ML13301A724

VC Summer Initial Exam 2013-301 Draft Sim IN-Plant Jpmss

ML13301A724
Person / Time
Site:	Summer
Issue date:	10/23/2013
From:	NRC/RGN-II
To:	South Carolina Electric & Gas Co
References
JPPF-013A
Download: ML13301A724 (127)

Text

2013 NRC In-Plant i: START AND LOAD THE DIESEL GENERATOR DURING CONTROL ROOM EVACUATIONCANDIDATE:EXAMINER:2 000-068-05-01SIMULATE20NODiesel started, field flashed, power is supplied to 1DA.PLANTTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.8PERFORM CONTROL ROOM EVACUATIONTOOLS:AOP-600.1, CONTROL ROOM EVACUATION, Attachment 3, LOCAL STARTING AND LOADING DIESEL GENERATOR A(B)CRS notified of 1DA status.

The CRS directs you to start the "A" Diesel Generator in accordance with AOP-600.1, Attachment 3, LOCAL STARTING AND LOADING DIESEL GENERATOR A(B)A control room evacuation has occurred. You as the BOP just completed AOP-600.1 Attachment 2, DUTIES OF THE BOP OPERATOR. During performance of the Attachment you determined that power was not available to 1DA.This JPM should only be run on a "A" train maintenance week and when the diesel rooms are not marked off as restricted areas due to EOOS. If it is a "B" train maintenance week use JPPF-013B.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Ensure both of the following breakers are open (IB-463): XSW1DA 01, BUS 1DA NORMAL INCOMING BKR. XSW1DA 15, BUS 1DA EMERG INCOMING BKR.Evaluator Cue: Cue examinee that green light is lit and red light is off for XSW1DA 01, BUS 1DA NORMAL INCOMING BKR and XSW1DA 15, BUS 1DA EMERG INCOMING BKR.YesVerifies green light lit and red light off for both incoming breakers.

No 1Determine the cause of Diesel Generator start failure:Check alarms and indications at the local DG Control Panel. REFER TO ARP-004-XCX-5201.Verify problems found will NOT prevent starting the DG.Evaluator Cue: When asked which alarms are present on XCX-5201 report that no annunciators are in alarm.YesDetermines that alarms do not indicate a problem that has to be fixed to start generator.

No 2

Place REMOTE/LOCAL/MAINT Switch in LOCAL.Evaluator Cue: When switch is taken to local indicate that XCX-5201 6-5, LOCAL CONTROL goes into alarm.YesREMOTE/LOCAL/MAINT Switch in LOCAL.Yes 3Ensure the VOLT REG is in AUTO.Examiner Cue: Cue examinee that VOLT REG switch is in AUTO.YesVerifies VOLT REG switch is in AUTO.

No 4

Depress the following reset pushbuttons: GEN RELAYS RESET.

EXCITER RESET.Evaluator Cue: Cue applicant that there are no changes to indications.YesDepresses GEN RELAYS RESET and EXCITER RESET.

No 5Attempt to start the Diesel Generator by depressing the ENGINE SHUT DOWN RESET Pushbutton.Examiner Cue: When button is pushed indicate that there are no change in indications.YesENGINE SHUT DOWN RESET is pushed. When cued that there is no response, goes to step 9 as an alternative action.

No 6

Attempt to start the Diesel Generator:Momentarily depress the EMERG START Pushbutton.

Verify the Diesel starts and accelerates to 514 rpm.Evaluator Cue: Cue applicant that there is no change in indications when button is pressed.YesPushes EMERG START Pushbutton and notices that Diesel does not start. Goes to alternative action.

No 7

b. Attempt to start the Diesel using the Main Air Start Valve:1) Using the attached spanner wrench, depress and hold the pushbutton on one of the following for five seconds (located at either end of the Diesel):

XVM10996A-DG, DIESEL GEN A MAIN AIR START VALVE A.

OR XVM10996B-DG, DIESEL GEN A MAIN AIR START VALVE B.

2) Verify the Diesel starts and accelerates to 514 rpm.Evaluator Cue: Cue applicant that diesel is heard to start. Cue that RPM's indicate 514 rpm if meter is observed.YesUses spanner wrench to push on one of the air start valves. Verifies that diesel accelerates to 514 rpm.Yes 8Verify the Generator voltage indication increased to between 6800 Volts and 7600 Volts.Examiner Cue: Cue applicant that voltage remains at 0 volts.YesDetermines that voltage has remained at 0 volts and goes to alternate action.

No 9

Perform a manual field flash:1) Momentarily place FIELD FLASH Switch to FLASH.

2) Verify Generator voltage increases to between 6800 Volts and 7600 Volts.Examiner Cue: Cue applicant that voltage has increased to 7200 volts.YesPlaces FIELD FLASH Switch to FLASH. Verifies generator voltage increase to 7200 volts.Yes 10Depress the EMERG START RESET Pushbutton.

Evaluator Cue: Cue applicant that EMERG START light at top of board goes from lit to off.YesEMERG START RESET Pushbutton depressed.

No 11 Reset all annunciators on XCX5201.Evaluator Cue: Cue applicant that only alarm in is 6-5, LOCAL CONTROL, before and after reset is pressed.Evaluator Note: Because there are no annunciators to reset the applicant may not press the reset pushbutton.YesPresses reset on XCX5201.

No 12Procedure Caution: If any DG annunciator will NOT reset, it should be evaluated by the Shift Supervisor prior to performing Step 12, since it may cause the DG or its output breaker to trip.Depress the TEST START Pushbutton.Evaluator Cue: Cue applicant that there is no change in indication after button is depressed.YesTEST START Pushbutton depressed.

No 13 Ensure BUS 1DA DG FEED is closed.Evaluator Cue: Cue applicant that BUS 1DA DG FEED indicates red light lit, green light off and voltage is indicated on 1DA.YesVerifies BUS 1DA DG FEED indicates red light lit, green light off and voltage is indicated on 1DA.

No 14Adjust Generator voltage to 7200 Volts using the AUTO VOLT CNTRL Switch.

Evaluator Cue: Cue applicant that voltage is at 7200 volts. If AUTO VOLT CNTRL Switch is used indicate changing voltages.Evaluator Note: This voltage band is that required for steady state operation in accordance with TSR 1068.YesGenerator Voltage is between 6840 and 7445 Volts.

No 15 Examiner ends JPM at this point.Adjust Generator frequency to 60 Hertz using the GOVERNOR Switch.Evaluator Cue: Cue applicant that frequency is at 60 Hz. If the GOVERNOR Switch is used indicate changing frequency.Evaluator Note: This frequency band is that required for steady state operation in accordance with TSR 1068.YesGenerator frequency is 60 +/-0.6 Hz.

No 16Notify the Control Room Supervisor at the CREP of DG status.Evaluator Note: Cue applicant that CRS understands that the diesel is started and at normal operating voltage and frequency and that the BOP should report to the CREP and the intermediate building operator will take over operation of the diesel.YesNotifies CRS.

No 17 JPPF-013A2013 NRC In-Plant i: START AND LOAD THE DIESEL GENERATOR DURING CONTROL ROOM EVACUATION N/AThis JPM should only be run on a "A" train maintenance week and when the diesel rooms are not marked off as restricted areas due to EOOS. If it is a "B" train maintenance week use JPPF-013B.

JPM SETUP SHEET The CRS directs you to start the "A" Diesel Generator in accordance with AOP-600.1, Attachment 3, LOCAL STARTING AND LOADING DIESEL GENERATOR A(B)A control room evacuation has occurred. You as the BOP just completed AOP-600.1 Attachment 2, DUTIES OF THE BOP OPERATOR. During performance of the Attachment you determined that power was not available to 1DA.

2013 NRC In-Plant j: LOCALLY CLOSE AND DE-ENERGIZE MS LOOP "B" TO TDEFPCANDIDATE:EXAMINER:7 000-169-05-04SIMULATE15NoTurbine driven emergency feed pump main steam loop "B" supply valve is manually closed and power removed from its motor operator per EOP-3.0.PLANTTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.8Locally Isolate a Faulted Steam Generator per EOP-3.0.TOOLS:EOP-3.0, STEP 5.h. ALTERNATIVE ACTIONMVG-02802A is closed and deenergized per EOP-3.0.EOP-3.0FAULTED STEAM GENERATOR ISOLATION035000A406S/G isolation on steam leak or tube rupture/leak 4.54.6 A4.06 061000K103Main steam system 3.53.9 K1.03 000040A104Isolation of all steam lines from header4.34.3 AA1.04 000040A110AFW System 4.14.1 AA1.10 RO directs you to open breaker 05EH on XMC1DA2X and locally closing valve XVG02802A-MS in accordance with EOP-3.0, Step 5.h, Alternative Action. The shift supervisor has approved the waiving of ISP-027 requirements due to the emergency condition.The plant was at 100% power when a steamline break occurred inside containment. "B" SG is faulted as indicated by steam pressure dropping in an uncontrolled manner. The CRS has implemented EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, out of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, following a Automatic SI. Both motor driven emergency feedwater pumps started.

TDEFP MS Isolation Valve MVG-02802A will not close from the MCB.Burn HazardWHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Examiner ends JPM at this point.Locally deenergize and close the appropriate valve. If SG B is faulted:Open XMC1DA2X 05EH, EF PUMP MAIN STEAM BLOCK VLV XVG-02802A-MS (IB-463).YesOperator locates the power supply (1DA2X, 05EH) for XVG-02802A and opens the breaker by pulling the breaker control lever down.Yes 1Close XVG02802A-MS, MS HEADER B EF PUMP TURBINE SUPPLY VLV (IB-436 East Pen).YesOperator locates and closes XVG02802A-MS by pulling the manual engagement clutch lever down and turning the valve handwheel in the clockwise direction until the valve position arrow of the handwheel points to the right and the handwheel will no longer rotate.Yes 2

JPP-1072013 NRC In-Plant j: LOCALLY CLOSE AND DE-ENERGIZE MS LOOP "B" TO TDEFPJPM SETUP SHEET RO directs you to open breaker 05EH on XMC1DA2X and locally closing valve XVG02802A-MS in accordance with EOP-3.0, Step 5.h, Alternative Action. The shift supervisor has approved the waiving of ISP-027 requirements due to the emergency condition.The plant was at 100% power when a steamline break occurred inside containment. "B" SG is faulted as indicated by steam pressure dropping in an uncontrolled manner. The CRS has implemented EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, out of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, following a Automatic SI. Both motor driven emergency feedwater pumps started.

TDEFP MS Isolation Valve MVG-02802A will not close from the MCB.

2013 NRC In-Plant k: LOCALLY ISOLATE RCP SEALS DURING A TOTAL LOSS OF ESF POWERCANDIDATE:EXAMINER:2 000-175-05-04SIMULATE15NoSeal injection and return valves for RCP seals have been manually isolated per EOP-6.0 Att 9.PLANTTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.6 Locally Isolate RCP Seals per EOP-6.0.TOOLS:EOP-6.0, Attachment 9, LOCALLY OPERATED ISOLATION VALVESFLASHLIGHTRCP seals isolated per Att 9 of EOP-6.0.EOP-6.0LOSS OF ALL ESF AC POWER000055K302Actions contained in EOP for loss of offsite and onsite power 4.34.6 EK3.02 The RO calls and directs you to isolate RCP seals in accordance with Step 1 of Attachment 9 of EOP-6.0, LOCALLY OPERATED ISOLATION VALVES.A total loss of offsite power has occurred and both DG's have failed to start. Alternate Seal injection also failed to start on the loss of power.

The CRS has implemented EOP-6.0, LOSS OF ALL ESF AC POWER, and is directing actions for locally isolating RCP seals.MVT-8100 is in the north end of the 412' West Penetration area, which is a Radiation Area. At the discretion of the examiner, have the examinee describe the general location of the valve. Operation of the valve is identical to MVT-8105 and MVG-9606. Ensure to view radiation surveys and to monitor EDs if entering Radiation area.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Locally isolate RCP Seals by closing the following (EOP Step 13):XVT08100-CS, RC PUMP SEAL RETURN HDR ISOL VLV(ORC) (AB-412 West Pen)Evaluator Note: MVT-8100 is in the north end of the 412' West Penetration area, which is a Radiation Area. At the discretion of the examiner, have the examinee describe the general location of the valve. Operation of the valve is identical to MVT-8105 and MVG-9606. Ensure to view radiation surveys and to monitor EDs if entering Radiation area.Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.YesEngages manual handwheel by pressing down on the declutch lever on XVT08100-CS and turns handwheel fully clockwise.Yes 1

Locally isolate RCP Seals by closing the following (EOP Step 13):XVG09606-CC, RB CC RETURN HEADER VALVE (AB-436 West Pen)Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.YesEngages manual handwheel by pressing down on the declutch lever on XVG09606-CC and turns handwheel fully clockwise.Yes 2Locally isolate RCP Seals by closing the following (EOP Step 13):

XVT08105-CS, SEAL INJECTION HEADER ISOLATION VALVE (AB-436)Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.YesEngages manual handwheel by pressing down on the declutch lever on XVT08105-CS and turns handwheel fully clockwise.Yes 3

Contact the Control Room to determine if the Alternate Seal Injection System has actuated.Evaluator Cue: If called as the control room reply that Alternate Seal Injection has not been actuated.YesDetermines from initial cue or from calling the control room that Alternate Seal Injection has not actuated and that the alternate action is necessary.

No 4If the Alternate Seal Injection System has not actuated, close all the following:XVT08102A-CS, RC PUMP A SEAL SUPPLY ISOL VALVE (ORC) (AB-412 West Pen).Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.YesEngages manual handwheel by pressing down on the declutch lever on XVT08102A-CS and turns handwheel fully clockwise.Yes 5

Examiner ends JPM at this point.If the Alternate Seal Injection System has not actuated, close all the following:XVT08102B-CS, RC PUMP B SEAL SUPPLY ISOL VALVE (ORC) (IB-412 East Pen).Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.Evaluator Note: When validated this valve did not have a large placard, but did have a CHAMPS tag.YesEngages manual handwheel by pressing down on the declutch lever on XVT08102B-CS and turns handwheel fully clockwise.Yes 6If the Alternate Seal Injection System has not actuated, close all the following:

XVT08102C-CS, RC PUMP C SEAL SUPPLY ISOL VALVE (ORC) (IB-412 East Pen).Evaluator Cue: Cue applicant that valve moves in the clockwise direction and then stops.YesEngages manual handwheel by pressing down on the declutch lever on XVT08102C-CS and turns handwheel fully clockwise.Yes 7

JPPF-066A2013 NRC In-Plant k: LOCALLY ISOLATE RCP SEALS DURING A TOTAL LOSS OF ESF POWERJPM SETUP SHEET The RO calls and directs you to isolate RCP seals in accordance with Step 1 of Attachment 9 of EOP-6.0, LOCALLY OPERATED ISOLATION VALVES.A total loss of offsite power has occurred and both DG's have failed to start. Alternate Seal injection also failed to start on the loss of power.

The CRS has implemented EOP-6.0, LOSS OF ALL ESF AC POWER, and is directing actions for locally isolating RCP seals.

2013 NRC Sim a RO&SRO-I&SRO-U: CONTINUOUS ROD WITHDRAWALCANDIDATE:EXAMINER:2 000-006-05-01PERFORM10NoThe reactor is tripped per AOP-403.3, CONTINUOUS CONTROL ROD MOTION, to terminate the transient prior to exceeding Reactor trip setpoints.

Immediate actions of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, are completed.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.3RESPOND TO CONTINUOUS ROD MOTIONTOOLS:GOP-3, REACTOR STARTUP FROM HOT STANDBY TO STARTUP (MODE 3 TO MODE 2)

AOP-403.3, CONTINUOUS CONTROL ROD MOTION EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATIONImmediate actions of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION are complete.0000012413Knowledge of crew roles and responsibilities during EOP usage.

4.04.6 2.4.13 Increase reactor power to 10-3% per GOP-3 starting at Step 3.12.GOP-3, REACTOR STARTUP FROM HOT STANDBY TO STARTUP (MODE 3 TO MODE 2), is in progress after a short mini-outage.

The shutdown banks have been fully withdrawn. Step 3.11 is complete. Estimated critical position is 100 steps on bank "D".WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Review GOP Appendix A, Generic Operating Precautions, for Reactor Startup.Evaluator Note: This JPM can be briefed outside of the simulator and this step can occur outside of the simulator.YesReviews GOP Appendix A, Generic Operating Precautions, for Reactor Startup.

No 1Procedure Caution: To prevent any inadvertent inward rod motion the ROD CNTRL BANK SEL Switch should not be placed in or pass through AUTO.Place the ROD CNTRL BANK SEL Switch in MAN.YesROD CNTROL BANK SEL Switch taken counter clockwise to MAN.Yes 2

Procedure Note: A stable Startup Rate of one decade per minute should NOT be exceeded.Using ROD CONTROL ROD MOTION lever, commence Control Bank Rod withdrawal to ten steps on Bank A.YesSteps indicate ten steps on Bank A.Yes 3Procedure Caution: 12 steps should NOT be exceeded until all Rod Bottom lights are off. If all Control Bank A Rod Bottom lights are NOT off at ten steps, AOP-403.5, Stuck Or Misaligned Control Rod, should be entered.At ten steps on Control Bank A, stop and verify:1) Bank A RB lights clear.2) ONE ROD ON BOTTOM (XCP-621 3-1) annunciator clears.

3) RODS ON BOTTOM (XCP-621 3-2) annunciator clears.Yes1) Bank A RB lights clear.

2) ONE ROD ON BOTTOM (XCP-621 3-1) annunciator clears.

3) RODS ON BOTTOM (XCP-621 3-2) annunciator clears.

No 4

Recommence withdrawing rods while observing that the groups sequence properly.Evaluator Note: When rods are >53 steps on Bank A then the continuous rod motion will occur.Booth Operator Cue: Cue examinee about next planned ICRRs in accordance with REP-109.002, Enclosure 9.2, ones necessary are (all are on Bank A) 0 (should have started JPM with this one done), 10 53, and 103.YesContinues to pull rods.

No 5Enters AOP-403.3, CONTINUOUS CONTROL ROD MOTION.Evaluator Note: The applicant is not expected to pull out the procedure, but may perform the actions of this procedure from memory and trip the unit.YesEnters AOP-403.3, CONTINUOUS CONTROL ROD MOTION.

No 6

Verify rod motion is NOT required:Tavg is within 1.5 °F of Tref.

AND No load rejection has occurred (C7A OR C7B).Evaluator Note: This is an immediate operator action.YesNotes that rod motion is not required.

No 7Verify rod motion is stopped.

Evaluator Note: This is an immediate operator action.YesNotes that rod motion has not stopped.

No 8

Perform the following:a) Trip the Reactor.

b) GO TO EOP-1.0. REACTOR TRIP/SAFETY INJECTION ACTUATION.Evaluator Note: This is an immediate operator action.YesTurns reactor trip switch to trip.Yes 9

Procedure Note: Steps 1 through 5 are Immediate Operator Actions. The EOP REFERENCE PAGE should be monitored throughout the use of this procedure.

Conditions for implementing Emergency Plan Procedures should be evaluated using EPP-001, ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN.Verify Reactor Trip:Trip the Reactor using either Reactor Trip Switch.Verify all Reactor Trip and Bypass Breakers are open.Verify all Rod Bottom Lights are lit.

Verify Reactor Power level is decreasing.Evaluator Note: This is an immediate operator action.YesReactor Trip and Bypass Breakers indicate green light lit red light off.Rod Bottom Lights are lit.

Reactor Power level is decreasing.

No 10 Verify Turbine/Generator Trip:a. Verify all Turbine STM STOP VLVs are closed.

b. Ensure Generator Trip (after 30 second delay):

1) Ensure the GEN BKR is open.

2) Ensure the GEN FIELD BKR is open.

3) Ensure the EXC FIELD CNTRL is tripped.Evaluator Note: This is an immediate operator action.YesGEN BKR, GEN FIELD BKR, and EXC FIELD CNTRL indicate green light lit and red light off.

No 11Verify both ESF buses are energized.

Evaluator Note: This is an immediate operator action.YesPotential lights on 1DA and 1DB are lit for all three phases.

No 12 Check if SI is actuated:a. Check if either:

SI ACT status light is bright on XCP-6107 1-1.

OR Any red first-out SI annunciator is lit on XCP-626 top row.Alternate action go to Step 5.Evaluator Note: This is an immediate operator action.YesGoes to Step 5.

No 13 Examiner ends JPM at this point.Check if SI is required: a. Check if any of the following conditions exist:

PZR pressure LESS THAN 1850 psig.

OR RB pressure GREATER THAN 3.6 psig.

OR Steamline pressure LESS THAN 675 psig.

OR Steamline differential pressure GREATER THAN 97 psid. Alternate action GOT TO EOP-1.1, REACTOR TRIP RECOVERY, Step 1.YesTransitions to EOP-1.1, REACTOR TRIP RECOVERY.

No 14 NJPSF-141A2013 NRC Sim a RO&SRO-I&SRO-U: CONTINUOUS ROD WITHDRAWAL 330/15 IC 15 MAL-PCS009AB REACTOR TRIP BREAKER A FAILURE (FAIL TO OPEN) Delay=0, Ramp=0, Final=AUTO_(UV)

MAL-PCS009BB REACTOR TRIP BREAKER B FAILURE (FAIL TO OPEN) Delay=0, Ramp=0, Final=AUTO_(UV)

Event #1Mcrfpa(5) >53 Trigger #1 MAL-CRF006B UNCONTROLLED MANUAL ROD MOTION Delay=0, Ramp=0, Final=ActiveJPM is terminated after the reactor is tripped and immediate operator actions of EOP-1.0 are completed.Provide a surrogate to conduct REP-109.002.make sure Auto Count Rate is in service. Data from REP-109.002 does not reset with a simulator reset so it must be manually reset as well as putting the reactivity point and in and out of service before and after the startup.Ensure Audio Count Rate (step 3.4.e), HIGH FLUX AT SHUTDOWN is blocked (step 3.11.b), IPCS indicates MODE 2 (step 3.11.f), NR-45 is in HI speed (Audio count rate and NR-45 should be the two that are not saved with the snap).

JPM SETUP SHEET Increase reactor power to 10-3% per GOP-3 starting at Step 3.12.GOP-3, REACTOR STARTUP FROM HOT STANDBY TO STARTUP (MODE 3 TO MODE 2), is in progress after a short mini-outage.

The shutdown banks have been fully withdrawn. Step 3.11 is complete. Estimated critical position is 100 steps on bank "D".

2013 NRC Sim b RO&SRO-I&SRO-U: SWAP RUNNING RBCU'SCANDIDATE:EXAMINER:2 022-003-01-01PERFORM5NOXFN-065B is secured (the original three RBCU's are running) and RBCU TRAIN B EMERG is selected to XFN-064B.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.4START THE REACTOR BUILDING VENTILATION SYSTEM PER SOP

-114.TOOLS:SOP-114 III. A. OPERATING REACTOR BUILDING COOLING UNITSXFN-065B is secured (the original three RBCU's are running) and RBCU TRAIN B EMERG is selected to XFN-064B.022000A401CCS fans 3.63.6 A4.01 The CRS directs you as the RO to start XFN-065B in fast speed and to secure XFN-065A in accordance with SOP-114 Section III. A.

OPERATING REACTOR BUILDING COOLING UNITS. The initial conditions have been verified to be complete.100% Power.

The current lineup of the RBCU's is as follows:

XFN-064A, XFN-065A, XFN-064B are all running in fast speed.

XFN-065B is secured.It is desired to tagout XFN-065A for testing.None.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Note: a. Due to eddy current brakes, RBCU control switches must be held in START position until the red beaker closed light is lit and starting current is indicated on appropriate meter.

B. Normal and preferred lineup is three RBCUs running in NORM (fast speed).

C. To increase stay times for teams entering containment, four RBCUs may be placed in service in NORM (fast speed).Place RBCUs in service by starting three or four RBCUs in SLOW or NORM as follows: For XFN0065B-AH, REACTOR BLDG COOLING UNIT 2B EMERG FAN, start one of the following: 1)

XFN 0065B-AH, 2B NORM.YesTakes and holds XFN 0065B-AH, 2B NORM to START until red breaker closed light is lit and starting current is indicated.

No 1

Procedure Note: Contact PSE to evaluate, if RBCU fan motor amps exceed the values given.Verify RBCU Fan motor amps return to normal operating range: 1) For fast speed operation, 275 amps to 300 amps. Remove RBCU fan from service due to above normal amps.Booth Cue: If called as PSE to evaluate, report "The fan is inoperable. Remove the fan from service to preclude damage."Evaluator Cue: If as the CRS/SS you are told of the discrepancy in amps by the RO report that the RBCU is being declared inoperable and should be removed from service.Evaluator Note: The candidate may secure the RBCU due to abnormal amps prior to contacting PSE but a cue has to be given that the RBCU is inoperable for Step 3 to be critical.Evaluator Note: This is where the JPM becomes alternate path.YesTakes and holds XFN 0065B-AH, 2B NORM to STOP until green breaker opened light is lit and current returns to zero.Yes 2

Examiner ends JPM at this point.Procedure Note: The RBCU TRAIN A (B) EMERG switch must be selected to an operable RBCU.Verify the following switches are in the desired position:1) XFN-64A/XFN 65A - RBCU TRAIN A EMERG.

2) XFN-64B/XFN 65B - RBCU TRAIN B EMERG.YesTakes XFN-64B/XFN 65B - RBCU TRAIN B EMERG to XFN-64B position.Yes 3

NJPSF-1592013 NRC Sim b RO&SRO-I&SRO-U: SWAP RUNNING RBCU'S 331/10 IC 10. Pre-Event Load Select RBCU TRAIN A EMERG to XFN-65A and select RBCU TRAIN B EMERG to XFN-65B.

PMP-AH049B XFN0065BH RB CLG RAN HIGH BRG FAILURE Final=1.1 Saved to IC 331.Need to provide copies of procedure since is not laminated in the simulator. Circle and slash steps 1.1-1.3.JPM SETUP SHEET The CRS directs you as the RO to start XFN-065B in fast speed and to secure XFN-065A in accordance with SOP-114 Section III. A.

OPERATING REACTOR BUILDING COOLING UNITS. The initial conditions have been verified to be complete.100% Power.

The current lineup of the RBCU's is as follows:

XFN-064A, XFN-065A, XFN-064B are all running in fast speed.XFN-065B is secured.It is desired to tagout XFN-065A for testing.

2013 NRC Sim JPM c RO&SRO-I: INCREASE LETDOWN FLOW TO A MAXIMUM TO IMPROVE CHEMISTRYCANDIDATE:EXAMINER:2 044-031-01-01PERFORM10NoLetdown flow is increased to about 120 gpm without ever exceeding 120 gpm. Letdown pressure controlled such that the letdown relief valve does not open.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.6Adjust Letdown Flowrate per SOP-102.TOOLS:SOP-102 Section IV. R. SHIFTING LETDOWN ORIFICES WITH NORMAL LETDOWN IN SERVICELetdown flow at 120 gpm with PCV-145 returned to AUTO.004000A419CVCS letdown orifice isolation valve and valve control switches 3.12.8 A4.19 The CRS directs you as the RO to increase letdown flow to the maximum in accordance with SOP-102,Section IV.R. SHIFTING LETDOWN ORIFICES WITH NORMAL LETDOWN IN SERVICE.100% power. Chemistry has called and wants to maximize letdown to improve primary chemistry.None.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Note: More than two Letdown Orifices may be placed in service when RCS pressure is less than or equal to 1000 psig as long as a Letdown flow rate of 120 gpm is not exceeded.Verify Initial Conditions:1.1 Letdown is in service (Letdown flow rate of 60 gpm to 120 gpm).1.2 Pressurizer level is greater than 18%.Evaluator Cue: The applicant may request further direction about what it means to raise letdown to a maximum (which valves are desired to be open). Ask for a recommendation and approve the recommendation given. The desired line up will be PVT-8149B and PVT-8149C open and PVT8149A closed.YesVerifies current letdown flow at 95 gpm.Verifies current pressurizer level is 60%.

No 1Place PCV-145, LO PRESS LTDN, in MAN and open to 70%.YesPCV-145, LO PRESS LTDN, indicates MAN and open to 70%.

No 2

If necessary, close the desired Orifice Isolation Valve:a. PVT-8149A, LTDN ORIFICE A ISOL (45 gpm).

B. PVT-8149B, LTDN ORIFICE B ISOL (60 gpm).

C. PVT-8149C, LTDN ORIFICE C ISOL (60 gpm).Evaluator Note: PVT-8149A, LTDN ORIFICE A ISOL (45 gpm) must be closed before PVT-8149C, LTDN ORIFICE C ISOL (60 gpm) is opened to preclude damage to the demins. If flow is allowed to exceed 120 gpm it constitutes a failure.YesTakes PVT-8149A, LTDN ORIFICE A ISOL (45 gpm) to CLOSE. Verifies green light lit and red light dim.Yes 3Open the desired Orifice Isolation Valve:a. PVT-8149A, LTDN ORIFICE A ISOL (45 gpm).b. PVT-8149B, LTDN ORIFICE B ISOL (60 gpm).

c. PVT-8149C, LTDN ORIFICE C ISOL (60 gpm).YesTakes PVT-8149C, LTDN ORIFICE C ISOL (60 gpm), to OPEN. Verifies red light and green light dim.Yes 4

Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS LTDN PRESS PSIG, between 300 psig and 400 psig.Evaluator Note: This step is critical in that the applicant must do it so that pressure does not exceed the letdown relief setpoint. This will be evidenced by annunciator XCP-613 2-2, LP LTDN RLF TEMP HI.YesPCV-145, LO PRESS LTDN, adjusted to maintain 300-400 psig as indicated on PI-145.Yes 5Ensure PCV-145 Setpoint Pot is set between 5.0 and 6.7.YesPCV-145 Setpoint Pot is between 5.0 and 6.7.

No 6

Examiner ends JPM at this point.Place PCV-145, LO PRESS LTDN, in AUTO.YesPCV-145, LO PRESS LTDN, indicates AUTO.

No 7

NJPS-034A2013 NRC Sim JPM c RO&SRO-I: INCREASE LETDOWN FLOW TO A MAXIMUM TO IMPROVE CHEMISTRY 10No special instructions, Just reset to IC-10.Need to provide copies of procedure since it is not laminated in the simulator.

JPM SETUP SHEET The CRS directs you as the RO to increase letdown flow to the maximum in accordance with SOP-102,Section IV.R. SHIFTING LETDOWN ORIFICES WITH NORMAL LETDOWN IN SERVICE.100% power. Chemistry has called and wants to maximize letdown to improve primary chemistry.

2013 NRC Sim JPM d RO&SRO-I: ALTERNATE ISOLATION OF RUPTURED SG ("C" MSIV FAILS TO CLOSE)CANDIDATE:EXAMINER:13 000-504-05-01PERFORM15NOThe "C" SG is completely isolated from the "A" and "B" SG's per EOP-4.0, steps 3.a - 3h, and step 3.i alternate actions.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.6Perform Ruptured Steam Generator Isolation.TOOLS:EOP-4.0, STEAM GENERATOR TUBE RUPTUREEOP-4.0, step 3.i complete.EOP-4.0STEAM GENERATOR TUBE RUPTURE000038A132Isolation of a ruptured S/G 4.64.7 EA1.32 The CRS has directed you as the BOP to isolate the "C" SG in accordance with EOP-4.0, STEAM GENERATOR TUBE RUPTURE, step 3.The "C" Steam Generator has experienced a tube rupture. The crew has taken actions through step 2 of EOP-4.0, STEAM GENERATOR TUBE RUPTURE. The RO has been assigned to monitor RCP trip criteria of step 1.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Caution: At least one SG must be maintained available for RCS cooldown.Place the Steamline PWR RELIEF A(B)(C) SETPT Controller(s) in MAN and closed.Yes"C" Steamline PWR RELIEF SETPT controller indicates manual and 0.

No 1Adjust the PWR RELIEF A(B)(C) SETPT Controller(s) to 8.85 (1150 psig).Yes"C" Steamline PWR RELIEF SETPT controller indicates 8.85 (1150 psig).Yes 2

Place the Steamline Power Relief A(B)(C) Mode Switch(s) in PWR RLF.Yes"C" Steamline Power Relief mode switch indicates PWR RLF.Yes 3Place the PWR RELIEF A(B)(C) SETPT Controller(s) in AUTO.Yes"C" Steamline PWR RELIEF SETPT controller indicates AUTO.

No 4

WHEN RCS Tavg is LESS THAN P-12 (552°F), THEN place both STM DUMP INTERLOCK Switches to BYP INTLK.Evaluator Note: If RCS Tavg is >552°F then this step is not performed at this time.YesBoth STM DUMP INTERLOCK switches indicate BYP INTLK (red flag) when RCS Tavg <552°F.

No 5Verify the Steamline PORV closed.YesPCV-2020 indicates red light off, green light on. Demand on controller is zero.

No 6

Procedure Caution: If the TD EFW Pump is the only available source of feed flow, the steam supply to the TD EFW Pump must be maintained from at least one SG, to maintain a secondary heat sink.Procedure Note: If the TD EFW Pump is tripped, it should be reset as time permits.

IF SG B OR SG C is RUPTURED, THEN perform the following:1) IF at least one MD EFW Pump is running, THEN isolate the TD EFW Pump by placing PVG-2030, STM SPLY TO TD EFP TRN A(B), to CLOSE.Evaluator Note: Both PVG-2030 switches must be taken to close before the valve closes.Booth Operator Cue: When called to reset the TD EFW Pump use the LOA resets page or trigger #1 to reset TD EFW Pump after it comes to a stop.YesPVG-2030 STM SPLY TO TD EFP TRN A (B) indicates red light off and green light on.Yes 7

Notify local Operators to perform Alternate Action Step 3.g, while continuing with this procedure.Booth Operator Cue: When called to perform Alternate Action Step 3.g use trigger #2 and #3 to do so.Booth Operator Note: If called for repeat back of Alternate Action Step 3.g it is as follows for SG C:1) Open XMC1DB2Y 05EH, EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463). Trigger #2 Unit 6U2) Close XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPLY VLV (IB-436 East Pen). Trigger #3 Unit 7.YesCalls local operator to perform Alternate Action Step 3.g No 8Close the following for each RUPTURED SG: SG Blowdown, PVG-503A(B)(C).YesPVG-503C indicates red light off, green light on.

No 9

Close the following for each RUPTURED SG:MS Drain Isolation, PVT-2843A(B)(C).YesPVT-2843C indicates red light OFF, green light ON.Yes 10Close the following for each RUPTURED SG:MS Drain Isolation, PVT-2877A for SG A PVT-2877B for SG C.YesPVT-2877B indicates red light OFF, green light ON.Yes 11 Close the following for each RUPTURED SG:- MS Isolation Valve, PVM-2801A(B)(C). - MS Isolation Bypass Valve, PVM-2869A(B)(C).Evaluator Note: Operator may send someone out to locally close the "C" MSIV while proceeding.Evaluator Note: This is when the JPM becomes alternate path.Booth Operator Cue: If called to locally close the "C" MSIV wait 5 minutes and report that you have bleed air off the "C" MSIV but it did not go closed.YesNotes MS Isolation Valve, PVM-2801C still indicates red light on, green light off (MSIV failed to close).MS Isolation Bypass Valve, PVM-2869C indicates red light off, green light on.

No 12

1) Close the following:All remaining MS Isolation and MS Isolation Bypass Valves.YesPVM-2801A&B, MS ISOLATION VALVE, PVM-2869A&B, MS ISOLATION BYPASS VALVE, indicate red light off and green light on.Yes 131) Close the following:PCV-2058, MS TO AUX STMYesPCV-2058, MS TO AUX STM, indicates red light off and green light on.

No 14

1) Close the following:MVG-1701, STEAM SEAL FEED VLVYesMVG-1701, STEAM SEAL FEED VLV, indicates red light off and green light on.Yes 151) Close the following:

MVG-2896A, SV-1 BSD.MVG-2896B, SV-2 BSD.

MVG-2896C, SV-3 BSD.

MVG-2896D, SV-4 BSD.YesCloses MVG-2896A-D, SV-1 (2,3,4) BSD, indicates red light off and green light on.Yes 16

1) Close the following:IPV-2231, MS/PEGGING STM TO DEAERATOR.YesPlaces IPV-2231, MS/PEGGING STM TO DEAERATOR, controller in MAN and output of 0%.

No 172) At the Digital Control Station for the MSRs, ensure the following are closed:

MVG-2811.XVG-2807.YesAt MSR DCS terminal, MVG-2811 and XVG-2807 indicate closed.

No 18

3) Place the STM DUMP CNTRL Controller in MAN and closed.YesSTM DUMP CNTRL controller in MAN with 0% output No 194) Place the STM DUMP MODE SELECT Switch in STM PRESS.YesSTM DUMP MODE SELECT Switch in STM PRESS.

No 20 Examiner ends JPM at this point.5) Place the following in AUTO and ensure the valves are closed (REFER TO ATTACHMENT 1, ALTERNATE ISOLATION OF RUPTURED STEAM GENERATORS, if necessary to locally isolate valves):PVT-2870, TO MSR A & B DRN.PVT-2875, TO MSR A & B DRN.

PVT-2851A,B,C,D, MS LINES TO TURB DRN.PVT-2713A,B,C,D, STM DUMP DRN BYP.PVT-2838A,B, HDR DRNS.6) Direct the Turbine Building Operator to complete ATTACHMENT 1, ALTERNATE ISOLATION OF RUPTURED STEAM GENERATORS.Evaluator Note: Step one of Attachment 1 is always done and step two contains backup valves for any valves that fail to close. PVT-2870 fails to close so the TB operator will be called to complete the alternate isolation of PVT-2870, TO MSR A & B DRN in step two of Attachment 1 as well as to perform step one of Attachment 1.Evaluator Note: Due to the complexity of this task the applicant may call an auxiliary operator to the control room to effectively communicate the desired local actions. Evaluator Note: The JPM can be stopped once the order to complete Attachment 1 is given.YesNotes PVT-2870, To MSR A&B DRN indicates mid-position with red and green light on. Directs Turbine Building Operator to complete ATTACHMENT 1, ALTERNATE ISOLATION OF RUPTURED STEAM GENERATORS. Including alternate isolation for PVT-2870.The following valve switches are in AUTO with red light OFF and green light ON:- PVT-2875, TO MSR A&B DRN

- PVT-2851A-D, MS LINES TO TURB DRN

- PVT-2713A-D, STEAM DUMP DRN BYP

- PVT-2838A,B, HDR DRNS.

No 21 NJPSF-059B2013 NRC Sim JPM d RO&SRO-I: ALTERNATE ISOLATION OF RUPTURED SG ("C" MSIV FAILS TO CLOSE) 333/ 10Start at IC 10 MAL-RCS002C STEAM GENERATOR C TUBE LEAK Final=400 RAMP=00:00:30 (SGTR ON 'C' S/G)MAL-MSS006C MAIN STEAM ISOLATION VALVE (S/G C) FAILURE Final= FAIL TO CLOSE (C MSIV FAIL TO CLOSE)VLV-MS041P XVT02870-MS MS LINE TO MOSS SEP DEP DRN FAIL POSITION Final = 80 (2870 Failed 80% open)

Manual SI and perform actions of EOP-1.0 & EOP-4.0 up through step 2.

Throttle EFW flow to 'C' S/G when > 40% level.

Silence HVAC alarms.

This is where IC is saved.

RUN 5 seconds day of and acknowledge annunciators When student is ready: RUN Local Operator Actions when instructed:Trigger #1: EOP-4.0, STEAM GENERATOR TUBE RUPTURE, 3.g LOA-MSS026 EMERGENCY FW TDFP MN STM THROTTLE VLV 2865 RESET Final=RESET (Reset TDEFW pump once RPM's reach 0.0.Trigger #2: EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Alternate action 3.g LOA-MSS033 TDEFP STM SUP VLV 2802B BRK Final=OPEN (Open XMC1DB2Y 05EH, EF PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463)Trigger #3: EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Alternate action 3.g VLV-MS009P XVG02802B-MS MS LP C TO TD EF PMP FAIL POSITION Final=0, Ramp=00:00:30 (CLOSE XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPLY VLV (IB-436 East Pen).EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Alternate Action 3.i.5) refer to Attachment 1, ALTERNATE ISOLATION OF RUPTURED STEAM GENERATORS PVT-2870, TO MSR A & B DRN.Currently there is no modeling of XVT02871A-MS MSR A&B MS SUP HDR DRAIN POT OUTLET VLV (TB-412) but report that it is closed .

Saved to IC 333 (about 3.5 minutes in get an ops crit alarm at about 4.5 minutes get a Lo-Lo Tavg due to drain vlv being open do we need cleaner?). RE-SNAP after Lo-Lo Tavg alarm comes in.

JPM SETUP SHEET Circle and slash up to step 3.0 of EOP-4.0, STEAM GENERATOR TUBE RUPTURE.

The CRS has directed you as the BOP to isolate the "C" SG in accordance with EOP-4.0, STEAM GENERATOR TUBE RUPTURE, step 3.The "C" Steam Generator has experienced a tube rupture. The crew has taken actions through step 2 of EOP-4.0, STEAM GENERATOR TUBE RUPTURE. The RO has been assigned to monitor RCP trip criteria of step 1.

2013 NRC Sim JPM e RO&SRO-I: SHIFT RHR LOOPS WITH RHR IN SERVICECANDIDATE:EXAMINER:3 005-001-01-01PERFORM15NORHR train "A" is providing core cooling. RHR Train "B" is secured. RCS temperatures remain less than 200°F to preclude unplanned/allowed entry into MODE 4.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.7Perform Lineups of the Residual Heat Removal SystemTOOLS:SOP-115, RESIDUAL HEAT REMOVALRHR Train "A" is in service with RHR Train "B" shut down.SOP-115RESIDUAL HEAT REMOVAL005000A401Controls and indication for RHR pumps3.63.4 A4.01 The CRS directs you as the RO to shift from RHR Train "B" to RHR Train "A" running in accordance with SOP-115, RESIDUAL HEAT REMOVAL, section III.E, SHIFTING FROM RHR TRAIN B TO RHR TRAIN A RUNNING, starting with step 2.1.

"A" CCW will remain the active loop.Plant heatup is in progress in accordance with GOP-2, PLANT STARTUP AND HEATUP (MODE 5 TO MODE 3).

The crew has performed all steps up to step 3.4 of GOP-2 and is currently drawing a bubble with pressurizer level on scale on wide range level. The ABLL has reported that the "B" RHR Pump bearing is making loud unusual noises and is worried about damage to the pump since it is vibrating excessively.

The CRS and Shift Supervisor have determined that "A" RHR loop be placed in service and the plant maintained in Mode 5.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Caution: a. Performance of this procedure while RCS Hot Leg temperatures are greater than or equal to 200°F renders both RHR Loops incapable of being aligned to the RWST (reference Technical Specification 3.5.3.d) until the Hot Leg temperatures are reduced to less than 200°F.

b. Unless Plant conditions absolutely require shifting trains of RHR, this procedure should not normally be utilized in Mode 4.c. PCV-145, LO PRESS LTDN, must be in MAN if starting or stopping an RHR Pump with the primary system solid with RHR letdown flow via HCV-142, LTDN FROM RHR.Ensure the following valves are energized and open per GOP-6, Plant Shutdown From Hot Standby To Cold Shutdown (Mode 3 To Mode 5):

a. MVG-8701A, RCS LP A TO PUMP A.B. MVG-8702A, RCS LP A TO PUMP A.YesVerifies MVG-8701A and MVG-8702A are energized and open - Red lights ON, green lights OFF No 1

Ensure Train "A" Component Cooling is aligned to supply RHR Heat Exchanger "A" per SOP-118YesDetermines that "A" Component Cooling is aligned to supply the "A" RHR heat exchanger.

No 2Close HCV-603A, A OutletYesRotates controller for HCV-603A fully counter-clockwise No 3

Place FCV-605A, A BYP, in MAN and adjust to 100%YesPlaces controller for FCV-605A in MANUAL and adjusts output to 100%

No 4Readjust FCV-605A, A BYP, in MAN to 40%.YesAdjusts output for FCV-605A to 40%

No 5

Place PCV-145, LO PRESS LTDN, in MANYesPlaces controller for PCV-145 in MANUAL No 6Procedure Note: a. RHR Pump run time on miniflow should not be permitted to exceed 30 minutes.b. After each RHR Pump start, IFI00602A (AB-374) indication should be evaluated to verify proper operation of IFV0602A.Start XPP-0031A, Pump ABooth Operator Cue: If called to check out the RHR pump for start report that the pump is good for start. If called to investigate the pump after start, report that the pump looks good after start. When called to investigate IFI00602A report that flow is 1000 gpm.Evaluator Note: Applicant will ask for a peer check as required by the procedure. Acknowledge that the applicant would ask for a peer check.YesPlaces RHR Pump "A" control switch in START. Verifies amps and control switch indication turns red.Yes 7

Place PCV-145, LO PRESS LTDN, in AUTOYesPlaces controller for PCV-145 in AUTOMATIC No 8Equalize flow between the two RHR loops by slowly opening FCV-605A, A BYP.Evaluator Note: Flow will not totally equalize between the two loops. It is critical that "A" loop RHR flow is established not that flows are brought to be equal.YesObserving flow, slowly increases the output of the controller for FCV-605A until flows are approximately equal.Yes 9

Place FCV-605A, A BYP, in AUTO.YesFCV-605A, A BYP, in AUTO No 10Procedure Caution: In Mode 6, RHR flow must be greater than 2800 gpm per Technical Specifications 3.9.7.1 and 3.9.7.2.Procedure Note: If RCPs or two trains of RHR are running, RHR flow may be less than 3750 gpm. FCV-605A controller setpoint may need to be adjusted to less than the normal flow setpoint to improve temperature control while cooling down.Ensure FCV-605A, A BYP, modulates to maintain between 2000 GPM and 3750 GPM as indicated on FI-605A, PUMP A FLOW GPM.YesVerifies indicated flow on FI-605A is between 2000 and 3750 GPM.

No 11 Shift Letdown from RHR Train B to RHR Train A as follows (AB-412):Open XVT08720A-RH, LETDOWN HDR RH RETURN HDR A INLET VALVE Close XVT08720B-RH, LETDOWN HDR RH RETURN HDR B INLET VALVEBooth Operator Cue: When called to Open XVT-8702A use Trigger 1 to open the valve.When called to close XVT8702B use Trigger 2 to close the valve.YesDirects operator to perform valve alignment No 12Align RHR Loop B for Standby Operation as follows:Shift all heat removal to Loop A by slowly opening HCV-603A, A OUTLET, while adjusting HCV-603B, B OUTLET, closedEvaluator Note: It is critical that RCS temperature is not allowed to increase above 200°F because this would be an unplanned mode change into MODE 4.YesAdjusts HCV-603A in the clockwise direction and HCV-603B in the counter clockwise direction while maintaining approximately the same total RHR flow.

Continues to throttle HCV-603A open and HCV-603B closed until all flow is on Train "A"Yes 13 Close HCV-603B, B OUTLET NoRotates controller for HCV-603B fully counter clockwise No 14Place FCV-605B, B BYP, in MAN and adjust to 40%YesPlaces controller for FCV-605B in MANUAL and adjusts controller output to 40%

No 15 Secure the RHR Pump B as follows:1) If the primary system is solid, a) Place PCV-145, LO PRESS LTDN, in MAN.

b) Stop XPP-0031B, PUMP B.

c) Place PCV-145, LO PRESS LTDN, in AUTO.

2) If there is a steam bubble in the Pressurizer, stop XPP-0031B, PUMP B.Evaluator Note: There is a bubble in the Pressurizer.Evaluator Cue: Cue the applicant as the CRS to place the B RHR pump control switch in PTL for maintenance to look at the pump.YesPlaces "B" RHR Pump Control Switch in STOP. Observes green light on, red light off. Amps go to zero.Yes 16Close FCV-605B, B BYPYesAdjusts the controller for FCV-605B to 0%

No 17 Examiner ends JPM at this point.Open HCV-603B, B OUTLET NoAdjusts the controller for HCV-603B fully clockwise No 18Establish a cooldown rate.YesAdjusts HCV-603A, A OUTLET, to establish a cooldown rate that does not exceed 50°F/hr.Yes 19 NJPS-1512013 NRC Sim JPM e RO&SRO-I: SHIFT RHR LOOPS WITH RHR IN SERVICE 334/2Start with IC 2. IC set 2 is collapsing the bubble. Change parameters to slowly draw a bubble. Stabilize RCS pressure 350-400 psig and RCS temperature at ~188°F (Open CCW "A" to RHR HX).

Saved to IC 334.

Trigger 1:8720A (open) LOA-RHR001 Final=1 Trigger 2: 8702B (close) LOA-RHR002 Final =0JPM SETUP SHEET The CRS directs you as the RO to shift from RHR Train "B" to RHR Train "A" running in accordance with SOP-115, RESIDUAL HEAT REMOVAL, section III.E, SHIFTING FROM RHR TRAIN B TO RHR TRAIN A RUNNING, starting with step 2.1.

"A" CCW will remain the active loop.Plant heatup is in progress in accordance with GOP-2, PLANT STARTUP AND HEATUP (MODE 5 TO MODE 3).

The crew has performed all steps up to step 3.4 of GOP-2 and is currently drawing a bubble with pressurizer level on scale on wide range level.

The ABLL has reported that the "B" RHR Pump bearing is making loud unusual noises and is worried about damage to the pump since it is vibrating excessively.

The CRS and Shift Supervisor have determined that "A" RHR loop be placed in service and the plant maintained in Mode 5.

2013 NRC Sim JPM f RO&SRO-I: RESPOND TO A FEED REGULATING VALVE CLOSURE AT LOW POWERCANDIDATE:EXAMINER:2 000-147-05-01PERFORM10NO"A" steam generator level is controlled by the operator without causing an automatic reactor trip.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.3 Respond to Feedwater Flow Control Valve Failure per AOP-201.1.TOOLS:AOP-210.1, FEEDWATER FLOW CONTROL VALVE FAILURE"A" S/G level is under control of the operator with the main feed reg bypass valve.059000A212Failure of feedwater regulating valves3.13.4 A2.12 Respond to developing plant conditions as the BOP operator.15% power BOL.None.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Diagnose entry into AOP-210.1, FEEDWATER FLOW CONTROL VALVE FAILURE.Procedure Note: Throughout this procedure, "AFFECTED" refers to any Feedwater Flow Control Valve that has failed open, closed, or does NOT respond to demand.1. Abnormal indication on the associated Feedwater Flow Control Valve controller:PVT-478, SG A FWF.

PVT-488, SG B FWF.

PVT-498, SG C FWF.2. Any of the following Main Control Board annunciators in alarm:SG A(B)© STF>FWF MISMATCH (XCP-624 4-3(5-3)(6-3)).SG A(B)© FWF>STF MISMATCH (XCP-624 4-4(5-4)(6-4)).SG A(B)© LVL DEV (XCP-624 1-5(2-5)(3-5)).

SG A(B)© LVL LO (XCP-624 1-3(2-3)(3-3)).

SG A(B)© LVL HI-HI (XCP-624 1-1(2-1)(3-1)).

SG A(B)© LVL LO-LO (XCP-624 1-2(2-2)(3-2)).Evaluator Note: The applicant may attempt to utilize the ARP actions to correct the level deviations but opening of the bypass valve is unique to the AOP.YesDiagnoses that PVT-478, SG A FWF is closing and enters AOP-210.1, FEEDWATER FLOW CONTROL VALVE FAILURE.

No 1

Manually adjust the AFFECTED Feedwater Flow Control Valve as necessary to maintain Narrow Range SG level between 60% and 65%:

PVT-478, SG A FWF.Evaluator Note: This is an immediate operator action and applicant may do this step without aid of the procedure although that is not required as long as the plant is brought to a stable condition.YesAttempts to take manual control of PVT-478, SG A FWF, but determines that the valve will not open manually.

No 2

Adjust Feedwater Pump speed and Main Turbine load as necessary to maintain SG level. Do NOT exceed 1600 psig Feedwater Pump discharge pressure.Evaluator Note: This is an immediate operator action and applicant may do this step without aid of the procedure although that is not required as long as the plant is brought to a stable condition.Evaluator Note: Note if 1600 psig Feedwater Pump discharge pressure is exceeded the MFP's will trip. Evaluator Note: With the malfunction that is present this action will not be effective and the applicant may skip this step and go directly to the bypass valve.YesRaises MFP speed. Does not exceed 1600 psig Feedwater Pump discharge pressure.

No 3

If feed flow remains low, THEN perform the following:Open the associated bypass valve as necessary to control SG level:

FCV-3321, LOOP A MAIN FW BYP.

FCV-3331, LOOP B MAIN FW BYP.

FCV-3341, LOOP C MAIN FW BYP.Evaluator Note: This is an immediate operator action and applicant may do this steps without aid of the procedure although that is not required as the plant is brought to a stable condition.YesFCV-331, LOOP A MAIN FW BYP is in manual and open. S/G level is controlled between 60% and

65%.Yes 4

Examiner ends JPM at this point.Procedure Note: If the Feedwater Flow Control Valve is closed, the maximum flow attainable with the bypass valve is 20% to 30%.Reduce plant load as necessary to control SG level using the bypass valve. REFER TO GOP-4, POWER OPERATION (MODE 1).Evaluator Note: This is an immediate operator action and applicant may do this steps without aid of the procedure although that is not required as the plant is brought to a stable condition.YesDetermines that "A" SG level can be maintained at current power level.

No 5

NJPSF-1612013 NRC Sim JPM f RO&SRO-I: RESPOND TO A FEED REGULATING VALVE CLOSURE AT LOW POWER 335/44Saved to IC 335 from IC 44When examiner is ready insert Trigger #1.Trigger # 1VLV-FW001P IFV00478-FW SG A FW CTRL VLV FAIL POSITION Delay=0, Ramp=00:01:00, Final=5.JPM SETUP SHEET Respond to developing plant conditions as the BOP operator.15% power BOL.

2013 NRC Sim JPM g RO&SRO-I: START AND LOAD THE MAIN GENERATORCANDIDATE:EXAMINER:2 045-005-01-01PERFORM15NOMain Generator is synchronized with the grid without causing damage to the main generator breaker (closing out of phase) and loaded to 50 MW.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.6Synchronize Turbine Generator with Grid at Minimum Load Per SOP-201/SOP-207/SOP-214/SOP-218/SOP-217TOOLS:SOP-301, MAIN GENERATOR SYSTEM.Main Generator is synchronized with grid and is carrying 50 MW.062000A401All breakers (including available switchyard) 3.33.1 A4.01 The CRS directs you as the BOP to synchronize the Main Generator and load it to 50 MW using SOP-301 Section III. A. STARTUP starting at step 2.3.15% power. The Main Generator is being synchronized in accordance with SOP-301 Section III. A. STARTUP. Step 2.2 has just been completed.None.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Note: The System Controller should be notified as soon as practical, but within 30 minutes if Automatic Regulation is not achieved.Place the GEN VOLT REG XFER Switch, in MAN.Booth Operator Cue: If called as the system controller respond that you understand they are putting the voltage adjust in Manual and to notify that condition exists for >30 minutes. Booth Operator Cue: If asked for a switching order respond that your switching order is 1.YesGEN VOLT REG XFER Switch, in MAN.

No 1Close the GEN FIELD BKR.YesGEN FIELD BKR take to CLOSE. Red light lit. Green light off.Yes 2

Using the EXC FIELD CNTRL Switch, energize the Exciter and Main Generator by placing the switch to CLOSE and verifying the red light illuminates.YesEXC FIELD CNTRL taken to CLOSE Red light lit. Green light off.Yes 3Procedure Note: To prevent inadvertently over or under exciting the Main Generator, the controls for both the Manual and Automatic Regulators are only activated for an interval of 1.0 second per adjustment.Using the EXC FIELD VOLT ADJ (MAN) Control Switch adjust Generator KILOVOLTS to 22 KV (normal band 20.9 to 23.1 KV).YesEXC FIELD VOLT ADJ (MAN) used. KILOVOLTS are between 20.9 and 23.1 KV.

No 4

Using the GEN VOLT SEL Switch, check phase voltages on KILOVOLTS Meter.YesAll positions of GEN VOLT SEL show voltage between 20.9 and 23.1 KV.

No 5Procedure Note: Failure of one regulation mode to track with the other is indicative of a problem with the in-service Core. I&C should be contacted to investigate the problem.Verify the Automatic Regulator tracks to match the Manual Regulator by observing the EXCITER VOLTS Meter trends to 0%.YesEXCITER VOLTS meter is at 0%.

No 6

Transfer the GEN VOLT REG XFER Switch, to AUTO.YesGEN VOLT REG XFER Switch in AUTO.Yes 7Using the GEN FIELD VOLT ADJ (AUTO) Control Switch, cycle Main Generator voltage above and below 22 KV (normal band 20.9 to 23.1 KV) sufficiently to verify control while monitoring that the EXCITER VOLTS Meter trends toward 0% following each cycle.YesVoltage raised and lowered. EXCITER VOLTS Meter trends toward 0%.

No 8

Procedure Note: In order to get the light to change state on any of the active OC2000 Pushbuttons, the button itself must be depressed.Ensure the PSS CNTRL ENABLE Pushbutton is lit (TB-436, OC2000).Booth Operator Cue: When called to ensure PSS CNTRL ENABLE Pushbutton is lit (TB-436, OC2000) respond that it is lit.YesCalls local operator to ensure PSS CNTRL ENABLE Pushbutton is lit (TB-436, OC2000).

No 9Notify the System Controller that the unit is ready to be paralleled and obtain a Switching Order.Booth Operator Cue: When called as System Controller for a Switching Order respond "Parallel to the Grid, Your Switching Order is 1."YesCalls System Controller for Switching Order.

No 10 Place the GEN SYNC NORM FEED Switch, to MAN.Yes GEN SYNC NORM FEED Switch, in MAN.Yes 11Using the GEN FIELD VOLT ADJ (AUTO) Control Switch, adjust GEN VOLTS equal to or slightly higher than SYS VOLTS.YesGEN VOLTS equal or slightly higher than SYS VOLTS.Yes 12 Using the Raise Lower Pushbuttons on the Main Control Board at the Turbine EHC HMI adjust Turbine speed until the SYNCHROSCOPE rotates slowly in the FAST (clockwise) direction.YesSYNCHROSCOPE rotates slowly in the FAST (clockwise) direction.Yes 13When the SYNCHROSCOPE indicator passes 11 o'clock and slowly approaches 12 o'clock, close the GEN BKR. (PEER check)Evaluator Note: This step requires a peer check. Respond that you understand that applicant desires a peer check.YesGEN BKR is closed in phase.Yes 14 Verify the GEN BKR is closed.YesGEN BKR is CLOSED. Red light lit. Green light off.

No 15On the EHC HMI, Control/Load screen, select Ramp Rate and enter desired rate of 1% or less. G. Raise Turbine load to 50 MW by one of the following methods:1) Using the EHC HMI, Control/Load screen, select Manual Adj, Raise.

2) Using the Raise Pushbutton on the Main Control Board at the Turbine EHC HMI.Evaluator Cue: If asked as SS what the desired rate of load increase is respond 0.5 %/min.YesMW indicate ~ 50 MW.

No 16 Examiner ends JPM at this point.Place the GEN SYNCH NORM FEED Switch in OFF.YesGEN SYNCH NORM FEED Switch in OFF.

No 17 NJPS-1622013 NRC Sim JPM g RO&SRO-I: START AND LOAD THE MAIN GENERATOR 336/44Saved to IC-336. Build from IC-44.IC-44.

Ensure IR and PR low trip setpoints are blocked.Roll Main Turbine to 1800 RPM, per SOP-214, Main Turbine And Controls.Freeze.

When applicant is ready go to run.JPM SETUP SHEET The CRS directs you as the BOP to synchronize the Main Generator and load it to 50 MW using SOP-301 Section III. A. STARTUP starting at step 2.3.15% power. The Main Generator is being synchronized in accordance with SOP-301 Section III. A. STARTUP. Step 2.2 has just been completed.

2013 NRC Sim JPM h RO: RESPOND TO HIGH REACTOR BUILDING PRESSURECANDIDATE:EXAMINER:NJPS-15214 029-004-01-01PERFORM20NoRB pressure is reduced <+0.05 and >-0.05 psig on PI-8254, RB NR PRESS PSI.Containment isolation is restored by closing the purge exhaust valves.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.5VENT THE REACTOR BUILDINGTOOLS:SOP-114, REACTOR BUILDING VENTILATION SYSTEM HPP-709, Attachment VI, REACTOR BUILDING PURGE RELEASE PERMIT.RB purge is secured.SOP-114REACTOR BUILDING VENTILATION SYSTEM028000A401HRPS controls 4.04.0 A4.01 Lower RB pressure as required in accordance with SOP-114, REACTOR BUILDING VENTILATION SYSTEM, III.P. LOWERING REACTOR BUILDING PRESSURE USING NORMAL PRESSURE CONTROL starting at step 2.5.Plant is at 100% power. Preparations are underway to conduct maintenance on the Personnel Access inner door.SOP-114, REACTOR BUILDING VENTILATION SYSTEM, III.P. LOWERING REACTOR BUILDING PRESSURE USING NORMAL PRESSURE CONTROL is being used to lower RB pressure.All initial conditions have been met.

A reactor building purge release permit has been issued in accordance with HPP-709. RM-A4 and RM-A2 are in service.RM-A4's setpoint has been adjusted in accordance with the Release Permit and step 2.4 of SOP-114, III.P.None.WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.

Procedure Caution: To prevent damage to Alternate Purge System ducting, Alternate Purge must not be placed in service if RB pressure is greater than 3 psi.Open the following:1) PVG-6066, CNTMT PUR EXH ISOL VLV.2) PVG-6067, CNTMT PUR EXH ISOL VLV.YesPlaces PVG-6066, CNTMT PUR EXH ISOL VLV and PVG-6067, CNTMT PUR EXH ISOL VLV.

switch in the OPEN position. Verifies the valve opens by observing the red light lit and the green light off.Yes 1

Start XFN-96, ALT PUR EXH FAN.Examiner Cue: Cue the applicant that "Time Compression" will be used to expedite the administration of the JPM.Evaluator Note: The procedure requires a peer check at this step. Acknowledge that you understand that the applicant will obtain a peer check.YesPlaces switch for XFN-96 ALT PUR EXH FAN in START. Observes red light ON and green light OFF.Yes 2

Record time release was started and flow rate as indicated on FI-8252, H2 PURGE FLOW CFM, in the following places:

1) Reactor Building Purge Release Permit.

2) Station Log Book.Examiner Cue: Cue applicant that FI-8252, H2 PURGE FLOW CFM is reading 500 cfm.Examiner Cue: Cue the applicant that the start time and flow rate will be transferred to the station log book.YesRecords start time and flowrate as indicated on FI-8252, H2 PURGE FLOW GPM in the Station Log Book and on the Continuous Waste Release Permit.

No 3Records release readings from RM-A2 and RM-A4.YesRecords release readings from RM-A2 and RM-A4.

No 4

If RB pressure is being lowered to support door maintenance, simultaneousopening of both personnel hatch doors or opening of equipment hatch door, perform the following:

a. Monitor PI-8254, RB NR PRESS PSI.

b. When RB pressure is between negative 0.05 psi and positive 0.05 psi, stop XFN-96, ALT PUR EXH FAN.YesChecks RB pressure <+0.05 and >-0.05 psig on PI-8254, RB NR PRESS PSI.

No 5Stop XFN-96, ALT PUR EXH FAN.YesStops XFN-96, ALT PUR EXH FAN.Yes 6

Examiner ends JPM at this point.Close the following:a. PVG-6066, CNTMT PUR EXH ISOL VLV.

b. PVG-6067, CNTMT PUR EXH ISOL VLV.YesPlaces PVG-6066 CNTMT PUR EXH ISOL VLV and PVG-6067 CNTMT PUR EXH ISOL VLV switches in the CLOSE position and verifies the valves go close by verifying green light lit and red light off.Yes 7Record time release was stopped in the following places:

a. Reactor Building Purge Release Permit.

b. Station Log Book.Examiner Cue: Cue the applicant that the release time will be recorded in the station log book and the continuous waste release permit.YesRecords time in the Station Log Book and on the Continuous Waste Release Permit.

No 8

NJPS-1522013 NRC Sim JPM h RO: RESPOND TO HIGH REACTOR BUILDING PRESSURE 99Run when applicant is ready.If IC-99 is not available:Reset to IC 10Event #1 x15i355t>0 Enter MALF RMS004C, CONT BREACH FHB436; Set = 10 SCFT, when examinee starts XFN-96.

Event #2 x15i355s>0&&jmlrms4c>0 (Deletes Malf RMS004C when the examinee secures XFN-96)Provide an operator to silence alarms and have operator silence alarms from the MCB while the applicant is conducting the realease from the HVAC panel.

JPM SETUP SHEET Lower RB pressure as required in accordance with SOP-114, REACTOR BUILDING VENTILATION SYSTEM, III.P. LOWERING REACTOR BUILDING PRESSURE USING NORMAL PRESSURE CONTROL starting at step 2.5.Plant is at 100% power. Preparations are underway to conduct maintenance on the Personnel Access inner door.SOP-114, REACTOR BUILDING VENTILATION SYSTEM, III.P. LOWERING REACTOR BUILDING PRESSURE USING NORMAL PRESSURE CONTROL is being used to lower RB pressure.All initial conditions have been met.A reactor building purge release permit has been issued in accordance with HPP-709. RM-A4 and RM-A2 are in service.RM-A4's setpoint has been adjusted in accordance with the Release Permit and step 2.4 of SOP-114, III.P.HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.