ML13029A078

RB 2012-11 Draft Operating Test

ML13029A078
Person / Time
Site:	River Bend
Issue date:	11/15/2012
From:	David Strickland Operations Branch IV
To:
Laura Hurley
References
ES-D-1
Download: ML13029A078 (259)

Text

NRC Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions:

Mode 1, Reactor power 68%. Power ascension in progress following downpower for Feedwater pump C seal replacement. APRM B in bypass due to downscale failure. FWS-P1A & B in service.

Turnover: Shift priorities: 1) Start lube oil system for FWS-P1C in preparation for pump start. 2) Place 3rd Feed Reg Valve in service. 3) Raise reactor power in accordance with Reactivity Control Plan Step 20, then await further guidance from reactor engineering.

Event Malf. Event Event No. No. Type* Description 1 NA N (CRS,BOP) Start Feedwater pump C lube oil system per SOP-0009.

rd 2 NA N (CRS,ATC) Place 3 Feedwater Regulating Valve in service per SOP-0009.

3 NA R (ATC) Raise reactor power in accordance with the reactivity control plan Step 20.

4 NMS015F I (CRS,ATC) (Tech Spec) APRM F Upscale failure due to flow converter downscale failure and half scram.

5 MSC011 C(CRS) (Tech Spec) 171 airlock inner door seal failure.

p870_54a:

6 g_5 C(CRS,BOP) Steam Packing Exhauster failure requiring equipment rotation.

FAIL ON 7 EHC001 M (ALL) Main Turbine Trip/Anticipated Transient Without Scram with MSIVs open due to failure of RPS to completely de-energize.

RPS001A 8 FWS004B C (CRS,ATC) Feedwater Master Level Controller output fails high.

9 EHC002B C (CRS,BOP) Main Turbine Bypass Valves fail closed.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7)APRM F, 171 airlock, Stm Packing Exh.,Turb trip, ATWS, Master Controller, Turb Bypass Valves.

Malfunctions after EOP entry (1-2) (2) Feedwater Master Controller, Turbine Bypass Valves Abnormal Events (2-4) (2) AOP-2,AOP-3 Major Transients (1-2) (1) ATWS EOPs entered (1-2) (2) EOP-1, EOP-2 EOP contingencies (0-2) (1) EOP-1A Critical Tasks (2-3) (2) Terminate injection to <-56, Begin control rod insertion Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1___ Event No.: _1__ Page ___ of ___

Event

Description:

Start Feedwater pump C lube oil system per SOP-0009 Event Initiation: Initiated by crew.

CUE: Turnover item.

Time Position Applicants Actions or Behavior CRS Direct the BOP to start up the lube oil system for Feedwater pump C in accordance with SOP-0009 Section 4.1 BOP Startup the lube oil system for Feedwater pump C as follows:

• Communicate with Turbine Building operator to verify adequacy of reservoir oil level.

ROLE PLAY As Turbine Building operator, notify the BOP that oil level on FWL-PI119C is approximately midrange.

BOP Continue startup the lube oil system for Feedwater pump C as follows:

• Check operation of FWS-P2C as follows:

o Place control switch to START o On H13-P680, check red RX FWP P1C MN LO PMP PRESS NORM light is on.

o Return the pump control switch to STOP.

• Check operation of FWS-P3C as follows:

o Place control switch to START o On H13-P680, check red RX FWP P1C MN LO PMP PRESS NORM light is on.

o Return the pump control switch to STOP.

• Communicate with the Turbine Building operator to verify adequacy of the gear increaser oil level in the bulls-eye.

ROLE PLAY As Turbine Building operator, notify the BOP that oil level is visible in the C gear increaser bulls-eye.

Rev 1

NRC BOP Continue startup the lube oil system for Feedwater pump C as follows:

• Check operation of FWL-P5C as follows:

o Place the pump control switch to START o On H13-P680, check red RX FWP P1C GEAR INCR LO PRESS NORM light is ON.

o Return the pump control switch to STOP.

BOP

• Place the control switches for the following pumps to AUTO:

o FWL-P1C o FWL-P5C

• At H13-P680, depress RX FWP P1C LUBE OIL SYSTEM START pushbutton and check the following:

o FWL-P1C starts o FWL-P5C starts o RX FWP P1C MN LO PUMP PRESS NORM red light is ON o RX FWP P1C GEAR INCR LO PRESS NORM red light is ON

• Place the control switches for the following pumps in AUTO:

o FWL-P2C o FWL-P3C

• Communicate with Turbine Building operator to verify proper oil flows through sight glasses on feed pump, motor bearings, and gear increaser supply on Feedwater pump C.

ROLE PLAY As Turbine Building operator, accept direction to verify proper oil flow on Feedwater pump C. Report that oil flow is satisfactory.

Termination Event is terminated upon completion of SOP-0009 Section 4.1 Point Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: _2_ Page ___ of ___

rd Event

Description:

Place 3 Feedwater Regulating Valve in service per SOP-0009 Event Initiation: Initiated by crew.

CUE: Turnover item.

Time Position Applicants Actions or Behavior CRS Direct the ATC to place the 3rd Feedwater Regulating Valve in service accordance with SOP-0009 Section 4.11 BOP Place the 3rd FWREG Valve in Service as follows:

o Verify at least one FWREG valve is in service on master level control per Section 4.9.

o Verify closed FWS-MOV27A(B)(C), FWREG VLV 1A(1B)(1C) INLT Valve o Ensure C33-R601A(R613)(R601B), FWREG VALVE A(B)(C) FLOW CONTROLLER IN MANUAL, set at 0%.

o IF the amber CONT SIGNAL FAILURE light is ON, THEN depress the A(B)(C) FWREG VLV CONT SIGNAL FAILURE RESET Pushbutton o Test stroke C33-LVF001A(B)(C), FWREG VALVE A(B)(C) as follows:

o Communicate with the turbine building operator to locally monitor valve position.

o Use the OPEN and CLOSE pushbuttons on C33-R601A(R613)(R601B), FWREG VALVE A(B)(C) FLOW CONTROLLER to stroke open and closed C33-LVF001A(B)(C).

o Communicate with turbine building operator to verify proper valve movement and smooth operation.

o Check C33-LVF001A(B)(C) full closed.

o Open FWS-MOV27A(B)(C), FWREG VLV 1A(1B)(1C) INLT Valve.

o Open C33-LVF001A(B)(C), FWREG VALVE A(B)(C) until all in service FWREGs are at the same position.

o Place C33-R601A(R613)(R601B) in AUTO.

ROLE PLAY Accept direction from ATC to locally verify smooth operation of regulating valve and report back that operation was smooth following the full stroke exercise.

Termination Event is terminated when all 3 Feedwater Regulating Valves are in service.

Point Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _1__ Event No.: _3__ Page ___ of ___

Event

Description:

Raise reactor power in accordance with the reactivity control plan Step 20 Event Initiation: Initiated by crew.

CUE: Turnover item.

Time Position Applicants Actions or Behavior CRS Direct the reactor power ascension in accordance with the Reactivity Control Plan (RCP)

ATC o Accept the direction for power ascension.

o Withdraw control rods in accordance with RCP by using SOP-0071.

o At H13-P680, on the ROD SELECT MODULE, select the rod to be moved.

o Depress SELECTED GROUP button to check positions of control rods within group are correct prior to movement o Check that a Rod Withdraw Block or Inhibit does not exist.

o On H13-P680, depress and hold, WITHDRAW Pushbutton until the IN indicator is lit or the start of rod motion is observed.

o Check that the new rod notch position displayed is the next highest even number.

o Repeat the rod motion as needed to satisfy the steps indicated on the turnover sheet.

o Report the power ascension complete.

Termination Event is terminated when Step 20 of the Reactivity Control Plan has been Point completed.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: _4__ Page ___ of ___

Event

Description:

(Tech Spec) APRM F Upscale failure due to flow converter downscale failure and half scram Event Initiation: At lead evaluator discretion.

CUE: Annunciator: H13-P680 6A A03 APRM B or F Upscale Trip or INOP & H13-P680 5A A10 RPS TRIP LOGIC B OR D ACTIVATED Time Position Applicants Actions or Behavior ATC

• Recognize and report APRM F failure and half scram condition.

• Per ARP 680-5-A10 Verify no individual rod scrams.

CRS

• Accept report of failed APRM

• Notify maintenance of failed instrument. Make OSP-0046 notifications, notify Reactor Engineering.

• Enter Technical Specification 3.3.1.1. Condition A.

• Recognize potential LCO for TS 3.3.2.1

• Direct ATC to remove APRM B from bypass and place APRM F in bypass, then reset the half scram.

ATC

• Remove APRM B from bypass and place APRM F in bypass

• Reset the half scram.

ROLE PLAY

• As Work Management or Maintenance accept report of failed instrument.

Termination Event is terminated when CRS has applied Technical Specifications to the APRM Point failure and has given direction to bypass the APRM and reset the half scram.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _1__ Event No.: __5__ Page ___ of ___

Event

Description:

(Tech Spec) 171 airlock outer door seal failure Event Initiation: At lead evaluator discretion.

Cue: Annunciator: H13-P863/71/B05 AUX BLDG/CNMT AL OUTBOARD DOOR SEAL FAILURE Time Position Applicants Actions or Behavior BOP

• Recognize and report annunciator status to CRS

• Respond to annunciator per ARP.

• Dispatch personnel to locally verify status of airlock.

CRS

• Accept report of airlock annunciator status.

ROLE PLAY

• As reactor building operator, accept direction to locally verify status of airlock.

• Report that the 171 airlock outer door seal has failed.

CRS

• Upon receipt of confirmation of door seal failure, enter Technical Specification 3.6.1.2 Condition A.

• Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inoperability, verify OPERABLE door (inner door) is CLOSED.

• Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of inoperability, verify OPERABLE door (inner door) is LOCKED.

Termination Event is terminated when the CRS has applied Technical Specifications to the Point airlock failure.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 1 Event No.: 6 Page ___ of ___

Event

Description:

Steam Packing Exhauster B failure requiring equipment rotation.

Event Initiation: At lead evaluator discretion.

Cue: Annunciator: H13-P870 54 G05 STEAM PACKING EXH FAN MOTOR HIGH TEMPERATURE Time Position Applicants Actions or Behavior BOP

• Recognize and report annunciator status on Steam Packing Exhauster.

• Dispatch Turbine Building operator to verify local status of Steam Packing Exhauster.

CRS

• Accept report of Steam Packing Exhauster high temperature condition.

• Direct BOP to swap Steam Packing Exhauster A in accordance with ARP and SOP-0115.

• Notify maintenance of high temperature condition on the Steam Packing Exhauster B.

ROLE PLAY

• As Turbine Building operator accept direction to verify local status of Steam Packing Exhauster.

• Provide local report that the B exhauster motor is extremely hot.

BOP

• Swap Steam Packing Exhausters per SOP-0015 Section 5.3 as follows:

• Partially open TME-MOVD1 for the fan to be started.

• WHEN at least 3 minutes have elapsed, THEN close TME-MOVD1 for the fan to be started.

• Start TME-SPEM-A.

• Throttle open TME-MOVD1 while closing TME-MOVD2 to maintain greater than or equal to 10 inches and less than or equal to 14 inches of water as indicated on TME-PIEPR-9.

• WHEN TME-MOVD2 is completely closed, THEN stop TME-SPEM-B.

ROLE PLAY

• After equipment rotation, as Turbine Building operator notify BOP that Packing Exhauster A is running fine with normal vibration and temperature.

Termination Event is terminated when the standby Steam Packing Exhauster has been placed Point in service and the previously running Steam Packing Exhauster has been secured.

Rev 1

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

Event

Description:

Main Turbine Trip/Anticipated Transient Without Scram with MSIVs open due to failure of RPS to de-energize.

Event Initiation: At lead evaluator discretion.

Cue: Numerous annunciators, turbine trip light indication, control rods remain withdrawn with a scram signal present.

Time Position Applicants Actions or Behavior ATC

• Place the mode switch to shutdown

• Determine that all control rods did not fully insert

• Arm and depress all four manual scram pushbuttons

• Determine that all control rods did not fully insert

• Arm and initiate Alternant Rod Insertion

• Determine that all control rods did not fully insert

• Give the SRO an ATWS report SRO Accept ATWS report from ATC

• Enter EOP-1 and transition to EOP-1A RPV control ATWS

• Direct the following EOP-1A actions:

o ATC Trip both reactor recirc pumps o BOP Terminate and prevent injection with HPCS o BOP Inhibit ADS o BOP Install EOP-5 Enclosures 16 and 24 o ATC Terminate injection with feedwater and lower reactor water level to -60 to -140 o BOP Initiate Standby liquid control system o BOP Install EOP-5 Enclosures 14 and 10 o BOP Maximize CRD cooling water flow o Direct a pressure band of 800-1090 psig with Bypass Valves and Drains Rev 1

NRC ATC

• Trip both reactor recirc pumps as follows:

o Depress STOP, RECIRC PUMP BREAKER 5A.

o Depress STOP, RECIRC PUMP BREAKER 5B.

o TRIP LFMG BRKR 1A o TRIP LFMG BRKR 1B BOP

• Terminate and prevent injection with High Pressure Core Spray as follows:

o Override Injection / Initiate High Pressure Core Spray o Verify E22-F004 amber override light is lit.

o Stop the High Pressure Core Spray pump.

o Notify the SRO that injection from HPCS has been terminated and prevented.

• Inhibit ADS as follows:

o Place Div I ADS key lock switch to INHIBIT o Place Div II ADS key lock switch to INHIBIT

• Install EOP-5 enclosures 16 and 24 o Request the back panel operator to perform needed actions o Verify that IAS-MOV106 is open ATC

• CRITICAL TASK Terminate injection with feedwater and lower reactor water level to -60 to -140 o Place the master RPV level controller into manual o Lower master controller output signal to 0 o When level is <-60 control level in the band by using the OPEN / CLOSED pushbutton on the selected controller.

Reference Event 8 Rev 1

NRC BOP

• Initiate Standby liquid control system as follows:

o Place SLC PUMP A(B) (NOT BOTH), control switch to RUN.

o Verify the following:

• SQUIB CONTINUITY A(B), light goes Off.

• C41-F001A(B), SLC PUMP A(B) SUCT VLV, Opens.

• C41-C001A(B), SLC PUMP A(B), Starts.

o Notify SRO of SLC injection status.

o Verify IAS-MOV106 is Open.

o Record SLC Tank Level gallons.

• CRITICAL TASK Begin control rod insertion o Request the back panel operator to perform needed actions to install needed Enclosures

• Maximize CRD cooling water flow as follows:

o Start C11-C001AP(BP), CRD AUX OIL PUMP A(B).

o Verify C11-C001A(B), CRD PUMP A(B), white control power available light on.

o Start C11-C001A(B), CRD PUMP A(B).

o Place CRD HYDRAULICS FLOW CONTROLLER, in MANUAL and raise signal to 100%.

o Fully Open C11-F003, CRD DRIVE WATER PRESS CONTROL VALVE.

o Verify IAS-MOV106 is Open.

• Stabilize/maintain pressure 800-1090 psig with Bypass Valves and Drains.

Reference Event 9 ROLE PLAY

• If directed, accept direction as Control Building operator to report to the Division III Diesel Generator Termination Event is terminated when Critical Tasks have been performed and the plant has Point been stabilized.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 1 Event No.: 8 Page ___ of ___

Event

Description:

Feedwater Master Level Controller output fails high.

Event Initiation: Event occurs when reactor water level reaches Level 2 (-43)

CUE: Output demand of Master Controller indicates 100%. Attempts to lower demand with CLOSE pushbutton are ineffective.

Time Position Applicants Actions or Behavior ATC

• Recognize and report failed output signal from Master Controller.

• Remove individual Feedwater Regulating Valves from AUTO control by depressing the individual regulating valves MANUAL (yellow) pushbutton.

• Control reactor water level with individual controllers in Manual by using the OPEN and CLOSE pushbuttons to maintain -60 to -140 reactor water level.

SRO

• Accept report of failed Master Controller.

Termination Event is terminated when ATC operator removes individual feedwater regulating Point valves from automatic Master control and controls them individually.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 1 Event No.: 9 Page ___ of ___

Event

Description:

Main Turbine Bypass Valves fail closed.

Event Initiation: Event is initiated 5 minutes after the Mode Switch is not in RUN position.

Cue: GREEN closed lights on for Turbine Bypass Valves with reactor pressure above the pressure setpoint.

Time Position Applicants Actions or Behavior BOP

• Recognize and report failure of Bypass Valves

• Utilize other methods of pressure control (additional drains and safety relief valves as necessary)

SRO

• Accept report of failed Bypass Valves

• Direct BOP to use alternate methods of pressure control (additional drains and safety relief valves as necessary)

Termination Event is terminated when alternate pressure control methods have been placed in Point service.

Rev 1

NRC Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 100% power, Division 1 work week, Div 1 DG tagged out Turnover: Shift Priorities: 1) Alternate HDL Pumps from A to B due to report of seal leakage on A. 2)

Run STP-402-0201 for scheduled surveillance.

Event Malf. Event Event No. No. Type* Description 1 NA N (CRS,ATC) Alternate HDL Pumps from A to B due to reported seal leakage.

2 NA N (CRS,BOP) Run STP-402-0201 for scheduled surveillance.

CRDM2809 R(ATC) 3 (Tech Spec) Control Rod Drop - Control Rod 28-09 Uncoupled C(CRS)

C 4 CRD001A (CRS,BOP) (Tech Spec) CRD pump trip 5 FWS001A C (CRS, ATC) Feedwater A pump trip 6 ED004F C (ALL) Trip of NJS-LDC1F/Loss of Feed/Reactor Scram RCS007 Coolant leak in the drywell with loss of power to E22-F004 and trip of RCIC E22MOV F004 M (ALL) 7 BREAKER TRIP RCIC001 ED003H ENS-SWG1A bus loss, RHR B fails to auto start, E12-F042C injection valve fails.

8 RHR009B C (CRS,BOP)

RHR001C

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) Rod drop, CRD trip, Feedpump trip, NJS Bus, Leak, E12-F042C Malfunctions after EOP entry (1-2) (2) Leak, E12-F042C Abnormal Events (2-4) (3)AOP-0061, AOP-0006, AOP-0003 Major Transients (1-2) (1) Leak EOPs entered (1-2) (2) EOP-1, EOP-2 EOP contingencies (0-2) (2) Alternate Level Control, Emergency Depressurization Critical Tasks (2-3) (3) Insert control rod 28-09, Open SRVs to depressurize vessel, manually start RHR B.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 1 Page ___ of ___

Event

Description:

Alternate HDL Pumps from A to B due to reported seal leakage.

Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior SRO

• Direct ATC to alternate Heater Drain Pumps from HDL-P1A to HDL-P1B in accordance with SOP-0010.

ATC

• Alternate from HDL-P1A to HDL-P1B as follows:

o Open HDL-MOV58B by placing the control switch in OPEN on H13-P870.

o Communicate with Turbine Building operator to determine if pump is rotating. If not rotating, then have Turbine Building operator verify HDL-V601 is open.

ROLE PLAY

• As Turbine Building operator report that HDL-P1B is NOT rotating and that HDL-V601 is open.

• If requested also notify ATC that oil level is satisfactory and the pump is ready to be started.

ATC

• Continue alternating HDL pumps as follows:

o Start HDL-P1B by depressing the START pushbutton on H13-P680.

o Open HDL-MOV55B by depressing the OPEN pushbutton on H13-P680.

o Close HDL-MOV58B by placing the control switch in the CLOSE position on H13-P870.

o Close HDL-MOV55A by depressing the CLOSE pushbutton on H13-P680.

o Stop HDL-P1A by depressing the STOP pushbutton on H13-P680.

o Communicate with the Turbine Building operator to verify idle pump is not rotating backwards.

ROLE PLAY When requested, notify ATC that HDL-P1A is NOT rotating backwards.

Termination Event is terminated when HDL-P1B is in service and HDL-P1A is secured.

Point Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 2 Page ___ of ___

Event

Description:

Run STP-402-0201 for scheduled surveillance.

Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior CRS

• Direct BOP to perform STP-402-0201 BOP

• Perform STP-402-0201 as follows:

• Contact Electrical Maintenance to obtain current and voltage readings on the filter train heater during the HVC-FN1A start.

ROLE PLAY

• As Electrical Maintenance personnel take direction to obtain current and voltage reading on the filter heater during the HVC-FN1A start.

BOP

• Open HVC-AOD19C.

• Open HVC-AOD19E

• Start HVC-FN1A and record start time

• Check open HVC-AOD43A

• Check open HVC-AOD3A

• Close HVC-MOV1A

• Close HVC-MOV1B

• Acknowledge annunciator H13-P863-74A-G02. (Expected for this evolution).

• Communicate with Control Building operator to verify local status checking for normal appearance, sound, and vibration.

• Communicate with Electrical Maintenance to obtain current and voltage readings.

ROLE PLAY As Control Building operator report that HVC-FN1A filter train is running normally.

As Electrical Maintenance report that current and voltage readings are normal and they will be logged in the procedure prior to the end of the shift.

As back panel operator, provide outside air temperature of 82°F when requested.

Termination Event is terminated when HVC-FN1A is in service in accordance with STP-402-Point 0201.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 3 Page ___ of ___

Event

Description:

(Tech Spec) Control Rod Drop - Control Rod 28-09 Event Initiation: At lead evaluator discretion Cue: Unexplained rise in reactor power Time Position Applicants Actions or Behavior ATC

• Recognize and report an unexplained rise in reactor power.

• Take action to lower power to <100%

• Diagnose Rod Drop as cause for rise in power.

SRO

• Notify reactor engineering of the rise in power.

• Direct entry into AOP-0061, MISPOSITIONED CONTROL ROD ROLE PLAY

• As Reactor Engineer, indicate the rise in power is in the vicinity of control rod 28-09 and suggest a coupling check.

SRO

• Direct ATC to perform a coupling check on 28-09 in accordance with SOP-0071 Section 5.4

• Direct ATC to enter AOP-0061 when the rod drop has been confirmed by coupling check.

• Direct ATC to fully insert control rod 28-09 in accordance with AOP-0061.

• Enter Technical Specification LCO 3.1.3 Condition C.

ATC

• Perform a coupling check on 28-09 as follows:

o Select the rod on the full core display o Check that position is at 48 o Check that Rod Withdrawal Block or Inhibit does not exist o Attempt to withdraw control rod past 48 by depressing C11A-S334 WITHDRAW pushbutton.

o Respond to CONTROL ROD OVERTRAVEL annunciator in accordance with ARP-680-07A-C02 o Depress ROD UNCOUPLED pushbutton and observe red light on 28-09.

o CRITICAL TASK - In accordance with AOP-0061 full insert control rod 28-09.

ROLE PLAY

• If requested, as Reactor Building operator, take direction to locally isolate control rod 28-09 using V103 and V105 on CRDM 28-09.

Termination Event is terminated when control rod 28-09 has been fully inserted and Technical Point Specifications have been applied to the control rod failure.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 4 Page ___ of ___

Event

Description:

(Tech Spec) CRD pump Event Initiation: At lead evaluator discretion Cue: Annunciator: H13-P680 22A A01 CRD PUMP A OR B AUTO TRIP Time Position Applicants Actions or Behavior BOP

• Recognize and report trip of CRD pump A

• Communicate to Reactor Building operator CRD pump trip and verify readiness of CRD B for a start.

SRO

• Acknowledge trip of CRD pump A. Direct BOP to perform ARP-601-22A-A01.

• Notify work management or maintenance of CRD pump trip.

• Enter Technical Specification 3.1.5 Condition B when the second accumulator fault occurs. (Candidate may also enter Condition A on the first fault, but due to the short duration between faults, he may only enter Condition B which is more restrictive).

ROLE PLAY

• As reactor building operator take direction to locally verify readiness of CRD B to be started and perform an inspection of CRD A to ascertain cause of trip. After receipt of 2nd accumulator fault, notify BOP that CRD B is ready to start. If needed to delay start of CRD pump, notify BOP that water is spraying from CRD A and you will establish a spray barrier prior to the CRD B start.

• As control building operator take direction to check local status of CRD A breaker indication to ascertain cause of trip. After 5 minutes report breaker indicates the CRD pump tripped on overcurrent.

ATC

• Acknowledge CRDM high temperature annunciators. (~1 minute after trip)

• Monitor for accumulator faults. (1st fault ~6 minutes after trip; 2nd fault ~7 minutes after trip).

Rev 1

NRC BOP

• Perform ARP-601-22A-A01 to start CRD B as follows:

o Start Aux Oil Pump C11-C001BP o Place Flow Controller C11-R600 to MANUAL o Close C11-R600 o Verify White Control Power Light on for CRD pump to be started.

o Start Standby Pump C11-C001B o Verify amps <45 amps o When flow drops below 45 gpm on C11-R606, then slowly throttle open C11-R600 to achieve 45 gpm.

o When C11-R600 is nulled out, Then place in AUTO.

Termination Event is terminated when CRD Pump B has been placed in service and Control Point Rod Drive System parameters are returned to normal.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 5 Page ___ of ___

Event

Description:

Feedwater A pump trip Event Initiation: At lead evaluator discretion Cue: Annunciator: H13-P680-03A-A01 RX FW PUMP BREAKERS AUTO TRIP Time Position Applicants Actions or Behavior ATC

• Recognize and report trip of A Feedwater pump ATC or BOP

• Communicate with Turbine Building and Control Building operators and direct them to the pump and breaker to ascertain cause of the trip.

SRO

• Acknowledge trip of A Feedwater pump

• Direct ATC to enter AOP-0006.

• Notify work management or maintenance of trip.

• Notify Reactor Engineering and Chemistry of power change.

ATC

• Lower power to mitigate any level transient in accordance with AOP-0006 by reducing reactor recirculation flow with B33-K603A & B flow controllers.

• If Level 4 is reached, verify a flow control valve runback occurs.

• When level is restored above Level 4, reset the flow control valve runback as follows:

o Adjust B33-K603A to obtain zero% LIMITER ERROR o Adjust B33-K603B to obtain zero% LIMITER ERROR o Depress CAVITATION INTLK RECIRC PMP A RESET pushbutton and verify H13-P680/04A/A03 resets o Depress CAVITATION INTLK RECIRC PMP B RESET pushbutton and verify H13-P680/04A/A09 resets ROLE PLAY

• As Turbine Building operator accept direction to investigate cause of pump trip.

• As Control Building operator accept direction to investigate feedpump breaker to determine cause of trip.

• As Auxiliary Control Room operator, accept report of power change.

Termination Event is terminated when the plant is stabilized following the trip of Feedwater Point Pump A.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 6 Page ___ of ___

Event

Description:

Trip of NJS-LDC1F/Loss of Feed/Reactor Scram.

Event Initiation: At lead evaluator discretion Cue: Numerous annunciators including H13-P808/86A/E07 NJS-LDC1E OR 1F UNDERVOLTAGE, trip of remaining Feedwater pumps due to loss of lube oil systems.

Time Position Applicants Actions or Behavior ATC

• Recognize and report loss of all high pressure feedwater from H13-P680.

• Place the mode switch in SHUTDOWN position.

• Deliver scram report

• Perform actions of AOP-1 and AOP-2 SRO

• Direct a reactor level band of -20 to 51 with RCIC and HPCS

• Direct a pressure band of 500 to 1090 psig with bypass valves and steam line drains until the MSIVs close.

• Then direct pressure control with SRVs

• Direct performance of AOP-0001 Reactor Scram and AOP-0002 Turbine Generator trip to the ATC

• Direct the performance of AOP-0003 Automatic Isolations to the BOP

• Enter Alternate Level Control

• Direct BOP to Inhibit ADS

• Communicate with work management or maintenance concerning bus loss, RCIC trip and HPCS failure BOP

• Attempt initiation of HPCS and RCIC. Recognize and report trip of RCIC and failure of E22-MOVF004(See Event 7)

• Verify isolations per AOP-0003

• Inhibit ADS Termination Event is terminated when Critical Tasks of Event 8 are met and critical plant Point parameters are stabilized.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 7 Page ___ of ___

Event

Description:

Coolant leak in the drywell with loss of power to E22-F004 and trip of RCIC.

Event Initiation: Event initiated at Reactor Water Level 2 (-43)

Cue: Rising drywell temperature and pressure.

Time Position Applicants Actions or Behavior ALL

• Recognize and report indications of a coolant leak in the drywell.

SRO

• Direct pressure band of 500-1090 psig and when <700 psig, direct band of 500-700 psig.

• Enter EOP-2 ATC

• Lower pressure to 500-700 psig with bypass valves and drains. Utilize SRVs for pressure control after MSIVs isolate at Level 1.

BOP

• Perform EOP-2 actions as directed by SRO Termination Event is terminated when Critical Tasks of Event 8 are met and critical plant Point parameters are stabilized.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 2 Event No.: 8 Page ___ of ___

Event

Description:

ENS-SWG1A and RHR B trip at Level 1, E12-F042C injection valve fails to auto open.

Event Initiation: Event initiated at Reactor Water Level 1 (-143)

Cue: Loss of light indication on Div 1 components, ENS A bus voltage is 0, RHR B Green indicating light ON and Red indicating light OFF with initiation signal present, E12-F042C loss of indication.

Time Position Applicants Actions or Behavior BOP

• Recognize and report loss of ENS-SWG1A

• Recognize and report RHR B failure to automatically start

• Recognize and report failure of E12-F042C.

• CRITICAL TASK - Manually start RHR B.

SRO

• When level can not be restored and maintained above -186 and an injection system is available, direct opening 7 ADS SRVs.

ATC

• CRITICAL TASK When directed, open 7 ADS/SRVs Termination Event is terminated when Critical Tasks are met and critical plant parameters are Point stabilized.

Rev 1

NRC Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 100% power. Startup Feed Reg Valve in Augmentation Mode per SOP-0009 to support maintenance on Feed Reg Valve C. Feed Reg Valve C has been returned to service.

Downpower for sequence exchange this shift.

Turnover: Shift Priorities: 1)Remove Startup Feed Reg Valve from Augmentation Mode. 2)Start RHR B for STP-204-6302and notify IST personnel when the pump is running at reference conditions. 3)Lower reactor power for sequence exchange per the reactivity control plan while field personnel gather data following RHR B pump start.

Event Malf. Event Event No. No. Type* Description Remove Startup Feedwater Regulating Valve from Augmentation Mode and 1 NA N (CRS,ATC) place in standby 2 NA N (CRS,BOP) Perform STP-204-6302 Section 7.1, RHR B Quarterly Surveillance.

Lower reactor power with Reactor Recirculation flow in accordance with the 3 NA R(ATC)

Reactivity Control Plan Step 1.

4 RHR002B C(CRS,BOP) (Tech Spec) RHR B trips DI-CNM- Feedwater Pump A minimum flow valve fails open.

5 HA68A- C(CRS,ATC)

CAM 6 RCIC005 I(CRS,BOP) (Tech Spec) Inadvertent RCIC initiation.

RCIC004 RCIC steam supply line break in the RCIC Room and Main Steam Tunnel with failure of RCIC Steam Supply Valves fail to isolate. Auto scram signals fail.

7 RCIC006 M(ALL)

RPS001B MSS008G Three Safety Relief Valves fail to energize when required for emergency depressurization.

8 MSS008D C(CRS,BOP)

MSS008I 9 FWS005A C(CRS,ATC) Startup Feedwater Regulating Valve fails closed.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) RHR B trip, A min flow, RCIC initiation, RCIC steam leak, SRV failure, Startup Reg Valve Failure Malfunctions after EOP entry (1-2) (2) SRV failure, Startup Reg Valve Abnormal Events (2-4) (2) AOP-0006-Min flow failure, AOP-0003-Steam Leak Major Transients (1-2) (1) Steam leak with failure to isolate affecting multiple areas EOPs entered (1-2) (2) EOP-1, EOP-3 EOP contingencies (0-2) (1) Emergency Depressurization Critical Tasks (2-3) (2) Place the mode switch in shutdown, Emergency Depressurize when more than one area exceeds Max Safe Temp or Rad Levels.

Rev 1

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

Event

Description:

Remove Startup Feedwater Regulating Valve from Augmentation Mode and place in standby Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior CRS

• Direct ATC to remove the Startup Feedwater Regulating Valve from Augmentation Mode per SOP-0009 Section 5.4 ATC

• Remove Startup Feedwater Regulating Valve from Augmentation Mode as follows:

o Place C33-R602 in Manual by depressing the Manual (Yellow) pushbutton.

o Close C33-LVF002 to 0% using the CLOSE pushbutton on C33-R602 while observing level is maintained by the Master Flow Controller.

o Check the in service regulating valves are able to maintain level while less than or equal to 92% open.

o Adjust C33-R602 tape set to 34 inches.

Termination Event is terminated when the Startup Feedwater Regulating Valve is removed Point from augmentation mode in accordance with SOP-0009 Section 5.4 Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 3 Event No.: 2 Page ___ of ___

Event

Description:

Perform STP-204-6302 Section 7.1, RHR B Quarterly Surveillance Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior CRS

• Direct BOP to perform Section 7.1 of STP-204-6302 BOP

• Perform STP-204-6302 Section 7.1 as follows:

o Communicate with IST personnel in the field to verify pump oil level and installation of suction pressure test gauge.

ROLE PLAY

• When requested, communicate to the BOP that RHR B pump oil level is within the High and Low marks on the Upper and Lower sightglasses AND the suction pressure gauge is installed.

BOP

• Continue performance of STP-204-6302 as follows:

o If Suppression Pool Cooling is desired THEN:

Verify SPC-AOV16 is CLOSED.

Open E12-F068B.

o Start E12-C002B o Verify pump amps < 91 amps on H13-P601, E12-PC002B RHR PUMP B MOTOR AMPS o Open and time E12-F024B o Record stroke time on Data Sheet 4.

o Check closed E12-F064B o Close E12-F048 o Throttle closed E12-F003B to establish Reference Value of 5100 gpm on E12-R603B o Notify IST personnel that RHR B is running at reference conditions.

Termination Event is terminated when RHR B is running at reference conditions in accordance Point with STP-204-6302.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 3 Event No.: 3 Page ___ of ___

Event

Description:

Lower reactor power with Reactor Recirculation flow in accordance with the Reactivity Control Plan Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior CRS

• Direct ATC to lower reactor power with Reactor Recirculation flow in accordance the Reactivity Control Plan.

ATC

• Lower reactor power in accordance with the Reactivity Control Plan as follows:

o Verify B33-K603A(B) are in Manual o Determine which loop is to be adjusted by observing Loop flows on B33-R612A and B33-R612B. Both loops may have to be adjusted to obtain desired power while maintaining Loop Flow mismatch with specifications.

o Note current valve position, generator load, MWth, APRMs and loop flows.

o Lower Reactor Recirculation Flow by toggling momentarily B33-K603A(B) controllers in the closed direction.

o Observed for expected changes in valve position, generator load, MWth, APRMs and loop flows.

o Repeat the above until desired power level is achieved.

Termination Event is terminated when Step 1 of the Reactivity Control Plan is complete with Point reactor power at 2967 MWth.

Rev 1

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

Event

Description:

(Tech Spec) RHR B Trips Event Initiation: Initiated at Lead Evaluator discretion Cue: Annunciator: H13-P601-17A-A4, RHR PUMP B MOTOR AUTO TRIP.

Time Position Applicants Actions or Behavior BOP

• Recognize and report trip of RHR B CRS

• Acknowledge trip of RHR B

• Notify Work Management Center or Maintenance of trip

• Enter LCO 3.5.1 Condition A and LCO 3.6.2.3 Condition A.

• Direct BOP to complete shutdown of RHR B per STP-204-6302 starting at step 7.1.12 BOP

• Complete shutdown of RHR B as follows:

o Close E12-F024B.

o Open/Verify open E12-F003B o Open E12-F048B o Open E12-F064B o Close E12-F068B o If required, vent the heat exchanger to reduce pressure to 100-150 psig as follows:

Throttle open E12-F073B Throttle open E12-F074B When RHR HX pressure is approximately 100-150 psig close E12-F074B.

Close E12-F073B.

ROLE PLAY

• As Control Building operator take direction to investigate RHR pump breaker following trip.

• As Reactor Building operator take direction to investigate RHR pump trip and take direction to perform fill and vent of RHR C if necessary.

Termination Event is terminated when the RHR line up has been restored to standby and Point Technical Specifications have been applied to the pump failure condition.

Rev 1

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

Event

Description:

Feedwater Pump A minimum flow valve fails open Event Initiation: Initiated at Lead Evaluator discretion Cue: RED indicating light on FWS-FV2A is ON and GREEN indicating light is OFF.

Time Position Applicants Actions or Behavior ATC

• Recognize and report FWR-FV2A failed open.

CRS

• Accept report of failed minimum flow valve

• Direct entry into AOP-0006.

ATC

• Enter AOP-0006

• Attempt to take manual control of FWR-FV2A by placing the controller in manual and depressing the CLOSE pushbutton.

• Refer to AOP-0007 for applicability ROLE PLAY

• As Turbine Building operator take direction to investigate failure of Feedwater pump A minimum flow valve.

Termination Event is terminated the appropriate notifications have occurred and the minimum Point flow valve has been manually closed.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 3 Event No.: 6 Page ___ of ___

Event

Description:

(Tech Spec) Inadvertent RCIC initiation Event Initiation: Initiated at Lead Evaluator discretion Cue: Annunciator: H13-P601-21A-E02 GLAND SEAL COMPRESSOR AUTO START, E51-F045 RED indicating light ON, GREEN indicating light OFF.

Time Position Applicants Actions or Behavior BOP

• Recognize and report inadvertent initiation of RCIC.

CRS

• Accept report of RCIC initiation.

• Verify by 2 independent means adequacy of reactor water level makeup and direct BOP to trip RCIC.

BOP

• Verify by 2 independent means adequacy of reactor water level makeup and trip RCIC as follows:

o Depress E51A.S17, RCIC TURBINE TRIP Pushbutton.

o Verify E51-MOVC002 RCIC TRIP & THROTTLE VALVE indicates closed.

o Verify RCIC speed lowering on E51-C002-1, RCIC TURB SPEED.

CRS When RCIC is tripped, Enter LCO 3.5.3 Condition A.

Termination Event is terminated when RCIC has been tripped and Technical Specifications Point have been applied for the RCIC failure and tripped condition.

Rev 1

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

Event

Description:

RCIC steam supply line break in the RCIC Room and Main Steam Tunnel with failure of RCIC Steam Supply Valves fail to isolate Event Initiation: Initiated at Lead Evaluator discretion Cue: Rising radiation levels at main plant exhaust and RCIC room, rising temperatures in RCIC room and steam tunnel.

Time Position Applicants Actions or Behavior BOP

• Recognize and report elevated temperature in RCIC room and Main Steam Tunnel.

• Enter AOP-0003.

• Recognize and report failure of RCIC to isolate.

• Attempt manual isolation of E51-F063 and E51-F064.

• Obtain RCIC room and Main Steam Tunnel temperatures from back panel indications.

• Continue to monitor and report temperatures throughout event.

• Control pressure 500-1090 psig and notify CRS when <700 psig.

Rev 1

NRC CRS

• Accept report of elevated temperature in RCIC room and Main Steam Tunnel.

• Direct entry into AOP-0003

• When Steam Tunnel temperature exceeds 144°F or RCIC Room temperature exceeds 144°F, enter EOP-0003.

• Accept report of failure of RCIC to isolate and direct attempt at manual isolation.

• Before RCIC Room or Steam Tunnel Temperatures exceed 200°F, Enter EOP-0001 and direct a manual reactor scram. (EOP entry may occur as a result of the MSIV isolation)

• Accept Scram Report from ATC

• Establish level band of -20 to 51

• Establish pressure band of 500-1090 psig with direction to ultimately be below 700 psig. When below 700 psig, adjust band to 500-700 psig.

• Notify Work Management or Maintenance of RCIC leak and failure to isolate.

• When >200°F is reached in more than one area, transition to Emergency Depressurization.

• Direct opening 7 ADS SRVs Rev 1

NRC ATC

• CRITICAL TASK Place the Mode Switch in Shutdown

• Check all control rods fully inserted

• Deliver Scram Report

• Verify Feedwater System is operating to restore reactor water level as follows:

o Verify level in prescribed band o Transfer to the Startup Level Controller as follows:

Place the Master controller to Manual and set output to 0 using the CLOSE pushbutton.

Select SINGLE ELEM control Roll the Startup Feedwater Level Controller tape set to 18 inches.

Place the Startup Feedwater Level Controller to AUTO as desired.

o Reduce to one Feed Pump.

o Depress Close on out of service Feed Reg Valve isolation MOVs.

o Reduce to two Condensate Pumps o Secure Operating Heater Drain Pumps o Request installation of Feed Pump Level 8 jumpers Termination Event is terminated when the RPV has been depressurized and plant parameters Point are stable.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 3 Event No.: 8 Page ___ of ___

Event

Description:

Three Safety Relief Valves fail to energize when required for emergency depressurization Event Initiation: Event initiated when operator attempts to open failed SRVs Cue: 3 ADS SRV RED indicating light fails to illuminate and GREEN indicating light remains illuminated.

Time Position Applicants Actions or Behavior BOP

• CRITICAL TASK When directed, open 7 ADS SRVs as follows:

o On H13-P601, place the control switches for the 7 ADS to OPEN and verify solenoid is energized (RED light ON, GREEN light OFF).

o Recognize and report 3 ADS SRVs failed to energize.

o Open 3 additional SRVs to accomplish Emergency Depressurization.

NOTE: For critical task criteria, a total of 5 SRVs are required to Emergency Depressurize.

CRS

• Accept report of ADS SRV failure.

• Direct opening of 3 other SRVs to satisfy Emergency Depressurization.

Termination Event is terminated when additional SRVs have been opened to accomplish Point Emergency Depressurization.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 3 Event No.: 9 Page ___ of ___

Event

Description:

Startup Feedwater Regulating Valve fails closed.

Event Initiation: Event initiated 5 minutes after the Mode Switch is removed from RUN position.

Cue: Output demand of Feedwater Regulating Valve indicates zero and Feedwater Flow to vessel is isolated.

Time Position Applicants Actions or Behavior ATC Recognize and report Startup Feedwater Regulating Valve failed closed.

Place Feedwater Regulating Valves in service by opening the inlet isolation valve FWS-MOV27A(B)(C) and opening the valve with the OPEN pushbutton or by placing in AUTO and utilizing the Master Controller.

Verify flow resumed to the RPV as needed to maintain level in the established band.

CRS Accept report of failed Startup Feedwater Regulating Valve Termination Event is terminated when alternate Feedwater Regulating Valves have been Point placed in service and level control is established.

Rev 1

NRC Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 4 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 75% power.

Turnover: Shift Priorities: 1) Start Feedwater Pump A 2) Continue power ascension with recirc flow per reactivity control plan. 3) Transfer Steam Seal Evaporator to Extraction Steam.

Event Malf. No. Event Type* Event No. Description 1 NA N (SRO, ATC) Start a Reactor Feedwater Pump A 2 NA R (ATC) Raise reactor power with reactor recirculation flow 3 NA N (SRO-BOP) Transfer Steam Seal Evaporator to Extraction Steam 4 RMS016A I(SRO) (Technical Specification) Failure of RMS-RE16A Drywell Radiation Monitor 5 ED004Q C (SRO, BOP) (Technical Specification) Loss of EJS-LDC2B 6 FWS016A I(SRO,ATC) Feedwater flow input to Feedwater Level Control failure 7 ED001 M (ALL) Loss of offsite power 8 RCIC003A C(SRO,BOP) RCIC Flow controller fails low SWP-P2A SWP-P2A pump breaker trip 9 C(SRO,ATC)

BKR TRIP

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) EJS-LDC2B, RMS-RE16A, FWLC input, Loss of Offsite power, RCIC controller, SWP-P2A Malfunctions after EOP entry (1-2) (2) RCIC controller, SWP-P2A Abnormal Events (2-4) (2) AOP-0006, AOP-0001 Major Transients (1-2) (1) Loss of offsite power EOPs entered (1-2) (1) EOP-0001 EOP contingencies (0-2) (1 potential) Alternate Level Control Critical Tasks (2-3) (2) Take manual control of FW, Maintain reactor water level >-162 with RCIC Rev 1

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

Event

Description:

Start a Reactor Feedwater Pump A Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior SRO

• Direct start of Reactor Feedwater Pump A per SOP-0009 Section 4.5 ATC

• Start Reactor Feedwater Pump A as follows:

o Verify lube oil system in service o Communicate with Turbine Building operator to verify the following:

CCS-V280 is OPEN CCS-V268 is OPEN CCS-V331 is OPEN CCS-V332 is OPEN CCS-V292 is OPEN CCS-V295 is OPEN CCS-V261 is OPEN CCS-V272 is OPEN Feedwater Pump A seals are vented.

Feedwater Pump A has been warmed.

FWS-V28 is OPEN.

ROLE PLAY

• When requested, as the Turbine Building operator, inform the ATC operator that:

CCS-V280 is OPEN CCS-V268 is OPEN CCS-V331 is OPEN CCS-V332 is OPEN CCS-V292 is OPEN CCS-V295 is OPEN CCS-V261 is OPEN CCS-V272 is OPEN Feedwater Pump A seals have been vented.

Feedwater Pump A has been warmed.

FWS-V28 is OPEN.

A general visual inspection has been performed and Feedwater Pump A is NOT rotating and is prepared for a START.

ATC

• Verify CNM-H/A68A is in AUTO and set at 68%

• Communicate with Auxiliary Control Room to verify sufficient Condensate Demineralizers and Condensate Filtration filters are in service to support pump start.

Rev 1

NRC ROLE PLAY

• As Auxiliary Control Room operator, when requested, inform ATC that sufficient Condensate Demineralizers are in service to support pump start.

ATC

• Verify FWR-FV2A is operable and unisolate.

• Verify the following CCS valves are fully opened:

o CCS-V5003A o CCS-V5004A ROLE PLAY

• As Turbine Building operator, when requested, inform ATC operator that CCS-V5003A and CCS-V5004A are fully open.

ATC

• Direct Turbine Building operator to close P73-PIT-R115A-V2 and verify P73-VF114A is open.

ROLE PLAY

• When requested, inform ATC that P73-PIT-R115A-V2 is closed and P73-VF114A is open.

ATC

• Depress the STOP pushbutton on FWS-P1A to reset any trips.

• Depress and hold the START pushbutton for FWS-P1A until FWR-FV2A has opened and the pump has started.

• Check motor amps on FWS-A03 are greater than 200 amps but less than or equal to 311 amps.

• Open FWS-MOV26A

• Verify closed FWS-MOV109

• Direct Turbine Building operator to continue field performance starting at Step 4.5.19.

ROLE PLAY

• As Turbine Building operator, accept direction to continue procedure performance starting at Step 4.5.19 Termination Event is terminated when Feedwater pump A is in service with its discharge valve Point open.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 2 Page ___ of ___

Event

Description:

Raise reactor power with reactor recirculation flow Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior SRO

• Direct ATC to raise power with reactor recirculation flow in accordance with the reactivity control plan.

ATC

• Raise power with reactor recirculation flow in accordance with the reactivity control plan as follows:

o Verify B33-K603A(B) is in Manual o Determine which B33-K603A(B) is to be adjusted by observing Loop Flows on B33-R612A and B33-R612B. Both loops may have to be adjusted to obtain the desired Reactor Power while maintaining Loop Flow mismatch within specification.

o Note the current valve position, generator load, MWth, APRMs and loop flows.

o Raise flow by toggling momentarily B33-K603A(B) in the open direction (right) using slow detent while observing a servo error deviation in the negative direction.

o Verify the servo error returns to its previous position.

o Observe valve position, generator load, MWth, APRMs and loop flows for expected changes.

o Repeat steps as necessary until the desired power level is reached.

Termination Event is terminated when Reactivity Control Plan Step 80 is complete and reactor Point thermal power is ~ 2425 MWth.

Rev 1

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

Event

Description:

Transfer Steam Seal Evaporator to Extraction Steam Event Initiation: Initiated by crew.

Cue: From turnover sheet.

Time Position Applicants Actions or Behavior SRO

• Direct transfer of SSE to Extraction Steam per SOP-0015 BOP

• Transfer SSE to Extraction Steam as follows:

o Verify annunciator P870-52A-E03 is clear o Verify ESS-MOV112 is closed o Verify ESS-MOV117 is open o Slowly throttle open ESS-MOV112 using the control switch and the STOP pushbutton.

o When ESS-MOV112 show dual indication, close DTM-AOV118.

o Monitor trip unit ESS-ES112 while throttling ESS-MOV112. If setpoint approaches 5.5 psid, ESS-MOV112 may be left throttled.

ROLE PLAY If back panel information is requested for ESS-ES112, provide a reading of 10 psid.

Termination Event is terminated when the Steam Seal Evaporator is being supplied by Point Extraction Steam.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 4 Page ___ of ___

Event

Description:

(Technical Specification) Failure of RMS-RE16A Drywell Radiation Monitor Event Initiation: Initiated at Lead Evaluator discretion.

Cue: Annunciator: H13-P863-71A-B06 Time Position Applicants Actions or Behavior BOP

• Recognize and report upscale alarm on RMS-RE16A

• Compare to RMS-RE16B and determine RMS-RE16A has failed.

SRO

• Accept report of failure of RMS-RE16A

• Enter Technical Specification LCO 3.3.3.1 Condition A.

Termination Event is terminated when Technical Specifications have been applied to the failed Point radiation monitor.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 5 Page ___ of ___

Event

Description:

(Technical Specification) Loss of EJS-LDC2B Event Initiation: Initiated at Lead Evaluator discretion.

Cue: Annunciator: H13-P877-32-D04 Time Position Applicants Actions or Behavior BOP

• Recognize and report loss of EJS-LDC2B.

• Dispatch Reactor Building operator to EJS-LDC2B to ascertain cause of trip.

SRO

• Acknowledge report of EJS-LDC2B.

• Notify Work Management Center of bus loss.

• Enter Technical Specification LCO 3.8.9 Condition A.

• Direct start of HVR-UC1A

• Direct start of HVR-UC11A

• Acknowledge low pressure condition on RHR B & C and direct racking out of RHR B and C pump breakers

• Enter Technical Specification 3.5.1 Condition C and 3.6.2.3 Condition A when pump breakers are racked out.

BOP

• Start HVR-UC1A as follows:

o Depress the START pushbutton for HVR-UC1A and verify HVN-TV5A opens.

• Start HVR-UC11A as follows:

o Depress the START pushbutton for HVR-UC11A and verify proper operation.

• Respond to RHR B & C low pressure annunciators ROLE PLAY

• As Reactor Building operator, take direction to investigate cause of trip of EJS-LDC2B. After 10 minutes, notify BOP that there is no obvious reason for bus loss.

• As Reactor Building operator, if requested following start of HVR-UC1A and HVR-UC11A, notify BOP that both coolers are operating normally.

• As Control Building operator, take direction to rack out RHR B & C pump breakers.

Termination Event is terminated when Technical Specifications have been applied to the failed Point electrical bus and RHR B & C after pump breakers are racked out.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 6 Page ___ of ___

Event

Description:

Feedwater flow input to Feedwater Level Control fails high Event Initiation: Initiated at Lead Evaluator discretion.

Cue: Lowering reactor water level, feedflow indicator on p680 rising.

Time Position Applicants Actions or Behavior ATC

• Recognize and report lowering reactor water level

• Enter AOP-0006

• CRITICAL TASK: Take manual control of feedwater level control by placing the Master Controller in manual and controlling valve positions with the OPEN and CLOSE pushbutton as needed to maintain level.

• Diagnose failure as feedflow input failure.

SRO

• Accept report of lowering reactor water level

• Direct entry into AOP-0006.

• Notify Work Management Center or maintenance of failure.

Termination Event is terminated when reactor water level is stable and under manual control.

Point Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 7 Page ___ of ___

Event

Description:

Loss of offsite power Event Initiation: Initiated at Lead Evaluator discretion.

Cue: Standby diesel generator initiation, loss of voltage to non-safety busses Time Position Applicants Actions or Behavior ATC

• Recognize and report the loss of offsite power

• Place the Mode Switch in Shutdown

• Verify all control rods fully inserted

• Deliver scram report

• Perform AOP-0004 o Dispatch operators to operating diesel generators o Verify diesel are supplying their respective switchgears o Verify initiation of Standby Service Water. See event 9.

o Dispatch personnel to rack out HPCS pump breaker o Attempt manual start of Div 3 DG

• Perform AOP-0001 and AOP-0002.

SRO

• Acknowledge scram report

• Direct entry into AOP-0004

• Direct entry into AOP-0001, AOP-0002, and AOP-0003.

• Enter EOP-0001

• Direct level band of -20 to 51 with RCIC

• Direct pressure band of 500-1090 psig

• Communicate with System Operator to coordinate restoration of power.

BOP

• Initiate RCIC See event 8.

• Control reactor pressure 500-1090 psig with Safety Relief Valves

• Perform AOP-0003 ROLE PLAY

• When contacted, as System Operator notify the SRO that loss of power problem has occurred at Fancy Point Switchyard and crews are on their way to the switchyard to determine the cause and establish an estimated time for restoration.

Termination Event is terminated when plant parameters are stable and Critical Task of Point subsequent event is met.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 8 Page ___ of ___

Event

Description:

RCIC Flow controller fails low Event Initiation: Initiated when RCIC turbine speed is >90% rated speed Cue: RCIC flow lower than 600 gpm Time Position Applicants Actions or Behavior BOP

• Recognize and report failure of RCIC controller

• CRITICAL TASK Take manual control of RCIC to maintain level > Top of Active Fuel (>-162) by placing the controller in MANUAL and depressing the OPEN pushbutton.

SRO

• Acknowledge report of RCIC controller failure

• Direct BOP to take manual control of RCIC if not already performed.

Termination Event is terminated when RCIC controller is placed in manual and RCIC is Point injecting to the RPV satisfying the Critical Task.

Rev 1

NRC Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: 4 Event No.: 9 Page ___ of ___

Event

Description:

SWP-P2A fails to start/trips Event Initiation: Initiated one minute after Event 7 (Loss of Offsite Power)

Cue: Indicating lights for SWP-P2A Green light ON, Amber light ON, Red light OFF Time Position Applicants Actions or Behavior ATC

• Recognize and report trip of SWP-P2A

• Recognize and report lack of cooling to Div 1 DG

• Open SWP-MOV505A and SWP-MOV505B OR Secure Div 1 DG

• Reduce loads cooled by Div 1 Service Water SRO

• Acknowledge report of SWP-P2A trip

• Recognize lack of cooling to Div 1 DG and direct opening of SWP-MOV505A and SWP-MOV505B OR Secure Div 1 DG if not already performed.

Termination Event is terminated when either the Division 1 Diesel Generator is tripped or Point cooling is provided from Division 2.

Rev 1

Number: *RJPM-NRC12-A1 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE WHEN HOT SHUTDOWN BORON WEIGHT HAS BEEN INJECTED INTO THE CORE REASON FOR REVISION:

2012 NRC Exam - RO A1 PREPARE / REVIEW:

Angie Orgeron 1538 7/2/2012 Preparer KCN Date David Bergstrom 257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A1 TASK DESCRIPTION: Determine when Hot Shutdown Boron weight has been injected into the core per EOP-0005 Enclosure 15 TASK

REFERENCE:

200051005001 K/A REFERENCE & RATING: 2.1.25 3.9 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 5 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A1 Page 2 of 9

RJPM-NRC12-A1 SIMULATOR SETUP SHEET Task

Description:

Determine when Hot Shutdown Boron weight has been injected into the core per EOP-0005 Enclosure 15 Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A1 Page 3 of 9

RJPM-NRC12-A1 DATA SHEET References for Development: OSP-0053, Rev 16 Attachment 13 Required Materials: OSP-0053, Rev 16 Attachment 13 Task Standard: The amount (weight) of Boron injected into the core, necessary to achieve Hot Shutdown Conditions and the time when this amount has been injected have been determined.

Required Plant Condition: N/A Applicable Objectives: R-LPOPS-HLO-513 Objective 6 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A1 Page 4 of 9

RJPM-NRC12-A1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

An Anticipated Transient without Scram (ATWS) has occurred, 32 rods have failed to fully insert into the core.

• Reactor Pressure is 1050 psig and lowering

• Suppression Pool temperature is 115oF and rising

• Both Recirculation Pumps are tripped

• Initial SLC tank level is 3150 gal

• SLC pump A was started at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> Initiating Cue:

The Control Room Supervisor has directed you to determine the tank level at which the Hot Shutdown Boron weight has been injected and approximately what time this will occur, in accordance with OSP-0053, Attachment 13.

RJPM-NRC12-A1

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A1 PERFORMANCE STEP STANDARD S/U COMMENTS Using the Standby Liquid Control The candidate used 3100 gallons as a Since the initial tank level is Injection Requirements table on page conservative value for tank level, The tank level between the values on the chart 2 of 2 of the Attachment 13 of OSP- for Hot Shutdown Boron weight is 2474 gals. the Note at the top directs the

• 1.

0053, determine the tank level which operator to use the smaller value must be reached to have injected Hot of 3100 gal as initial level.

Shutdown Boron weight into the core.

Using the Standby Liquid Control The candidate identified that Hot Shutdown Injection Requirements table on page Boron should be injected in 16 minutes, therefore 2 of 2 of Attachment 13 of OSP-0053, the time will be 1531 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.825455e-4 months <br /> when Hot Shutdown

• 2.

determine the time when Hot Boron Weight is injected.

Shutdown Boron weight will be injected.

Terminating Cue: Hot Shutdown Boron weight tank level and injection time have been determined per OSP-0053 Attachment 13 and record on the Answer Sheet.

RJPM-NRC12-A1

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A1 Page 7 of 9

RJPM-NRC12-A1 ANSWER KEY:

Tank Level for Hot Shutdown Boron Weight: 2474 gallons Approximate time at which Hot Shutdown Boron Weight is injected: 1531 RJPM-NRC12-A1 Page 8 of 9

RJPM-NRC12-A1 JPM Task Conditions/Cues (Operator Copy)

An Anticipated Transient without Scram (ATWS) has occurred, 32 rods Initial Conditions:

have failed to fully insert into the core.

• Reactor Pressure is 1050 psig and lowering

• Suppression Pool temperature is 115oF and rising

• Both Recirculation Pumps are tripped

• Initial SLC tank level is 3150 gal

• SLC pump A was started at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> The Control Room Supervisor has directed you to determine the tank Initiating Cues:

level at which the Hot Shutdown Boron weight has been injected and approximately what time this will occur, in accordance with OSP-0053, Attachment 13.

Tank Level for Hot Shutdown Boron Weight:

Approximate time at which Hot Shutdown Boron Weight is injected: ______________

RJPM-NRC12-A1 Page 9 of 9

Number: *RJPM-NRC12-A2 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE MAINTENANCE REQUIREMENTS TO MAINTAIN AN ACTIVE LICENSE REASON FOR REVISION:

2012 NRC Exam - RO A2 PREPARE / REVIEW:

Angie Orgeron 1538 7/2/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A2 TASK DESCRIPTION: Determining maintenance requirements to maintain an active license.

TASK

REFERENCE:

Admin K/A REFERENCE & RATING: 2.1.4 3.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 5 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A2 Page 2 of 9

RJPM-NRC12-A2 SIMULATOR SETUP SHEET Task

Description:

This task requires reviewing watch stand events and determining which operators have met the requirements to maintain an active license.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A2 Page 3 of 9

RJPM-NRC12-A2 DATA SHEET References for Development: Operations Standards & Expectations Required Materials: Operations Standards & Expectations, Pg 49-50 Task Standard: Determination has been made that Operator 2 can fill the July 5, 2012 ATC position.

Required Plant Condition: N/A Applicable Objectives: Admin Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A2 Page 4 of 9

RJPM-NRC12-A2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A review of the Operations schedule has determined that an insufficient number of people have been scheduled to cover all shift positions on July 5, 2012. Due to numerous vacations, Operations licensed personnel assigned to the office staff must be used to cover the At the Controls (ATC) watch station on July 5th. The shift history of office staff individuals is shown below. All other days not shown were worked in office staff positions working 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> days.

Initiating Cue:

Review the work history of the staff personnel below and determine which individual(s) are proficient and can cover the ATC watch on July 5, 2012. Record your answer in the space provided.

Operator 1 Operator 2 Operator 3 Operator 1 was proficient in the 1st Operator 2 was NOT proficient in Operator 2 was proficient in the 1st quarter of 2012 the 1st quarter of 2012 quarter of 2012 Work History Work History Work History 4/10/12 - ATC 0600-1800 4/9/2012 - ATC under instruction 5/8/12 - ATC 0600-1800 0600-1800 4/20/12 - Unit 1800-0600 4/10/12 - Unit under instruction 5/16/12 - Unit 0600-1800 0600-1800 5/6/12 - Unit 0600-1800 4/11/12 - ATC under instruction 5/31/12 - Control Building 0600-0600-1800 1800 6/17/12 ATC 0600-1800 4/12/12 - Conducted a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> plant 6/7/12 - ATC 1800-0600 tour under the instruction of a licensed operator 0600-1000 6/28/12 - Tagging Official 0600- 6/30/12 Unit 0600-1800 1800 RJPM-NRC12-A2

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A2 PERFORMANCE STEP STANDARD S/U COMMENTS Determine eligibility of Operator 1 to Candidate recognized that Operator 1 will not be work July 5, 2012 to fill At the proficient on July 5, 2012 because he will not Controls watch. have had 5 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> proficiency watches in the 1.

second quarter due to the Tagging Official position not being an acceptable position to maintain license proficiency.

Determine eligibility of Operator 2 to Candidate recognized that Operator 2 will be

2. work July 5, 2012 to fill At the proficient and can stand the ATC watch on July Controls watch. 5, 2012.

Determine eligibility of Operator 3 to Candidate recognized that Operator1 3 will not be work July 5, 2012 to fill At the proficient on July 5, 2012 because he will not Controls watch. have had 5 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> proficiency watches in the 3.

second quarter due to the Control Building position not being an acceptable position to maintain license proficiency.

Record Operator 2 on the Operator Candidate recorded Operator #2 as the

• 4. Cue Sheet. available candidate to cover the July 5, 2012 ATC watch.

Terminating Cue: Answer recorded on Answer Sheet.

RJPM-NRC12-A2

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A2 Page 7 of 9

RJPM-NRC12-A2 ANSWER KEY:

The July 5th ATC watch may be covered by Operator(s) # 2 RJPM-NRC12-A2 Page 8 of 9

RJPM-NRC12-A2 JPM Task Conditions/Cues (Operator Copy)

A review of the Operations schedule has determined that an insufficient Initial Conditions:

number of people have been scheduled to cover all shift positions on July 5, 2012. Due to numerous vacations, Operations licensed personnel assigned to the office staff must be used to cover the At the Controls (ATC) watch station on July 5th. The shift history of office staff individuals is shown below. All other days not shown were worked in office staff positions working 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> days Initiating Cues: Review the work history of the staff personnel below and determine which individual(s) are proficient and can cover the ATC watch on July 5, 2012. Record your answer in the space provided.

Operator 1 Operator 2 Operator 3 Operator 1 was proficient in the 1st Operator 2 was NOT proficient in Operator 2 was proficient in the 1st quarter of 2012 the 1st quarter of 2012 quarter of 2012 Work History Work History Work History 4/10/12 - ATC 0600-1800 4/9/2012 - ATC under instruction 5/8/12 - ATC 0600-1800 0600-1800 4/20/12 - Unit 1800-0600 4/10/12 - Unit under instruction 5/16/12 - Unit 0600-1800 0600-1800 5/6/12 - Unit 0600-1800 4/11/12 - ATC under instruction 5/31/12 - Control Building 0600-0600-1800 1800 6/17/12 ATC 0600-1800 4/12/12 - Conducted a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> plant 6/7/12 - ATC 1800-0600 tour under the instruction of a licensed operator 0600-1000 6/28/12 - Tagging Official 0600- 6/30/12 Unit 0600-1800 1800 The July 5th ATC watch may be covered by Operator(s) #

RJPM-NRC12-A2 Page 9 of 9

Number: *RJPM-NRC12-A3 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE EFFECTS OF REMOVING CONTROL POWER FUSE FOR FUEL BUILDING VENTILATION DAMPER HVF-AOD20A REASON FOR REVISION:

2012 NRC Exam JPM - RO A3 PREPARE / REVIEW:

Angie Orgeron 1538 7/3/2012 Preparer KCN Date David Bergstrom 0257 8/8/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/8/2012 Approved KCN Date

• Indexing Information

RJPM-NRC12-A3 TASK DESCRIPTION: Determine Effects of Removing Control Power Fuse for Fuel Building Ventilation Damper HVF-AOD20A TASK

REFERENCE:

299003001001 K/A REFERENCE & RATING: 2.2.15 3.9 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A3 Page 2 of 9

RJPM-NRC12-A3 SIMULATOR SETUP SHEET Task

Description:

Determine Effects of Removing Control Power Fuse for Fuel Building Ventilation Damper HVF-AOD20A Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A3 Page 3 of 9

RJPM-NRC12-A3 DATA SHEET References for Development: ESK-7HVF01 ESK-7HVF02 ESK-7SCC21 ESK-10ANN23 ARP-P863-75A-B01 Required Materials: ESK-7HVF01 ESK-7HVF02 ESK-7SCC21 Required Plant Condition: N/A Task Standard: Determined the effects of removal of F1-1HVFA06 in panel H13-P851 in agreement with the answer key.

Applicable Objectives: HLO-542-1, Obj. 5, 6, 7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A3 Page 4 of 9

RJPM-NRC12-A3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Electrical Maintenance is conducting Work Order to replace the solenoid for HVF-AOD20A. A tag out has been prepared to support this work and personnel are standing by to implement the tag out. The next step of the tagging order requires removal of F1-HVFA06 to de-energize the solenoid to be replaced.

Initiating Cue:

Given the appropriate drawings, the CRS has directed you to determine the following:

1. The fail position of HVF-AOD20A, when the fuse is removed.

2. Any other component(s) positions that are affected by the fuse removal and the associated affect.

3. Identify any control room alarms, status lights and / or component indication affected. (Alarm # is sufficient)

RJPM-NRC12-A3

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A3 PERFORMANCE STEP STANDARD S/U COMMENTS Using ESK-7HVF01 & ESK-7HVF02 1. The candidate determined that HVF-AOD20A

• 1.

determine damper fail position. fails OPEN when de-energized Using ESK-7HVF01 & ESK-7HVF02 2. The candidate determined that HVF-AOD31A

• 2. determine other component(s) also fails OPEN when the fuse is removed.

positions affected by the fuse removal.

Using ESK-7 ESK-7HVF01 & 3. The candidate identified that fuse removal will ESK-7HVF02, determine impact of also cause the following on P863:

fuse removal on Control Room Must have the four of the six items correct to indication and alarm status.

meet pass criteria for this critical step.

• De-energizes (green and red) position indication light for HVF-AOD20A.

• De-energizes (green and red) position indication light for HVF-AOD31A.

• 3.

• De-energizes (green and red) position indication light for HVF-AOD3A.

• De-energizes (green and red) position indication light for HVF-AOD33A.

• Energizes (or turns on) the Amber INOP status light (postage stamp) FB Vent Dmprs.

• Initiates alarm window No. 0463 RJPM-NRC12-A3

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A3 Terminating Cue: Fuse removal fail position of HVF-AOD20A, its impact on HVF-AOD31A and Control Room H13-P863 indications and alarms have been listed on Answer Sheet.

ANSWER KEY:

(80% required to pass JPM)

1. HVF-AOD20A fails OPEN. (1 point)

2. HVF-AOD31A also fails OPEN (1 point)

3. The following control room indications are also affected by the fuse removal:

a. The following dampers lose red and green position indications:

i. HVF-AOD20A (0.25 point) ii. HVF-AOD31A (0.25 point) iii. HVF-AOD3A (0.25 point) iv. HVF-AOD33A (0.25 point)

b. Amber Status light (Postage Stamp) FB Vent Dmprs (1 point)

c. Alarm 0463 in alarm (1 point)

RJPM-NRC12-A3

• Denotes Critical Step Page 7 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A3 Page 8 of 9

RJPM-NRC12-A3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Electrical Maintenance is conducting Work Order to replace the solenoid for HVF-AOD20A. A tag out has been prepared to support this work and personnel are standing by to implement the tag out. The next step of the tagging order requires removal of F1-HVFA06 to de-energize the solenoid to be replaced.

Given the appropriate drawings, the CRS has directed you to determine Initiating Cues:

the following:

1. The fail position of HVF-AOD20A, when the fuse is removed.

2. Any other component(s) positions that change when the fuse is removed.

3. Identify any control room alarms, status lights and / or component indication affected. (Alarm # is sufficient)

Write answers below:

1.

2.

3.

RJPM-NRC12-A3 Page 9 of 9

Number: *RJPM-NRC12-A4 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

OBTAIN RADIOLOGICAL INFORMATION FROM A SURVEY MAP REASON FOR REVISION:

2012 NRC Exam - RO A4 PREPARE / REVIEW:

Angie Orgeron 1538 7/2/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A4 TASK DESCRIPTION: Radiological information correctly obtained from data on survey map in accordance with EN-RP-106.

TASK

REFERENCE:

Admin K/A REFERENCE & RATING: 2.3.7 3.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 5 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A4 Page 2 of 9

RJPM-NRC12-A4 SIMULATOR SETUP SHEET Task

Description:

This task requires review of survey information in order to answer questions regarding the radiological conditions in the Steam Jet Air Ejector rooms.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A4 Page 3 of 9

RJPM-NRC12-A4 DATA SHEET References for Development: Survey Maps for SJAE rooms EN-RP-106 Required Materials: Survey Maps for SJAE rooms EN-RP-106 Task Standard: All radiological protection questions correctly answered regarding radiological conditions in the Steam Jet Air Ejector rooms to allow entry for required inspections.

Required Plant Condition: N/A Applicable Objectives: Admin Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A4 Page 4 of 9

RJPM-NRC12-A4 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

A plant startup is in progress at 30% power. Steam Jet Air Ejector A is in service. Scheduled surveillances require a general inspection walk down of both SJAE rooms. Hydrogen Water Chemistry system is out of service.

Initiating Cue:

The CRS has directed you to make entry into both SJAE rooms to perform a general inspection. The Radiological Protection Technician has provided you with survey information and requires you to answer the following questions prior to entry:

(Provide answer in spaces below)

1. What is the highest contamination level in either of the rooms?

2. Based on these contamination levels, is protective clothing required?

3. What is the highest general area dose rate that will be encountered

4. Where will the highest general area dose rate be encounter? (Provide room and compass location relative to SJAE).

5. What is the value of the highest contact dose?

6. Where is the highest contact dose located? (Provide room and compass location relative to SJAE).

RJPM-NRC12-A4

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A4 PERFORMANCE STEP STANDARD S/U COMMENTS Review maps and determine where the Candidate reviewed both maps and determined

1. highest contamination level is located. that the highest contamination level is <1000 dpm

/ 100 cm2 Based on contamination levels Candidate recognized that the area is not

2. determine whether or not protective contaminated therefore protective clothing is not clothing is required. required.

Review maps and determine the value Candidate reviewed both maps and determined

3. of the highest general area dose rates. that the highest general area dose rate is 110mR/hr.

Review maps and determine location Candidate reviewed both maps and determined 4.. of highest general area dose rates. that the highest general area dose rate is in the A SJAE Room on the north side of the SJAE.

Review maps and determine the value Candidate reviewed both maps and determined

5. of the highest contact dose rates. that the highest general area dose rate is 150 mR/hr.

Review maps and determine location Candidate reviewed both maps and determined

6. of highest contact dose rates. that the highest contact dose rate is in the A SJAE Room on the north side of the SJAE.

Complete answer sheet. Candidate correctly annotated the above

• 7. information on the answer sheet.

Terminating Cue: Answer recorded on Answer Sheet.

RJPM-NRC12-A4

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A4 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A4 Page 7 of 9

RJPM-NRC12-A4 ANSWER KEY:

1. What is the highest contamination level in either of the rooms? <1000 dpm / 100 cm2

2. Based on these contamination levels, is protective clothing required? No

3. What is the highest general area dose rate that will be encountered? 110mR / hr

4. Where will the highest general area dose rate be encounter? (Provide room and compass location relative to SJAE)? SJAE Room A on the north side of the SJAE

5. What is the value of the highest contact dose? 150 mR / hr

6. Where is the highest contact dose located? (Provide room and compass location relative to SJAE). SJAE Room A on the north side of the SJAE RJPM-NRC12-A4 Page 8 of 9

RJPM-NRC12-A4 JPM Task Conditions/Cues (Operator Copy)

A plant startup is in progress at 30% power. Steam Jet Air Ejector A is Initial Conditions:

in service. Scheduled surveillances require a general inspection walk down of both SJAE rooms. Hydrogen Water Chemistry system is out of service.

Initiating Cues: The CRS has directed you to make entry into both SJAE rooms to perform a general inspection. The Radiological Protection Technician has provided you with survey information and requires you to answer the following questions prior to entry:

(Provide answer in spaces below)

1. What is the highest contamination level in either of the rooms?

2. Based on these contamination levels, is protective clothing required?

3. What is the highest general area dose rate that will be encountered?

4. Where will the highest general area dose rate be encounter? (Provide room and compass location relative to SJAE).

5. What is the value of the highest contact dose?

6. Where is the highest contact dose located? (Provide room and compass location relative to SJAE).

RJPM-NRC12-A4 Page 9 of 9

Number: RJPM-NRC12-A5 RIVER Revision: 0 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

GENERATE A MANUAL LCO TRACKING SHEET REASON FOR REVISION:

2012 NRC EXAM JPM - SRO A5 PREPARE / REVIEW:

Angie Orgeron 1538 7/3/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A5 TASK DESCRIPTION: GENERATE A MANUAL LCO TRACKING SHEET TASK

REFERENCE:

300061003002 K/A REFERENCE & RATING: Generic 2.1.18 3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Simulator Classroom X Room COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A5 Page 2 of 10

RJPM-NRC12-A5 SIMULATOR SETUP SHEET Task

Description:

Generate a manual LCO Tracking Sheet Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A5 Page 3 of 10

RJPM-NRC12-A5 DATA SHEET References for Development: Technical Specifications OSP-0040, LCO TRACKING AND SAFETY FUNCTION DETERMINATION Required Materials: Technical Specifications OSP-0040, LCO TRACKING AND SAFETY FUNCTION DETERMINATION Required Plant Condition: N/A Task Standard: LCO Tracking Sheet complete in accordance with OSP-0040 and JPM Answer Key.

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A5 Page 4 of 10

RJPM-NRC12-A5 If In-Plant or In the Control Room:

Caution the Operator is NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1 at 100% power when the Main Turbine Bypass Valve surveillance performance was determined to be unsatisfactory. The Main Turbine Bypass Valves were declared inoperable at 0930 on 11/15/2012. It is estimated that it will take 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair the valves.

Initiating Cue:

The LCO module of eSoms is unavailable due to a system upgrade. Complete a manual LCO tracking sheet in accordance with OSP-0040 for the current Condition and Required Actions as well as any subsequent Conditions expected during the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The next available LCO number is TS-12-C85-001.

RJPM-NRC12-A5

• Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A5 PERFORMANCE STEP STANDARD S/U COMMENTS Complete OSP-0040 Attachment 2 for LCO Status Sheet completed as indicated on JPM inoperable Main Turbine Bypass key.

Valves.

• 1.

Only the highlighted data is required as critical.

Terminating Cue: LCO Status Sheet completed for inoperable Main Turbine Bypass Valves.

RJPM-NRC12-A5

• Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A5 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A5 Page 7 of 10

RJPM-NRC12-A5 ANSWER KEY LCO No.: 1-TS 0047 1 Date: 11/15/2012 2 Time: 0930 3 % PWR 100% 4 Mode: 1 Page 1 of 1 5 TS/TRM No.: 3.7.5 6 Mode Change Allowed: Yes No 7 Mark No.C85- Sys. No.:509 8 Applicable Modes:___1 ___2 ___3 ___4 ___ 5

Description:

Main Turbine Bypass Valve System Other: Thermal Power .23.8%

9 CONDITION INITIATING LCO: Scheduled Outage______ Equipment Failure Main Turbine Bypass Valves failed surveillance testing.

10 Condition 11 Required Action 12 Completion Time A. Main Turbine Bypass A.2 Apply the APLHGR, Required by: Completed:

System inoperable. LHGR and MCPR limits for Date: 11/15/2012 Date:___/___/___

inoperable Main Turbine Time:__________

Bypass System as specified in Time: 1130 Initials:_________

the COLR..

B. Required Action and B.1. Reduce THERMAL Required by: Completed:

associated Completion Time POWER to 23.8% RTP. Date: 11/15/2012 Date:___/___/___

not met. (This line optional) Time:__________

Time: 1330 Initials:_________

________________________ ________________________ Required by: Completed:

________________________ ________________________ Date:_ ______ Date:___/___/___

________________________ ________________________ Time:__________

____________________ __________________ Time:____ Initials:_________

13 LCO 3.0.6 ENTERED 14 LOSS OF SAFETY FUNCTION NA EVALUATION COMPLETED Initials/KCN:____/____

15 PREPARED BY: 16 REVIEWED BY:

LCO CLOSEOUT 17 COMMENTS/CORRECTIVE ACTIONS 18 LCO RESTORED DATE/TIME 19 RESTORED BY: 20 REVIEWED BY:

RJPM-NRC12-A5 Page 8 of 10

RJPM-NRC12-A5 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions:

The plant is operating in Mode 1 at 100% power when the Main Turbine Bypass Valve surveillance performance was determined to be unsatisfactory. The Main Turbine Bypass Valves were declared inoperable at 0930 on 11/15/2012. It is estimated that it will take 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair the valves Initiating Cues:

The LCO module of eSoms is unavailable due to a system upgrade. Complete a manual LCO tracking sheet in accordance with OSP-0040 for the current Condition and Required Actions as well as any subsequent Conditions expected during the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The next available LCO number is TS C85-001.

RJPM-NRC12-A5 Page 9 of 10

RJPM-NRC12-A5 LCO No.: 1-TS- ____ - _________

1 Date: 2 Time: 3 % PWR 4 Mode: Page 1 of _____

5 TS/TRM No.: 6 Mode Change Allowed:___Yes ___No 7 Mark No.__________________ Sys. No.:______ 8 Applicable Modes:___1 ___2 ___3 ___4 ___5 Description_______________________________ Other_____________________________________

9 CONDITION INITIATING LCO: Scheduled Outage______ Equipment Failure_____

10 Condition 11 Required Action 12 Completion Time

________________________ ________________________ Required by: Completed:

________________________ ________________________ Date:___/___/___ Date:___/___/___

________________________ ________________________ Time:__________

________________________ ________________________ Time:__________ Initials:_________

________________________ ________________________ Required by: Completed:

________________________ ________________________ Date:___/___/___ Date:___/___/___

________________________ ________________________ Time:__________

________________________ ________________________ Time:__________ Initials:_________

________________________ ________________________ Required by: Completed:

________________________ ________________________ Date:___/___/___ Date:___/___/___

________________________ ________________________ Time:__________

________________________ ________________________ Time:__________ Initials:_________

________________________ ________________________ Required by: Completed:

________________________ ________________________ Date:___/___/___ Date:___/___/___

________________________ ________________________ Time:__________

________________________ _______________________ Time:__________ Initials:_________

13 LCO 3.0.6 ENTERED 14 LOSS OF SAFETY FUNCTION EVALUATION COMPLETED Initials/KCN:____/____

15 PREPARED BY: 16 REVIEWED BY:

LCO CLOSEOUT 17 COMMENTS/CORRECTIVE ACTIONS 18 LCO RESTORED DATE/TIME 19 RESTORED BY: 20 REVIEWED BY:

RJPM-NRC12-A5 Page 10 of 10

Number: *RJPM-NRC12-A6 RIVER Revision: 0 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE PLANT SAFETY LEVEL DURING SHUTDOWN CONDITIONS REASON FOR REVISION:

2012 NRC Exam JPM - SRO A6 PREPARE / REVIEW:

Angie Orgeron 1538 7/3/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A6 TASK DESCRIPTION: Determine Plant Safety Level during shutdown conditions per OSP-0037 TASK

REFERENCE:

300029001005 K/A REFERENCE & RATING: 2.1.23, 4.3/4.4 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A6 Page 2 of 10

RJPM-NRC12-A6 SIMULATOR SETUP SHEET Task

Description:

Determine Plant Safety Level during shutdown conditions per OSP-0037 Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A6 Page 3 of 10

RJPM-NRC12-A6 DATA SHEET References for Development: OSP-0037, Rev 27 Shutdown Operations Protection Plan (SOPP)

Required Materials: OSP-0037, Rev 27, Shutdown Operations Protection Plan (SOPP)

Required Plant Condition: N/A Task Stardard: The SRO has filled out the SOPP Status sheet and identified that the most conservative safety level is YELLOW for Shutdown Cooling.

Applicable Objectives: RBS-1-LEC-LOR-00910.00 Obj. 4 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A6 Page 4 of 10

RJPM-NRC12-A6 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

RBS is at day 25 of Refueling Outage 15 (RF-15). The last time the SOPP Status Sheet was completed it indicated that all Safety Levels were GREEN. Since that time the following changes have occurred:

• The Upper Storage Pool is +23 1 and the cavity gate has been closed to prepare for draining the upper cavity.

• Reactor coolant temperature is 105ºF.

• Decay heat is Medium

• RHR A was started in Shutdown Cooling; RHR B was secured and is available for shutdown cooling

• All fuel handling activities in Containment and Fuel Building have been completed

• ADHR is not available due to signature testing of the suction valves

• LPCS is now Operable following STP run.

• All other equipment status is unchanged from last shift Initiating Cue:

The oncoming Admin. CRS has been called for a Fitness for Duty random test prior to completing the Plant Safety Index. The OSM has directed you to finish the Plant Safety Level for the on-coming Shift Brief. Complete the SOPP Status Sheet to show the Plant Safety Level per OSP-0037, Shutdown Operations Protection Plan.

RJPM-NRC12-A6

• Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A6 PERFORMANCE STEP STANDARD S/U COMMENTS Using Attachment 1 determine the The candidate using Attachment 1 determined Safety level for Shutdown Cooling that Med Decay Heat/ Not Flooded Up With only

• 1.

Function Color State RHR A&B available, ADHR is not available places the plant in YELLOW (TS)

Using Attachment 2 determine the The candidate using Attachment 2 determined Safety level for Inventory Control that RHR A&B and LPCS available therefore 3

• 2.

Function Color State ECCS trains are available and >23 above the flange status is still GREEN Using Attachment 6 determine the Candidate recognized that previous shift the color Safety level for Fuel Building was Green indicating that 2 HVF Trains were

• 3.

Ventilation Function Color State available, with no fuel movement in progress the color remains GREEN Using the Color State from the Key The candidate selected the most conservative

• 4. Shutdown Function Areas Determine Overall Status color of YELLOW in accordance the Overall Risk with step 3.12 of OSP-0037.

Terminating Cue: OSP-0037, Shutdown Operations Protection Plan (SOPP) status sheet completed.

RJPM-NRC12-A6

• Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A6 ANSWER KEY SHUTDOWN OPERATIONS PROTECTION PLAN (SOPP)

Status Sheet Shutdown EOOS Safety Index 9.4 - GREEN

1. Shutdown Cooling YELLOW

2. Inventory Control GREEN

3. AC Power GREEN

4. Fuel Pool Cooling GREEN

5. Containment Control GREEN

6. Fuel Building GREEN

7. Reactivity Control GREEN

8. Fire GREEN OVERALL RISK YELLOW RJPM-NRC12-A6 Page 7 of 10

RJPM-NRC12-A6 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A6 Page 8 of 10

RJPM-NRC12-A6 JPM Task Conditions/Cues (Operator Copy)

RBS is at day 25 of a Refueling Outage. The last time the SOPP Status Initial Conditions:

Sheet was completed it indicated that all Safety Levels were GREEN.

Since that time the following changes have occurred:

• The Upper Storage Pool is +23 1 and the cavity gate has been closed to prepare for draining the upper cavity.

• Reactor coolant temperature is 105ºF.

• Decay heat is Medium

• RHR A was started in Shutdown Cooling; RHR B was secured and is available for shutdown cooling

• All fuel handling activities in Containment and Fuel Building have been completed

• ADHR is not available due to signature testing of the suction valves

• LPCS is now Operable following STP run.

• All other equipment status is unchanged from last shift The individual who was completing the Plant Safety Index Initiating Cues:

determination has been called for a Fitness for Duty random test prior to completing the Plant Safety Index. The OSM has directed you to finish the Plant Safety Level for the on-coming Shift Brief. Complete the SOPP Status Sheet to show the Plant Safety Level per OSP-0037, Shutdown Operations Protection Plan.

RJPM-NRC12-A6 Page 9 of 10

RJPM-NRC12-A6 JPM Task Conditions/Cues (Operator Copy)

SHUTDOWN OPERATIONS PROTECTION PLAN (SOPP)

Status Sheet Shutdown EOOS Safety Index 9.4 - GREEN

1. Shutdown Cooling ____________

2. Inventory Control ____________

3. AC Power GREEN

4. Fuel Pool Cooling GREEN

5. Containment Control GREEN

6. Fuel Building _________

7. Reactivity Control GREEN

8. Fire GREEN OVERALL RISK ____________

RJPM-NRC12-A6 Page 10 of 10

Number: *RJPM-NRC12-A7 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

REVIEW AND APPROVE A COMPLETED SURVEILLANCE TEST PROCEDURE REASON FOR REVISION:

2012 NRC Exam JPM - SRO A7 PREPARE / REVIEW:

Angie Orgeron 1538 7/9/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A7 TASK DESCRIPTION: Review a completed performance of a monthly operating surveillance and either approve or document reasons for not approving.

TASK

REFERENCE:

300132003002 K/A REFERENCE & RATING: 2.2.12 4.1 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

RJPM-NRC12-A7 Page 2 of 9

RJPM-NRC12-A7 SIMULATOR SETUP SHEET Task

Description:

Review a completed performance of a monthly operating surveillance and document reasons for not approving.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A7 Page 3 of 9

RJPM-NRC12-A7 DATA SHEET References for Development: STP-000-0201, Rev 308 ADM-0015, Rev 36 Required Materials: STP-000-0201, Rev 308 Marked up as completed performance.

Required Plant Condition: N/A Task Stardard: The candidate has reviewed the complete STP and has NOT signed for approval. Candidate has documented 5 issues leading to disapproval.

Applicable Objectives: RLP-HLO-0221 Objective 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A7 Page 4 of 9

RJPM-NRC12-A7 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1 at 100%. The plant has been online for 256 days. The Monthly Operating Logs, STP-000-0201 was scheduled and has been completed on your shift.

Initiating Cue:

As the CRS, review the completed performance of STP-000-0201 and either approve the performance or document the reason(s) for disapproval. Document your answer on the Operator Cue sheet.

RJPM-NRC12-A7

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A7 PERFORMANCE STEP STANDARD S/U COMMENTS Review completed performance of The candidate reviewed the procedure and did STP-000-0102 NOT approve the performance.

Candidate documented the following reasons for disapproval.

• Pg 12 of 35 - (1-3 Step 9) CMS-TI40D channel check is Unsatisfactory. This temperature is not consistent with other points monitoring the same parameter. In addition, this temperature is above Tech Spec and EOP entry conditions.

• Pg 15 of 35 - (Section 1-4 Step 17)

• 1.

Concurrent Verification has not been performed.

• Pg 18 of 35 - (Section 1-5 Step 1) RMS-RE125 not circled indicating surveillance was not performed.

• Pg 19 of 35 - (Section 1-6 Step 2) SVV-ES3B recorded reading does not meet the acceptance criteria.

• Pg 21 of 35 - (Section 1-7 Step 25) CCP-PNL102 PANEL DOOR was not initialed as being LOCKED CLOSED.

Terminating Cue: Procedure has been reviewed, disapproved and reasons documented on Cue Sheet.

RJPM-NRC12-A7

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A7 ANSWER KEY (Check appropriate box)

APPROVED DISAPPROVED ;

Document reason(s) for disapproval below if necessary.

• Pg 12 of 35 - (1-3 Step 9) CMS-TI40D channel check is Unsatisfactory. This temperature is not consistent with other points monitoring the same parameter. In addition, this temperature is above Tech Spec and EOP entry conditions.

• Pg 15 of 35 - (Section 1-4 Step 17) Concurrent Verification has not been performed.

• Pg 18 of 35 - (Section 1-5 Step 1) RMS-RE125 not circled indicating surveillance was not performed.

• Pg 19 of 35 - (Section 1-6 Step 2) SVV-ES3B recorded reading does not meet the acceptance criteria.

• Pg 21 of 35 - (Section 1-7 Step 25) CCP-PNL102 PANEL DOOR was not initialed as being LOCKED CLOSED.

RJPM-NRC12-A7 Page 7 of 9

RJPM-NRC12-A7 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A7 Page 8 of 9

RJPM-NRC12-A7 JPM Task Conditions/Cues (Operator Copy)

The plant is operating in Mode 1 at 100%. The plant has been online for Initial Conditions:

256 days. The Monthly Operating Logs, STP-000-0201 was scheduled and has been completed on your shift.

Initiating Cues: As the CRS, review the completed performance of STP-000-0201 and either approve the performance or document the reason(s) for disapproval. Document your answer on the Operator Cue sheet..

(Circle One)

APPROVED DISAPPROVED Document reason(s) for disapproval below if necessary.

RJPM-NRC12-A7 Page 9 of 9

Number: *RJPM-NRC12-A8 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

CALCULATE MAXIMUM PERMISSIBLE STAY TIME REASON FOR REVISION:

2012 NRC Exam JPM - SRO A8 PREPARE / REVIEW:

Angie Orgeron 1538 7/9/2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A8 TASK DESCRIPTION: Review radiological condition data, cumulative dose and time to perform several tasks and calculate the maximum permissible stay time to complete a specific task.

TASK

REFERENCE:

300241004002 301023005003 K/A REFERENCE & RATING: 2.3.7 3.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A8 Page 2 of 9

RJPM-NRC12-A8 SIMULATOR SETUP SHEET Task

Description:

Review radiological condition data, cumulative dose and time to perform several tasks and calculate the maximum permissible stay time to complete a specific task.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC12-A8 Page 3 of 9

RJPM-NRC12-A8 DATA SHEET References for Development: EN-RP-201, Rev 3 Required Materials: EN-RP-201, Rev 3 Required Plant Condition: N/A Task Stardard: The candidate has reviewed the radiological data, cumulative dose and associated tasks and determined that the maximum permissible stay time for task #3 is 13-15 minutes.

Applicable Objectives: Admin Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A8 Page 4 of 9

RJPM-NRC12-A8 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The reactor has scrammed due to a leak in the RWCU pump room which failed to completely isolate. Although automatic isolation occurred, leakage pass isolation valve seats continue to cause elevated temperatures and radiation levels. Efforts are underway to enter affected areas and attempt to manually seat various valves. Only one qualified operator is available to perform ALL the affected tasks. This operators year to date dose is 780 mRem.

Initiating Cue:

As the CRS, review the radiological information for the specific tasks and the operators year to date dose. Assuming the same operator completes all 3 tasks, determine the maximum permissible stay time to complete Task #3 without exceeding the routine annual administration dose limit.

RJPM-NRC12-A8

• Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A8 PERFORMANCE STEP STANDARD S/U COMMENTS Review the radiological information Candidate determined that the operator may for the specific tasks and the receive 1220 mR to complete all tasks and not

1. operators year to date dose. exceed site administrative limits. (2000mR-780mR=1220mR)

Determine dose received from Task #1 Candidate determined that the dose received

2. from Task #1 is 500 mRem Determine dose received from Task #2 Candidate determined that the dose received from Task #2 is 500 mRem 3.

Determine maximum permissible stay Candidate determined that the maximum

• 4. time during performance of Task #3. permissible stay time for Task #3 is 14.67 minutes (Acceptable range is 13-15 minutes).

Terminating Cue: Maximum permissible stay time has been determined and recorded on the cue sheet. .

RJPM-NRC12-A8

• Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A8 ANSWER KEY Maximum Permissible Stay Time in the RWCU Pump Room 13-15 minutes RJPM-NRC12-A8 Page 7 of 9

RJPM-NRC12-A8 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A8 Page 8 of 9

RJPM-NRC12-A8 JPM Task Conditions/Cues (Operator Copy)

The reactor has scrammed due to a leak in the RWCU pump room which Initial Conditions:

failed to completely isolate. Although automatic isolation occurred, leakage pass isolation valve seats continue to cause elevated temperatures and radiation levels. Efforts are underway to enter affected areas and attempt to manually seat various valves. Only one qualified operator is available to perform ALL the affected tasks. This operators year to date dose is 780 mRem.

Initiating Cues: As the CRS, review the radiological information for the specific tasks and the operators year to date dose. Assuming the same operator completes all 3 tasks, determine the maximum permissible stay time to complete Task #3 without exceeding the routine annual administration dose limit.

Task Task Description Time to Dose Rate Number complete task 1 Drywell entry to close G33-MOVF001 10 mins 3 Rem 2 Steam tunnel entry to close G33-MOVF004 15 mins 2 Rem 3 RWCU Pump Room entry to verify status of leak and close  ? 900 mRem manual valves if necessary Maximum Permissible Stay Time in the RWCU Pump Room RJPM-NRC12-A8 Page 9 of 9

Number: RJPM-NRC12-A9 RIVER Revision: 0 BEND STATION Page 1 of 11 TIME CRITICAL JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

CLASSIFY AN EMERGENCY REASON FOR REVISION:

2012 NRC EXAM JPM - SRO A9 PREPARE / REVIEW:

Angie Orgeron 1538 7-9-2012 Preparer KCN Date David Bergstrom 0257 8/6/2012 Technical Review (SME) KCN Date Tim Schenk 0717 7/24/2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-A9 TASK DESCRIPTION: CLASSIFY AN EMERGENCY TASK

REFERENCE:

301001005003 K/A REFERENCE & RATING: 2.4.41 4.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: 15 min JOB LEVEL: SRO TIME CRITICAL: Yes EIP CLASSIFICATION Yes REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-A9 Page 2 of 11

RJPM-NRC12-A9 SIMULATOR SETUP SHEET Task

Description:

Classify an emergency Required Power: N/A IC No.: N/A Notes: This Administrative JPM will be conducted in the classroom.

RJPM-NRC12-A9 Page 3 of 11

RJPM-NRC12-A9 DATA SHEET References for Development: EIP-2-001, Rev 23, CLASSIFICATION OF EMERGENCIES Required Materials: EIP-2-001, Rev 23, CLASSIFICATION OF EMERGENCIES Required Plant Condition: N/A Applicable Objectives: RCBT-EP-SRORMED Obj. 16 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-A9 Page 4 of 11

RJPM-NRC12-A9 If In-Plant or In the Control Room:

Caution the Operator is NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

While operating in Mode 1 a failure of the feedwater level control system resulted in reactor water level lowering to below the scram setpoint. The reactor did NOT automatically scram. The At the Controls operator placed the Reactor Mode Switch in the SHUTDOWN position and all control rods fully inserted.

The reactor is shutdown. Reactor water level and pressure are stable. Reactor water level was recovered prior to reaching any other actuation setpoint.

Meterological data indicates wind speed at 6 mph from 145 degrees. No release is in progress.

Initiating Cue:

You are the Operations Shift Manager, classify the event, AND fill out the applicable notification short form.

This is a time critical JPM.

RJPM-NRC12-A9

• Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A9 PERFORMANCE STEP STANDARD S/U COMMENTS Consult EIP-2-001 Classification of Candidate classified the event as an ALERT

• 1.

Emergencies for this event (SA--3).

Complete the notification short form Candidate completed the Short Notification 2.

Message Form for an ALERT.

Terminating Cue: Emergency Plan is applied to classify the event as an ALERT and Alert Short Form completed in accordance with the answer key.

RJPM-NRC12-A9

• Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A9 ANSWER KEY The ALERT form is the 3rd of the 4 forms provided.

Notification of Alert Time/Date: Current Message: 1 This is River Bend Station An Alert was declared at Current on Current date for time SA-3 Reactor Protection System failed to complete and automatic scram once an RPS setpoint was exceeded and manual scram was successful.

Wind from 145 Deg. At 6 MPH 9 No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by: Candidate name

Title:

Emergency Director /

Recovery Manager RJPM-NRC12-A9

• Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-A9 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-A9 Page 8 of 11

RJPM-NRC12-A9 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: While operating in Mode 1 a failure of the feedwater level control system resulted in reactor water level lowering to below the scram setpoint. The reactor did NOT automatically scram. The At the Controls operator placed the Reactor Mode Switch in the SHUTDOWN position and all control rods fully inserted.

The reactor is shutdown. Reactor water level and pressure are stable. Reactor water level was recovered prior to reaching any other actuation setpoint.

Meterological data indicates wind speed at 6 mph from 145 degrees. No release is in progress.

Initiating Cues: You are the Operations Shift Manager, classify the event, AND fill out the applicable notification short form.

This is a time critical JPM.

RJPM-NRC12-A9 Page 9 of 11

RJPM-NRC12-A9 Notification of General Emergency Time/Date: Message:

This is River Bend Station A General Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release PAR Reference Scenario No.:

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

Notification of Site Area Emergency Time/Date: Message:

This is River Bend Station A Site Area Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC12-A9 Page 10 of 11

RJPM-NRC12-A9 Notification of Alert Time/Date: Message:

This is River Bend Station An Alert was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

Notification of Unusual Event Time/Date: Message:

This is River Bend Station A Notification of Unusual Event was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC12-A9 Page 11 of 11

Number: *RJPM-NRC12-C1 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

RESPOND TO A LOSS OF CONTROL ROOM ANNUNCIATORS REASON FOR REVISION:

2012 NRC Exam JPM C1 PREPARE / REVIEW:

Angie Orgeron 1538 8-22-2012 Preparer KCN Date David Bergstrom 0257 8/23/2012 Technical Review (SME) KCN Date Tim Schenk 0717 8/22/2012 Operations Representative KCN Date John Fralick 0788 8/23/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-C1 TASK DESCRIPTION: RESPOND TO A LOSS OF ALL CONTROL ROOM ANNUNCIATORS TASK

REFERENCE:

400083004001 K/A REFERENCE & RATING: 263000 K2.01 3.1/3.4 263000 K3.03 3.4/3.8 263000 A4.01 3.3/3.5 TESTING METHOD: Simulate Actual Performance X Performance Control Room X Simulator In-Plant COMPLETION TIME: 15 MINUTES.

MAX TIME: 30 MINUTES JOB LEVEL: RO/SRO TIME CRITICAL: NO EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 6 RJPM-NRC12-C1 Page 2 of 10

RJPM-NRC12-C1 SIMULATOR SETUP SHEET Task

Description:

NA Required Power: NA IC No.: NA Notes: NONE: This JPM is performed in the Control Room and Plant.

RJPM-NRC12-C1 Page 3 of 10

RJPM-NRC12-C1 DATA SHEET References for Development: AOP-0055 Rev 017 Required Materials: AOP-0055 Rev 017 Section 5.3 Required Plant Condition: ANY Task Standard Cause of annunciator loss has been identified and corrected.

Applicable Objectives: RLP-HLO-547 Objective 4 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-C1 Page 4 of 10

RJPM-NRC12-C1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

While operating at 100 percent power a total loss of control room annunciators occurred. AOP-0055, LOSS OF CONTROL ROOM ANNUNCIATORS has been entered. The Operations Shift Manager is reviewing EIP Emergency Action Levels for applicability. All available operations personnel are stationed to monitor indications for changing plant parameters. Maintenance personnel have been notified of the loss of annunciators.

Initiating Cue:

The CRS has directed you to perform Section 5.3 of AOP-0055 to determine the cause for and correct the loss of annunciator condition.

RJPM-NRC12-C1

• Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C1 PERFORMANCE STEP STANDARD S/U COMMENTS Dispatch an operator to H13-P630 and Candidate located H13-P630 and observed the EVALUATOR CUE: When the H13-P850 to ascertain the status of the status of the 24 VDC and 125 VDC power candidate has located the power supplies as indicated by the 24 available lights. power available lights in H13-VDC and 125 VDC power available P630, notify the candidate that lights. all lights are extinguished.

Note: There are a total of 4 sets of Candidate located H13-P850 and observed the power supply lights in H13-P630.

status of the 24 VDC and 125 VDC power Three power supplies are behind available lights. the right side door, and one behind

1. the middle door.

5.3 EVALUATOR CUE: When the candidate has located the power available lights in H13-P850, notify the candidate that all lights are extinguished.

Note: There are a total of 5 sets of power supply lights in H13-P850.

Two power supplies are behind the left side door and one behind each of the other 3 doors.

RJPM-NRC12-C1

• Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C1 PERFORMANCE STEP STANDARD S/U COMMENTS IF all power supplies in either H13- EVALUATOR CUE: When the P630 OR H13-P850 are observed to candidate has located BYS-be deenergized, THEN dispatch an PNL02B2 BKR 2 notify the operator to Main Control Room north candidate that the breaker is in

2. end to check the following breakers: the ON position.

Candidate located, identified and verified BYS-5.3.1

• For H13-P630, BYS-PNL02B2 PNL02B2 BKR 2 is in the ON position.

BKR 2 EVALUATOR CUE: When the Candidate located, identified and verified BYS- candidate has located BYS-

• For H13-P850, BYS-PNL02B2 PNL02B2 BKR 17 is in the ON position. PNL02B2 BKR 17 notify the BKR 17 candidate that the breaker is in the ON position.

IF all power supplies in both H13- Candidate located, identified and verified the EVALUATOR CUE: When the P630 AND H13-P850 are observed to status of BYS-SWG01B BKR 528 candidate has located BYS-3.

be deenergized, THEN dispatch an SWG01B BKR 528 notify the 5.3.2 operator to Normal Switchgear candidate the breaker is Building 98 ft el. to check BYS- OPEN.

SWG01B BKR 528.

IF any of the following breakers are Candidate located, identified and simulated EVALUATOR CUE: After found to be open, THEN close the closing BYS-SWG01B BKR 528 by simulating candidate has simulated applicable breakers: movement of the breaker handle downward and closing the BWS-SWG01B

• 4. then back up to close the breaker. BKR 528, notify the candidate BYS-PNL02B2 BKR 2 that the breaker indication 5.3.3 indicates the breaker is BYS-PNL02B2 BKR 17 CLOSED.

BYS-SWG01B BKR 528 RJPM-NRC12-C1

• Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C1 PERFORMANCE STEP STANDARD S/U COMMENTS IF a breaker was closed in Step 5.3.3 Candidate took no further action. No action required by this step AND the breaker trips open, THEN due to the breaker remaining NA

5. contact Electrical Maintenance for closed in the previous step.

assistance before attempting another 5.3.4 closure.

Terminating Cue: BYS-SWG01B has been closed (simulated) restoring power to control room annunciators.

RJPM-NRC12-C1

• Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-C1 Page 9 of 10

RJPM-NRC12-C1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: While operating at 100 percent power a total loss of control room annunciators occurred. AOP-0055, LOSS OF CONTROL ROOM ANNUNCIATORS has been entered. The Operations Shift Manager is reviewing EIP Emergency Action Levels for applicability. All available operations personnel are stationed to monitor indications for changing plant parameters. Maintenance personnel have been notified of the loss of annunciators.

Initiating Cues: The CRS has directed you to perform Section 5.3 of AOP-0055 to determine the cause for and correct the loss of annunciator condition.

RJPM-NRC12-C1 Page 10 of 10

Number: *RJPM-NRC12-C2 RIVER Revision: 00 BEND STATION Page 1 of 15 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

PERFORM AVERAGE POWER RANGE MONITOR SETDOWN CHANNEL FUNCTIONAL TEST FOR APRM B REASON FOR REVISION:

2012 NRC Exam JPM - SRO/RO C2 PREPARE / REVIEW:

Angie Orgeron 1538 6-25-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-C2 TASK DESCRIPTION: Perform the APRM Weekly Setdown Channel Functional Test FOR APRM B TASK

REFERENCE:

215001002001 K/A REFERENCE & RATING: 215005 A4.03 3.2/3.2 215005 A 4.05 3.4/3.4 215005 A 4.06 3.6/3.8 TESTING METHOD: Simulate Actual Performance X Performance Control Room X Simulator In-Plant COMPLETION TIME: 20 minutes MAX TIME: 40 minutes JOB LEVEL: SRO/RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 7 RJPM-NRC12-C2 Page 2 of 15

RJPM-NRC12-C2 SIMULATOR SETUP SHEET Task

Description:

N/A Required Power: N/A IC No.: N/A Notes: None. This JPM is simulated in the Control Room.

RJPM-NRC12-C2 Page 3 of 15

RJPM-NRC12-C2 DATA SHEET References for Development: STP-505-4517 Rev 10 Required Materials: STP-505-4517 Rev 10 Required Plant Condition: Any Task Standard Candidate has simulated performance of STP-505-4517 for APRM B in accordance with Section 7.13 Applicable Objectives: RLP-STM-0503 Objectives 23, 24, 26, 27 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-C2 Page 4 of 15

RJPM-NRC12-C2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

The plant is in Mode 1, operating at 100% power. STP-505-4517, RPS/CONTROL ROD BLOCK-APRM SETDOWN CHANNEL FUNCTION TEST (C51-K505A THROUGH C51-K605H) was completed last shift for all APRM except APRM B due to other maintenance on that APRM. APRM B maintenance has now been completed.

Initiating Cue:

The CRS has directed you to perform Section 7.13-7.14 for APRM B ONLY of the weekly surveillance STP-505-4517 RPS/CONTROL ROD BLOCK-APRM SETDOWN CHANNEL FUNCTION TEST (C51-K505A THROUGH C51-K605H).

RJPM-NRC12-C2

• Denotes Critical Step Page 5 of 15

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C2 PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: No action required. This is a procedure note.

All switches, status lights, test NOTE connections, and adjustments are to be NA made at H13-P670, APRM B unless otherwise noted Channel Functional Test for APRM B NA No action performed in this 7.13 step.

Notify NCO, commencing surveillance Candidate notified the NCO of commencement of EVALUATOR CUE: As

____1. APRM B testing.

testing of APRM B NCO, acknowledge report of 7.13.1 commencement of APRM B testing.

At H13-P680, place APRM B in Candidate located/identified the joystick on EVALUATOR CUE:

BYPASS H13-P680 and simulated placing it in the APRM

• ___2. B position. If requested, notify

____ candidate that the BYPASS 7.13.2 light below the full core display for APRM B is illuminated.

During Mode 1 operation, experience No action required. This is a shows that usually, only APRM C and G procedure note.

NOTE NA will bring in an annunciator, SRM Upscale Alarm or Inop RJPM-NRC12-C2

• Denotes Critical Step Page 6 of 15

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C2 Inform the NCO that performance of Candidate notified the NCO that the annunciators EVALUATOR CUE: As NCO Step 7.13.6 enables IRM Annunciator listed in the Performance Step may alarm. acknowledge report of potential circuitry, therefore if conditions do exist, annunciators.

the following Annunciators will alarm:

____3.

• Annunciator, P680-06A-A10, IRM UPSCALE TRIP OR INOP RPS 7.13.3 CHAN B

• Annunciator, P680-06A-C10, IRM UPSCALE Place MODE Switch to PWR FLOW Candidate located/identified the MODE Switch EVALUATOR CUE: After TEST and simulated placing it in the PWR FLOW candidate located/identified and

• ____4. TEST position. simulated placing the Mode

____ Switch in the PWR FLOW 7.13.4 TEST position, notify him that the switch is in the PWR FLOW TEST position.

Verify METER FUNCTION Switch is in Candidate located/identified the METER EVALUATOR CUE: After AVERAGE FUNCTION Switch and verified it in the candidate located/identified the

____5.

AVERAGE position. METER FUNCTION switch, notify the candidate that the 7.13.5 METER FUNCTION switch is in the AVERAGE position.

RJPM-NRC12-C2

• Denotes Critical Step Page 7 of 15

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C2 IF the Bypass Pushbutton is depressed, No action required. This is a the APRM will come out of bypass, and procedure caution.

may cause a Half Scram CAUTION NA Robust Barriers shall be utilized to prevent depressing the Bypass Pushbutton

• ____6. Depress and hold the SETDOWN TEST Candidate located/identified the SETDOWN Pushbutton TEST pushbutton, simulated depressing and ____

7.13.6 simulated maintaining the pushbutton depressed.

Adjust POWER Control for an indication Candidate has located/identified the POWER EVALUATOR CUE: After the of 8% power on the APRM Front Panel Control and simulated adjusting to obtain a candidate has simulated

• ____7.

Meter reading of 8% power on the APRM Front Panel adjustment of the POWER Meter Control, notify him that the 7.13.7 APRM B Front Panel Meter indicates 8%.

____8. Momentarily press the Trip Reset Candidate has located/identified the Trip Reset Pushbutton pushbutton and simulated momentarily ____

7.13.8 depressing the button.

Verify Status Light UPSCALE ALARM Candidate has located/identified the UPSCALE EVALUATOR CUE: After

____9.

is OFF ALARM and verified it is OFF. candidate has located the UPSCALE ALARM light, notify 7.13.9 him that the light is OFF.

NOTE: No action required. This is a NOTE NA procedure note.

Expected Trip Value = 12%

Adjust Power Control until Status Light Candidate has located/identified the POWER EVALUATOR CUE: After the

• ___10. UPSCALE ALARM, just comes on Control and simulated adjusting until the candidates begins the simulated UPSCALE ALARM light comes on and then ____ adjustment, notify the candidate 7.13.10 stops the simulated adjustment. that the UPSCALE ALARM light is ON.

RJPM-NRC12-C2

• Denotes Critical Step Page 8 of 15

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C2 NOTE: No action required. This is a procedure note.

NOTE Check that the alarm came in due to NA Setdown limits being in effect Check UPSCALE ALARM came on Candidate has located/identified the APRM Front EVALUATOR CUE: After the

• ___11.

before 15% on the Front Panel Meter Panel Meter and verified that the UPSCALE candidate locates the APRM ALARM light illuminated before 15%. Front Panel Meter, notify him 7.13.11 that the meter indicates 12%

Verify Status Light UPSCALE Candidate has located/identified the UPSCALE EVALUATOR CUE: After the

____12.

NEUTRON is OFF NEUTRON light and verified it is OFF. candidate locates the UPSCALE NEUTRON LIGHT notify him 7.13.12 that the light is OFF.

NOTE: No action required. This is a NOTE NA procedure note.

Expected Trip Value = 15%.

Raise Power Control until Status Light Candidate has located/identified the POWER EVALUATOR CUE: After the

• ___13. UPSCALE NEUTRON, just comes on Control and simulated adjusting until the candidate begins the simulated UPSCALE NEUTRON light comes on and then ____ adjustment, notify the candidate 7.13.13 stops the simulated adjustment. that the UPSCALE NEUTRON light is ON.

Check UPSCALE NEUTRON came on Candidate has located/identified the APRM Front EVALUATOR CUE: After the

• ___14.

before 20% on the Front Panel Meter Panel Meter and verified that the UPSCALE candidate locates the APRM NEUTRON light illuminated before 20%. Front Panel Meter, notify him 7.13.14 that the meter indicates 15%

Adjust Power Control for an indication Candidate has located/identified the POWER EVALUATOR CUE: After the of 8% on the Front Panel Meter Control and simulated adjusting until the Front candidate begins simulated

____15.

Panel Meter indicates 8%. adjustment of the Power Control, notify the candidate 7.13.15 that the APRM Front Panel Meter indicates 8%.

____16. Release the SETDOWN TEST Candidate has simulated release of the Pushbutton SETDOWN TEST pushbutton. ____

7.13.16 RJPM-NRC12-C2

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RJPM-NRC12-C2

• ___17. Momentarily press the Trip Reset Candidate simulated momentary depressing of the Pushbutton Trip Reset pushbutton. ____

7.13.17 Check Status Light UPSCALE ALARM Candidate has verified the UPSCALE ALARM EVALUATOR CUE: After

____18.

is OFF light is OFF. candidate locates/identifies the UPSCALE ALARM light, notify 7.13.18 him that the light is OFF.

Check Status Light UPSCALE Candidate has verified the UPSCALE EVALUATOR CUE: After

____19.

NEUTRON is OFF NEUTRON light is OFF. candidate locates/identifies the UPSCALE NEUTRON light, 7.13.19 notify him that the light is OFF.

NOTE: No action required. This is a procedure note.

All switches, status lights, test NOTE connections, and adjustments are to be NA made at H13-P670, APRM B unless otherwise noted Restoration of APRM B No action performed in this step.

7.14 NA Actions follow below.

Place MODE Switch to OPERATE Candidate located/identified and simulated EVALUATOR CUE: After

• ___20.

placing the switch to the OPERATE position. candidate locates/identifies the MODE switch, notify him that it 7.14.1 is in the OPERATE position.

____21. Momentarily press the Trip Reset Candidate located/identified and simulated Pushbutton momentarily depressing the Trip Reset ____

7.14.2 Pushbutton.

Verify the following: No action performed in this step.

NA 7.14.3 Actions follow below.

Status Light UPSCALE ALARM, is off Candidate located/identified and verified the EVALUATOR CUE: After the

____22.

UPSCALE ALARM light is off. candidate located/identified the UPSCALE ALARM light, notify 7.14.3.1 him that the light is OFF.

RJPM-NRC12-C2

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-C2 Status Light UPSCALE NEUTRON, is Candidate located/identified and verified the EVALUATOR CUE: After the

____23.

off UPSCALE NEUTRON light is off. candidate located/identified the UPSCALE NEUTRON light, 7.14.3.2 notify him that the light is OFF.

Status Light UPSCL THERM TRIP, is Candidate located/identified and verified the EVALUATOR CUE: After the

____24. off UPSCALE THERMAL TRIP light is off. candidate located/identified the

____ UPSCALE THERMAL TRIP 7.14.3.3 light, notify him that the light is OFF.

Status Light INOP, is off Candidate located/identified and verified the EVALUATOR CUE: After the

____25.

INOP light is off. candidate located/identified the INOP light, notify him that the 7.14.3.4 light is OFF.

Verify APRM B MODE Switch to Candidate located/identified and verified the EVALUATOR CUE: If

____26.

OPERATE APRM B MODE Switch is in OPERATE. requested by the candidate, perform the Independent 7.14.4 Verification steps at 7.14.4 At H13-P680, place C51B-S6, Candidate located/identified the joystick on H13- EVAULATOR CUE:If NEUTRON MONITOR BYPASS Switch P680 and simulated removing it from the APRM requested as CRS, notify the to the proper position for current plant B position and returning it to the center position. candidate the proper position conditions for APRM B for current plant

• ___27. conditions is Not Bypassed 7.14.5 If requested, after simulation of removing APRM B from bypass, notify candidate that Bypass light for APRM B below the full core display is OFF.

Check that no RPS Half-Scrams have Candidate verified no RPS Half Scram occurred EVALUATOR CUE: Notify

____28. occurred by verifying the RPS status lights on H13-P680 candidate that no RPS Half are illuminated OR by verifying the RPS status ____ Scrams occurred.

7.14.6 lights on H13-P691, P692, P693 and P694 are illuminated.

RJPM-NRC12-C2

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RJPM-NRC12-C2

____29. Check that no single rod scrams have Candidate verified no single rod scrams occurred. EVALUATOR CUE: Notify occurred ____ candidate that no single rod 7.14.7 scrams occurred.

Check the following No action performed in this step.

NA 7.14.8 Actions follow below.

Status Light on H13-P680, BYPASS, is Candidate located/identified and verified that the EVALUATOR CUE: After

____30. off. Bypass lights for APRM B below the full core candidate locates/identifies the display is OFF. ____ Bypass light for APRM B below 7.14.8.1 the full core display, notify him that the light is OFF.

Status Light on H13-P670, BYPASS for Candidate located/identified and verified that the EVALUATOR CUE: After

____31. APRM B, is off Bypass lights for APRM B at H13-P670 is OFF. candidate locates/identifies the

____ Bypass light for APRM B at 7.14.8.2 H13-P670, notify him that the light is OFF.

Check the APRM is functioning before No action required. This is a NOTE NA procedure note.

going to another.

Perform the following No action performed in this step.

7.14.9 NA Actions follow below.

Verify METER FUNCTION Switch in Candidate located/identified the METER EVALUATOR CUE: After

____32. AVERAGE FUNCTION switch and verified it was in the candidate locates/identifies the AVERAGE position. ____ METER FUNCTION switch 7.14.9.1 notify him that the switch is in the AVERAGE position.

Record instrument readings Candidate recorded the readings for APRM B & EVALUATOR CUE: When the F. candidate locates the Front

____33.

Panel Meters for APRM B & F, notify him that the readings are:

7.14.9.2 APRM B 100%

APRM F 100%

RJPM-NRC12-C2

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RJPM-NRC12-C2

____34. Check that instrument readings are Candidate recognized that the readings were within 12%. IF greater than 12%, THEN within 12% and took no further action. ____

7.14.9.3 notify OSM/CRS Notify NCO that surveillance testing of Candidate notified the NCO that surveillance EVALUATOR CUE: As NCO, APRM B is complete testing of APRM B was completed. acknowledge report of the

____35. completion of APRM B testing.

Note: Candidate may state that they will return ____

7.14.10 the Meter Function switch in accordance with OP AID 2001-P-005. This is not required for satisfactory performance of this JPM.

Terminating Cue: Simulated performance of STP-505-4517 Section 7.13 for APRM B has been completed and APRM B has been restored to operational per section 7.14.

RJPM-NRC12-C2

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RJPM-NRC12-C2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-C2 Page 14 of 15

RJPM-NRC12-C2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is in Mode 1, operating at 100% power. STP-505-4517, RPS/CONTROL ROD BLOCK-APRM SETDOWN CHANNEL FUNCTION TEST (C51-K505A THROUGH C51-K605H) was completed last shift for all APRM except APRM B due to other maintenance on that APRM. APRM B maintenance has now been completed.

Initiating Cues: The CRS has directed you to perform Section 7.13-7.14 for APRM B ONLY of the weekly surveillance STP-505-4517 RPS/CONTROL ROD BLOCK-APRM SETDOWN CHANNEL FUNCTION TEST (C51-K505A THROUGH C51-K605H) .

RJPM-NRC12-C2 Page 15 of 15

Number: *RJPM-NRC12-P1 RIVER Revision: 00 BEND STATION Page 1 of 10 TIME CRITICAL JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

TRANSFER RCIC STEAM SUPPLY ISOLATION VALVE TO ALTERNATE POWER REASON FOR REVISION:

2012 NRC Exam JPM P1 PREPARE / REVIEW:

Angie Orgeron 1538 6-21-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-P1 TASK DESCRIPTION: TRANSFER RCIC STEAM SUPPLY ISOLATION VALVE TO ALTERNATE POWER PER AOP-0031 TASK

REFERENCE:

294001002004 K/A REFERENCE & RATING: 295016 A1.04 3.1/3.2 295016 A1.07 4.2/4.3 295016 A1.09 4.0/4.0 TESTING METHOD: Simulate Actual X

Performance Performance Control Simulator In-Plant x Room COMPLETION TIME: 10 MINUTES.

MAX TIME: 10 MINUTES JOB LEVEL: RO/SRO TIME CRITICAL: YES EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 2 RJPM-NRC12-P1 Page 2 of 10

RJPM-NRC12-P1 SIMULATOR SETUP SHEET Task

Description:

NA Required Power: NA IC No.: NA Notes: NONE: This JPM is performed in the plant.

RJPM-NRC12-P1 Page 3 of 10

RJPM-NRC12-P1 DATA SHEET References for Development: AOP-0031 Rev 315 Required Materials: AOP-0031 Rev 315 Attachment 14 Required Plant Condition: ANY Task Standard E51-MOVF063 is powered by a Division 1 power source in accordance with AOP-0031 Section 5.8.

Applicable Objectives: RLP-OPS-AOP031 Objective 5 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-P1 Page 4 of 10

RJPM-NRC12-P1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

While operating at 100 percent power a fire was discovered in the Main Control Room. Initial actions to extinguish the fire have been unsuccessful. AOP-0031, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM has been entered and Control Room abandonment is in progress.

Initiating Cue:

The CRS has directed you to perform Section 5.8 of AOP-0031, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM, to transfer E51-MOVF063 to Division 1 alternate power.

This is a time critical JPM.

START TIME: ___________

RJPM-NRC12-P1

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P1 PERFORMANCE STEP STANDARD S/U COMMENTS WARNING N/A This is a procedure warning. No action required. These Due to extreme differential pressure, conditions would be present 123 ft el access doors into the Aux during an actual event, but not WARNING Bldg may be a personnel hazard. expect during the examination When operating conditions permit, period. It is acceptable to use the Aux Bldg access should be from the 123 ft el access during this 95 ft el or 67 ft el. examination.

NA 5.8 WHEN directed by the CRS, THEN perform Steps 5.8.1 through 5.8.6 This is a procedure note. No Steps 5.8.1 through 5.8.6, in addition action is required.

to the RCIC lineup steps performed by the ATC operator at the Div I RSS NA panel, are required to be completed NOTE within 10 minutes of scramming the reactor due to a Main Control Room fire. These actions are performed at EHS-MCC2L, west side and EHS-MCC2D, east side of Aux Bldg, 141 el.

Candidate has located/identified EHS-MCC2L

• 1.

Close EHS-MCC2L BKR 6AT, BKR 6AT and simulated placing the breaker ____

E51-SW63 BRKR 1 ALT DIV I PWR handle in the ON position.

5.8.1.

E51-MOVF063 RJPM-NRC12-P1

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RJPM-NRC12-P1 PERFORMANCE STEP STANDARD S/U COMMENTS Candidate has located/identified EHS-MCC2L

• 2. BKR 6AB and simulated placing the breaker Close EHS-MCC2L BKR 6AB, handle in the ON position. ____

5.8.2 E51-SW63 BRKR 2 ALT DIV I PWR E51-MOVF063

• 3.

Candidate has located/identified EHS-MCC2D Open EHS-MCC2D BKR 3C, RCIC BKR 3C and simulated placing the breaker ____

5.8.3 & RHR STEAM SUPPLY VALVE. handle in the OFF position.

• 4. Candidate has located/identified E51-SW63 and On wall to right side of EHS-MCC2D, simulated placing the switch in the CLOSED ____

5.8.4 close E51-SW63, DIV I ALT PWR position.

SUPPLY E51-MOVF063.

Candidate has located/identified 43-1ICSA02 and

• 5. On right side of EHS-MCC2D, place simulated placing the switch in the ALTERNATE ____

43-1ICSA02, CONTROL XFER position.

5.8.5 E51-MOVF063 in ALTERNATE and check the following:

6. EXAMINER CUE:

Candidate has located/identified W2-1ICSA02 W2-1ICSA02, DIV I ALT CONTROL and verified light is illuminated. ____ Once the candidate has located 5.8.5 POWER E51-MOVF063 is W2-1ICSA02, notify him that the

• illuminated. light is ON.

EXAMINER CUE:

7. Candidate has located/identified W1-1ICSA02 W1-1ICSA02 NORMAL CONTROL and verified light is extinguished. ____

POWER E51-MOVF063 is Once the candidate has located 5.8.5 W1-1ICSA02, notify him that the extinguished

• light is OFF.

RJPM-NRC12-P1

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RJPM-NRC12-P1 PERFORMANCE STEP STANDARD S/U COMMENTS EXAMINER CUE:

Candidate notifies the ATC operator that Inform ATC Operator that E51-MOVF063 has been transferred to the Div I ____

8. Role Play: As ATC operator, E51-MOVF063 has been transferred Alternate Power.

to the Div I Alternate Power. The Div accept information regarding 5.8.6 transfer of E51-MOVF063 to I Remote Shutdown Room number is 2903 alternate power.

Terminating Cue: E51-MOVF063 has been transferred to alternate power per AOP-0031 Section 5.8 COMPLETION TIME: __________

RJPM-NRC12-P1

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-P1 Page 9 of 10

RJPM-NRC12-P1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: While operating at 100 percent power a fire was discovered in the Main Control Room. Initial actions to extinguish the fire have been unsuccessful. AOP-0031, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM has been entered and Control Room abandonment is in progress.

Initiating Cues: The CRS has directed you to perform Section 5.8 of AOP-0031, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM, to transfer E51-MOVF063 to Division 1 alternate power.

This is a time critical JPM.

RJPM-NRC12-P1 Page 10 of 10

Number: *RJPM-NRC12-P2 RIVER Revision: 0 BEND STATION Page 1 of 13 ALTERNATE PATH JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

START OF FIRE PROTECTION WATER PUMP REASON FOR REVISION:

2012 NRC Exam JPM - SRO/RO P2 PREPARE / REVIEW:

Angie Orgeron 1538 6-20-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-P2 TASK DESCRIPTION: Start of Fire Protection Water Pump TASK

REFERENCE:

286018001004 K/A REFERENCE & RATING: 286000 K4.05 3.7/3.8 K5.05 3.0/3.1 A2.08 3.2/3.3 A3.01 3.4/3.4 A4.06 3.4/3.4 TESTING METHOD: Simulate Actual Performance X Performance Control Room Simulator In-Plant X COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: Yes ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION: 8 RJPM-NRC12-P2 Page 2 of 13

RJPM-NRC12-P2 SIMULATOR SETUP SHEET Task

Description:

Start of Fire Protection Water Pump Required Power: N/A IC No.: N/A Notes: This JPM task is simulated in the plant.

RJPM-NRC12-P2 Page 3 of 13

RJPM-NRC12-P2 DATA SHEET References for Development: SOP-0037 Rev 32, Fire Protection Water System Operating Procedure Required Materials: SOP-0037, Rev 32 Fire Protection Water System Operating Procedure, Section 4.2.2 through 4.2.3 Required Plant Condition: N/A Task Standard: The A Diesel Driven Fire Pump is running with proper cooling water pressure.

Applicable Objectives: STM-250, Obj# N04, N07 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-P2 Page 4 of 13

RJPM-NRC12-P2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1, at 100% steady state power. FPW-P1B Diesel Fire Pump is tagged out for pump replacement. A fire has occurred in the Auxiliary Boiler/Water Treatment Building. Attempts to start FPW-P1A, Diesel Fire Pump from the Auxiliary Control Room have failed.

The power supply to FPW-P2, MOTOR DRIVEN FIRE PUMP, has been damaged by the fire rendering the pump unavailable.

Initiating Cue:

The CRS has directed you to perform a local manual start of FPW-P1A, Diesel Driven Fire Pump, in accordance with SOP-0037 Fire Protection Water System Operating Procedure, beginning at Section 4.2.2.

RJPM-NRC12-P2

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS No action is required for this step.

At FPW-MST2, MOTOR DRIVEN The Initial Conditions indicated FIRE PUMP 2 CONTROLLER, NA that FPW-P2 was unavailable due 4.2.2.1 depress START pushbutton to start to power supply damage.

FPW-P2, MOTOR DRIVEN FIRE PUMP No action is required. This is a The following pump start method is Procedure Note. In addition, the only to be used in an emergency NA associated step is not required.

NOTE situation. The Initial Conditions indicated that FPW-P2 was unavailable due to power supply damage.

No action is required for this step.

IF Step 4.2.2.1 does not start FPW-P2, The Initial Conditions indicated THEN lift the yellow MANUAL NA that FPW-P2 was unavailable due EMERGENCY START ONLY handle to power supply damage.

4.2.2.2 on FPW-P2, MOTOR DRIVEN FIRE PUMP 2 CONTROLLER, and latch in the raised position No action is required. This is a NOTE Procedure Note.

NOTE MANUAL 1 and MANUAL 2 NA correspond to manual starting with Bank 1 or Bank 2 respectively.

RJPM-NRC12-P2

• Denotes Critical Step Page 6 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS EVALUATOR CUE: After the Place the selector switch on controller Candidate has located/identified the proper

1. manipulation has been FPW-MST1A, DIESEL FIRE PUMP controls, and simulated manipulation of the simulated, notify performer that 1A CONTROLLER in MANUAL 1 or selector switch to either MANUAL 1 or 4.2.2.3 the Auto On light has MANUAL 2. MANUAL 2.

extinguished.

Place the selector switch on controller No action required. FPW-P1B was FPW-MST1B, DIESEL FIRE PUMP NA identified as being tagged out in 4.2.2.4 1B CONTROLLER in MANUAL 1 or the initiating cue.

MANUAL 2 NOTE No action is required. This is a Limit the maximum number of start Procedure Note.

NOTE attempts to six. NA Do not hold the START pushbutton for greater than 30 seconds.

Depress and hold local START Candidate has located/identified the proper EVALUATOR CUE: After the

2. pushbutton for 15 seconds or until controls, and simulated depressing and holding performer has simulated engine starts for the following: the START pushbutton for 15 seconds depressing the START 4.2.2.5 pushbutton, notify the

• FPW-P1A, DIESEL DRIVEN performer that diesel fire pump FIRE PUMP A fails to crank.

IF FPW-P1A or FPW-P1B failed to ALTERNATE PATH ____

______3. attempt to start due to battery Candidate has transitioned back to Step 4.2.2.3 problems, THEN re-perform steps 4.2.2.6 4.2.2.3 through 4.2.2.5 with the battery bank that was not used.

RJPM-NRC12-P2

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS Place the selector switch on controller Candidate has located/identified the proper 4.

FPW-MST1A, DIESEL FIRE PUMP controls, and simulated manipulation of the 1A CONTROLLER in MANUAL 1 or selector switch to the alternate position.

4.2.2.3 MANUAL 2. .

Place the selector switch on controller This step is not required. Fire FPW-MST1B, DIESEL FIRE PUMP Pump B is tagged out as stated in 4.2.2.4 1B CONTROLLER in MANUAL 1 or NA the initial conditions.

MANUAL 2.

No action is required. This is a NOTE Procedure Note.

Limit the maximum number of start NOTE attempts to six.

NA Do not hold the START pushbutton for greater than 30 seconds.

Depress and hold local START Candidate has located/identified the proper EVALUATOR CUE: After the pushbutton for 15 seconds or until controls, and simulated depressing and holding performer has simulated 5.

engine starts for the following: the START pushbutton for 15 seconds depressing the START pushbutton, notify the 4.2.2.5

• FPW-P1A, DIESEL DRIVEN Candidate proceeded to 4.2.2.7 performer that diesel fire pump FIRE PUMP A fails to crank.

ALTERNATE PATH

6. IF an engine fails to start, THEN Candidate transitions to Step 4.2.3. ____

Go To Step 4.2.3.

4.2.2.7 RJPM-NRC12-P2

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS No action is required. This is a NOTE Procedure Note.

In the following mode, all other means of stopping the Fire Protection Diesel NA NOTE Engine are disabled, including overspeed protection. The engine continues to run until the Fuel Solenoid Manual Knob is returned to the OUT position.

Open FPW-SOV19A,FUEL SUPPLY EVALUATOR CUE:Notify the

• 7. SOLENOID by turning the knurled Candidate has located/identified the Fuel Supply performer that the knob has manual knob clockwise or IN to open Solenoid and simulated turning the knob in the been rotated fully clockwise and 4.2.3.1 the solenoid. clockwise direction. stopped.

Greater than 50 psig cooling water No action is required. This is a pressure can damage the Diesel Procedure Caution.

CAUTION Engine Cooling System. Do not NA exceed 50 psig cooling water pressure.

EVALUATOR CUE: Notify the Open FPW-V3009, FPW-P1A Candidate has located/identified FPW-V3009 and performer that handwheel

• 8. ENGINE COOLING SYSTEM simulated opening the valve by turning the motion has stopped and the BYPASS VALVE handwheel in the counter-clockwise direction valve stem now appears similar 4.2.3.2 until handwheel motion stops. to FPW-V176 (Located just below FPW-V3009)

Throttle open 2 turns FPW-V179, Candidate has located/identified FPW-V179 and EVALUATOR CUE: If

• 9.

FPW-P1A ENGINE COOLING simulated throttling the valve by turning the requested, notify the candidate SYSTEM BYPASS VALVE handwheel in the counter-clockwise direction for that FPW-PI27A indicates 4.2.3.3 2 turns. similar to FPW-PI3A.

RJPM-NRC12-P2

• Denotes Critical Step Page 9 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS No action required. Actions follow 4.2.3.4 Engage the starter per the following: NA below.

Raise the Lever on either of the two Candidate has located/identified the starter EVALUATOR CUE: After one

• ____10. starter contactors. FPW-SRT1AA or manual lever and has simulated raising the lever. of the levers has been raised, FPW-SRT1AB, MANUAL START notify the performer that the 4.2.3.4.1 SWITCH A FOR PUMP FPW engine has started.

FPW-P1A Release the Lever for Candidate has simulated release of the starter ____

_____11.

FPW-SRT1AA(BA) or FPW- manual lever.

SRT1AB(BB), MANUAL START 4.2.3.4.2 SWITCH A(B) FOR PUMP FPW-P1A(B) as soon as the engine starts.

IF engine fails to start, THEN repeat No action is required since the 4.2.3.4.3 steps 4.2.3.4.1 and 4.2.3.4.2 above NA engine started in the previous step.

using the other starter contactor.

Greater than 50 psig cooling water No action is required. This is a pressure can damage the Diesel NA Procedure Caution.

CAUTION Engine Cooling System. Do not exceed 50 psig cooling water pressure.

RJPM-NRC12-P2

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 PERFORMANCE STEP STANDARD S/U COMMENTS Throttle open FPW-V179, FPW-P1A Candidate located FPW-PI27A & FPW-V179 and EVALUATOR CUE: Prior to ENGINE COOLING SYSTEM turned the handwheel for FPW-V179 until FPW- manipulation of FPW-V179, BYPASS VALVE as needed to PI27A indicated >40 psig and < 50 psig. FPW-PI27A indicates 32 psig.

maintain cooling water pressure After the candidate has

• ____12. greater than 40 psig but less than 50 simulated manipulation of one psig additional turn of the handwheel 4.2.3.4.4 in the counter clockwise direction, notify the candidate that FPW-PI27A indicates 45 psig.

Terminating Cue: FPW-P1A, Diesel Fire Pump is running.

RJPM-NRC12-P2

• Denotes Critical Step Page 11 of 13

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-P2 Page 12 of 13

RJPM-NRC12-P2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating in Mode 1, at 100% steady state power. FPW-P1B Diesel Fire Pump is tagged out for pump replacement. A fire has occurred in the Auxiliary Boiler/Water Treatment Building. Attempts to start FPW-P1A, Diesel Fire Pump from the Auxiliary Control Room have failed. The power supply to FPW-P2, MOTOR DRIVEN FIRE PUMP, has been damaged by the fire rendering the pump unavailable The CRS has directed you to perform a local manual start of FPW-P1A, Initiating Cues:

Diesel Driven Fire Pump, in accordance with SOP-0037 Fire Protection Water System Operating Procedure, beginning at Section 4.2.2.

RJPM-NRC12-P2 Page 13 of 13

Number: *RJPM-NRC12-P3 RIVER Revision: 00 BEND STATION Page 1 of 15 TIME CRITICAL JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

INITIATE FULL SCRAM AND NSSSS ISOLATION FROM THE ELECTRICAL PROTECTION ASSEMBLY (EPA) BREAKERS REASON FOR REVISION:

2012 NRC Exam JPM - SRO/RO P3 PREPARE / REVIEW:

Angie Orgeron 1538 6-21-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Validation KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-P3 TASK DESCRIPTION: As ATC Perform Attachment 12, Section 5.7of AOP-0031, Shutdown From Outside the Main Control Room Following a Fire in the Main Control Room TASK

REFERENCE:

400047004001 400048004001 K/A REFERENCE & RATING: 295016 AK2.02, 4.0/4.1 295016 AK3.01, 4.1/4.2 295016 AA1.01, 3.8/3.9 295016 AA1.04, 3.1/3.2 TESTING METHOD: Simulate Actual Performance X Performance Control Room Simulator In-Plant X COMPLETION TIME: 5 minutes MAX TIME: 5 minutes JOB LEVEL: SRO/RO TIME CRITICAL: YES EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC12-P3 Page 2 of 10

RJPM-NRC12-P3 SIMULATOR SETUP SHEET Task

Description:

N/A Required Power: N/A IC No.: N/A Notes: None. This JPM is simulated in the plant.

RJPM-NRC12-P3 Page 3 of 10

RJPM-NRC12-P3 DATA SHEET References for Development: AOP-0031, Shutdown From Outside the Main Control Room Required Materials: AOP-0031, Attachment 12, Section 5.7 Required Plant Condition: Any Task Standard A reactor scram and full NSSSS isolation have been initiated from the Electrical Protection Assemblies (EPA) Area in accordance with AOP-0031 Section 5.7 of Attachment 12 Applicable Objectives: RLP-OPS-AOP031 Objective 5 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-P3 Page 4 of 10

RJPM-NRC12-P3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

The Reactor has just been shutdown from 100% power due to a fire in the Control Room that necessitates evacuation.

Initiating Cue:

The CRS has directed you to complete Section 5.7.1 of AOP-0031, Shutdown From Outside the Main Control Room, Attachment 12, to initiate a Reactor Scram and full NSSSS Isolation.

This is a time critical JPM.

STATE TIME __________

RJPM-NRC12-P3

• Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P3 PERFORMANCE STEP STANDARD S/U COMMENTS NOTE This is a procedure note. No action is required.

If CONTROL POWER MONITOR LIGHTS or LOCAL EMERGENCY CONTROL ALIGNED LIGHTS are off, NOTE then continue the procedure until the NA RSS transfer is complete. The CRS determines when corrective actions can be performed.

The Div 1 Remote Shutdown Room number is 2903.

IF a Control Room fire is in progress, No action required in this THEN initiate a Reactor Scram and a full step.

NA 5.7 NSSSS Isolation by directing the ATC Operator to perform the following If a Main Control Room fire is in This is a procedure note. No progress, then Steps 5.7.1.1 and 5.7.1.2 action is required.

NOTE NA shall be completed within 5 minutes of scramming the reactor.

Proceed briskly to Control Bldg 116 ft el Candidate has arrived at the Div 1 Electrical

____1. Div 1 Electrical Protection Assemblies Protection Assemblies on the Control Building area and perform the following: 116 ft el. ____

5.7.1 At Control Bldg 116 ft el, place the Action is performed in bulleted following Div I Electrical Protection steps below.

NA 5.7.1.1 Assemblies in OFF:

RJPM-NRC12-P3

• Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P3

1. C71-S003C Candidate has located/identified C71-S003C and

• ___2. simulated turning the switch counter clockwise to the OFF position.

5.7.1.1

• ___3. 2. C71-S003F Candidate has located/identified C71-S003F and simulated turning the switch counter clockwise to 5.7.1.1 the OFF position

• ___4. 3. C71-S003A Candidate has located/identified C71-S003A and simulated turning the switch counter clockwise to 5.7.1.1 the OFF position

• ___5. 4. C71-S003E Candidate has located/identified C71-S003E and simulated turning the switch counter clockwise to 5.7.1.1 the OFF position At Control Bldg 116 ft el, place the Action is performed in bulleted following Div II Electrical Protection NA steps below.

5.7.1.2 Assemblies in OFF:

1. C71-S003H Candidate has located/identified C71-S003H and

• 6. simulated turning the switch counter clockwise to the OFF position

2. C71-S003D Candidate has located/identified C71-S003D and

• 7. simulated turning the switch counter clockwise to the OFF position RJPM-NRC12-P3

• Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P3

3. C71-S003G Candidate has located/identified C71-S003G and

• 8. simulated turning the switch counter clockwise to the OFF position

4. C71-S003B Candidate has located/identified C71-S003B and

• 9. simulated turning the switch counter clockwise to the OFF position Terminating Cue: A reactor scram and full NSSSS isolation have been initiated from the Electrical Protection Assemblies (EPA) Area in accordance with AOP-0031 Section 5.7.1 of Attachment 12, within 5 minutes.

COMPLETION TIME __________

RJPM-NRC12-P3

• Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-P3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-P3 Page 9 of 10

RJPM-NRC12-P3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Reactor has just been shutdown from 100% power due to a fire in the Control Room that necessitates evacuation.

Initiating Cues: The CRS has directed you to complete Section 5.7.1 of AOP-0031, Shutdown From Outside the Main Control Room, Attachment 12, to initiate a Reactor Scram and full NSSSS Isolation.

This is a time critical JPM.

RJPM-NRC12-P3 Page 10 of 10

Number: *RJPM-NRC12-S1 RIVER Revision: 00 BEND STATION Page 1 of 10 ALTERNATE PATH JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

RESPOND TO HIGH RADIATION LEVELS IN THE AUXILIARY BUILDING REASON FOR REVISION:

2012 NRC Exam JPM S1 PREPARE / REVIEW:

Angie Orgeron 1538 6-25-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8/6/2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S1 TASK DESCRIPTION: Respond to High Radiation Levels in the Auxiliary Building by isolating secondary containment dampers and verifying initiation of Standby Gas Treatment TASK

REFERENCE:

234002003020 300159003001 K/A REFERENCE & RATING: 290001 A2.03 3.4/3.6 290001 A2.06 3.7/4.0 290001 A3.01 3.9/4.0 290001 A4.09 3.2/3.2 290001 A4.10 3.4/3.3 261000 A3.02 3.2/3.1 261000 A3.03 3.0/2.9 261000 A4.03 3.0/3.0 261000 A4.09 2.7/2.7 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 MINUTES.

MAX TIME: 30 MINUTES JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH YES (FAULTED):

SAFETY FUNCTION 5 RJPM-NRC12-S1 Page 2 of 10

RJPM-NRC12-S1 SIMULATOR SETUP SHEET Task

Description:

Respond to High Radiation Levels in the Auxiliary Building by isolating secondary containment dampers and verifying initiation of Standby Gas Treatment.

Required Power: NA, determined by paired JPM.

IC No.: 202 Notes: Insert switch override for 1-GT-HVRA19.

RMS-RE110 in high alarm status RJPM-NRC12-S1 Page 3 of 10

RJPM-NRC12-S1 DATA SHEET References for Development: OSP-0053, Rev 16 Required Materials: OSP-0053, Rev 16 Attachment 21 Hard Card (Simulator copy)

Required Plant Condition: ANY Task Standard OSP-0053 Attachment 21 has been completed, failures recognized and compensatory actions taken such that all dampers listed in step 1.2 are closed and both trains of Standby Gas Treatment are in service.

Applicable Objectives: RLP-STM-0409 Objectives 4c, 5c, 8c Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S1 Page 4 of 10

RJPM-NRC12-S1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Radiation monitor RMS-RE110 has just gone into the High Alarm condition.

Initiating Cue:

The CRS has directed you to respond to this condition by performing Attachment 21 of OSP-0053, EMERGENCY AND TRANSIENT RESPONSE SUPPORT PROCEDURE. The CRS desires both Standby Gas Trains remain in service so perform Section 1 ONLY.

RJPM-NRC12-S1

• Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S1 PERFORMANCE STEP STANDARD S/U COMMENTS Perform the following: NA No action performed in this 1.1 steps. Actions follow below.

Place HVR-AOD22A, ANNULUS Candidate located/identified and positioned the ____

• _____1. MIX SPLY TO SGT in Man Init HVR-AOD22A, ANNULUS MIX SPLY TO

• SGT to the Man Init position.

Place HVR-AOD22B, ANNULUS Candidate located/identified and positioned the ____

• _____2. MIX SPLY TO SGT in Man Init HVR-AOD22B, ANNULUS MIX SPLY TO

• SGT to the Man Init position.

Depress AUX BLDG TO SGT FLTR Candidate located/identified and depressed AUX ____

• _____3. A MANUAL INITIATION BLDG TO SGT FLTR A MANUAL

• INITIATION Pushbutton.

Depress AUX BLDG TO SGT FLTR Candidate located/identified and depressed AUX ____

• _____4. B MANUAL INITIATION BLDG TO SGT FLTR B MANUAL

• INITIATION Pushbutton.

Verify the following dampers are NA No action performed in this step.

1.2 closed

Actions follow below.

HVR-AOD143, DN STREAM ISOL Candidate verified the damper closed by ____

______5. SUPPLY verifying the GREEN light is ON and the RED

• light is OFF.

RJPM-NRC12-S1

• Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S1 PERFORMANCE STEP STANDARD S/U COMMENTS HVR-AOD164, UP STREAM ISOL ALTERNATE PATH ____

SUPPLY Candidate recognized that HVR-AOD164 UP STEAM ISOL SUPPLY failed to isolate and

• _____7. turned the control handswitch to the CLOSE

• position and verified the damper closed by verifying the GREEN light is ON and the RED light is OFF.

HVR-AOD263, SGT UPSTREAM Candidate verified the damper closed by ____

______8. SPLY ISOL verifying the GREEN light is ON and the RED

• light is OFF.

HVR-AOD264, SGT DNSTREAM Candidate verified the damper closed by ____

______9. SPLY ISOL verifying the GREEN light is ON and the RED

• light is OFF.

HVR-AOD262, AUX/CNTMT BLDG Candidate verified the damper closed by ____

_____10. EXH ISOL verifying the GREEN light is ON and the RED

• light is OFF.

HVR-AOD214, AUX/CNTMT BLDG ALTERNATE PATH ____

EXH ISOL Candidate recognized that HVR-AOD214, AUX/CNTMT BLDG EXH ISOL failed to isolate

• ____11. and turned the control handswitch to the CLOSE

• position and verified the damper closed by verifying the GREEN light is ON and the RED light is OFF.

HVR-AOD161, ANNULUS PRESS Candidate verified the damper closed by ____

_____12. CONT SUCT verifying the GREEN light is ON and the RED

• light is OFF.

HVR-AOD142, APC UP STREAM Candidate verified the damper closed by ____

_____13. DISCH verifying the GREEN light is ON and the RED

• light is OFF.

RJPM-NRC12-S1

• Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S1 PERFORMANCE STEP STANDARD S/U COMMENTS HVR-AOD261, APC DN STREAM Candidate verified the damper closed by ____

_____14. DISCH verifying the GREEN light is ON and the RED

• light is OFF.

Verify both divisions of GTS start. Candidate verified the GTS-FN1A and GTS-

_____15. ____

FN1B are both running by verifying RED 1.3 indicating lights are ON.

Terminating Cue: All dampers listed in Step 1.2 of OSP-0053 Attachment 21 are closed and both trains of Standby Gas Treatment are in service.

RJPM-NRC12-S1

• Denotes Critical Step Page 8 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S1 Page 9 of 10

RJPM-NRC12-S1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Radiation monitor RMS-RE110 has just gone into the High Alarm condition.

Initiating Cues: The CRS has directed you to respond to this condition by performing Attachment 21 of OSP-0053, EMERGENCY AND TRANSIENT RESPONSE SUPPORT PROCEDURE. The CRS desires both Standby Gas Trains remain in service so perform Section 1 ONLY.

RJPM-NRC12-S1 Page 10 of 10

Number: RJPM-NRC12-S2 RIVER Revision: 00 BEND STATION Page 1 of 11 ALTERNATE PATH JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

TRANSFER RECIRC PUMPS FROM FAST TO SLOW SPEED REASON FOR REVISION:

2012 NRC Exam JPM S2 PREPARE / REVIEW:

Angie Orgeron 1538 6-25-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S2 TASK DESCRIPTION: Transfer Recirc Pumps from Fast to Slow Speed TASK

REFERENCE:

202010001001; 400041004001 K/A REFERENCE & RATING: 202001 A4.01: 3.7/3.7; 202001 A2.03: 3.6/3.7; 202001 A3.07: 3.3/3.3 202002 A1.01: 3.2/3.2; 202002 A2.01: 3.4/3.4; 202002 A4.07: 3.3/3.2 295001 AA1.01: 3.5/3.6; 295001 AA1.05: 3.3/3.3; 295001 AA2.01: 3.5/3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION 1 RJPM-NRC12-S2 Page 2 of 11

RJPM-NRC12-S2 SIMULATOR SETUP SHEET Task

Description:

Transfer Recirc Pumps to SLOW speed.

Required Power: Reactor Power ~40%

IC No.: 210 Notes: Insert malfunction RCS008B to result in a transfer failure for Reactor Recirculating Pump B.

RJPM-NRC12-S2 Page 3 of 11

RJPM-NRC12-S2 DATA SHEET References for Development: SOP-0003 Rev 308, REACTOR RECIRCULATION SYSTEM (SYS #053)

AOP-0024, Rev 24, THERMAL HYDRAULICS STABILITY CONTROLS Required Materials: SOP-0003 Rev 308, REACTOR RECIRCULATION SYSTEM (SYS #053) Simulator copy AOP-0024 Rev 24, THERMAL HYDRAULICS STABILITY CONTROLS Simulator copy Required Plant Condition: Reactor Power ~40%

Task Standard: Reactor Recirculation pump A is in slow speed and Reactor Recirculation pump B is OFF with the associated discharge valve closed.

Applicable Objectives: RLP-STM-0053 Obj 6 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S2 Page 4 of 11

RJPM-NRC12-S2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at about 40% power and lowering power to support a drywell entry.

Initiating Cue:

The Control Room Supervisor has directed you Transfer Recirculation Pumps to Slow Speed, per SOP-0003, Section 5.2 RJPM-NRC12-S2

• Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S2 PERFORMANCE STEP STANDARD S/U COMMENTS No actions performed by this step.

5.2 Transferring from Fast Speed to Slow NA Actions follow below.

Speed Simultaneously depress B33-C001A and Candidate simultaneously depressed B33-C001A and

• 1. B RECIRC PUMP A and B MOTOR B RECIRC PUMP A and B MOTOR BREAKER 5A BREAKER 5A and 5B XFER TO and 5B XFER TO LFMG pushbuttons.

5.2.1. LFMG pushbuttons.

5.2.2 Observe the following: NA Actions performed below.

Both B33-S001A LFMG MOT BRKR Candidate verified B33-S001A LFMG MOT BRKR 1A and B33-S001B LFMG MOT 1A closed.

2. BRKR 1B close.

5.2.2.1. ALTERNATE PATH Candidate recognized that B33-S001B LFMG MOT BRKR 1B failed to close.

Both B33-C001A RECIRC PUMP A Candidate verified both B33-C001A RECIRC PUMP

3. MOTOR BREAKER 5A and A MOTOR BREAKER 5A and B33-C001B RECIRC 5.2.2.2 B33-C001B RECIRC PUMP B PUMP B MOTOR BREAKER 5B open.

MOTOR BREAKER 5B open.

RJPM-NRC12-S2

• Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S2 PERFORMANCE STEP STANDARD S/U COMMENTS WHEN B33-C001A and B, RECIRC Candidate verified that B33-S001A LFMG A GEN EVALUATOR CUE: As the CRS, PUMP A and B coast down to BRKR 2A closed and pump speed stabilized near 450 acknowledge the report that approximately 360 - 470 RPM, THEN RPM. Reactor Recirculation Pump B B33-S001A and B LFMG A and B transfer has failed, THEN direct GEN BRKR 2A and 2B close and pump ALTERNATE PATH the candidate to perform the

4. speeds stabilize near 450 RPM. actions of AOP-0024 THERMAL 5.2.2.3 Recognized and reported that B33-S001B LFMG B HYDRAULIC STABILITY GEN BRKR 2B did not close and pump coasting to 0 CONTROL Section 5.9.

RPM.

Also, notify the candidate that another operator will perform GOP-0004, SINGLE LOOP OPERATIONS requirements.

TRANSITIONING TO AOP-0024 Section 5.9 IF a single Recirculation Pump Trip Actions performed below.

5.9 occurs, THEN perform the following NA actions:

NOTE: This is a procedure note. No action is Process computer point B33NA01V required.

is used to determine core flow when one Reactor Recirculation Pump is NA OFF and the other is in fast speed.

B33-R613, TOTAL CORE FLOW NOTE (Red Pen) is not accurate in this configuration and is not to be used.

Refer to ERIS point ONWTDPM (enter GD ONWT* in ERIS ) if remaining Recirc pump configuration is 1 Slow/0 RJPM-NRC12-S2

• Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S2 PERFORMANCE STEP STANDARD S/U COMMENTS Enter GOP-0004, Single Loop No action required. This task is being 5.9.1 Operation NA performed by another operator.

5. Place B33-HYV-F060A (B), FLOW Candidate verified both loops are in MANUAL as CONT VLV for both loops in indicated by MANUAL pushbuttons being backlit at _____

5.9.2 MANUAL B33-K603A & B Perform the following actions for the Actions performed below.

shutdown loop: NA 5.9.3 Closure of both suction and No action required. This is a discharge valves with seal purge procedure caution.

valved in causes high pressures in the isolated loop which can result in NA damage to the seals. Do not close CAUTION B33-F023A(B), RECIRC PUMP A(B) SUCTION VALVE and B33-F067A(B), RECIRC PUMP A(B)

DISCH VALVE if seal purge is valved in.

Candidate closed B33-F067B, RECIRC PUMP B

• 6.

Close B33-F067A(B), RECIRC PUMP DISCH VALVE by depressing the CLOSE push A(B) DISCH VALVE. button and verified valve is closed by checking the 5.9.3.1. RED light OFF and the GREEN light ON.

NOTE:

Reopening of the Discharge Valve and the FCV following pump coastdown is NA NOTE:

expected to maintain the shutdown loop temperature within 50°F of the operating loop.

RJPM-NRC12-S2

• Denotes Critical Step Page 8 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S2 PERFORMANCE STEP STANDARD S/U COMMENTS Candidate requested guidance from the CRS regarding EVALUATOR CUE: Inform the

7. IF Recirc pump restart is anticipated, pump restart. candidate that pump restart is not 5.9.3.2 THEN perform the following actions: anticipated at this time and that the task is complete.

Terminating Cue: Reactor Recirculation pump A is in slow speed and Reactor Recirculation pump B is OFF with the associated discharge valve closed.

RJPM-NRC12-S2

• Denotes Critical Step Page 9 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S2 Page 10 of 11

RJPM-NRC12-S2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at about 40% power and lowering power to support a drywell entry.

Initiating Cues: The Control Room Supervisor has directed you to Transfer Recirculation Pumps to Slow Speed, per SOP-0003, Section 5.2 RJPM-NRC12-S2 Page 11 of 11

Number: RJPM-NRC12-S3 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

MANUAL ISOLATION OF A MAIN STEAM LINE DURING POWER OPERATION REASON FOR REVISION:

2012 NRC Exam JPM S3 PREPARE / REVIEW:

Angie Orgeron 1538 6/26/2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S3 TASK DESCRIPTION: Manual Isolation of a Main Steam Line During Power Operation TASK

REFERENCE:

239008001001 K/A REFERENCE & RATING: 239001 A2.10 3.8/3.9 239001 A4.01 4.2/4.0 TESTING METHOD: Simulate Actual Performance Performance X Control Simulator X In-Plant Room COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 3 RJPM-NRC12-S3 Page 2 of 10

RJPM-NRC12-S3 SIMULATOR SETUP SHEET Task

Description:

Manual Isolation of a Main Steam Line During Power Operation.

Required Power: 75%

IC No.: 212 Notes:

RJPM-NRC12-S3 Page 3 of 10

RJPM-NRC12-S3 DATA SHEET References for Development: SOP-0011, Rev 027, MAIN STEAM SYSTEM (SYS

1. 109)

Required Materials: SOP-0011, Rev 027, MAIN STEAM SYSTEM (SYS

1. 109) (Simulator copy)

Required Plant Condition: 75% power Task Standard: Both MSIV on A have been slow close and reactor power, pressure, and level are stable.

Applicable Objectives: RLP-STM-0109 Objectives 3h, 7, 8, 10 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S3 Page 4 of 10

RJPM-NRC12-S3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1 at 70% power. A packing leak in the steam tunnel has resulted in the need to isolate the A steam line to isolate this leak.

Initiating Cue:

The CRS has directed you to isolate the A main steam line in accordance with SOP-0011, MAIN STEAM SYSTEM, Section 5.1 RJPM-NRC12-S3

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S3 PERFORMANCE STEP STANDARD S/U COMMENTS Section 5.1 denotes isolation of Main No action required. This is a Steam Line A with MSL B, C, and D procedure note.

parentheses.

Reactor power is limited to less than or NA equal to 75% RTP with one Main Steam Line out of service.

NOTE: Isolation of a main steam line inputs a reactor trip signal to one of the divisional logic circuits of RPS. AOP-0003, Automatic Isolations contains actions to be taken upon an automatic isolation of the main steam lines.

A high steam line flow isolation in any steam line causes all MSIVs to close.

Candidate verified reactor power less than or equal to

______ 1. Lower Reactor power to less than or 75%.

equal to 75%.

5.1.1 Perform a slow closure of No action required. Actions follow

______ 2. B21-AOVF028A(B)(C)(D), MSL NA below.

A(B)(C)(D) OUTBD MSIV as

5.1.2 follows

Place B21-AOVF028A(B)(C)(D), Candidate located/identified and positioned B21-

• _____ 3. MSL A(B)(C)(D) OUTBD MSIV, AOVF028A to the OPEN/SLOW TEST position.

Control Switch in OPEN/SLOW 5.1.2.1 TEST RJPM-NRC12-S3

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S3 PERFORMANCE STEP STANDARD S/U COMMENTS Depress and hold MSL A(B)(C)(D) Candidate located/identified and depressed the MSL The following alarms will annunciate A OUTBD MSIV TEST pushbutton and maintained and are expected for this evolution:

• _____ 4. OUTBD MSIV TEST Pushbutton.

the button in the depressed condition.

• H13-P808-52A-H01 5.1.2.2.

• H13-P680-06A-B06 WHEN B21-AOVF028A(B)(C)(D), When B21-AOVF028A reached the fully closed

• _____ 5. position indicated by GREEN light ON and RED light MSL A(B)(C)(D) OUTBD MSIV, is fully closed, THEN place the OFF, the candidate placed the B21-AOVF028A 5.1.2.3. control switch to the CLOSE position.

OPEN-SLOW TEST Control Switch in CLOSE

______ 6.

Release MSL A(B)(C)(D) OUTBD Candidate released the MSL A OUTBD MSIV TEST 5.1.2.4. MSIV TEST Pushbutton. pushbutton.

No action required. Actions follow

______ 7. Perform a slow closure of below.

B21-AOVF022A(B)(C)(D), MSL 5.1.3. A(B)(C)(D) INBD MSIV, as NA follows:

• _____ 8. Place B21-AOVF022A(B)(C)(D), Candidate located/identified and positioned MSL A(B)(C)(D) INBD MSIV B21-AOVF022A to the OPEN/SLOW TEST position.

5.1.3.1 Control Switch in OPEN/SLOW TEST The following alarms will annunciate Candidate located/identified and depressed the MSL

• _____ 9. Depress and hold MSL A(B)(C)(D) and are expected for this evolution:

INBD MSIV TEST Pushbutton. A INBD MSIV TEST pushbutton and maintained the button in the depressed condition.

• H13-P808-52A-H02 5.1.3.2

• H13-P680-06A-B06 RJPM-NRC12-S3

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S3 PERFORMANCE STEP STANDARD S/U COMMENTS WHEN B21-AOVF022A(B)(C)(D), When B21-AOVF022 reached the fully closed

• ____10. position indicated by GREEN light ON and RED light MSL A(B)(C)(D) INBD MSIV, is fully closed, THEN place the OFF, the candidate placed the B21-AOVF022A 5.1.3.3. control switch to the CLOSE position.

OPEN-SLOW TEST Control Switch in CLOSE.

_____11.

Release MSL A(B)(C)(D) INBD Candidate released the MSL A INBD MSIV TEST 5.1.3.4. MSIV TEST Pushbutton. pushbutton.

Terminating Cue: The A Main Steam Line is isolated in accordance with SOP-0011 Section 5.1.

RJPM-NRC12-S3

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S3 Page 9 of 10

RJPM-NRC12-S3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating in Mode 1 at 70% power. A packing leak in the steam tunnel has resulted in the need to isolate the A steam line to isolate this leak.

Initiating Cues: The CRS has directed you to isolate the A main steam line in accordance with SOP-0011, MAIN STEAM SYSTEM, Section 5.1 RJPM-NRC12-S3 Page 10 of 10

Number: RJPM-NRC12-S4 RIVER Revision: 00 BEND STATION Page 1 of 12 ALTERNATE PATH JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

SHIFT DIVISIONS OF CONTROL BUILDING CHILLERS REASON FOR REVISION:

2012 NRC Exam JPM S4 PREPARE / REVIEW:

Angie Orgeron 1538 6-25-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S4 TASK DESCRIPTION: Shift Control Building Chillers between divisions TASK

REFERENCE:

291012001004 K/A REFERENCE & RATING: 290003 A2.01 3.1/3.2 A3.01 3.3/3.5 A4.01 3.2/3.2 K4.01 3.1/3.2 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH YES (FAULTED):

SAFETY FUNCTION 9 RJPM-NRC12-S4 Page 2 of 12

RJPM-NRC12-S4 SIMULATOR SETUP SHEET Task

Description:

Shift Control Building Chillers between divisions.

Required Power: Any IC No.: 210 Notes: Insert the following:

Malfunctions:

P863_74a:c_6 Overrides:

DI_HVK-P1B STOP LO_HVC-D2A1-A OFF T1 LO_HVK-CHL1A-A ON T1 LO_HVK-CHL1A-G ON T1 LO_HVK-CHL1A-R OFF T2 LO_HVK-CHL1A-G ON delete in 2 seconds T2 LO_HVK-CHL1A-R OFF delete in 2 seconds T2 LO_HVK-CHL1A-A OFF RJPM-NRC12-S4 Page 3 of 12

RJPM-NRC12-S4 DATA SHEET References for Development: SOP-0066, Rev 309 Control Building HVAC Chilled Water System (Sys #410)

Required Materials: SOP-0066, Rev 309 Control Building HVAC Chilled Water System (Sys #410) (Simulator copy)

Required Plant Condition: Any Task Standard: Following identification of failure, original division is returned back to service.

Applicable Objectives: RLP-STM-0402, Objectives 7, 8 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S4 Page 4 of 12

RJPM-NRC12-S4 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

HVK-P1A is to be tagged out for scheduled maintenance. The A chiller has been running for 3 days.

Initiating Cue:

The CRS directs you to rotate divisions of HVK from Div 1 to Div 2 with HVK-CHL1B in service with HVK-P1B in accordance with SOP-0066, Control Building HVAC Chilled Water System, Section 5.4.

RJPM-NRC12-S4

• Denotes Critical Step Page 5 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 PERFORMANCE STEP STANDARD S/U COMMENTS Check that the operating chiller has been Candidate verified that the chiller had been running 1.

running for at least 20 minutes. for 3 days per the Initial Conditions 5.4.1 NOTE: The controls and indications in No action required. This is a this section are located at H13-P863, NA procedure note.

NOTE:

unless otherwise specified.

Candidate turned the HVK-P1A pump control switch Note: Several annunciators will be to the STOP postion. received on H13-P863 when this step

• 2. Stop the running Control Building Chilled is performed.

5.4.2 Water Pump.

Verify the running chiller automatically Candidate verified that HVK-CHL1A tripped by

3. trips. observing the red light extinguish and green light on.

5.4.3 _____

NOTE:

Chiller 1B/1D or 1A/1C pre-trip NA comes in and clears NOTE:

Division I Chilled Water Pumps have a 30 second start time delay ALTERNATE PATH Check that the standby chilled water

• 4.

pump starts and its discharge valve opens. Candidate identified that the HVK-P1B did not start.

5.4.4 RJPM-NRC12-S4

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 PERFORMANCE STEP STANDARD S/U COMMENTS IF the standby chilled water pump does Candidate transitioned to Section 5.4.7 of SOP-0066. EVALUATOR CUE: If a report is not start, THEN go to Step 5.4.7. provided to the CRS concerning the

• 5.

trip, acknowledge the report.

5.4.5 TRANSITION TO SECTION 5.4.7 NOTE: No action required. This is a Steps 5.4.7 thru 5.4.11 resets the procedure note.

chiller logic and places the chiller in NA standby. A chiller can not be started NOTE: until 2 1/2 minutes have elapsed since it was stopped. This time delay allows sufficient time for the guide vanes to close and ensure no-load starting of the chiller Check the previously running AHUs and Candidate checked that previously running AHUs fans have stopped have stopped as follows:

6.

5.4.7 HVC-ACU1A and 2A Green light ON, Red light OFF and Amber light ON.

HVC-FN3A Grren light ON and Red light OFF.

Verify at least 3 minutes has elapsed since chiller was stopped, THEN Reset trips on Candidate waited 3 minutes prior to proceeding.

• 7.

the previously running AHUs as follows:

5.4.8 Depress STOP on HVC-ACU1A(B), CR Candidate depressed STOP on HVC-ACU1A

• 8.

AHU A(B).

RJPM-NRC12-S4

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 PERFORMANCE STEP STANDARD S/U COMMENTS Depress STOP on HVC-ACU2A(B), Candidate depressed STOP on HVC-ACU2A

• 9.

CONTROL BLDG AHU A(B).

Place HVC-ACU3A(B), EQPT RM AHU Candidate placed switch for HVC-ACU3A to STOP

• 10 A(B) Switch to STOP then back to and then back to AUTO

• AUTO.

NA No action required by this conditional IF when resetting the AHUs in Step step.

5.4.8, a running AHU trips, THEN

_____11.

depress the LOCKOUT and then the RESET Pushbutton on the tripped 5.4.9 AHU to automatically restart the AHU.

NA No action required. This is a Note: procedure note.

NOTE:

Step 5.4.10 & 5.4.11 Resets the Chilled Water Pump start logic.

Verify HVK-P1A(B)(C)(D), CHILLED Candidate checked that HVK-P1A switch is in STOP.

12 WATER PUMP A(B)(C)(D) Switch for

. the previously running pump is in STOP.

5.4.10.

• ____ 13. Place HVK-P1A(B)(C)(D), CHILLED Candidate placed HVK-P1A switch to AUTO WATER PUMP A(B)(C)(D) Switch for 5.4.11. the previously running pump to AUTO.

RJPM-NRC12-S4

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 PERFORMANCE STEP STANDARD S/U COMMENTS No action required. Actions Perform the following for the previously NA performed below.

5.4.12.

running chiller:

Depress STOP on HVK- Candidate depressed STOP pushbutton on HVK-

• ____14. CHL1A(B)(C)(D), CONT BLDG CHL1A CHILLER A(B)(C)(D) Start/Stop/Reset 5.4.12.1 Pushbutton.

• ___15. Depress RESET on Candidate depressed RESET pushbutton on HVK-HVK-CHL1A(B)(C)(D) Start/Stop/Reset CHL1A Pushbutton 5.4.12.2 Verify the following: No action required. Actions 5.4.13 performed below.

NA

16. Standby Chiller starts. Candidate verified that HVK-CHL1A restarted.

5.4.13.1

17. Standby Chiller Recirc Service Water Candidate verified that SWP-MOV27A opened.

Pump suction valve opens.

5.4.13.2 Standby Chiller Recirc Service Water Candidate verified that SWP-P3A starts EVALUATOR CUE:

Pump starts. When the candidate makes contact with the Control Building operator 18.

to perform Section 5.4.14, notify the candidate as the Control Building 5.4.13.3 operator that you will complete the remainder of Section 5.4 of SOP-0066.

Terminating Cue: HVK-CHL1A, is restored to service following the failure of Division 2.

RJPM-NRC12-S4

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 RJPM-NRC12-S4

• Denotes Critical Step Page 10 of 12

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S4 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S4 Page 11 of 12

RJPM-NRC12-S4 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: HVK-P1A is to be tagged out for scheduled maintenance. The A chiller has been running for 3 days.

Initiating Cues: The CRS directs you to rotate divisions of HVK from Div 1 to Div 2 with HVK-CHL1B in service with HVK-P1B in accordance with SOP-0066, Control Building HVAC Chilled Water System, Section 5.4.

RJPM-NRC12-S4 Page 12 of 12

Number: RJPM-NRC12-S5 RIVER Revision: 00 BEND STATION Page 1 of 11 ALTERNATE PATH JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

SHUTDOWN THE HIGH PRESSURE CORE SPRAY PUMP AFTER AN INADVERTENT AUTOMATIC INITIATION REASON FOR REVISION:

2012 NRC Exam JPM S5 PREPARE / REVIEW:

Angie Orgeron 1538 6-26-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S5 TASK DESCRIPTION: Shutdown the High Pressure Core Spray Pump after an Inadvertent Automatic Initiation.

TASK

REFERENCE:

206016001001 K/A REFERENCE & RATING: 209002 A1.01 3.6/3.7 209002 A1.02 3.4/3.6 209002 A1.08 3.1/3.3 209002 A2.08 3.1/3.2 209002 A3.01 3.3/3.3 209002 A3.03 3.6/3.6 209002 A3.04 3.7/3.7 209002 A4.01 3.7/3.7 209002 A4.03 3.8/3.8 209002 A4.04 3.1/3.1 209002 A4.15 3.6/3.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH YES (FAULTED):

SAFETY FUNCTION 2 RJPM-NRC12-S5 Page 2 of 11

RJPM-NRC12-S5 SIMULATOR SETUP SHEET Task

Description:

Shutdown the High Pressure Core Spray Pump after an Inadvertent Automatic Initiation with a failure of the HPCS minimum flow valve to automatically open.

Required Power: Reactor Power 70%

IC No.: 212 Notes: The following malfunctions are snapped into this IC to support this JPM:

DG002C HPCS006 RJPM-NRC12-S5 Page 3 of 11

RJPM-NRC12-S5 DATA SHEET References for Development: SOP-0030, Rev 027 High Pressure Core Spray Required Materials: SOP-0030, Rev 027 High Pressure Core Spray (Simulator copy)

Required Plant Condition: ANY Task Standard: High Pressure Core Spray Pump is shutdown with the minimum flow valve open.

Applicable Objectives: RLP-STM-0203 Objectives 3, 4, 7, and 11 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S5 Page 4 of 11

RJPM-NRC12-S5 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating at about 70% power after an inadvertent HPCS initiation. The HPCS Diesel Generator has been shutdown.

Initiating Cue:

The CRS has directed you to shutdown the High Pressure Core Spray Pump using SOP-0030, High Pressure Core Spray, Section 6.

RJPM-NRC12-S5

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S5 PERFORMANCE STEP STANDARD S/U COMMENTS No action required. This is a NOTE: procedure note.

NOTE: Precautions 2.9 and 2.10 should be NA referred to prior to HPCS System shutdown Candidate attempted to rotate Manual Initiation

1. Verify E22A-S2, HPCS MANUAL pushbutton collar to the DISARM position or noted INITIATION collar is in the DISARM that the red indicator mark on the collar is aligned 6.1 position. with the DISARM position.

If the HPCS initiation signal is No action required. This is a unable to be reset using E22A-S7, procedure note.

HPCS INITIATION RESET Pushbutton, the HPCS Pump can be NA overridden and stopped. This will prevent an automatic start of the HPCS Pump until the initiation NOTE:

signals clear and E22A-S7 is depressed.

Resetting the High Level 8 signal prior to resetting the injection signal will result in opening E22-F004, HPCS INJECT ISOL VALVE.

Candidate depressed HPCS INITIATION RESET

• 2. Depress E22A-S7, HPCS INITIATION pushbutton and verified WHITE light is OFF.

RESET pushbutton and check the white 6.2 light goes off.

RJPM-NRC12-S5

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S5 PERFORMANCE STEP STANDARD S/U COMMENTS No action required. Actions follow 6.3 Verify closed the following valves: below.

NA

3. E22-F023, HPCS TEST RETURN VLV TO SUPPRESSION POOL Candidate located/identified and verified E22-F023 is CLOSED by GREEN light indication ON and RED 6.3.1 light indication OFF.

4. E22-F010, HPCS TEST BYPASS VLV TO CST Candidate located/identified and verified E22-F010 is CLOSED by GREEN light indication ON and RED 6.3.2 light indication OFF.

5. E22-F011, HPCS TEST RETURN VALVE TO CST Candidate located/identified and verified E22-F011 is CLOSED by GREEN light indication ON and RED 6.3.3 light indication OFF.

E22-F004, HPCS INJECT ISOL

• 6. VALVE Candidate located/identified and closed E22-F004 by placing the handswitch to the CLOSED position and verifying the GREEN light indication ON and RED 6.3.4 light indication OFF following completion of the valve stroke.

RJPM-NRC12-S5

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S5 PERFORMANCE STEP STANDARD S/U COMMENTS When flow lowers below 625 gpm on ALTERNATE PATH Candidate may wait for up to 21 E22-R603, HPCS FLOW, verify E22- seconds for transmitter saturation to F012, HPCS MIN FLOW VALVE TO Candidate recognized the failure of E22-F012 to open dissipate prior to recognizing failure SUPPRESSION POOL opens. automatically. of E22-F012 (Precaution & Limitation 2.2)

Candidate manually opened E22-F012 by placing the

• 7. handswitch in OPEN and verifying RED light ON and GREEN light OFF OR immediately tripped the NOTE: As a conservative action, an HPCS pump. immediate pump trip may be initiated.

6.4 Remaining steps should be performed ACTION SHOULD OCCUR WITHIN 60 SECONDS following the trip.

EVALUATOR CUE: As CRS acknowledge report of the failure of E22-F012 to open.

5. If E22-PC003, HPCS LINE FILL Candidate verified that E22-PC003 running with RED PUMP is not running, then start E22- light ON, GREEN light OFF.

6.5 PC003.

• 6.

Trip E22-ACB02, HPCS PUMP Candidate manually opened breaker E22-ACB02 by SUPPLY BRKR. placing the handswitch to the TRIP position and 6.6 verified by GREEN light ON, RED light OFF.

When HPCS Pump discharge pressure Candidate checked that E22-F012 auto close when

7. lowers below 300 psig on E22-R601, pressure drops below 300 psig by observing GREEN HPCS PUMP DISCH PRESSURE, then light ON, RED light OFF.

verify E22-F012, HPCS MIN FLOW 6.7 VALVE TO SUPPRESSION POOL closes.

RJPM-NRC12-S5

• Denotes Critical Step Page 8 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S5 PERFORMANCE STEP STANDARD S/U COMMENTS No action required. Initial conditions

8. IF the HPCS DG is operating, THEN NA stated that the diesel generator was shut down the DG per SOP-0052, secured.

6.8 HPCS Diesel Generator Terminating Cue: High Pressure Core Spray Pump is shutdown and faulty minimum flow valve was identified.

RJPM-NRC12-S5

• Denotes Critical Step Page 9 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S5 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S5 Page 10 of 11

RJPM-NRC12-S5 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at about 70% power after an inadvertent HPCS initiation. The HPCS Diesel Generator has been shutdown.

Initiating Cues: The CRS has directed you to shutdown the High Pressure Core Spray Pump using SOP-0030, High Pressure Core Spray, Section 6.

RJPM-NRC12-S5 Page 11 of 11

Number: *RJPM-NRC12-S6 RIVER Revision: 00 BEND STATION Page 1 of 16 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

START RESIDUAL HEAT REMOVAL IN THE SHUTDOWN COOLING MODE REASON FOR REVISION:

2012 NRC Exam JPM S6 PREPARE / REVIEW:

Angie Orgeron 1538 6-26-2012 Preparer KCN Date Dave Bergstrom 0257 7-17-2012 Technical Review (SME) KCN Date Tim Schenk 0717 7-24-2012 Operations Representative KCN Date John Fralick 0788 8-6-2012 Facility Reviewer KCN Date

• Indexing Information

RJPM-NRC12-S6 TASK DESCRIPTION: Start RHR A in the Shutdown Cooling Mode TASK

REFERENCE:

205011001001 K/A REFERENCE & RATING: 205000 A4.01 3.7/3.7 A4.02 3.6/3.5 205000 A4.03 3.6/3.5 A4.04 3.4/3.3 205000 A4.06 3.8/3.7 A4.07 3.7/3.7 205000 A4.09 3.1/3.1 A4.10 2.9/3.0 205000 A4.11 3.2/3.2 A4.12 3.4/3.4 205000 K1.14 3.6/3.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 20 MINUTES.

MAX TIME: 40 MINUTES JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 4 RJPM-NRC12-S6 Page 2 of 16

RJPM-NRC12-S6 SIMULATOR SETUP SHEET Task

Description:

Start RHR A in the Shutdown Cooling Mode.

Required Power: Shutdown, RPV pressure < 135 psig.

IC No.: 202 Notes: Insert malfunction: E12MOVF064A Breaker Trip Place Caution Tag on E12-MOVF064A RJPM-NRC12-S6 Page 3 of 16

RJPM-NRC12-S6 DATA SHEET References for Development: SOP-0031 Rev 315, RESIDUAL HEAT REMOVAL (SYS #204)

Required Materials: SOP-0031 Rev 315, RESIDUAL HEAT REMOVAL (Simulator copy)

Required Plant Condition: RPV Pressure < 135 psig, Reactor Level > 9.7 inches Task Standard RHR A placed in Shutdown Cooling Mode in accordance with SOP-0031 Section 4.4.9.

Applicable Objectives: RLP-STM-0204 Objective 8f Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC12-S6 Page 4 of 16

RJPM-NRC12-S6 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The unit has been shutdown and is being depressurized for a refueling outage. The plant is currently in Mode 4. RHR A has been flushed and warmed for Shutdown Cooling operation. The system has been filled and vented.

E12-MOV64A is de-energized and Administrative controls are in place for EHS-MCC2E BKR 5C.

This valve has been field verified to be closed.

HVR-UC6 is in service.

Initiating Cue:

The CRS has directed you to place RHR A in the Shutdown Cooling Mode in accordance with SOP-0031 Section 4.4.9 and continuing through 4.4.9.17.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS CAUTION: NA No action required. This is a If adequate core circulation is not procedure caution.

maintained, Reactor coolant temperature indication is not accurate.

CAUTION Natural circulation through the core must be established by raising the Reactor water level to greater than or equal to 75 inches to establish natural circulation to allow flow through the core and the feed water annulus RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: No action required. This is a In Mode 5, during startup or line up procedure note.

changes of shutdown cooling, stop fuel movement in the upper cavity and ensure that all bundles are placed in NA their proper storage locations. This prevents the possibility of a suspended fuel bundle during a concurrent loss of cavity level.

NOTE: During SDC Operation, it is preferred

• to use B21-R605, RX WATER LEVEL SHUTDOWN RANGE for level indication.

Level instrument inputs to RHR isolations may fail to provide Level 3 isolations if the reference leg backfill system is out of service due to the potential of degassing of the reference legs.

IF any of the following RHR EVALUATOR CUE: If asked at Shutdown Cooling interlocks are to be the CRS, notify the candidate bypassed, THEN obtain senior plant that the listed Shutdown Cooling management review and approval and NA interlocks will not be bypassed.

verify contingency methods are in 4.4.9.1 place to supply sufficient makeup water if a draining event occurs while the SDC interlocks are bypassed:

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS Only one Shutdown Cooling Isolation NA No action required. This is a Valve is required to be operable. procedure note.

Opening the power supply breaker or lifting leads on one valve per NOTE:

approved procedures to prevent system isolation and loss of SDC during maintenance or testing is permissible.

Low reactor water level isolation of NA No action performed by this step.

E12-F008, RHR SHUTDOWN Interlocks will not be bypassed.

COOLING OUTBD ISOL VALVE

• and E12-F009, RHR SHUTDOWN COOLING INBD ISOL VALVE.

Interlocks between E12-F004, RHR NA No action performed by this step.

PUMP SUP PL SUCTION VALVE Interlocks will not be bypassed.

and E12-F006, RHR PUMP SDC SUCTION.

On H13-P601, verify less than 135 Candidate located/identified B21-R623A(B), RX psig Reactor Pressure as indicated on LEVEL/PRESSURE RECORDER A(B)and

______1. B21-R623A(B), RX verified reactor pressure is less than 135 psig ____

4.4.9.2 LEVEL/PRESSURE RECORDER A(B).

Verify closed the following NA No action performed in this step.

4.4.9.3 Actions follow below.

E12-F004A(B), RHR PUMP A(B) Candidate located/identified E12-F004A and

______2. SUP PL SUCTION VALVE verified it closed by the GREEN light indicating ON and the RED light indicating OFF. ____

4.4.9.3.1 RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS E12-F064A(B), RHR PUMP A(B) Candidate verified E12-F064A closed by

______3. MIN FLOW TO SUP PL information provided in Initial Conditions.

4.4.9.3.2 E12-F024A(B), RHR PUMP A(B) Candidate located/identified E12-F024A and

______4. TEST RTN TO SUP PL verified it closed by the GREEN light indicating ON and the RED light indicating OFF. ____

4.4.9.3.3 E12-F037A(B), RHR A(B) TO Candidate located/identified E12-F037A and

______5. UPPER POOL FPC ASSIST verified it closed by the GREEN light indicating ON and the RED light indicating OFF. ____

4.4.9.3.4 E12-F048A(B), RHR A(B) HX Candidate located/identified E12-F048A and

______6. BYPASS VALVE. verified it closed by the GREEN light indicating ON and the RED light indicating OFF. ____

4.4.9.3.5 E12-F011A(B), RHR A(B) HX CNDS Candidate located/identified E12-F011A and

______7. FLUSH TO SUP PL. verified it closed by the GREEN light indicating ON and the RED light indicating OFF. ____

4.4.9.3.6 Place in OFF and initiate Candidate verified administrative controls on administrative controls for EHS-MCC2E BKR5C for C002A DISCH MIN

_____8. FLOW VALVE by information provided in ____

EHS-MCC2E(2F) BKR 5C(7B),

C002A(B) DISCH MIN FLOW Initial Conditions.

4.4.9.4 VALVE IF Standby Service Water is No action required for this supplying service water loads, THEN conditional step. Normal Service 4.4.9.5 on H13-P870, verify closed SPC- NA Water is in service.

AOV16, SPC HX SW DISCH VLV.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: No action required. This is a Two Standby Service Water Pumps procedure note.

NA NOTE: are required in each loop when operating the Standby Service Water System for heat removal through the RHR Heat Exchangers.

On H13-P870, throttle open E12- Candidate located/identified E12-F068A and Note that valve control switch and F068A(B), RHR HX A(B) SVCE throttled open the valve to establish less than or flow indicator are on different WTR RTN to establish less than or equal to 5800 gpm as indicated on H13-P601, panels and may require the

• _____9. E12-R602A.

equal to 5800 gpm flow as indicated candidate to make several trips 4.4.9.6 on H13-P601, E12-R602A(B), RHR across the room to accomplish this HX A(B) SVCE WTR FLOW. step.

Candidate verified step 4.4.2 complete by EVALUATOR CUE: When requesting the status of Electrical Maintenance Verify Step 4.4.2 has been performed. PM Task to re-land the thermal overload/loss of requested, as Electrical

_____10. Maintenance, notify the power annunciator leads for E12-F009, RHR candidate that the thermal SHUTDOWN COOLING INBD ISOL VALVE.

4.4.9.7 overload/loss of power annunciator lead for E12-F009 has been re-landed.

At H13-P601, depress B21H- Candidate located/identified AND depressed

_____11. B21H-S32(33) OUTBD(INBD) ISOLATION S32(33), OUTBD(INBD)

ISOLATION SEAL-IN RESET SEAL-IN RESET PUSHBUTTON on H13-P601.

4.4.9.8 Pushbutton.

_____12. At H13-P601, check RHR Candidate located/ identified and verified the ISOLATION Status Lights are ON RHR ISOLATION Status Lights are ON for 4.4.9.9 for E12-F008 and E12-F009. E12-F008 and E12-F009 on H13-P601.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS In the Div 1 RSS Room at C61- Candidate verified E12-MOVF008 EVALUATOR CUE: When PNL001, verify E12-MOVF008 ENABLE/DISABLE Switch is in ENABLE by requested, as Control Building

_____13. ENABLE/DISABLE Switch is in contacting the Control Building operation to operator, notify the candidate ENABLE. request status.

that E12-MOVF008 4.4.9.10 ENABLE/DISABLE switch in ENABLE.

CAUTION: No action required. This is a Opening the Shutdown Cooling procedure caution.

Isolation Valves with portions of the RHR piping empty, a significant NA CAUTION lowering in reactor level can occur.

Do not open the Shutdown Cooling Isolation Valves unless the RHR piping including suction lines is completely filled.

Verify open the following: NA No action required. Actions follow 4.4.9.11 below.

E12-F010, RHR SDC MAN ISOL Candidate located/identified and verified

_____14. VLV E12-F010 open by checking RED indicating light ON and GREEN indicating light OFF.

4.4.9.11.1

_____15. E12-F009, RHR SHUTDOWN Candidate located/identified and verified COOLING INBD ISOL VALVE E12-F009 open by checking RED indicating light 4.4.9.11.2 ON and GREEN indicating light OFF.

_____16. E12-F008, RHR SHUTDOWN Candidate located/identified and verified COOLING OUTBD ISOL VALVE E12-F008 open by checking RED indicating light 4.4.9.11.3 ON and GREEN indicating light OFF.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS

_____17. E12-F006A(B), RHR PUMP A(B) Candidate located/identified and verified SDC SUCTION VALVE E12-F006A open by checking RED indicating 4.4.9.11.4 light ON and GREEN indicating light OFF.

_____18. E12-F047A(B), RHR A(B) HX Candidate located/identified and verified INLET VALVE E12-F0047A open by checking RED indicating 4.4.9.11.5 light ON and GREEN indicating light OFF.

Verify open one of the following: Candidate recognized that in Mode 4, the only viable path is through E12-MOV-F053A.

• E12-F053A(B), RHR PUMP A(B)

SDC INJECTION VALVE Candidate located/identified and opened E12-

• ___19. MOVF053A by holding the control switch in the NOTE:

OPEN position and by verifying the GREEN 4.4.9.12 Flow can be diverted to the refueling indicating light OFF and the RED indication light

& cavity sparger only if the Drywell and ON.

NOTE RPV heads are removed and in shutdown cooling

• E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST Close E12-F003A(B), RHR A(B) HX Candidate located/identified and closed

• ____20. OUTLET VALVE E12-F003A by placing the control switch in the CLOSE position and verifying the GREEN 4.4.9.13 incidating light ON and the RED indicating light OFF.

Verify the respective cubicle unit Candidate verified HVR-UC6 in service from cooler is in service initial conditions OR from indicating lights on

_____21.

H13-P870.

HVR-UC6 is indicated running by RED 4.4.9.14 indicating light ON and GREEN indicating light OFF.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS CAUTION: No action required. This is a Failure to establish greater than 1100 procedure caution.

gpm within 25 seconds of pump start may cause pump damage from NA CAUTION operation with less than minimum flow requirement. Do not allow more than 25 seconds to elapse before establishing greater than 1100 gpm NOTE: No action required. This is a The initiation of Shutdown Cooling procedure note.

with the reference leg backfill system NOTE out of service can result in more NA pronounced notching of indicated reactor level requiring reactor level trends to be monitored more closely.

Start E12-C002A(B), RHR PUMP Candidate located/identified and started E12- The following alarm will A(B) and IMMEDIATELY throttle C002A by placing the control switch to the annunciate and is expected for this open E12-F048A(B), RHR A(B) HX CLOSE position and verified RED indicating evolution:

BYPASS VALVE to obtain greater light ON and GREEN indicating light OFF.

• ____22.

than or equal to 2000 gpm and less AND

• H13-P680-19A-F07 4.4.9.15 than or equal to 3000 gpm.

Candidate located/identified and opened E12-F048A to obtain 2000-3000 gpm on E12-R603A RHR A LOOP FLOW meter.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 PERFORMANCE STEP STANDARD S/U COMMENTS Establish a stable flow of greater than

• ____23. or equal to 4000 gpm and less than or Candidate located/identified and continued to equal to 5000 gpm by throttling E12- open E12-F048A to obtain 4000-5000 gpm on 4.4.9.16 F048A(B), RHR A(B) HX BYPASS E12-R603A RHR A LOOP FLOW meter.

VALVE Throttle open E12-F003A(B), RHR Candidate located/identified and throttle open

• ____24. A(B) HX OUTLET VALVE to E12-F003A to approximately 10 percent as approximately 10 PERCENT as indicated on E12-R611A, HX A OUTLET VLV 4.4.9.17 indicated on E12-R611A(B), HX POS A(B) OUTLET VLV POS Terminating Cue: RHR A is operating in the Shutdown Cooling lineup in accordance with SOP-0031 Section 4.4.9 through 4.4.9.17.

RJPM-NRC12-S6

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^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC12-S6 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC12-S6 Page 15 of 16

RJPM-NRC12-S6 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The unit has been shutdown and is being depressurized for a refueling outage. The plant is currently in Mode 4. RHR A has been flushed and warmed for Shutdown Cooling operation. The system has been filled and vented.

E12-MOV64A is de-energized and Administrative controls are in place for EHS-MCC2E BKR 5C.

This valve has been field verified to be closed.

HVR-UC6 is in service.

Initiating Cues: The CRS has directed you to place RHR A in the Shutdown Cooling Mode in accordance with SOP-0031 Section 4.4.9 and continuing through 4.4.9.17.

RJPM-NRC12-S6 Page 16 of 16