operator Actions Form ES-D-2 I

I Op-Test No: 1 Scenario No: 1 Event No.: 2 Page 2 of 2 I

I Event

Description:

Thot fails high.

Time -

Position BOP RO Lead Evaluator Defeat Loop IV Delta-T (rack B-8)

Defeat Loop IV Tavg (rack D-8)

Return control of charging pump speed to auto (if desired)

Proceed to the next event when CRS has evaluated Technical Specifications and determined BS must be tripped, or at the discretion of the lead evaluator.

Direct the Booth Instructor to actuate Trigger 2

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No:

1 Scenario No: I Event No.: 3 I

I Event

Description:

SG Tube Leak -20GPM on 34 SG.

Time -

Position BOP CRS ALL RO Applicants Actions or Behavior Diagnose alert alarm and rising trend on R-I 5, SJAE Exhaust Radiation Monitor (alert alarm occurs 2-3 minutes after event is initiated).

Enters AOP-SG-1, Steam Generator Tube Leak 0

Directs crew actions to estimate the size of the leak and minimize secondary contamination 0

Directs Chemistry to calculate leak rate 0

Notifies HP of SGTL 0

Determines shutdown must be made 0

Develops shutdown plan to remove the unit from service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Evaluate Technical Specification 3.4.1 3 RCS Operational Leakage 0

Determine Condition A applies because primary to secondary exceeds limit - reduce leakage to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hrs Diagnose leak rate is approximately 20 GPM Monitors Pressurizer Level and Pressure for abnormal trends due to SGTL. If level is lowering:

0 If desired, reduces letdown flow to 45 gpm 0

If desired, starts a second charging pump.

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No:

1 Scenario No: 1 Event No.: 3 I Event

Description:

SG Tube Leak -20GPM on 34 SG.

Time -

Posit ion BOP Lead Evaluator p

Coordinates with RO to reduce letdown to 45 GPM, if desired 0

Open200A 0

Close 2006 and 200C 0

Verify PCV-135 controlling between 225 and 275 psig Estimate leak rate using Attachment-I, Initiates AOP-SG-1 Attachment 3 Secondary Side Isolation to minimize secondary side contamination and radioactivity release.

Proceed to the next event when the CRS has developed a shutdown plan, or at the discretion of the lead evaluator.

Direct the Booth Instructor to actuate Trigger 3

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Steam Generator Tube Rupture. Loss of Offsite power occurs when 6.9KV buses transfer. 31 and 33 SI pumps auto start failure.

Position RO CRS RO BOP CRS CRS RO Applicants Actions or Behavior Diagnose increased leak rate, lowering pressurizer pressure and lowering pressurizer level 0

Determine IAAT Step 4.1 applies - Reactor power is leak rate is > 50 gpm.

50% and Verify that IAAT step 4.1 is met 0

Direct the RO to trip the reactor and verify reactor is tripped 0

Direct BOP to manually actuate SI 0

Direct team to perform immediate actions of E-0, Reactor Trip or Safety Injection Verify reactor is tripped Verify turbine is tripped Verify Safety Injection is actuated Verify 480 V safeguards buses are energized 0

Diagnose loss of offsite power-all 480V buses energized by the emergency diesel generators Verify immediate actions using the procedure Direct RO and BOP actions during use of EOPS Check status of AFW flow to SGs

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Steam Generator Tube Rupture. Loss of Offsite power occurs when 6.9KV buses transfer. 31 and 33 SI pumps auto start failure.

Lead Evaluator Posit ion BOP nt's Actions or Behavior Perform RO-1, BOP Operator Actions During Use of EOPs Monitor CR Annunciators Verify SI Pumps - Starts 31 and 33 SI Pumps 0

Verify FCU status 0 Verify SI valve alignment 0

Verify ABFP status Verify ABFP valve alignment 0

Verify CCW pump status 0

Verify ESW status 0

Verify Containment Isolation status Verify Containment Ventilation status 0

Verify EDG status Verify CCR Ventilation status 0

Verify Emergency DC Oil pump status 0

Reset SI 0

Reset MCCS 0

Check with CRS to see if additional actions are required Proceed to the next event when the BOP operator has commenced RO-

1.

Direct the Booth Instructor to actuate Trigger 4

Appendix D Required Operator Actions Form ES-D-2

~~

~~~

Op-Test No: 1 Scenario No: 1 Event No.: 7 Event

Description:

Steam Generator Tube Rupture I

Page 1 of 5 Booth Instructor RO CRSIRO A

p p

l i

c a

n t

s Actions or Behavior Aji?er the BOP operator commences RO-I, execute Trigger 4 to fail open a safety valve on 34 SG.

Diagnose rising level in 34 SG. Using prudent operator action, isolates AFW flow to 34 SG.

Continue E-0 actions:

Verify Feedwater Isolation Verify SI Flow Verify CS not required Check RCP seal cooling Verify RCP stopped Establish Charging Flow 0

Dispatch NPO to align backup cooling 0

Check HCV-142 full open 0

Check 204B open 0

Open LCV-112B 0

Close LCV-112C 0

Start one charging pump and adjust to manual maximum speed until NPO has aligned backup cooling Check RCS temperatures stable (expected is no) 0 Reduce AFW Flow 0

Stop dumping steam 0

Close all MSlVs Check RCPs stopped Check PORVs, Safety Valves and Spray valves Determine if SGs are faulted 0

Diagnose 34 SG faulted40 to E-2

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Steam Generator Tube Rupture Time

~~~

~

Position CRStRO Critical Task CRSIRO CRS Perform E-2, Faulted SG Isolation 0

Check MSlVs and bypass valves closed 0

Check 31, 32, 33 SGs intact 0

Identify 34 SG faulted 0

Isolate Faulted SG Check 32 and 33 SGs intact Isolate Main Feedwater FRV or MOV Isolate Bypass Feedwater FRV or MOV Isolate AFW Verify Atmospheric steam dump closed Close SG Blowdown isolation valves Close SG sample valves Isolate MSlV upstream steam traps WOG CT: E-Z--A Isolate the faulted SG before transition out of E-2 Check secondary radiation 0

Check seismic event not occurred 0

Direct chemistry to sample SGs 0

Direct HP to survey SG steamlines and SGBD lines Reset SG Sample lines 0

Check secondary radiation o Go to E-3, Steam Generator Tube Rupture Direct the crews actions in E-3, Steam Generator Tube Rupture

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: 1 Event No.: 7 Page 3 of 5 Event

Description:

Steam Generator Tube Rupture Time -

Position CRStRO Critical Task ALL Determine if RCPs should be stopped Identify ruptured SG Isolate Flow from ruptured SG Adjust 34 SG atmo controller to 1040 psig Check 34 SG atmospheric closed Check 32 and 33 SGs intact Verify blowdown isolation valves closed Dispatch NPO to locally isolate ruptured SG using posted aid Ensure ruptured (34) SG MSlV and bypass closed Check ruptured SG isolated from at least one other SG Check 34 SG level > 9%, then stop feed flow to 34 SG NOTE: Keeps AFW Flow isolated due to to FaultedlRuptured SG WOG CT: E-3--A Isolate feedwater flow to and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

Check PORVs and Block valves Determine if SGs are Faulted Check all faulted SGs isolated Check intact SG levels Reset SI Reset Phase A Reset and open IA to containment PCV-1228 Stop RHR pumps Check Ruptured SG > 400 psig Transition to ECA-3.1, SGTR With Loss of Reactor Coolant -

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: I Event No.: 7 Event

Description:

Steam Generator Tube Rupture Page 4 of 5 Time -

Position CRS CRSIRO BOP 3

B e

havio r Direct the crews actions in ECA-3.1 SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired.

Reset SI Reset Phase A Open 1228 Check 480V bus status and MCCs and lighting reset Check CS status Check 34 SG level - Feed flow should remain isolated per the caution Determine if RHR pumps should be isolated Evaluate Plant Status 0

Initiate Attachment 1 Perform Attachment I, Plant Equipment Status Evaluation

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No: 1 Scenario No: 1 Event No.: 7 Page 5 of 5 Event

Description:

Steam Generator Tube Rupture I

Time -

Position CRSlRO Critical Task Lead Evaluator Check RCP Seal Cooling status Establish Charging flow 0

Start all charging pumps and establish maximum flow Determine if SGs are faulted and previously isolated Check intact SG levels Initiate RCS Cooldown to Cold Shutdown 0

Verify all rods inserted 0

Maintain cooldown rate 100"F/hr in cold legs 0

Dump steam from intact SGs using atmospherics NOTE: IF WR Cold Leg Temperatures lower to transitions to FR-P.l due to Orange Path in Integrity. Terminate the scenario after transition to FR-P. 1 290°F, then WOG CT: ECA-3.1--B Initiate an RCS cool down to cold shutdown conditions at the highest achievable rate but less than 100°F/hr in all RCS cold legs.

If cooldown rate exceeds 10O0F/hr due to the effects of the faulted ruptured SG, then the team demonstrates the ability to monitor the coodown rate and takes no actions to increase it.

Terminate the scenario after the team has demonstrated the ability to monitor and control the cooldown rate, or at the discretion of the Lead Evaluator.

If necessary, administer JPM SRO-A-5

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No:

2 Op-Test No:

1 Examiners :

Operators:

Initial Conditions:

The scenario begins at 100% power with 32 EDG out of service due to malfunctioning governor.

Turnover:

32 EDG out of service due to malfunctioning governor.

Maintain current plant conditions.

Event No:

2 3

4 5

6 7

8 Malf.

No.

~~

MAL-SWS001 C MAL-EPS005C N/A MAL-NIS006A MAL-EPS001 MAL-DSG001A MAL-PRS003D MAL-SWS001 E Event

, T y p e C (BOP)

C (ALL)

R (ATC)

R (CRS)

N (BOP)

N (CRS)

C (ATC)

C(CRS)

M (ALL)

C (BOP)

C (ATC)

C (BOP)

Event Description 33 SWP trips 480V Bus 5A Fault TS required shutdown Power Range Channel 41 Upper Detector Fails High Station Blackout 31 EDG fail to start PRZ PORV Fails Open SW pump does not auto start after bus energized

Scenario Event Description NRC Scenario #2 The scenario begins at 100% power with 32 EDG out of service due to malfunctioning governor. Each crew will be provided turnover information outside of the simulator and allowed to brief prior to entering the simulator.

After the crew has the watch, 33 SWP trips. Team responds per ARP and starts a SW pump. Bus 5A then faults. Team enters AOP-480V-1 to stabilize the plant. CRS evaluates TS and determines shutdown must commence. Shutdown plan is developed and team begins shutdown.

After -50 MWe power reduction, a failure of Power Range channel N41 upper detector occurs. Control Rods auto insert until the ATC operator places rods in manual. The CRS implements AOP-NI-1, Nuclear Instrument Failure to stabilize the plant and perform required actions.

During performance of the subsequent actions of the nuclear instrument failure procedure, a loss of grid and loss of offsite power occur. The unit trips and the crew responds per EOP E-0. 33 EDG is the only diesel running, but bus 5A is faulted and cannot be energized. 31 EDG fails to start. Team diagnoses that no 480V bus is energized and transitions to ECA-0.0, Loss of All AC.

BOP operator manually aligns 32 ABFP to supply AFW flow the SGs.

When RCS pressure rises to PORV actuation setpoint, one PORV fails to close. ATC closes the failed open PORV using the control switch.

When an NPO is dispatched to emergency start EDGs, 31 EDG will start. The associated SW pump will fail to auto start. The BOP operator will start the essential service water pump to provide EDG cooling. The running EDG will then trip.

The team will place auto-start capable equipment in pullout and dispatch an NPO to isolate RCP seal injection and thermal barrier cooling. The team will then proceed to depressurize SGs to minimize RCS inventory loss and cool the RCP seals.

The scenario will be terminated when SG atmos are dumping steam at the maximum rate.

Procedure Flowpath: ARP-SJF, AOP-480V-1, POP-2.1, EOP E-0, ECA-0.0

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Setup Scenario 2 N RC-2. bat A LOA-DSG032 IRF LOA-DSG032 (-1 0) OFF ASWI-DSG006G D/G #32 MAN/OFF/AUTO MODE SWITCH PULL OUT POS 480V BUS N0.6A EMERG. FEED BREAKER CONTRO IOR SWI-DSG006G (-1 0) ON A MAL-DSG001A IMF MAL-DSG001A (-1 0) TRUE A MAL-SWS001 E IMF MAL-SWSOO1 E (-1 0) 1 A MAL-SWS007C IMF MAL-SWS007C (1 0) 20.000000 0 0.000000 A MAL-SWS001 C IMF MAL-SWS001C (1 0) 0 A MAL-EPS005C IMF MAL-EPS005C (2 0) TRUE A MAL-NIS006A IMF MAL-NIS006A (1 0 0) 0.000000 0 5.0 A MAL-EPS001 STATION BLACKOUT IMF MAL-EPS001 (3 0) TRUE DIESEL 31 GENERATOR FAILURE SERVICE WATER PUMP 35 FAILURES SVC WTR PUMP DISCHG CHECK VLV FAILS TO SEAT (SWNl-3)

SERVICE WATER PUMP 33 FAILURES LOSS OF 480 V BUS 5A POWER RANGE CHANNEL 41 DETECTOR A FAILURE A Deletes MAL-DSG001A and resetsktarts 31 EDG TRG 4 "bat IrqsesOl5a.bat"

• Fails 31 EDG again TRG 5 "IMF MAL-DSG001A (-1 0) TRUE" A MAL-PRS003D IMF MAL-PRS003D (3 48) 100.000000 0 0.000000 PRESSURIZER RELIEF VALVE 456 VALVE POSITION FAILURE

/\\Activates trigger 29 when 31 SWP control switch placed in START TRGSET 29 "hwxcoil31 r.eq.1" A Deletes 33 SWP Check Valve malf A Activates trigger 30 when PORV 456 control switch placed in closed TRGSET 30 "hwxeoi327c.eq.l I' A Deletes PORV failed open malf TRG 29 "DMF MAL-SWSOO7C" TRG 30 "DMF MAL-PRS003D"

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario 2 IC Reset SES Setup Batch File Floor Setup Event 1 Role Play 1 Event 3 Role Play Event 4 L

Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS 10 Run setup batch file NRC-

%.bat and verify malfunctions and over-rides have been entered Perform setup checklist Actuate Trigger 1 At lead evaluator direction When NPO is dispatched to investigate Actuate trigger 2 At lead evaluator direction When NPO isdispatched to investigate When various personnel contacted Actuate Trigger 3 1

At lead evaluator direction 1

EXPECTED RESPONSEANSTRUCTOR CUES Reset Simulator to IC 10 Place the control switch for 32 EDG to pullout and apply danger tag. Put protected equipment placards on 31 and 33 EDGs. Update the protected equipment PC display. Risk is yellow.

A MAL-SWS001C IMF MAL-SWSOOlC (1 0) 0 SERVICE WATER PUMP 33 FAILURES Report no abnormalities at the pump. Report unusual odor at the breaker at bus 5A. Breaker tripped on over current.

A MAL-EPS005C IMF MAL-EPS005C (2 0) TRUE LOSS OF 480 V BUS 5A When NPOreports back, state that bus 5A has acrid burnt electrical odor, There is no fire or smoke.

Technical Specification Required Shutdown NPOs Perform LOAs as requested.

When dispatched to swap BA transfer pumps:

Close 360: LOA-CVCO51 Open 370: LOA-CVC052 If maintenance is requested to return 32 EDG to service, report that maintenance will expedite re-assembly of the governor.

A MAL-EPS001 STATION BLACKOUT IMF MAL-EPS001 (3 0) TRUE

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario 2 SetupEvent Role Play Event 5 Event 6 Role Play Role Play Role Play Role Play Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS When ConEd contacted following blackout/loss of grid If NPO dispatched to APP R EDG When NFO is dispatched to emergency start EDGs Activate Trigger 4 PORV 456 Fails Open After 35 SWP has been started and Attachment 1 is in progress, activate Trigger 5 to trip 31 EDG Activate Trigger 5 After 31 EDG trips, NPO contact Control Room When NPO dispatched to break vacuum When NPO dispatched to close 1158-1 or 2 When NPO dispatched to isolate RCP seals EXPECTED RESPONSEDNSTRUCTOR CUES ConEd reports that a widespread system blackout has occurred across NYC, Westchester County, Long Island, and Connecticut Appendix R EDG will not start. Generator Lockout Relay is tripped and will not reset.

Executes batch file bat lrqsesO15a.bat: Deletes MAL-DSG001A and resetdstarts 31 EDG.

Associated ESW pump does not auto start and must be manually started.

Occurs automatically 48 seconds after trigger 3 is actuated.

TRG 5 "IMF MAL-DSG001A (-1 0) TRUE" NPO contact Control Room and inform them that 31 EDG has been tripped Note: Any further attempts to restart 31 EDG are not successful.

Perform LOAs as requested per NPO Local Task Log to break vacuum Perform LOAs as requested per NPO Local Task Log Perform LOAs as requested per NPO Local Task Log to isolate seals

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 2 Watch Team Turnover Sheet:

Da te/Time:

TODAY RCS Temp:

RCS Press:

PZR Level:

Condition:

% Power:

MW Gross:

Boron Conc:

Control Rods 567 OF 2235 psig 45 %

Power Ops 100%

1078 1032 ppm 224 CBD Plant Equipment Status:

1. 32 EDG out of service due to malfunctioning governor.

0 Expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Declared inoperable 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

0 TS LCO 3.8.1 Condition B applies.

0 SR 3.8.1.1 was last performed one hour ago

2. Maintain current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: 2 Event No.:

1 Page 1 of 1 I 1 Event

Description:

33 SWP trips. Team responds per ARP and starts a SW pump.

I Booth Instructor BOP CRS Lead Evaluator

-ants Actions or Behavior P

When Directed by the lead evaluator, activate trigger 1 to cause 33 Service Water Pump trip.

Diagnose trip of 33 Service Water Pump Perform ARP-012 for alarm Service Water Header (3 High Low Pressure 0

Observe low pressure indication for 31, 32, 33 header 132733) 0 Refers to SOP-RW-5 and starts 31 Service Water Pump 0

Dispatch NPO to investigate 33 SWP Direct BOP operator response to service water transient.

The CRS may evaluate TS 3.7.9 Service Water System:

0 The LCO is satisfied with 2 pumps and required flow path for the nonessential SWS header operable.

NOTE: The CRS may refer to AOP-SW-1, Service Water Malfunctions for subsequent actions.

Continue with the next event at the discretion of the Lead Evaluator Direct the Booth Instructor to actuate Trigger 2

Appendix D Required Operator Actions Form ES-D-2 Time I Position Booth Instructor BOP CRS RO/BOP Booth Instructor Lead Evaluator Applicants Actions or Behavior When directed by the lead evaluator, activate trigger 2 to fault Bus 5A Diagnose bus 5A de-energized PerformARPs Dispatch NPO to investigate Implement AOP-480V-1, Loss of 480V Bus Direct crew actions of AOP-480V-1 Verify charging pump running Verify CCW pumps running Check SW essential and non-essential headers > 60 psig Perform ARPs Verify IRPls energized Verify condenser vacuum stable Dispatch an NPO to the monitor EDGs Evaluate Technical Specification 3.8.9 NPO reports back acrid burnt electrical odor. No fire or smoke.

Determine that bus 5A is inoperable. Since 32 EDG is also inoperable, per LCO 3.8.9 Condition E, enter LCO 3.0.3 Immediately 0

Determine shutdown must commence within one hour Be in mode 3 in next six hours Proceed to next event when unit shutdown is commenced.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: 2 Event No.:

3 Page 1 of 1 Event

Description:

Technical Specification required shutdown.

P Time Position CRS RO

_r Applicants Actions or Behavior Refers to POP-2.1 Operation at Greater Than 45% Power Implements section 4.3 Lowering Plant Load Implements Attachment 3, Reactor Power Reduction Checklist Develops shutdown plan for power reduction Using Attachment 5, develops a reactivity plan for power reduction Initiate notifications Perform a brief with the crew Directs reactivity changes Directs load changes Energize all pressurizer backup heaters Dispatch NPO to swap boric acid transfer pumps 0

31 BA transfer is de-energized due to loss of bus 5A 0

Ensures 32 BA Transfer Pump aligned to blender Commence boration per 3-SOP-CVCS-003, Reactor Coolant System Boron Concentration Control 0

Verify heaters energized 0

Direct chemist to sample 0

Set boric acid flow integrator to desired volume 0 Adjust FCV-11 OA Boric Acid Flow Control Blender controller for desire flow rate 0

Place Makeup Mode Selector switch to Borate 0

Turn Makeup Control switch to Start and return to Norm Verify boration has started properly 0

Monitor Tavg, rod position, delta flux, and RCP seal injection Insert control rods as directed by CRS to maintain Tavg on program and delta-flux within target band.

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No: 1 Scenario No: 2 Event No.: 3 Page 2 of 2 Event

Description:

Technical Specification required shutdown.

I BOP Lead Evaluator Initiate generator load reduction at rate directed by CRS 0

Monitor Tave - Tref deviation 0

Coordinate load reductions with RO reactivity addition rate.

0 Maintain Feed Water Regulating Valve controllers manual setpoint nulled during power reduction.

Proceed to the next event when sufficient load reduction had been observed.

Direct the Booth Instructor to activate trigger 3

Appendix D Required Operator Actions Form ES-D-2 I

Event

Description:

Power Range Nuclear Instrument Channel 41 Upper Detector Fails High.

I Booth Instructor ATC CRS BOP CRS/ATC CRS Lead Evaluator Applicants Actions or Behavior

_L When directed by the Lead Evaluator, activate trigger 70 to activate MAL-NISOO6A causing Power Range N4 1 Upper detector to fail high.

Diagnose failed nuclear instrument.

Place Control rods in manual to stop auto rod insertion Direct actions of the team during AOP-NI-1, Nuclear Instrument Failurew. (Note: The crew may perform AOP-INST-1 immediate actions and then transition to AOP-NI-1 when directed, or they may directly enter AOP-NI-1.)

Perform ARPs for alarms associated with the failed instrument.

Adjust control rods, boron concentration, or turbine load as necessary to maintain Tave at programmed Tref.

Evaluate TS 3.3.1 functions 2 and 17 Proceed to the next event at the discretion of the Lead Evaluator

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: 2 Event No.:

5,6,7 Page 1 of 1 I

Event

Description:

Blackout/Loss of Grid. Unit trips, all 480V buses are de-energized. PRZ PORV 456 Fails Open.

CRS RO BOP Booth Instructor CRS RO Applicants Actions or Behavior When directed by the Lead Evaluator, activate trigger 3 to cause loss of grid/station blackout Direct crew to perform immediate actions of E-0, Reactor trip or safety injection Verifies reactor is tripped Verifies turbine is tripped Diagnose none of the 480V buses are energized 0

Observe that the only EDG running is 33 EDG and bus 5A cannot be energized due to fault. 31 and 32 EDGs are not running. 31 EDG did not start. 32 EDG is out of service.

0 Informs CRS that transition to ECA-0.0 is required.

Transitions to ECA-0.0, Loss of All AC Power and directs crew actions during implementation of ECA-0.0 Verify Reactor trip Close all MSlVs

~~

~

PORV 456 fails open 48 seconds after the unit trips.

Determine if RCS is isolated 0

When PORV 456 fails open, observes pressurizer pressure e 2335 psig and lowering and places control switch for PCV-456 to close. Observes PORV PCV-456 closed

Appendix D Required Operator Actions Form ES-D-2 Position Critical Task BOP RO/BOP Critical Task BOP

~

Applicants Actions or Behavior WOG CT: ECA-0.0--A Manually close the open PRZ PORV before completing step 3 of ECA-0.0 Close Letdown Isolation valves 0

Places control switches for LCV-459,460,20OA, 200B, and 200C to CLOSE 0

Check Excess letdown stop valves APV-213A and 21 3B closed 0

Check HCV-133 Closed 0

CLOSE RCS Sample Isolation valves SP-AOV-956A C, E, G and SP-AOV-956B, D, F, H Check 32 ABFP running Adjust HCV-1118 ABFP Turb Speed Control to maintain discharge pressure > SG Pressure Check SG levels > 9%

Adjust 32 ABFP FCV-405A, B, C, and D as necessary to maintain total feed flow > 365 gpm.

Preferentially feed 32 or 33 SG (selects one and feeds at a higher rate)

Maintain feed flow in all other SGs at 5 100 gpm WOG CT: ECA-0.0-B Establish at least 365 gpm ARN flow to the SGs before SG WR level decreases to below 16%

Check status of 480V buses 2A and 3A - both de-energized

Appendix D Required Operator Actions Form ES-D-2 Time -

Position ALL Lead Evaluator Try to restore power to any 480V Ac Safeguards Bus Dispatch NPO to emergency start EDGs and energize 480V bus per SOP-EL-1 Contact ConEd and request urgent power restoration 0 Attempt to energize any 480V bus using SOP-EL-1 or SOP-EL-5 Proceed to next event after NPO has been dispatched to emergency start EDGs.

Direct Booth Instructor to activate trigger 4 to start 31 EDG

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

31 EDG is successfully started but must be shutdown due to insufficient cooling water. Loads are placed to pullout, RCP seals are isolated, and the RCS is depressurized to weserve the RCP seals.

BOP CRS BOP/RO Applicants Actions or Behavior When NPO is dispatched to emergency start EDGs, activate trigger 4 to execute batch file bat lrqsesOl5a.bat: Deletes MAL-DSG001A and resetshtarts 31 EDG.

APP R EDG will not start.

When ConEd contacted, report that a widespread system blackout has occurred across NYC, Westchester County, Long Island, and Connecticut. ConEd cannot estimate when oflsite power will be available to IPEC.

Observes 480V buses 2A and 3A are energized from 31 EDG.

Manually starts 35 Service Water Pump Determines two SW Pumps cannot be started on the essential header Initiates Attachment 1, Essential Service Water Alignment Close 1 104 and 1 105, Serv Wtr Cont Clg valves Direct NPO to monitor temperature of running EDGs and trip when jacket water temperature exceeds high temperature alarm setpoint.

Monitor ESW header pressure. Determine that pressure cannot be maintained above the SERVICE WTR HDR HIGH LOW PRESS alarm setpoint (60 psig)

Direct NPO to trip EDGs After 35 SWP has been started and Attachment I is in progress, activate Trigger 5 to trip 31 EDG NPO contact Control Room and inform them that 31 EDG has been tripped Note: Any further attempts to restart 31 EDG are not successfil.

Perform Attachment 2, Preventing overheating of equipment and instrumentation.

Appendix D Required Operator Actions Form ES-D-2 Scenario No: 2 Event No.:

8 Position CRS/RO RO CRS/RO RO Check SI Actuated 0

Reset Safety Injection in accordance with ECA-0.0 step 20 (per step 8 caution) 0 Return to step 8 Place control switches to pullout:

0 PZR Heaters Containment Spray Pumps 0

FCUs SI Pumps 0

Motor Drive ABFPs 0

RHRPumps CCWPumps Determine RCP seal should be isolated Dispatch NPO to close the following valves 0

MOV-222, Seal Water Return Isolation FCV-625, CCW return From RCP Thermal Barrier 0

RCP Seal Injection needle valves CH-241A, B, C, and D Check CST Hotwell Isolation Valves 1158-1 and 2 closed Check Main and bypass FRVs Closed Check SG Blowdown Isolation valves and sample valves closed Dispatch NPO to break condenser vacuum Check for faulted or ruptured SG Check SG levels and control AFW

Appendix D Required Operator Actions Form ES-D-2 Scenario No: 2 Event No.:

8 Time -

Position CRS/RO L

RO Critical Task Lead Evaluator Applicants Actions or Behavior Determine if intact SGs should be depressurized 0

Check seal cooling established 0

Check 32 HHSl pump available Depressurize intact SGs to 225 psig Check SG NR Levels - any > 9%

Manually dump steam at maximum rate using SG atmospherics WOG CT: ECA-0.0--G If all of the following conditions are met, depressurize intact SGs at maximum rate:

Any intact SG NR level > 9%

SG Pressure does not decrease below 125 psig RCS Cold Leg Temperatures > 320°F SUR 0 or negative Terminate scenario when SG Atmospherics are dumping steam at the maximum rate, or at the discretion of the Lead Evaluator.

If necessary, administer JPM SRO-A-5 to the CRS.

Appendix D Scenario Outline Form ES-D-1 Malf.

No.

MAL-PRS005A MAL-PRS003C ASISRWST NIA MAL-RCSOO7C MAL-RCSOI 2C MAL-RCS002C MAL-RCS001 K MAL-SIS001 A MAL-SIS001 B MAL-SIS004B Event Type*

I (ATC)

I (SRO)

C (ATC)

C (SRO)

C (SRO)

R (ATC)

R (CRS)

N (BOP)

N (CRS)

Facility: Indian Point 3 Scenario No:

3 Op-Test No:

1 Examiners:

Operators:

Initial Conditions:

The scenario begins at 100% power steady state conditions and no equipment 00s.

Turnover:

Maintain current plant conditions.

Event No:

1 2

3 4

5 6

7 8

9 C (ATC)

M (ALL) c (BOP)

C (BOP)

Event PRZR pressure Instrument PT-455 fails high. Spray valves open and actual pressure lowers until manual action is taken.

TS for SRO PORV 4556 fails open. Block valve can be manually closed to isolate the leak. TS for SRO Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over 40 minutes. TS for SRO Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown.

RCP Seal malfunction - High vibrations and #I seal degradation.

During shutdown, indications of RCP malfunction occur.

While team is investigating RCP malfunction the affected RCP trips. RO must manually actuate reactor trip.

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation SI fails to auto actuate, but manual SI is successful 32 SI Pump fails to auto start 34 and 35 FCU dampers do not auto reposition to incident mode.

Scenario Event Description NRC Scenario #3 The scenario begins at 100% power steady state conditions and no equipment 00s.

After taking the watch, PRZ Pressure controlling channel (PT-455) fails high. The team manually controls pressure and takes actions per AOP-INST-1. After TS are addressed the team will trip bistables. When pressure control is placed back in auto, PORV 455C fails open. The ATC will attempt to close the PORV and then close its Block Valve.

A fork truck moving equipment near the containment building equipment hatch has a brake failure and crashes into the RWST. RWST level will lower to 11 feet in 40 minutes. The team will evaluate TS and commence a plant shutdown.

During the shutdown, 33 RCP # I seal degrades and vibrations increase. The team responds per AOP-RCP-1, Reactor Coolant Pump Malfunction. The RCP trips but auto reactor trip does not occur as it should. The team will manually actuate reactor trip.

Concurrent with the trip, 33 RCP seal degrades further to 300 gpm LOCA. Auto SI actuation will not occur requiring manual SI actuation. 32 SI pump does not auto start and the dampers on two Fan Cooler Units do not automatically reposition to incident mode.

The team progresses through E-0 and E-I until RWST level reaches the cold leg recirculation switchover level. The team will transition to ES-1.3, Transfer to Cold Leg Recirculation, but indication of adequate sump levels will not exist to support cold leg recirculation. The team will be directed to ECA-1.I, Loss of Emergency Coolant Recirculation. In ECA-1.I they will align makeup to the RWST and reduce ECCS suction to a single train to conserve inventory. The scenario will be terminated when SI flow has been reduced to a single train (one SI pump).

Procedure Flowpath: AOP-INST-1, ARP, POP-2.1, AOP-RCP-1, E-0, E-I, ES-1.3, ECA-1.1.

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Setup Scenario 3 Run Batch File NRC3.bat Verify the following commands are pending:

A IND-CNM037B 3LR-1254 REC 2 SIGNAL CONTAINMENT LEVEL RECORDER TRAIN IOR IND-CNM037B (-1 0) 0 0 A IND-CNM037A 3LR-1254 REC 1 SIGNAL CONTAINMENT LEVEL RECORDER TRAIN IOR IND-CNM037A (-1 0) 0 0 A IND-CNM032B 3LR-1253 REC 2 SIGNAL CONTAINMENT LEVEL RECORDER TRAIN IOR IND-CNMO32B (-1 0) 0 0 A IND-CNM032A 3LR-1253 REC I SIGNAL CONTAINMENT LEVEL RECORDER TRAIN IOR IND-CNM032A (-1 0) 0 0 A SWI-CNMO16A 1302 GREEN LAMP CONT RECIRC UNIT #34 FLOW VLV 1302 CONT IOR SWI-CNMOI 6A (-1 0) OFF TRG 10 "DOR SWI-CNMOI 6A" A SWI-CNMO16B 1302 RED LAMP CONT RECIRC UNIT #34 FLOW VLV 1302 CONT S IOR SWI-CNMO16B (-1 0) ON TRG 11 "DOR SWI-CNMO16B" A SWI-CNM017A 1303 GREEN LAMP CONT RECIRC UNIT #34 FLOW VLV 1303 CONT IOR SWI-CNM017A (-1 0) OFF TRG 12 "DOR SWI-CNMO17A" A SWI-CNM017B 1303 RED LAMP CONT RECIRC UNIT #34 FLOW VLV 1303 CONT S IOR SWI-CNMOI 7B (-1 0) ON TRG 13 "DOR SWI-CNMO17B" A SWI-CNMO18A 1304 GREEN LAMP CONT RECIRC UNIT #34 FLOW VLV 1304 CONT IOR SWI-CNM018A (-1 0) ON TRG 14 "DOR SWI-CNMO18A" A SWI-CNM018B 1304 RED LAMP CONT RECIRC UNIT #34 FLOW VLV 1304 CONT S IOR SWI-CNM018B (-1 0) OFF TRG 15 "DOR SWI-CNMOI 8B" A SWI-CNMOISA 1305 GREEN LAMP CONT RECIRC UNIT #35 FLOW VLV 1305 CONT IOR SWI-CNMOISA (-1 0) OFF TRG 16 "DOR SWI-CNMO19A" A SWI-CNMOISB 1305 RED LAMP CONT REClRC UNIT #35 FLOW VLV 1305 CONT S IOR SWI-CNMOISB (-1 0) ON TRG 17 "DOR SWI-CNMO19B" A SWI-CNM020A 1306 GREEN LAMP CONT RECIRC UNIT #35 FLOW VLV 1306 CONT IOR SWI-CNM020A (-1 0) OFF TRG 18 "DOR SWI-CNM020A" A SWI-CNM020B 1306 RED LAMP CONT RECIRC UNIT #35 FLOW VLV 1306 CONT S IOR SWI-CNM020B (-1 0) ON TRG 19 "DOR SW I-CNM020B" A SWI-CNM021A 1307 GREEN LAMP CONT RECIRC UNIT #35 FLOW VLV 1307 CONT IOR SWI-CNM021A (-1 0) ON TRG 20 "DOR SWI-CNM021A"

• SWI-CNM021B 1307 RED LAMP CONT RECIRC UNIT #35 FLOW VLV 1307 CONT S IOR SWI-CNM021B (-1 0) OFF TRG 21 "DOR SWI-CNM021 B" TRGSET 10 "hwxaoil590.eq.O" TRGSET 11 "hwxaoi1590.eq.O" TRGSET 12 "hwxaoi160o.eq.O" TRGSET 13 "hwxaoil6Oo.eq.O" TRGSET 14 "hwxaoi 161 o.eq. 1 "

TRGSET 15 "hwxaoil6lo.eq.l" TRGSET 16 "hwxaoil62o.eq.O" TRGSET 17 "hwxaoil62o.eq.O" TRGSET 18 "hwxaoil63o.eq.O" TRGSET 19 "hwxaoil63o.eq.O" TRGSET 20 "hwxaoi164o.eq.l" TRGSET 21 "hwxaoi164o.eq.l"

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Setup Scenario 3 A MAL-RPS002A REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO FAILURE)

IMF MAL-RPS002A (-1 0) TRUE A MAL-SIS001A IMF MAL-SIS001A (-1 0) TRUE

• MAL-SIS001B IMF MAL-SIS001B (-1 0) TRUE IMF MAL-SIS004B (-1 0) 1 A MAL-PRSOOSA IMF MAL-PRS005A (1 0) 2500.000000 21 2235.330078 A MAL-PRS003C IMF MAL-PRS003C (2 0) 100.000000 180 0.000000 SAFETY INJECTION FAILURE TRAIN A SAFETY INJECTION FAILURE TRAIN B MAL-SIS004B SAFETY INJECTION PUMP 32 FAILURES PRESSURIZER PRESSURE CHANNEL 455 FAILURE PRESSURIZER RELIEF VALVE 455C VALVE POSITION FAILURE A RWST Leak to 11 ft level in 40 minutes TRG 3 "RAMP ASISRWST 2.82e6 7e5 2400" A MAL-RCS007C RCP 33 VIBRATION IMF MAL-RCS007C (4 IO) 14.000000 120 11.000000 A MAL-RCS012C IMF MAL-RCS012C (4 0) 0.625000 0 0.000000 A MAL-RCS002C IMF MAL-RCS002C (5 0) TRUE RCP 33 NUMBER 1 SEAL FAILURE REACTOR COOLANT PUMP 33 TRIP A Makes seal leak big after reactor trips TRGSET 30 "jpplp4(l).eq.l" TRG 30 "IMF MAL-RCS012C (-1 0) 100.0 0 0.625000" A MAL-RCS001K IMF MAL-RCS001K (30 0) 0.028000 0 0.000000 RCS RUPTURE (LOOP 3 CROSSOVER LEG)

Indian Point Unit 3 2606 NRC Initial License Examination Booth Instructor Directions Scenario 3 Setup/Event IC Reset SES Setup Batch File Floor Setup Event 1 Role Play Event 2 Role Play Event 3 Role Play Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS 10 Run setup batch fde NRC-3.bat and verify malfunctions and over-rides have been entered Perform setup checklist Actuate Trigger 1 At lead evaluator direction If I&C is sent to investigate

~~

Actuate h-igger 2 At lead evaluator direction If NPO sent to de-energize the block valve Actuate Trigger 3 At lead evaluator direction After lo level alarm, security calls and reports damage to RWST:

If maintenance sent to try to stop the leak If NPO directed to align makeup to the RWST EXPECTED RESPONSEANSTRUCTOR CUES Reset Simulator to IC 10

• MAL-PRS005A PRESSURIZER PRESSURE CHANNEL 455 FAILURE IMF MAL-PRS005A (1 0) 2500.000000 21 2235.330078 Inform team you will look into the problem (no diagnosis before the end of the scenario).

MAL-PRS003C PRESSURIZER RELIEF VALVE 455C VALVE POSITION FAILURE IMF MAL-PRS003C (2 0) 100.000000 180 0.000000 Override the panel lamps off (red lamp and green lamp)

RWST Leak. The tank will be at 11 feet in 40 minutes from time of actuation.

The brakes failed on a truck which crashed into the tank and ruptured the tank. Water is gushing out from about 15 feet above the ground.

Maintenance is unable to stop the leak Perform local NPO actions as requested to align makeup to the RWST

Indian Point Unit 3 2606 NRC Initial License Examination Booth Instructor Directions Scenario 3 Setup/Event Event 4 Event 5 Event 5 Events 6-9 Role Play Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS When outside agencies and personnel notified of shutdown.

NPO directions during shutdown Actuate Trigger 4 At lead evaluator direction Actuate Trigger 5 At lead evaluator direction When reactor is tripped, trigger 30 auto actuates:

Perform actions as directed by CCR When directed to align makeup to RWST EXPECTED RESPONSE/INSTRUCTOR CUES Acknowledge reports and communication for plant shutdown Perform requested NPO actions during shutdown A MAL-RCS007C RCP 33 VIBRATION IMF MAL-RCS007C (4 IO) 14.000000 120 11.OOOOOO A MAL-RCS012C IMF MAL-RCS012C (4 0) 0.625000 0 0.000000 RCP 33 NUMBER 1 SEAL FAILURE A MAL-RCS002C IMF MAL-RCS002C (5 0) TRUE REACTOR COOLANT PUMP 33 TRIP A Makes seal leak big afier reactor trips TRGSET 30 "jpplp4(l).eq.l" TRG 30 "IMF MAL-RCS012C (-1 0) 100.0 0 0.625000" A MAL-RCS001K RCS RUPTURE (LOOP 3 CROSSOVER LEG)

IMF MAL-RCS001K (30 0) 0.028000 0 0.000000 Perform various LOA'S per NPO local task list Align RWST makeup as requested

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Turnover Information Scenario I Watch Team Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

Condition:

YO Power:

MW Gross:

Boron Conc:

Control Rods Plant Equipment Status:

TODAY 567 O F 2235 psig 45 %

Power Ops 100%

1078 1032 ppm 224 CBD

1. No equipment out of service.

2. Maintain current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Pressurizer Pressure Instrument (Controlling Channel) fails High RO CRS BOP CRS BOP Applicants Actions or Behavior When directed by the Lead Evaluator, actuate trigger I :

MAL-PRSOOSA PRESSURIZER PRESSURE CHANNEL 455 FAILURE Diagnose pressurizer pressure controlling channel instrument failure 0

Take manual control of pressurizer pressure control, close spray valves and energize heaters.

0 From memory, perform AOP-INST-1 immediate operator actions.

0 Control pressurizer pressure in manual.

0 Return pressurizer pressure to program.

Direct team to perform immediate actions of AOP-INST-I, Instrument Controller Failures.

0 Verify that RO has taken manual control of pressurizer pressure Implement AOP-INST-1 Perform ARPs for alarms associated with the instrument failure 0

Pressurizer High Press Channel Trip 0

Pressurizer Low Press Direct BOP to defeat the failed PRZR Pressure Channel Defeat failed PRZR Pressure Channel 0

In rack 6-6, place P/455A to DFT CH I IV 0

In rack B-8, place 3T1411A in DFT CH I

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Pressurizer Pressure Instrument (Controlling Channel) fails High Time 1 Position Lead Evaluator Evaluate Technical Specifications:

3.4.1 - Requires pressure > 2205 in two hours 3.3.1 - Requires RPS Bistables tripped in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 3.3.2 - Requires SI Bistables tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Low Pressure Unblock SI in correct condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Proceed to the next event after TS have been evaluated, or at the discretion of the lead evaluator.

Direct the Booth Instructor to activate trigger 2

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Pressurizer PORV 455C fails open.

RO Booth Instructor:

BOP/RO When directed by the Lead Evaluator, actuate trigger 2:

MAL-PRS003C PRESSURIZER RELIEF VALVE 455C VALVE POSITION FAILURE Diagnose open PORV - Take the following actions based on prudent operator actions to control the plant before an auto trip occurs:

0 Observe RCS pressure and determine that PORV should not be open for current conditions 0

Place control switch for PORV 45% to close 0

Observe that PORV is still Open 0

Place control switch for PORV 4556 Block Valve to close 0

Observe block valve closed and PRZR Pressure rising Perform ARP-004 page 32 and 33 for PCV-455C NOT FULLY CLOSED 0

Verify alarm 0

Check if PORV closes on pressure reduction 0

Determine PORV open due to failure 0

Close (or verify closed) affected block valve 0

Remove fuses for affected PORV solenoid (inside Flight Panel) 0 Dispatch NPO to de-energize affected block valve (MOV-535)

Perform ARP-003 page 13 and I 4 for PZR LOW PRESS alarm

~

_ _ ~

AppendixD Required Operator Actions Form ES-D-2 Event

Description:

Pressurizer PORV 455C fails open.

Lead Evaluator Applicants Actions or Behavior Direct crews response to failed PORV Ensure block valve is closed Evaluate Technical Specification 3.4.1 1 Condition B - One PORV inoperable and incapable of being manually cycled:

0 Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0

Remove power from associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0

Restore PORV to operable status with 7 days Proceed to the next event Direct the Booth Instructor to activate trigger 3

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Event 3: Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over Event 4: Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown Booth Instructor:

Booth Instructor:

CRS CRS A

p p

l l

c a

n t

s h

a v

i o

r When directed by the Lead Evaluator, actuate trigger 3:

A RWST Leak to 11 ft level in 40 minutes TRG 3 RAMP ASISRWST 2.82e6 7e5 2400 Diagnose Lowering RWST Level Perform ARP-012 for alarm panel SJF REFUELING WATER STORAGE TANK LO LEVEL 0

Direct watch personnel to check for source of leakage 0

Monitor sump levels Telephone CCR and inform them as Security Guard that a fork truck crashed into the R WST and split open a weld about I O feet from the bottom of the tank and water is gushing from the tank, Evaluate TS 3.5.4 0

Determine RWST is not operable 0

Determine Condition C applies and unlikely to restore operability within one hour 0

Determine Condition D applies and plant shutdown to mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> required.

Implement POP-2.1 Attachment 3, Reactor Power Reduction Checklist 0

Develop reactivity plan to place unit in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 0

Direct shutdown activities during TS required shutdown

Appendix D Required Operator Actions Form ES-D-2 Op-Test No: 1 Scenario No: 3 Event No.: 3, 4 Page 2 of 2 Event

Description:

Event 3: Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over 40 minutes Event 4: Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown I

Time -

Position RO BOP Lead Evaluator Applicants Actions or Behavior Borate the RCS at rate determined by reactivity plan 0

Monitor TAVE and TREF 0

Monitor Delta-Flux and ensure control rods insert when required to maintain TAVE on program and Delta-flux within target band Initiate generator load reduction at rate directed by CRS Proceed to the next event after load reduction has commenced Direct the Booth Instructor to activate trigger 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

1 Scenario No: 3 Event No.: 5 Page 1 of 1 Event

Description:

RCP Seal malfunction - High vibrations and #I seal degradation. During shutdown, indications of RCP malfunction occur.

Booth Instructor:

TEAM BOP RO CRS Lead Evaluator When directed by the Lead Evaluator, actuate trigger 4:

• MAL-RCS007C RCP 33 VIBRATION IMF MAL-RCS007C (4 10) 14.000000 120 11.OOOOOO

• MAL-RCS012C RCP 33 NUMBER 1 SEAL FAILURE IMF MAL-RCSO12C (4 0) 0.625000 0 0.000000 Diagnose RCP Seal Malfunction Perform ARPs for associated Alarms:

ARP-013, REACTOR COOLANT PUMP HIGH VIBRATIONS ARP-009, RCP NO. 1 SEAL RETURN HIGH LOW FLOW 0

Observe 33 RCP is affected Diagnose rising seal return flow on RCP 33 seal return flow recorders Implement AOP-RCP-1 Proceed to the next event after team determines that 33 RCP is affected Direct the Booth Instructor to activate trigger 5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

1 Scenario No: 3 Event No.: 6 Page I of I I Event

Description:

While team is investigating RCP malfunction, the affected RCP trips. Auto reactor trip does not occur but manual trip is successful

~~~~

~

Booth Instructor:

RO Critical Task TEAM CRS Lead Evaluator When directed by the Lead Evaluator, actuate trigger 5:

• MAL-RCS002C IMF MAL-RCS002C (5 0) TRUE REACTOR COOLANT PUMP 33 TRIP Determine reactor trip is required but has not actuated 0

Manually trips the reactor WOG CT E-0--A Manually trip the reactor from the CCR before completing E-0, Step 1 Diagnose 33 RCP has tripped Direct the team to perform the immediate actions of E-0, Reactor Trip or Safety Injection 0

Ensures that the reactor is manually tripped following trip of 33 RCP without auto reactor trip Proceed to the next event after team manually trips the reactor

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

1 Scenario No: 3 Event No.: 7,8,9 Page 1 of 3 Event

Description:

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation. SI fails to auto actuate, but manual SI is successful. 32 SI Pump fails to auto start and 34 and 35 FCU dampers do not auto reposition to incident mode 300th Instructor:

I CRS RO Critical Task C ri tica I Task Applicant's Actions or Behavior Veri& that trigger 30 actuated when the reactor tripped. Trigger 30 causes a 300 gpm seal LOCA on 33 RCP.

Enter EOP E-0, Reactor Trip or Safety Injection and direct the actions of the crew.

Verifies immediate actions using the procedure Directs BOP to implement RO-1 When RCS subcooling lowers, directs RO to trip RCPs Diagnoses Loss of RCS Coolant and transitions to EOP E-I Performs EOP actions as directed by the CRS Determines SI is required but not actuated and manually actuates SI.

(Critical task)

When RCS subcooling lowers to stops all RCPs. (Critical task) 32"F, verifies SI pumps running and WOG CT E-O--D Manually actuate at least one train of SIS actuated safeguards before any of the following:

Transition to any E-I, E-2, or E-2 series or FR procedures 0

Completion of ES-0.1, step 5A WOG CT E-I--C Trip all RCPs before the completion of E-I, step I NOTE: This task is only critical if subcooling lowers to ~ 3 2 ° F and is dependant upon timing of previous actions. If subcooling does not lower to 32"F, then this task will not be performed and is not critical.

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No:

I Scenario No: 3 Event No.: 7,8,9 page 2 of 3 I Event

Description:

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation. SI fails to auto actuate, but manual SI is successful. 32 SI Pump fails to auto start and 34 and 35 FCU dampers do not auto reposition to incident mode Time Position BOP CRS RO/BOP CRS TEAM A

f l

Verifies automatic actions occurred 0

Determines that 32 SI pump did not auto start and manually starts it.

0 Determines 34 and 35 FCU dampers did not auto repostion to incident mode and manually repositions dampers using control switches.

0 Informs CRS of status Resets SI Enter EOP E-I Loss of Reactor or Secondary Coolant and direct the actions of the crew 0

Holds a crew brief upon transition 0

Transitions to ES-1.3 when RWST Low-Low level annunciators alarm.

When RWST LOW-LOW LEVEL annunciators alarm, immediately inform the CRS so that a transition to ES-I.3 is made.

Directs the crew actions during performance of ES-1.3, Transfer to Cold Leg Recirculation Diagnose that containment level is not trending upwards and that VC level is not greater than 478 (due to RWST rupture from fork truck.)

Transition to ECA-1.I, Loss of Emergency Coolant Recirculation

Appendix D Required Operator Actions Form ES-D-2 Scenario No: 3 Event No.: 7,8,9 Event

Description:

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation. SI fails to auto actuate, but manual SI is successful. 32 SI Pump fails to auto start and 34 and 35 FCU dampers do not auto reposition to incident mode Time Position CRS RO BOP Critical Task Applicant's Actions or Behavior Directs crew actions during performance of ECA-1.I, Loss of Emergency Coolant Recirculation 0

Diagnose cause of loss of recirculation capability is not due to sump blockage 0

Verify availability of recirculation equipment (equipment is available, adequate sump level to support recirc is not) 0 Dispatch personnel to align makeup to the RWST Initiate RCS cooldown 0 Verify all rods inserted 0

Dump steam to condenser using high pressure steam dumps 0

Maintain cooldown rate 100"F/hr Check for indications of sump blockage Check recirc equipment available Align makeup to the RWST Check FCU aligned for incident mode Verify SI reset Establish one train of SI flow 0

Stops two SI pumps WOG CT ECA-1.l--B Make up to the RWST and minimize outflow before the end of the scenario.

0 This CT is satisfied by dispatching personnel to align makeup to the RWST and by reducing SI flow to a single train

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

1 Scenario No: 3 Event No.: 7,8,9 Page 4 of 3 Event

Description:

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation. SI fails to auto actuate, but manual SI is successful. 32 SI Pump fails to auto start and 34 and 35 FCU dampers do not auto reposition to incident mode I

Lead Evaluator 1 Terminate the after scenario SI has been reduced to one train, or at the discretion of the Lead Evaluator.

If required, administer JPM SRO-A-5 to the CRS

Acmendix D Scenario Outline Form ES-D-I 1 Facility: Indian Point 3 Scenario No:

4 Rev.1 Op-Test No: 1 Examiners :

Operators:

~ Initial Conditions:

Scenario begins with the plant stable at 100% power. 31 ABFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Turnover:

31 ABFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Maintain Current Plant Conditions Event No:

1 2

3 4

5 6

7 Malf.

No.

XMT-MSSOI 9 XMT-MSSOI 9 AL-CFWOOSC MAL-CFWOI 5 MAL-RPS002A MAL-CFW001 C MAL-CFW001 B Event Type*

I (ATC)

I (CRS)

C (ATC)

N (BOP)

N (CRS)

R (ATC)

R (CRS)

C (ALL)

R (ATC)

R (CRS)

M (ALL)

C (ATC)

C( BOP)

Event Descri Dt io n PT-412A fails low TS CRS Loss of Condenser Vacuum and subsequent power reduction Condensate Pump trip FW rupture in Turbine bldg Auto reactor trip failure, one RTB does not open MDAFP 33 fails to start (with 31 MDADP 00s) manual action required to feed with turbine driven ABFP TDAFP trip, results in loss of heat sink

Scenario Event Description NRC Scenario #4 Scenario begins with the plant stable at 100% power. 31 ABFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

After the crew has the watch, PT-412A fails low. The crew responds by placing rods in manual and entering AOP-INST-1, Instrument/Controller Failures. CRS will direct the crew to restore delta-flux to target and return Tave to program (withdraw rods to pre-failure position is expected.) CRS will reference TS for ESFAS instruments, and for power distribution if rod inserted enough to affect delta flux.

After the plant is stabilized, a condenser vacuum leak will occur. The crew will identify the loss of vacuum and perform a load reduction per AOP-VAC-1, Loss of Condenser Vacuum.

After load has been reduced about 50 MW, 33 Condensate Pump will trip. The team will perform AOP-FW-I, Loss of Feedwater to stabilize the plant. Prior to completing the actions of AOP-FW-1, a rupture will occur in the main feedwater pipe in the turbine building.

The reactor will not auto trip, but manual trip is successful.

The team will enter EOP E-0, Reactor Trip or Safety Injection. 33 ABFP will trip immediately after start. The team will manually align FCVs to feed SGs with the turbine driven ABFP and then exit E-0 to ES-0.1, Reactor Trip Response. While performing ES-0.1, the Turbine Drive ABFP will trip resulting in a loss of heat sink. The team will recognize a red path in Heat Sink with heat sink required and transition to FRP FR-H.7, Loss of Heat Sink. SG levels will require the plant be aligned for bleed and feed.

The scenario will be terminated when adequate core cooling has been verified following alignment of bleed and feed.

Procedure Flowpath: AOP-INST-1, AOP-VAC-1, AOP-FW-1, EOP E-0, EOP ES-0.1, FRP FR-H. 1

Indian Point Unit 3 2006 NRC Initial License Examination Siinulator Scenario Setup Scenario 4 NRC-4. bat A SWI-AFW009A GREEN LAMP AUX FEEDWATER PUMP NO. 31 CONTROL SWITCH MO IOR SWI-AFW009A (-1 0) OFF A SWI-AFW009D STOP AUX FEEDWATER PUMP NO. 31 CONTROL SWITCH MODULE IOR SWI-AFW009D (-1 0) ON A SWI-AFW009F START AUX FEEDWATER PUMP NO. 31 CONTROL SWITCH MODULE IOR SWI-AFW009F (-1 0) OFF A SWI-AFW009G PULL OUT POS AUX FEEDWATER PUMP NO. 31 CONTROL SWITCH IOR SWI-AFW009G (-1 0) OFF A MAL-RPS002A IMF MAL-RPS002A (-1 0) TRUE A MAL-RPSOOGA IMF MAL-RPSOO6A (-1 0) TRUE A XMT-MSSOI 9 TURB 1 ST STAGE PRESSURE IMF XMT-MSSO19 ( I 0) 0.000000 0 653.484985 IMF MAL-CND002B (2 0) 20.000000 0 0.000000 A MAL-CFW005C IMF MAL-CFW005C (3 0) 1.OOOOOO 0 0.000000 A MAL-CFWO15A REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO FAILURE)

REACTOR TRIP BREAKER A FAILURE TO OPEN MAL-CND002B LOSS OF VACUUM CONDENSOR 32 CONDENSATE PUMP 33 TRIP DUE TO BRG FAILURE FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 31 IMF MAL-CFWO15A (4 0) le6 0 0.000000 IMF MAL-CFWO15B (4 0) le6 0 0.000000 IMF MAL-CFWOI 5C (4 0) 1 e6 0 0.000000 IMF MAL-CFWOI 5D (4 0) le6 0 0.000000 A MAL-CFWO15B FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 32 FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 33

• MAL-CFWO15C MAL-CFWOI 5D FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 34 A MAL-CFWOOI B IMF MAL-CFW001B (5 0) TRUE A MAL-CFWOOI C IMF MAL-CFW001C (30 80) 0 AUXILIARY FEEDWATER PUMP 32 TRIP AUXILIARY FEEDWATER PUMP 33 FAILURES TRGSET 30 "jpplp4(2).eq.l"

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario 4 Setup/Event IC Reset SES Setup Batch File Floor Setup Event 1 Role Play Event 2 Role Play Event 3 Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS 10 Run setup batch file NRC-3.bat and verify malfunctions and over-rides have been entered Perform setup checklist Actuate Trigger 1 At lead evaluator direction If I&C or NPO is sent to investigate Actuate trigger 2 At lead evaluator direction BOOTH INSTRUCTOR:

Control size of vacuum leak to maintain condenser vacuum greater than 26.5 Hg.

Delete the air leak malfunction after the load reduction has begun.

If NPO sent to investigate loss of vacuum Actuate Trigger 3 At lead evaluator direction

~~

EXPECTED RESPONSE/INSTRUCTOR CUES Reset Simulator to IC 10 Place 3 1 ABFP to pullout and apply a danger tag. Put protected equipment placards on 32 and 33 ABFPs. Update the protected equipment computer display. Risk is yellow.

• XMT-MSSOI 9 TURB 1 ST STAGE PRESSURE IMF XMT-MSSO19 (I

0) 0.000000 0 653.484985 I&C will review prints and develop a troubleshooting plan but will not actually do anything during this scenario There are no obvious anomalies locally at the transmitter.

A MAL-CND002B LOSS OF VACUUM CONDENSOR 32 IMF MAL-CND002B (2 0) 20.000000 0 0.000000 Acknowledge request to search for vacuum leak.

Dont report back before next event.

A MAL-CFW005C CONDENSATE PUMP 33 TRIP DUE TO BRG FAILURE IMF MAL-CFWOOSC (3 0) 1.OOOOOO 0 0.000000

Indian Point Unit 3 2006 NRC Initial License Examination Booth Instructor Directions Scenario 4 Setup/Event Role Play Event 4 Role Play Event 5,6 Role Play Events 7 Role Play Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS If NPO dispatched Actuate Trigger 4 At lead evaluator direction but before team trips reactor or auto reactor trip if not successful at stabilizing plant following previous events.

NPO Report When NPO dispatched to open failed RTB Actuate Trigger 5 At lead evaluator direction When dispatched to reset 32 ABFP Perform actions as directed by CCR

~~

EXPECTED RESPONSE/INSTRUCTOR CUES Oil has come out of the upper motor bearing A MAL-CFWO15A FEEDLINE BREAK OUTSIDE CONTAINMENT - SIG 31 A MAL-CFW015B FEEDLINE BREAK OUTSIDE CONTAINMENT - SIG 32

• MAL-CFWO15C FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 33 IMF MAL-CFW015A (4 0) l e 6 0 0.000000 IMF MAL-CFWO15B (4 0) le6 0 0.000000 IMF MAL-CFW015C (4 0) le6 0 0.000000 IMF MAL-CFWOI 5D (4 0) 1 e6 0 0.000000 A MAL-CFW015D FEEDLINE BREAK OUTSIDE CONTAINMENT - S/G 34 Call the CCR and NPO report that feedwater line has ruptured in the overhead of the 15 elevation north end of turbine hall Delete MAL-RPS006A

• MAL-CFW001 B AUXILIARY FEEDWATER PUMP 32 TRIP IMF MAL-CFW001 B (5 0) TRUE NPO reports that he cannot reset the overspeed latch on 32 ABFP. It is broken.

Perform various LOAS per NPO local task list

Indian Point Unit 3 2006 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 4 Watch Team Turnover Sheet:

DateRime:

RCS Temp:

RCS Press:

PZR Level:

Condition:

% Power:

MW Gross:

Boron Conc:

Control Rods Plant Equipment Status:

TODAY 567 O F 2235 psig 45 %

Power Ops 100%

1078 1032 ppm 224 CBD

1. 3 1 ABFP has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for bearing inspections with an expected return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

0 Technical Specification 3.7.5 Condition B applies.

2. Maintain current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Scenario No: 4 Event No.: 1 Op-Test No:

Page 1 of 3 Event

Description:

PT-412A, Turbine First Stage Pressure instrument fails low. This causes Tref to fail low and control rods auto insert. Team takes actions per AOP-INST-1 RO CRS BOP Time Position Booth Instructor RO CRS Diagnose PT-412A instrument failure 0

Check Tave, Turbine Load, Reactor Power and determine that auto rod insertion is not required 0

Place Rod Control Mode Selector switch to MAN to stop auto rod insertion Direct RO to perform immediate actions of AOP-INST-1, InstrumenffController Failures I

Perform ARPs for alarms associate with instrument failure:

0 TAVG TREF DEVIATION 0

Verify instrument failure has occurred and CRS has implemented HIGH STEAM FLOW SI CHANNEL TRIP AOP-INST-1.

Performs AOP-INST-1 Immediate Actions:

0 Checks for control system failures 0

Determines that Rod Control has failed and places rod control in manual 0

Announce immediate actions complete when all control systems havebeenchecked Announces entry into AOP-INST-1 and directs the actions of the crew Verifies that all control systems have been checked and manual actions performed to stabilize the plant (rods in manual) 0 Verifies that an instrument failure has occurred 0

Performs section for Turbine I Stage Pressure instrument failure 0

Verify that Channel A has failed

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

PT-412A, Turbine First Stage Pressure instrument fails low. This causes Tref to fail low and control rods auto insert. Team takes actions per AOP-INST-1 Time Posit ion CRS RO BOP RO BOP Applicant's Actions or Behavior Direct crew activities 0

Verify that rods are in manual 0

Direct RO to determine Tref based on graph RPC-9 0

Develop a reactivity plan to restore Tave to program (expected action is to withdraw control rods to pre-failure position) using rods, boron, or turbine load.

0 Direct RO to perform reactivity manipulation (withdraw rods)

Refer to graphs RPC-9 (Tref vs 1 stage Pressure) and PT-412B indication to determine program Tref.

Restore Tave to Tref and Delta-flux to target by withdrawing control rods 0

Operates Rod Control In-Hold-Out switch in OUT position o observes Control Bank D bank demand and o IRPl position, o monitors reactor power, o delta-flux, and o Tavg.

Performs peer check of rod withdrawal Place Steam Controller in Pressure Mode 0

Place steam dump controller in manual 0

Adjust controller output to 0%

0 Place steam dump control switch to RESET and then to PRESS CONT.

Place AMSAC BS/2MSS 400 block switch to BYPASS (up) position

~

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

PT-412A, Turbine First Stage Pressure instrument fails low. This causes Tref to Position CRS Time Lead Evaluator Lead Evaluator BOP BOP d

p l

i c

a n

t

s Actions or Behavior Evaluate Technical Specification table 3.3.1-1 Function 17 for required action 0

Verify interlocks (P-7) in correct state for plant conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

0 Direct RO to verify Power Below P-7 lamp is extinguished (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

Evaluate Technical Specification 3.3.2 Condition A 0

Requires evaluation of Table 3.3.2-1.

0 Functions If, Ig, 4d, and 4e all require entry into Condition D 0

Condition D requires tripping bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Evaluate TRM 3.1.A AMSAC - 30 Days to restore AMSAC to operable.

Direct the Booth Instructor to actuate Trigger 2 to start the condenser vacuum leak. It will be a couple minutes until the team notices vacuum lowering Check bistables status lights for redundant channels extinguished per 1 Table 1 Trip bistables for failed instrument listed in Attachment 11 Table 2 Verify bistable status lights for failed instrument are illuminated per Attachment I 1 Table 3.

Proceed to next event when the team determines vacuum is lowering, or at the discretion of the Lead Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Condenser vacuum begins to lower due to air in-leakage. The team takes nces a turbine load reduction.

RO CRS When directed by the lead examiner, actuate trigger 2.

Control the size of the vacuum leak to maintain condenser vacuum greater than 26.5 Hg.

Delete the air leak malfunction after the load reduction has begun.

Diagnose loss of vacuum 0

Generator MW load lowering 0

Vacuum recorder on panel FDF 0

Computer Trends Implement AOP-VAC-1, Loss of Condenser Vacuum 0

Supervise and direct actions of the crew 0

Develop a reactivity plan (-100 MWe expected) to reduce turbine load to maintain condenser and LP turbine parameters within allowed values.

0 Dispatch NPOs to perform Attachment 5 to investigate source of vacuum loss When NPOs are dispatched, acknowledge request but do not report back with source of vacuum leak Check condenser vacuum parameters to determine if load reduction is necessary.

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~

Direct power reduction and reactivity manipulations Borate and/or insert control rods per the reactivity plan

Appendix D Required Operator Actions Form ES-D-2 I Op-Test No:

Scenario No: 4 Event No.: 2 I

Page 2 of 2 Event

Description:

Condenser vacuum begins to lower due to air in-leakage. The team takes action per AOP-VAC-1 and commences a turbine load reduction.

I Time Position +

BOPlRO L

Lead Evaluator Lower turbine load After - 50 MWe load reduction, proceed to next event.

Direct the Booth Instructor to activate Trigger 3 to cause 33 Condensate Pump trip

Appendix D Required Operator Actions Form ES-D-2 Scenario No: 4 Event No.: 3 Event

Description:

33 Condensate Pump trips. Team implements AOP-FW-1, Loss of Feed Water ALL

~

CRS RO Booth Instructor Lead Evaluator BOP CRS When directed by the Lead Evaluator, activate trigger 3 to trip 33 Condensate Pump Diagnose Condensate Pump Trip

~

Implement AOP-FW-1, Loss of Feedwater.

0 Direct the RO to perform immediate actions of AOP-FW-1 0

Supervise and direct the actions of the crew Perform immediate actions of AOP-FW-I 0

Check both Main Boiler Feed Pumps operating 0

Announce immediate actions complete Continue load reduction to reduce Steam Flow c Feed Flow Verify immediate actions complete Perform procedure section for Heater Drain or Condensate Pump trip 0

Verify all available condensate pumps are running 0

Direct RO/BOP to initiatekontinue load reduction as necessary to maintain F F S F and MBFP suction pressure > 265 psig.

Direct the Booth Instructor to activate trigger 4 before the reactor trips (or before manual trip). Allow the team to continue load reduction until F F S F or at the discretion of the Lead Evaluator. MBFP suction pressure cutback is expected and is the planned initiator for the next event: Main Feed Line Rupture in turbine hall

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Main Feed Line rupture in the turbine hall (due to the flow oscillations from the MBFP suction pressure cutback). Auto reactor trip does not occur. Reactor must be manually Time 1 Position Booth Instructor RO Critical Task CRS RO When directed by the Lead Evaluator (or before reactor trip occurs ifthe team has dificulty stabilizing the plant) execute trigger 4 to cause a main feedwater line rupture in the turbine hall. After E-0 immediate actions are complete, call the CCR and NPO report that feedwater line has ruptured in the overhead of the 15 elevation north end of turbine hall.

Diagnose rapidly lowering SG levels 0

Manually actuate reactor trip WOG CT: E-0--A Manually trip the reactor from the CCR before completion of E-0, step I.

Direct team to perform immediate actions of E-0 Reactor Trip or Safety Injection Verifies immediate actions using the procedure.

Verify Reactor is tripped 0

Determine one RTB did not open 0

Dispatch NPO to locally open RTBs Verify turbine is tripped Verify all 480 V buses energized

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

Scenario No: 4 Event No.: 4,5,6 Page 2 of 3 Event

Description:

Main Feed Line rupture in the turbine hall (due to the flow oscillations from the MBFP suction pressure cutback). Auto reactor trip does not occur. Reactor must be manually RO RO Critical Task Booth Instructor Check if SI is actuated 0

Checks for SI annunciators 0

Checks for SI system pumps running Check if SI is required 0

Checks Containment pressure 0

Checks PRZR Pressure 0

Checks PRZR Level 0

Checks Steamline delta-P 0

Checks High Steam Flow 0

Checks subcooling 0

Determines SI is not required Observes 33 ABFP has tripped and 31 ABFP is 00s Manually aligns 32 ABFP to establish > 686 gpm feed flow to the SGs 0

Throttles open FCV-405A though D 0

Adjust HCV-1118 as necessary to obtain desired discharge pressure 0

Announces immediate actions complete WOG CT: E-0--F Establish greater than 365 gpm ARN flow to the SGs before transition out of E-0 or tripping RCPs in FR-H.l NPO reports that feedwater line has ruptured in the overhead of the 1.5 elevation north end of turbine hall

Amendix D Reauired Operator Actions Form ES-D-2 CRS RO Verifies completion of immediate actions using the procedure Transitions to ES-0.1, Reactor Trip Response Holds a brief Directs the actions of the crew in ES-0.1 Check RCS Average Temperatures stable or trending to 547°F Check 345KV Motor Operated Disconnect F1-3 OPEN Lead Evaluator Proceed to the next event when the team determines a transition to FR-H.l is required Direct the Booth Instructor to activate Trigger 5 to trip 32 ABFP

Appendix D Required Operator Actions Form ES-D-2 ALL CRS BOP/RO CRS RO RO Amlicants Actions or Behavior When directed by the Lead Evaluator, activate Trigger 5 to trip 32 ABFP When an NPO is dispatched to attempt to reset it, the NPO is unable to re-latch the over-speed trip mechanism {it is broke).

Diagnose trip of 32 ABFP Determine that a Red Path exists on the heat sink CSF and transition to FR-H.1, Response to Loss of Secondary Heat Sink Direct the actions of the crew Review Foldout page Criteria for Bleed and Feed Check the average of the three lowest WR SG Levels < 25%

Check RCS pressure > than the highest SG Pressure Immediately proceed to step 9 to establish bleed and feed Manually actuate SI Close all MSIVs Stop all Reactor Coolant Pumps Verify RCS Feed Path 0

Check SI pumps running 0

Check Safeguard Valve Off Normal Position alarm clear 0

Ensure BIT discharge valves 1835A and 1835B open 0

Ensure BIT Inlet valves 1852A and 1852B open 0

Ensure High Head Stop Valves 856J, 856H, 856C, 856E open

Appendix D Required Operator Actions Form ES-D-2

~

~

~

~

Op-Test No:

Scenario No: 4 Event No.: 7 Page 2 of 3 Event

Description:

32 ABFP trips with no other ABFPs available and SG levels very low. Team goes to FR-H.1, Response to Loss of Secondary Heat Sink and must immediately proceed to the RO RO Critical Task BOP Establish RCS Bleed Path 0

Check power available to both PORV Block valves 0

Check both PORV Block Valves open 0

OPEN both PRZR PORVS Verify adequate RCS Bleed path 0

Check both PORVs open 0

Check both Block valves open WOG CT: FR-H.1-F Establish RCS bleed and feed when the average of the three lowest SG Levels reach 25% WR Reset SI 0

Place FCU damper control switches to SI position 0

Place 1 104 and 1 105 control switches to OPEN 0

Place control room AC to switch position 3 0

Dispatch NPO to set switches for 1 176 and 11 76A to OPEN 0

Perform steps 35-42 of E-0 o Verify SI pumps running o Verify FCU status o Verify SI valve alignment o Verify ABFP status - Dispatch NPO o Verify CCW status o Verify ESW status o Verify Phase A actuated o Verify Containment Ventilation Isolation status

Appendix D Required Operator Actions Form ES-D-2 Op-Test No:

Scenario No: 4 Event No.: 7 Page 3 of 3 Event

Description:

32 ABFP trips with no other ABFPs available and SG levels very low. Team goes to FR-H.1, Response to Loss of Secondary Heat Sink and must immediately proceed to the steps for aligning bleed and feed.

BOP ALL Lead Evaluator Reset SI Reset Phase A 0

Check PORV N2 Lo pressure alarm clear Maintain RCS Heat Removal 0

Maintain SI Flow 0

Maintain PORVs open Terminate the scenario at this point, or at the discretion of the Lead Evaluator If required, administer JPM SRO-A-5 to the CRS