ML13301A739

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

ML13301A739
Person / Time
Site:	Summer
Issue date:	10/23/2013
From:	NRC/RGN-II
To:	South Carolina Electric & Gas Co
References
JPPF-013A
Download: ML13301A739 (130)

Text

2013 NRC In-Plant i: START AND LOAD THE DIESEL GENERATOR DURING CONTROL ROOM EVACUATIONCANDIDATE:EXAMINER:3 000-068-05-01SIMULATE20NODiesel 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.No1Determine 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.No2 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.Yes3Ensure the VOLT REG is in AUTO.Examiner Cue: Cue examinee that VOLT REG switch is in AUTO.

YesVerifies VOLT REG switch is in AUTO.No4 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.No5Attempt 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.No6 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.No7

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.

ORXVM10996B-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.Yes8Verify 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.No9 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.Yes10Depress 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.No11 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.No12Procedure 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.No13 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 7200 KV on 1DA.

YesVerifies BUS 1DA DG FEED indicates red light lit, green light off and voltage is indicated on 1DA.No14Adjust 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.No15 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.No16Notify 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.No17 JPPF-013 A2013 NRC In-Plant i: START AND LOAD THE DIESEL GENERATOR DURING CONTROL ROOM EVACUATIONN/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" AND "C" TO TDEFPCANDIDATE:EXAMINER:2 000-169-05-04SIMULATE20NoTurbine driven emergency feed pump main steam loop "B" and "C" supply valve is manually closed and power removed from 2802A 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-2802A and MVG-2802B are closed and deenergized per EOP-3.0.EOP-3.0FAULTED STEAM GENERATOR ISOLATION035000A406S/G isolation on steam leak or tube rupture/leak4.54.6A4.06061000K103Main steam system3.5 3.9K1.03000040A104Isolation of all steam lines from header4.34.3AA1.04000040A110 AFW System4.14.1AA1.10 RO directs you as the IB operator (Unit 7) to open breaker 05EH on XMC1DA2X and locally close valves XVG02802A-MS and XVG02802B-MS in accordance with EOP-3.0, Step 5.h, Alternative Action. The AB operator (Unit 6 upper) has already opened breaker 05EH on XMC1DB2Y. 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" and "C" SGs are 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. MVG-2802A, MS LOOP B TO TD EFP and MVG-2802B, MS LOOP C TO TD EFP 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.

Locally deenergize and close the appropriate valve. If SG B is faulted:Open XMC1DA2X 05EH, EF PUMP MAIN STEAM BLOCK VLV XVG-2802A-MS (IB-463).Evaluator Note: The only sequence that is important is to open each breaker before closing each valve. If the examinee repositions a valve prior to opening the breaker the JPM is considered unsat.

YesOperator locates the power supply (1DA2X, 05EH) for XVG-02802A and opens the breaker by pullingthe breaker control lever down.Yes1Locally deenergize and close the appropriate valve. If SG C is faulted:

Open XMC1DB2Y 05EH, EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463).Evaluator Note: The only sequence that is important is to open each breaker before closing each valve. If the examinee repositions a valve prior to opening the breaker the JPM is considered unsat.

YesDetermines that the AB operator has already opened XMC1DB2Y 05EH, EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463).No2 Examiner ends JPM at this point.Close XVG02802A-MS, MS HEADER B EF PUMP TURBINE SUPPLY VLV (IB-436 East Pen).Evaluator Note: The only sequence that is important is to open each breaker before closing each valve. If the examinee repositions a valve prior to opening the breaker the JPM is considered unsat.

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.Yes3Close XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPLY VLV (IB-436 East Pen).Evaluator Note: The only sequence that is important is to open each breaker before closing each valve. If the examinee repositions a valve prior to opening the breaker the JPM is considered unsat.

YesOperator locates and closes XVG02802B-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.Yes4 JPP-107 A2013 NRC In-Plant j: LOCALLY CLOSE AND DE-ENERGIZE MS LOOP "B" AND "C" TO TDEFPJPM SETUP SHEET RO directs you as the IB operator (Unit 7) to open breaker 05EH on XMC1DA2X and locally close valves XVG02802A-MS and XVG02802B-MS in accordance with EOP-3.0, Step 5.h, Alternative Action. The AB operator (Unit 6 upper) has already opened breaker 05EH on XMC1DB2Y. 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" and "C" SGs are 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. MVG-2802A, MS LOOP B TO TD EFP and MVG-2802B, MS LOOP C TO TD EFP will not close from the MCB.

2013 NRC In-Plant k: LOCALLY ISOLATE RCP SEALS DURING A TOTAL LOSS OF ESF POWERCANDIDATE:EXAMINER:3 000-175-05-04SIMULATE15NoSeal 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 VALVES FLASHLIGHTRCP 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 power4.34.6EK3.02 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-6.0 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.Yes1 Locally isolate RCP Seals by closing the following (EOP-6.0 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.Yes2Locally isolate RCP Seals by closing the following (EOP-6.0 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.Yes3 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.No4If 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.Yes5 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 CHAMPS tag, but did have a small metal OEM tag.YesEngages manual handwheel by pressing down on the declutch lever on XVT08102B-CS and turns handwheel fully clockwise.Yes6If 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.Yes7 JPPF-066 A2013 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:3 000-006-05-01PERFORM10NoThe 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 MOTIONEOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATIONREP-109.002, Enclosure 9.2, Recommended Rod Positions for ICRR.Immediate actions of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION are complete.0000012413Knowledge of crew roles and responsibilities during EOP usage.4.04.62.4.13 Increase reactor power to 10-3% per GOP-3 starting at Step 3.12. The Examiner will play the role of CRS and Reactor Engineering for this JPM. Reactor engineering has started REP-109.002, INVERSE COUNT RATE RATIO PLOT, and has taken all necessary data and is ready to collect data at 53 steps on Control Bank A.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 of GOP-3 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.No1Procedure 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.Yes2 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.Yes3Procedure 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.No4 Recommence withdrawing rods while observing that the groups sequence properly.Evaluator Cue: The examinee should stop pulling rods at 53 steps to collect data for inverse count rate ratio plot. Once the examinee determines that count rates are stable then cue the examinee that the estimated critical condition (ECC) is at 230 steps on Bank "D". Evaluator Note: When rods are >53 steps on Bank A then the continuous rod motion will occur.

YesContinues to pull rods.No5Enters 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.No6 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.No7Verify rod motion is stopped.

Evaluator Note: This is an immediate operator action.

YesNotes that rod motion has not stopped.No8 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.Yes9 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.No10 Examiner ends JPM at this point.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.No11Verify 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.No12 NJPSF-141A2013 NRC Sim a RO&SRO-I&SRO-U: CONTINUOUS ROD WITHDRAWAL330/15IC 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) >53Trigger #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.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). Reactivity is returned to service (see REP-109.002).

JPM SETUP SHEET Increase reactor power to 10-3% per GOP-3 starting at Step 3.12. The Examiner will play the role of CRS and Reactor Engineering for this JPM. Reactor engineering has started REP-109.002, INVERSE COUNT RATE RATIO PLOT, and has taken all necessary data and is ready to collect data at 53 steps on Control Bank A.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 of GOP-3 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:4 022-003-01-01PERFORM5NOXFN-64A, XFN-064B, and XFN-65A are running in fast/norm speed and RBCU TRAIN B EMER Gis selected to XFN-064B.SIMULATORTIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE45.a.4START THE REACTOR BUILDING VENTILATION SYSTEM PER SOP114.TOOLS:SOP-114 IV. D. SHIFTING REACTOR BUILDING COOLING UNITS FAN SPEEDSOP-114 IV. D. SHIFTING REACTOR BUILDING COOLING UNITS FA NSPEED complete.SOP-114REACTOR BUILDING VENTILATION SYSTEM022000A401 CCS fans3.63.6A4.01 The CRS directs you as the RO to start XFN-64A, XFN-64B, and XFN-65B in NORM speed in accordance with SOP-114 Section IV. D.

SHIFTING REACTOR BUILDING COOLING UNITS FAN SPEED, in order to align the plant for a normal preferred at power lineup.Mode 3.The current lineup of the RBCU's is as follows: XFN-64A and XFN-64B are running in slow speed.It is desired to run XFN-64A, XFN-64B, and XFN-65B in NORM speed in order to prepare for reactor startup.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.

Shift RBCU's as follows:a. Shutdown RBCUs by placing appropriate switch(es) in STOP:1) XFN 0064A-AH, 1A NORM.2) XFN 0064A-AH, 1A SLOW.

3) XFN 0064B-AH, 1B NORM.

4) XFN 0064B-AH, 1B SLOW.5) XFN 0065A-AH, 2A NORM.6) XFN 0065A-AH, 2A SLOW.

7) XFN 0065B-AH, 2B NORM.

8) XFN 0065B-AH, 2B SLOW.

YesTakes XFN 0064A-AH, 1A SLOW and XFN 0064B-AH, 1B SLOW to stop. Verifies red light off and green light on.Yes1 Ensure the RBCU dampers are in BYP:1) XDP-110A, RBCU 64A HEPA FLTR BYP DMPR.2) XDP-111A, RBCU 65A HEPA FLTR BYP DMPR.

3) XDP-110B, RBCU 64B HEPA FLTR BYP DMPR4) XDP-111B, RBCU 65B HEPA FLTR BYP DMPR.

YesTakes XDP-110A, RBCU 64A HEPA FLTR BYP DMPR and XDP-110B, RBCU 64B HEPA FLTR BYP DMPRto BYP. Verifies red light lit and green light off.Yes2 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 XFN0064A-AH, REACTOR BLDG COOLING UNIT 1A EMERG FAN, start one of the following:a) XFN 0064A-AH, 1A NORM.For XFN0064B-AH, REACTOR BLDG COOLING UNIT 1B EMERG FAN, start one of the following:a) XFN 0064B-AH, 1B NORM.For XFN0065B-AH, REACTOR BLDG COOLING UNIT 2B EMERG FAN, start one of the following: a) XFN 0065B-AH, 2B NORM.

YesTakes and holds XFN 0064A-AH, 1A NORM, 0064B-AH, 1B NORM, and 0065B, 2B NORM to START until red breaker closed light is lit and starting current is indicated.Yes3 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.

YesDetermines normal amps for XFN0064A and XFN0064BYes4 Determines that XFN0065B has tripped.Enters XCP-607, 1-1, RBCU 1B/2B FAN TRIP CORRECTIVE ACTIONS:1. Determine which fan tripped and place the control switch in Normal After Stop.

2. Start the non-running Reactor Building Cooling Unit fan after ensuring cooling water is lined up.

3. Dispatch an operator to XPN7077 (CB-436, TSC Equipment Room) to select the RACK RESET and reset the alarm.SUPPLEMENTAL ACTIONS:1. Determine the cause of the fan trip, correct and return to service as soon as possible.2. Continued normal operation is allowed when one fan per group in slow speed is operable per Technical Specification 3.6.2.3.

3. Notify PSE (Predictive Maintenance) for further assistance.Evaluator Note: This is where the JPM becomes alternate path.Booth Operator Cue: If called to go to XPN7077 (CB-436, TSC Equipment Room) and to select the RACK RESET and reset the alarm, report that it is complete after 5 minutes.

YesTakes XFN 0065B-AH, 2B NORM to stop.No5 From ARP:2. Start the non-running Reactor Building Cooling Unit fan after ensuring cooling water is lined up.From SOP:Place RBCUs in service by starting three or four RBCUs in SLOW or NORM as follows:For XFN0065A-AH, REACTOR BLDG COOLING UNIT 2A EMERG FAN, start one of the following:a) XFN 0065A-AH, 2A NORM.

YesTakes and holds XFN 0065A, 2A NORM to START until red breaker closed light is lit and starting current is indicated.Yes6Verify RBCU Fan motor amps return to normal operating range: 1) For fast speed operation, 275 amps to 300 amps YesVerifies RBCU motor amps return to normal operating range.No7 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.Evaluator Cue: If applicant reports that an inoperable RBCU is selected for start, ask for a recommendation and approve it.Evaluator Note: The section of XFN-64B causes XCP-6103 5-6, RB RECRIC UNIT C 3108C/ 3109C MISALIGN and XCP-6103 5-7, RB RECRIC UNIT D 3108D/ 3109D to change condition (dim/bright).

YesTakes XFN-64B/XFN 65B - RBCU TRAIN B EMERG to XFN-64B position.Yes8 NJPSF-1592013 NRC Sim b RO&SRO-I&SRO-U: SWAP RUNNING RBCU'S331/4IC 4. Pre-Event LoadSelect RBCU TRAIN A EMERG to XFN-65A and select RBCU TRAIN B EMERG to XFN-65B.Stop all RBCUsStart XFN-64A and XFN-64B in slow.Take XDP-110A, RBCU 64A HEPA FLTR BYP DMPR and XDP-110B, RBCU 64B HEPA FLTR BYP DMPR to FILTER.

PMP-AH049B XFN0065BH RB CLG RAN HIGH BRG FAILURE Final=1.2Event 1:X02O104R==1 (red light lit for XFN-65BTrigger 1:PMP-AH049T Delay=2 seconds Trip of XFN-65B. Saved to IC 331.Need to provide copies of procedure since is not laminated in the simulator.

JPM SETUP SHEET The CRS directs you as the RO to start XFN-64A, XFN-64B, and XFN-65B in NORM speed in accordance with SOP-114 Section IV. D. SHIFTING REACTOR BUILDING COOLING UNITS FAN SPEED, in order to align the plant for a normal preferred at power lineup.Mode 3.The current lineup of the RBCU's is as follows: XFN-64A and XFN-64B are running in slow speed.It is desired to run XFN-64A, XFN-64B, and XFN-65B in NORM speed in order to prepare for reactor startup.

2013 NRC Sim JPM c RO&SRO-I: INCREASE LETDOWN FLOW TO A MAXIMUM TO IMPROVE CHEMISTRYCANDIDATE:EXAMINER:4 044-031-01-01PERFORM5NoLetdown 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 switches3.12.8A4.19 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.

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%.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.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%.No1Place PCV-145, LO PRESS LTDN, in MAN and open to 70%.

YesPCV-145, LO PRESS LTDN, indicates MAN and open to 70%.Yes2 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.Yes3Open 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.Yes4 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.Yes5Ensure PCV-145 Setpoint Pot is set between 5.0 and 6.7.

YesPCV-145 Setpoint Pot is between 5.0 and 6.7.No6 Examiner ends JPM at this point.Place PCV-145, LO PRESS LTDN, in AUTO.

YesPCV-145, LO PRESS LTDN, indicates AUTO.No7 NJPS-034A2013 NRC Sim JPM c RO&SRO-I: INCREASE LETDOWN FLOW TO A MAXIMUM TO IMPROVE CHEMISTRY10No special instructions, Just reset to IC-10.Need to provide copies of procedure since it is not laminated in the simulator. Allow students to mark up procedure in books and then replace after JPM.

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.

CANDIDATE:EXAMINER:

TIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATETOOLS:

JPM SETUP SHEET

CANDIDATE:EXAMINER:

TIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATETOOLS:

JPM SETUP SHEET

CANDIDATE:EXAMINER:

TIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE TOOLS:

JPM SETUP SHEET

CANDIDATE:EXAMINER:

TIME START:TIME FINISH:SAT:UNSAT:PERFORMANCE TIME:SIGNATUREDATE TOOLS:

JPM SETUP SHEET

2013 NRC Sim JPM h RO: RESPOND TO HIGH REACTOR BUILDING PRESSURECANDIDATE:EXAMINER:NJPS-15215 029-004-01-01PERFORM15NoRB 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 SYSTEMHPP-709, Attachment VI, REACTOR BUILDING PURGE RELEASE PERMIT.RB purge is secured.SOP-114REACTOR BUILDING VENTILATION SYSTEM028000A401 HRPS controls4.04.0A4.01 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. FI-8252, H2 PURGE FLOW CFM is out of service. The CRS has completed 702 Attachment VI.S-3, 6" RB PURGE OPERATING WITH IFT08252 AND/OR RMA-4 INOPERABLE, which requires that the release flowrate be estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The CRS has determined that the flow rate will be estimated at 600 cfm for the duration of the release.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.Yes1 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 understandthat 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.Yes2 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 the applicant that the start time and flow rate will be transferred to the station log book.Examiner Note: Initial conditions indicate that the flowrate of the release is estimated at 500 cfm.

YesRecords start time and flowrate estimate of 600 cfm in the Station Log Book and on the Continuous Waste Release Permit.No3Records release readings from RM-A2 and RM-A4.

YesRecords release readings from RM-A2 and RM-A4.No4 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.No5Stop XFN-96, ALT PUR EXH FAN.

YesStops XFN-96, ALT PUR EXH FAN.Yes6 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.Yes7Record 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.No8 NJPS-1522013 NRC Sim JPM h RO: RESPOND TO HIGH REACTOR BUILDING PRESSURE363/10Run when applicant is ready.If IC-363 is not available:Reset to IC 10Event #1 x15i355t>0 Enter MALF RMS004C, CONT BREACH FHB436; Set = 2 SCFT, when examinee starts XFN-96.Event #2 x15i355s>0&&jmlrms4c>0 (Deletes Malf RMS004C when the examinee secures XFN-96)Hang an Orange R&R tag on FI-8252, H2 PURGE FLOW CFM.

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. FI-8252, H2 PURGE FLOW CFM is out of service. The CRS has completed 702 Attachment VI.S-3, 6" RB PURGE OPERATING WITH IFT08252 AND/OR RMA-4 INOPERABLE, which requires that the release flowrate be estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The CRS has determined that the flow rate will be estimated at 600 cfm for the duration of the release.HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.