|
|
| (5 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 11/15/2012 | | | issue date = 11/15/2012 |
| | title = RB 2012-11 Draft Operating Test | | | title = RB 2012-11 Draft Operating Test |
| | author name = Strickland D G | | | author name = Strickland D |
| | author affiliation = NRC/RGN-IV/DRS/OB | | | author affiliation = NRC/RGN-IV/DRS/OB |
| | addressee name = | | | addressee name = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:NRC Rev 1 Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 Op-Test No.: _______ | | {{#Wiki_filter:}} |
| 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 3 rd 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 No. Malf. No. Event Type* Event Description 1 NA N (CRS,BOP) Start Feedwater pump "C" lube oil system per SOP-0009. 2 NA N (CRS,ATC) Place 3 rd 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.
| |
| 6 p870_54a:g_5 FAIL ON C(CRS,BOP) Steam Packing Exhauster failure requiring equipment rotation.
| |
| 7 EHC001 RPS001A M (ALL) Main Turbine Trip/Anticipated Transient Without Scram with MSIVs open due to failure of RPS to completely de-energize. 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
| |
| | |
| NRC Rev 1 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 Applicant's 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.
| |
| NRC Rev 1 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 Point Event is terminated upon completion of SOP-0009 Section 4.1
| |
| | |
| NRC Rev 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1
| |
| __ Event No.: _2_ Page ___ of ___
| |
| | |
| Event
| |
| | |
| == Description:==
| |
| | |
| Place 3 rd Feedwater Regulating Valve in service per SOP-0009 Event Initiation: Initiated by crew.
| |
| CUE: Turnover item.
| |
| Time Position Applicant's Actions or Behavior CRS Direct the ATC to place the 3 rd Feedwater Regulating Valve in service accordance with SOP-0009 Section 4.11 BOP Place the 3 rd 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 Point Event is terminated when all 3 Feedwater Regulating Valves are in service.
| |
| | |
| NRC Rev 1 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 Applicant's 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 S ELECT 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 Point Event is terminated when Step 20 of the Reactivity Control Plan has been completed.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when CRS has applied Technical Specifications to the APRM failure and has given direction to bypass the APRM and reset the half scram.
| |
| NRC Rev 1 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 Applicant's 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 hour of inoperability, verify OPERABLE door (inner door) is CLOSED. Within 24 hours of inoperability, verify OPERABLE door (inner door) is LOCKED. Termination Point Event is terminated when the CRS has applied Technical Specifications to the airlock failure.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when the standby Steam Packing Exhauster has been placed in service and the previously running Steam Packing Exhauster has been secured.
| |
| | |
| NRC Rev 1 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 Applicant's 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 NRC Rev 1 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 NRC Rev 1 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 Point Event is terminated when Critical Tasks have been performed and the plant has been stabilized.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when ATC operator removes individual feedwater regulating valves from automatic Master control and controls them individually.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when alternate pressure control methods have been placed in service.
| |
| NRC Rev 1 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 No. Malf. No. Event Type* Event 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.
| |
| 3 CRDM2809 Uncoupled R(ATC) C(CRS) (Tech Spec) Control Rod Drop - Control Rod 28-09 4 CRD001A C (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 7 RCS007 E22MOV F004 BREAKER TRIP RCIC001 M (ALL) Coolant leak in the drywell with loss of power to E22-F004 and trip of RCIC 8 ED003H RHR009B RHR001C C (CRS,BOP) ENS-SWG1A bus loss, RHR B fails to auto start, E12-F042C injection valve fails. * (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.
| |
| | |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when HDL-P1B is in service and HDL-P1A is secured.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when HVC-FN1A is in service in accordance with STP-402-0201.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when control rod 28-09 has been fully inserted and Technical Specifications have been applied to the control rod failure.
| |
| NRC Rev 1 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 Applicant's 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 2 nd 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.
| |
| (1 st fault ~6 minutes after trip; 2 nd fault ~7 minutes after trip).
| |
| | |
| NRC Rev 1 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 Point Event is terminated when CRD Pump B has been placed in service and Control Rod Drive System parameters are returned to normal.
| |
| NRC Rev 1 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-A0 1 RX FW PUMP BREAKERS AUTO TRIP Time Position Applicant's 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 Point Event is terminated when the plant is stabilized following the trip of Feedwater Pump A.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Critical Tasks of Event 8 are met and critical plant parameters are stabilized.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Critical Tasks of Event 8 are met and critical plant parameters are stabilized.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Critical Tasks are met and critical plant parameters are stabilized.
| |
| NRC Rev 1 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 No. Malf. No. Event Type* Event Description 1 NA N (CRS,ATC) Remove Startup Feedwater Regulating Valve from Augmentation Mode and place in standby 2 NA N (CRS,BOP) Perform STP-204-6302 Section 7.1, RHR B Quarterly Surveillance. 3 NA R(ATC) Lower reactor power with Reactor Recirculation flow in accordance with the Reactivity Control Plan Step 1. 4 RHR002B C(CRS,BOP) (Tech Spec) RHR B trips 5 DI-CNM-HA68A-CAM C(CRS,ATC) Feedwater Pump "A" minimum flow valve fails open. 6 RCIC005 I(CRS,BOP) (Tech Spec) Inadvertent RCIC initiation.
| |
| 7 RCIC004 RCIC006 RPS001B M(ALL) 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.
| |
| 8 MSS008G MSS008D MSS008I C(CRS,BOP) Three Safety Relief Valves fail to energize when required for emergency depressurization. 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.
| |
| | |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when the Startup Feedwater Regulating Valve is removed from augmentation mode in accordance with SOP-0009 Section 5.4 NRC Rev 1 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 Applicant's 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 Point Event is terminated when RHR B is running at reference conditions in accordance with STP-204-6302.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Step 1 of the Reactivity Control Plan is complete with reactor power at 2967 MWth.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when the RHR line up has been restored to standby and Technical Specifications have been applied to the pump failure condition.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated the appropriate notifications have occurred and the minimum flow valve has been manually closed.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when RCIC has been tripped and Technical Specifications have been applied for the RCIC failure and tripped condition.
| |
| NRC Rev 1 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 Applicant's 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.
| |
| | |
| NRC Rev 1 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 NRC Rev 1 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 Point Event is terminated when the RPV has been depressurized and plant parameters are stable.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when additional SRVs have been opened to accomplish Emergency Depressurization.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when alternate Feedwater Regulating Valves have been placed in service and level control is established.
| |
| NRC Rev 1 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 No. Malf. No. Event Type*
| |
| Event 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 S pecification) 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 9 SWP-P2A BKR TRIP C(SRO,ATC) SWP-P2A pump breaker 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 NRC Rev 1 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 Applicant's 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.
| |
| NRC Rev 1 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 Point Event is terminated when Feedwater pump A is in service with its discharge valve open.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Reactivity Control Plan Step 80 is complete and reactor thermal power is ~ 2425 MWth.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when the Steam Seal Evaporator is being supplied by Extraction Steam.
| |
| | |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Technical Specifications have been applied to the failed radiation monitor.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when Technical Specifications have been applied to the failed electrical bus and RHR B & C after pump breakers are racked out.
| |
| | |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when reactor water level is stable and under manual control.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when plant parameters are stable and Critical Task of subsequent event is met.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when RCIC controller is placed in manual and RCIC is injecting to the RPV satisfying the Critical Task.
| |
| NRC Rev 1 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 Applicant's 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 Point Event is terminated when either the Division 1 Diesel Generator is tripped or cooling is provided from Division 2.
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A1 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A1 Page 2 of 9 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 5 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A1 RJPM-NRC12-A1 Page 3 of 9 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 RJPM-NRC12-A1 Page 4 of 9 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 RJPM-NRC12-A1
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 115 o F and rising Both Recirculation Pumps are tripped Initial SLC tank level is 3150 gal SLC pump 'A' was started at 1515 hours Initiating Cue: The Control Room Supervisor has directed you to determine the ta nk level at which the Hot Shutdown Boron weight has been inject ed and approximately what time this will occur, in accordance with OSP-0053, Attachment 13.
| |
| | |
| RJPM-NRC12-A1 RJPM-NRC12-A1
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 1. Using the Standby Liquid Control Injection Requirements table on page 2 of 2 of the Attachment 13 of OSP-0053, determine the tank level which must be reached to have injected Hot
| |
| | |
| Shutdown Boron weight into the core.
| |
| The candidate used 3100 gallons as a conservative value for tank level, The tank level for Hot Shutdown Boron weight is 2474 gals. Since the initial tank level is between the values on the chart
| |
| | |
| the Note at the top directs the
| |
| | |
| operator to use the smaller value
| |
| | |
| of 3100 gal as initial level.
| |
| *
| |
| : 2. Using the Standby Liquid Control Injection Requirements table on page 2 of 2 of Attachment 13 of OSP-0053, determine the time when Hot
| |
| | |
| Shutdown Boron weight will be
| |
| | |
| injected.
| |
| The candidate identified that Hot Shutdown Boron should be injected in 16 minutes, therefore the time will be 1531 hours when Hot Shutdown Boron Weight is 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 RJPM-NRC12-A1 Page 7 of 9 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 RJPM-NRC12-A1 Page 8 of 9 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 RJPM-NRC12-A1 Page 9 of 9 JPM Task Conditions/Cues (Operator Copy)
| |
| 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 115 o F and rising Both Recirculation Pumps are tripped Initial SLC tank level is 3150 gal SLC pump 'A' was started at 1515 hours Initiating Cues: 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, 3.
| |
| Tank Level for Hot Shutdown Boron Weight:
| |
| | |
| _______________
| |
| | |
| Approximate time at which Hot Shutdown Boron Weight is
| |
| | |
| injected: ______________
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A2 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A2 Page 2 of 9 TASK DESCRIPTION: Determining maintenance requirements to maintain an active license. TASK
| |
| | |
| ==REFERENCE:==
| |
| Admin K/A REFERENCE & RATING: 2.1.4 3.3 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 5 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A2 RJPM-NRC12-A2 Page 3 of 9 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 RJPM-NRC12-A2 Page 4 of 9 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 RJPM-NRC12-A2
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 A t the Controls (ATC) watch station on July 5 th. The shift history of office staff individuals is shown below. All other days not shown were worked in office staff positions working 8 hour days.
| |
| Initiating Cue:
| |
| Review the work history of the staff personnel below and determin e which individual(s) are proficient and can cover the ATC wat ch on July 5, 2012. Record your answer in the space provided. Operator 1 Operator 2 Operator 3 Operator 1 was proficient in the 1 st quarter of 2012 Operator 2 was NOT proficient in the 1 st quarter of 2012 Operator 2 was proficient in the 1 st quarter of 2012 Work History Work History Work History 4/10/12 - ATC 0600-1800 4/9/2012 - ATC under instruction 0600-1800 5/8/12 - ATC 0600-1800 4/20/12 - Unit 1800-0600 4/10/12 - Unit under instruction 0600-1800 5/16/12 - Unit 0600-1800 5/6/12 - Unit 0600-1800 4/11/12 - ATC under instruction 0600-1800 5/31/12 - Control Building 0600-1800 6/17/12 ATC 0600-1800 4/12/12 - Conducted a 4 hour plant tour under the instruction of a licensed operator
| |
| | |
| 0600-1000 6/7/12 - ATC 1800-0600 6/28/12 - Tagging Official 0600-1800 6/30/12 Unit 0600-1800 RJPM-NRC12-A2 RJPM-NRC12-A2
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1. Determine eligibility of Operator 1 to work July 5, 2012 to fill At the
| |
| | |
| Controls watch.
| |
| Candidate recognized that Operator 1 will not be proficient on July 5, 2012 because he will not
| |
| | |
| have had 5 12 hour proficiency watches in the
| |
| | |
| second quarter due to the Tagging Official
| |
| | |
| position not being an acceptable position to maintain license proficiency.
| |
| : 2. Determine eligibility of Operator 2 to work July 5, 2012 to fill At the
| |
| | |
| Controls watch.
| |
| Candidate recognized that Operator 2 will be proficient and can stand the ATC watch on July
| |
| | |
| 5, 2012.
| |
| : 3. Determine eligibility of Operator 3 to work July 5, 2012 to fill At the
| |
| | |
| Controls watch.
| |
| Candidate recognized that Operator1 3 will not be proficient on July 5, 2012 because he will not
| |
| | |
| have had 5 12 hour proficiency watches in the
| |
| | |
| second quarter due to the Control Building
| |
| | |
| position not being an acceptable position to maintain license proficiency.
| |
| * 4. Record Operator 2 on the Operator Cue Sheet.
| |
| Candidate recorded "Operator #2" as the available candidate to cover the July 5, 2012
| |
| | |
| ATC watch.
| |
| Terminating Cue:
| |
| Answer recorded on Answer Sheet.
| |
| RJPM-NRC12-A2 RJPM-NRC12-A2 Page 7 of 9 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 RJPM-NRC12-A2 Page 8 of 9 ANSWER KEY:
| |
| | |
| The July 5 th ATC watch may be covered by Operator(s) # 2
| |
| | |
| RJPM-NRC12-A2 RJPM-NRC12-A2 Page 9 of 9 JPM Task Conditions/Cues (Operator Copy)
| |
| 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 5 th. The shift history of office staff individuals is shown below. All other days not shown were worked in
| |
| | |
| office staff positions working 8 hour 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 1 st quarter of 2012 Operator 2 was NOT proficient in the 1 st quarter of 2012 Operator 2 was proficient in the 1 st quarter of 2012 Work History Work History Work History 4/10/12 - ATC 0600-1800 4/9/2012 - ATC under instruction 0600-1800 5/8/12 - ATC 0600-1800 4/20/12 - Unit 1800-0600 4/10/12 - Unit under instruction 0600-1800 5/16/12 - Unit 0600-1800 5/6/12 - Unit 0600-1800 4/11/12 - ATC under instruction 0600-1800 5/31/12 - Control Building 0600-1800 6/17/12 ATC 0600-1800 4/12/12 - Conducted a 4 hour plant tour under the instruction of a licensed operator
| |
| | |
| 0600-1000 6/7/12 - ATC 1800-0600 6/28/12 - Tagging Official 0600-1800 6/30/12 Unit 0600-1800
| |
| | |
| The July 5 th ATC watch may be covered by Operator(s) #
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A3 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A3 Page 2 of 9 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 15 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A3 RJPM-NRC12-A3 Page 3 of 9 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 RJPM-NRC12-A3 Page 4 of 9 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 RJPM-NRC12-A3
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, and you should inform me when you have completed this task.
| |
| Initial Conditions:
| |
| Electrical Maintenance is conducting Work Order to replace the so lenoid 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 t o 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 RJPM-NRC12-A3
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 1. Using ESK-7HVF01 & ESK-7HVF02 determine damper fail position. 1. The candidate determined that HVF-AOD20A fails OPEN when de-energized
| |
| * 2. Using ESK-7HVF01 & ESK-7HVF02 determine other component(s) positions affected by the fuse removal.2. The candidate determined that HVF-AOD31A also fails OPEN when the fuse is removed.
| |
| * 3. Using ESK-7 ESK-7HVF01 & ESK-7HVF02, determine impact of fuse removal on Control Room indication and alarm status. 3. The candidate identified that fuse removal will also cause the following on P863:
| |
| Must have the four of the six items correct to 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. 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 RJPM-NRC12-A3
| |
| * Denotes Critical Step Page 7 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| 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 RJPM-NRC12-A3 Page 8 of 9 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 RJPM-NRC12-A3 Page 9 of 9 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.
| |
| Initiating Cues: 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 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A4 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A4 Page 2 of 9 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 5 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A4 RJPM-NRC12-A4 Page 3 of 9 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 RJPM-NRC12-A4 Page 4 of 9 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 RJPM-NRC12-A4
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 Techni cian 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 RJPM-NRC12-A4
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1. Review maps and determine where the highest contamination level is located. Candidate reviewed both maps and determined that the highest contamination level is <1000 dpm
| |
| | |
| / 100 cm 2 2. Based on contamination levels determine whether or not protective
| |
| | |
| clothing is required.
| |
| Candidate recognized that the area is not contaminated therefore protective clothing is not
| |
| | |
| required.
| |
| : 3. Review maps and determine the value of the highest general area dose rates. Candidate reviewed both maps and determined that the highest general area dose rate is 110mR/hr.
| |
| 4.. Review maps and determine location of highest general area dose rates. Candidate reviewed both maps and determined that the highest general area dose rate is in the "A" SJAE Room on the north side of the SJAE.
| |
| : 5. Review maps and determine the value of the highest contact dose rates. Candidate reviewed both maps and determined that the highest general area dose rate is 150 mR/hr.
| |
| : 6. Review maps and determine location of highest contact dose rates. Candidate reviewed both maps and determined that the highest contact dose rate is in the "A" SJAE Room on the north side of the SJAE.
| |
| * 7. Complete answer sheet. Candidate correctly annotated the above information on the answer sheet.
| |
| Terminating Cue:
| |
| Answer recorded on Answer Sheet.
| |
| RJPM-NRC12-A4 RJPM-NRC12-A4 Page 7 of 9 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 RJPM-NRC12-A4 Page 8 of 9 ANSWER KEY:
| |
| : 1. What is the highest contamination level in either of the rooms? <1000 dpm / 100 cm 2 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 RJPM-NRC12-A4 Page 9 of 9 JPM Task Conditions/Cues (Operator Copy)
| |
| 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 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).
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-A5 Revision: 0 Page 1 of 10 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 RJPM-NRC12-A5 Page 2 of 10 TASK DESCRIPTION:
| |
| GENERATE A MANUAL LCO TRACKING SHEET TASK
| |
| | |
| ==REFERENCE:==
| |
| | |
| 300061003002 K/A REFERENCE & RATING: Generic 2.1.18 3.8 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 20 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A5 RJPM-NRC12-A5 Page 3 of 10 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 RJPM-NRC12-A5 Page 4 of 10 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 RJPM-NRC12-A5
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 tak e 12 hours 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-004 0 for the current Condition and Required Actions as well as any subseque nt Conditions expected during the next 12 hours. The next ava ilable LCO number is TS-12-C85-001.
| |
| RJPM-NRC12-A5 RJPM-NRC12-A5
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *
| |
| : 1. Complete OSP-0040 Attachment 2 for inoperable Main Turbine Bypass
| |
| | |
| Valves. LCO Status Sheet completed as indicated on JPM key. Only the highlighted data is required as critical.
| |
| | |
| Terminating Cue: LCO Status Sheet completed for inoperable Main Turbine Bypass Valves.
| |
| | |
| RJPM-NRC12-A5 RJPM-NRC12-A5 Page 7 of 10 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 RJPM-NRC12-A5 Page 8 of 10 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
| |
| | |
| == Description:==
| |
| Main Turbine Bypass Valve System 8 Applicable Modes:___1 ___2 ___3 ___4 ___ 5 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 System inoperable.
| |
| A.2 Apply the APLHGR, LHGR and MCPR limits for inoperable Main Turbine Bypass System as specified in the COLR..
| |
| Required by:
| |
| Date: 11/15/2012 Time: 1130 Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| B. Required Action and associated Completion Time not met. (This line optional)
| |
| B.1. Reduce THERMAL POWER to 23.8% RTP.
| |
| Required by:
| |
| Date: 11/15/2012
| |
| | |
| Time: 1330 Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ____________________
| |
| ________________________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| __________________
| |
| Required by:
| |
| Date:_ ______
| |
| | |
| Time:____ Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| 13 LCO 3.0.6 ENTERED
| |
| | |
| NA 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 RJPM-NRC12-A5 Page 9 of 10 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 hours 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 hours. The next available LCO number is TS C85-001.
| |
| RJPM-NRC12-A5 RJPM-NRC12-A5 Page 10 of 10 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.:______
| |
| Description_______________________________
| |
| | |
| _________________________________________
| |
| 8 Applicable Modes:___1 ___2 ___3 ___4 ___5 Other_____________________________________
| |
| | |
| _________________________________________ 9 CONDITION INITIATING LCO: Scheduled Outage______ Equipment Failure_____
| |
| | |
| 10 Condition 11 Required Action 12 Completion Time
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| ________________________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| Required by:
| |
| Date:___/___/___
| |
| | |
| Time:__________ Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| ________________________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| Required by:
| |
| Date:___/___/___
| |
| | |
| Time:__________ Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| ________________________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| Required by:
| |
| Date:___/___/___
| |
| | |
| Time:__________ Completed:
| |
| Date:___/___/___
| |
| Time:__________
| |
| | |
| Initials:_________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| | |
| ________________________
| |
| ________________________
| |
| ________________________
| |
| | |
| ________________________
| |
| | |
| _______________________
| |
| Required by:
| |
| Date:___/___/___
| |
| | |
| Time:__________ Completed:
| |
| Date:___/___/___
| |
| 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:
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A6 Revision: 0 Page 1 of 10 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 RJPM-NRC12-A6 Page 2 of 10 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 20 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A6 RJPM-NRC12-A6 Page 3 of 10 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 RJPM-NRC12-A6 Page 4 of 10 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 RJPM-NRC12-A6
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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' wa s 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 RJPM-NRC12-A6
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 1. Using Attachment 1 determine the Safety level for Shutdown Cooling
| |
| | |
| Function Color State The candidate using Attachment 1 determined that Med Decay Heat/ Not Flooded Up With only
| |
| | |
| RHR A&B available, ADHR is not available places the plant in YELLOW (TS)
| |
| * 2. Using Attachment 2 determine the Safety level for Inventory Control
| |
| | |
| Function Color State The candidate using Attachment 2 determined that RHR A&B and LPCS available therefore 3
| |
| | |
| ECCS trains are available and >23' above the flange status is still GREEN
| |
| * 3. Using Attachment 6 determine the Safety level for Fuel Building
| |
| | |
| Ventilation Function Color State Candidate recognized that previous shift the color was Green indicating that 2 HVF Trains were available, with no fuel movement in progress the color remains GREEN
| |
| * 4. Using the Color State from the Key Shutdown Function Areas Determine
| |
| | |
| the Overall Risk The candidate selected the most conservative Overall Status color of YELLOW in accordance
| |
| | |
| with step 3.12 of OSP-0037.
| |
| Terminating Cue:
| |
| OSP-0037, Shutdown Operations Protection Plan (SOPP) status sheet completed.
| |
| RJPM-NRC12-A6 RJPM-NRC12-A6 Page 7 of 10 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 RJPM-NRC12-A6 Page 8 of 10 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 RJPM-NRC12-A6 Page 9 of 10 JPM Task Conditions/Cues (Operator Copy)
| |
| Initial Conditions: RBS is at day 25 of a Refueling Outage. 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 Cues: The individual who was completing the Plant Safety Index 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 RJPM-NRC12-A6 Page 10 of 10 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 ____________
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A7 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A7 Page 2 of 9 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 20 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| Yes RJPM-NRC12-A7 RJPM-NRC12-A7 Page 3 of 9 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 RJPM-NRC12-A7 Page 4 of 9 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 RJPM-NRC12-A7
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 RJPM-NRC12-A7
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 1. Review completed performance of STP-000-0102 The candidate reviewed the procedure and did 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)
| |
| 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 RJPM-NRC12-A7 Page 7 of 9 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 RJPM-NRC12-A7 Page 8 of 9 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 RJPM-NRC12-A7 Page 9 of 9 JPM Task Conditions/Cues (Operator Copy)
| |
| 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 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-A8 Revision: 0 Page 1 of 9 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 RJPM-NRC12-A8 Page 2 of 9 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 20 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A8 RJPM-NRC12-A8 Page 3 of 9 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 RJPM-NRC12-A8 Page 4 of 9 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 RJPM-NRC12-A8
| |
| * Denotes Critical Step Page 5 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 o ccurred, 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 operator's year to date dose is 780 mRem.
| |
| Initiating Cue: As the CRS, review the radiological information for the specific tasks and the operator's 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 adm inistration dose limit.
| |
| | |
| RJPM-NRC12-A8 RJPM-NRC12-A8
| |
| * Denotes Critical Step Page 6 of 9 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1. Review the radiological information for the specific tasks and the
| |
| | |
| operator's year to date dose. Candidate determined that the operator may receive 1220 mR to complete all tasks and not exceed site administrative limits. (2000mR-780mR=1220mR)
| |
| : 2. Determine dose received from Task #1Candidate determined that the dose received from Task #1 is 500 mRem
| |
| : 3. Determine dose received from Task #2Candidate determined that the dose received from Task #2 is 500 mRem
| |
| * 4. Determine maximum permissible stay time during performance of Task #3. Candidate determined that the maximum 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 RJPM-NRC12-A8 Page 7 of 9 ANSWER KEY
| |
| | |
| Maximum Permissible Stay Time in the RWCU Pump Room 13-15 minutes RJPM-NRC12-A8 RJPM-NRC12-A8 Page 8 of 9 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 RJPM-NRC12-A8 Page 9 of 9 JPM Task Conditions/Cues (Operator Copy)
| |
| 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 operator's year to date dose is 780 mRem.
| |
| Initiating Cues: As the CRS, review the radiological information for the specific tasks and the operator's 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 Number Task Description Time to complete task Dose Rate 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 manual valves if necessary ? 900 mRem
| |
| | |
| Maximum Permissible Stay Time in the RWCU Pump Room
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-A9 Revision: 0 Page 1 of 11 TIME CRITICAL 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 RJPM-NRC12-A9 Page 2 of 11 TASK DESCRIPTION:
| |
| CLASSIFY AN EMERGENCY TASK
| |
| | |
| ==REFERENCE:==
| |
| | |
| 301001005003 K/A REFERENCE & RATING: 2.4.41 4.6 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator Classroom X COMPLETION TIME: 15 min. MAX TIME: 15 min JOB LEVEL:
| |
| SRO TIME CRITICAL:
| |
| Yes EIP CLASSIFICATION REQUIRED:
| |
| Yes PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-A9 RJPM-NRC12-A9 Page 3 of 11 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 RJPM-NRC12-A9 Page 4 of 11 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 RJPM-NRC12-A9
| |
| * Denotes Critical Step Page 5 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 a ll 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 RJPM-NRC12-A9
| |
| * Denotes Critical Step Page 6 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *
| |
| : 1. Consult EIP-2-001 Classification of Emergencies for this event Candidate classified the event as an ALERT (SA--3).
| |
| : 2. Complete the notification short form Candidate completed the Short Notification 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 RJPM-NRC12-A9
| |
| * Denotes Critical Step Page 7 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| ANSWER KEY The ALERT form is the 3 rd of the 4 forms provided.
| |
| Notification of Alert Time/Date: Current Message:1 This is River Bend Station An Alert was declared at Current time on Current date for 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 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 RJPM-NRC12-A9 Page 8 of 11 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 RJPM-NRC12-A9 Page 9 of 11 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 RJPM-NRC12-A9 Page 10 of 11 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 RJPM-NRC12-A9 Page 11 of 11 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:
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-C1 Revision: 00 Page 1 of 10 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 RJPM-NRC12-C1 Page 2 of 10 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 Simulate Performance X Actual Performance TESTING METHOD:
| |
| Control Room X Simulator In-Plant COMPLETION TIME:
| |
| 15 MINUTES.
| |
| MAX TIME:
| |
| 30 MINUTES JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| NO EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No SAFETY FUNCTION 6
| |
| RJPM-NRC12-C1 RJPM-NRC12-C1 Page 3 of 10 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 RJPM-NRC12-C1 Page 4 of 10 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 RJPM-NRC12-C1
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 cond ition.
| |
| RJPM-NRC12-C1 RJPM-NRC12-C1
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1. 5.3 Dispatch an operator to H13-P630 and H13-P850 to ascertain the status of the
| |
| | |
| power supplies as indicated by the 24
| |
| | |
| VDC and 125 VDC power available
| |
| | |
| lights. Candidate located H13-P630 and observed the status of the 24 VDC and 125 VDC power
| |
| | |
| available lights.
| |
| | |
| Candidate located H13-P850 and observed the status of the 24 VDC and 125 VDC power
| |
| | |
| available lights.
| |
| | |
| EVALUATOR CUE:
| |
| When the candidate has located the power available lights in H13-
| |
| | |
| P630, notify the candidate that
| |
| | |
| all lights are extinguished.
| |
| Note: There are a total of 4 sets of power supply lights in H13-P630.
| |
| | |
| Three power supplies are behind
| |
| | |
| the right side door, and one behind
| |
| | |
| the middle door.
| |
| 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 RJPM-NRC12-C1
| |
| * Denotes Critical Step Page 7 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 2.
| |
| 5.3.1 IF all power supplies in either H13-P630 OR H13-P850 are observed to be deenergized, THEN dispatch an operator to Main Control Room north
| |
| | |
| end to check the following breakers: For H13-P630, BYS-PNL02B2 BKR 2 For H13-P850, BYS-PNL02B2 BKR 17 Candidate located, identified and verified BYS-PNL02B2 BKR 2 is in the ON position.
| |
| Candidate located, identified and verified BYS-PNL02B2 BKR 17 is in the ON position.
| |
| | |
| EVALUATOR CUE:
| |
| When the candidate has located BYS-
| |
| | |
| PNL02B2 BKR 2 notify the
| |
| | |
| candidate that the breaker is in
| |
| | |
| the ON position.
| |
| EVALUATOR CUE:
| |
| When the candidate has located BYS-
| |
| | |
| PNL02B2 BKR 17 notify the
| |
| | |
| candidate that the breaker is in
| |
| | |
| the ON position.
| |
| : 3.
| |
| 5.3.2 IF all power supplies in both H13-P630 AND H13-P850 are observed to be deenergized, THEN dispatch an operator to Normal Switchgear
| |
| | |
| Building 98 ft el. to check BYS-SWG01B BKR 528.
| |
| Candidate located, identified and verified the status of BYS-SWG01B BKR 528 EVALUATOR CUE:
| |
| When the candidate has located BYS-
| |
| | |
| SWG01B BKR 528 notify the
| |
| | |
| candidate the breaker is
| |
| | |
| OPEN.
| |
| * 4.
| |
| 5.3.3 IF any of the following breakers are found to be open, THEN close the applicable breakers:
| |
| BYS-PNL02B2 BKR 2
| |
| | |
| BYS-PNL02B2 BKR 17 BYS-SWG01B BKR 528 Candidate located, identified and simulated closing BYS-SWG01B BKR 528 by simulating movement of the breaker handle downward and
| |
| | |
| then back up to close the breaker.
| |
| EVALUATOR CUE:
| |
| After candidate has simulated
| |
| | |
| closing the BWS-SWG01B
| |
| | |
| BKR 528, notify the candidate
| |
| | |
| that the breaker indication
| |
| | |
| indicates the breaker is
| |
| | |
| CLOSED.
| |
| RJPM-NRC12-C1 RJPM-NRC12-C1
| |
| * Denotes Critical Step Page 8 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 5.
| |
| 5.3.4 IF a breaker was closed in Step 5.3.3 AND the breaker trips open, THEN
| |
| | |
| contact Electrical Maintenance for assistance before attempting another
| |
| | |
| closure. Candidate took no further action.
| |
| NA No action required by this step due to the breaker remaining
| |
| | |
| closed in the previous step.
| |
| Terminating Cue: BYS-SWG01B has been closed (simulated) restoring power to control room annunciators.
| |
| | |
| RJPM-NRC12-C1 RJPM-NRC12-C1 Page 9 of 10 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 RJPM-NRC12-C1 Page 10 of 10 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-C2 Revision: 00 Page 1 of 15 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 RJPM-NRC12-C2 Page 2 of 15 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 Simulate Performance X Actual Performance TESTING METHOD:
| |
| Control Room X Simulator In-Plant COMPLETION TIME: 20 minutes MAX TIME: 40 minutes JOB LEVEL:
| |
| SRO/RO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No SAFETY FUNCTION 7
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2 Page 3 of 15 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 RJPM-NRC12-C2 Page 4 of 15 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 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 5 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 ma y 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 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 6 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS NOTE NOTE: All switches, status lights, test connections, and adjustments are to be made at H13-P670, APRM B unless
| |
| | |
| otherwise noted NA No action required. This is a procedure note.
| |
| 7.13 Channel Functional Test for APRM B NA No action performed in this step. ____1.
| |
| 7.13.1 Notify NCO, commencing surveillance testing of APRM B Candidate notified the NCO of commencement of APRM B testing.
| |
| ____ EVALUATOR CUE
| |
| : As NCO, acknowledge report of
| |
| | |
| commencement of APRM B
| |
| | |
| testing. *___2.
| |
| 7.13.2 At H13-P680, place APRM B in BYPASS Candidate located/identified the joystick on H13-P680 and simulated placing it in the APRM
| |
| | |
| B position.
| |
| ____ EVALUATOR CUE
| |
| : If requested, notify candidate that the BYPASS light below the full core
| |
| | |
| display for APRM B is
| |
| | |
| illuminated.
| |
| NOTE During Mode 1 operation, experience shows that usually, only APRM C and G
| |
| | |
| will bring in an annunciator, SRM Upscale Alarm or Inop NA No action required. This is a procedure note.
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 7 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| ____3.
| |
| 7.13.3 Inform the NCO that performance of Step 7.13.6 enables IRM Annunciator
| |
| | |
| circuitry, therefore if conditions do exist, the following Annunciators will alarm: Annunciator, P680-06A-A10, IRM UPSCALE TRIP OR INOP RPS CHAN B Annunciator, P680-06A-C10, IRM UPSCALE Candidate notified the NCO that the annunciators listed in the Performance Step may alarm.
| |
| ____ EVALUATOR CUE
| |
| : As NCO acknowledge report of potential
| |
| | |
| annunciators.
| |
| *____4.
| |
| 7.13.4 Place MODE Switch to PWR FLOW TEST Candidate located/identified the MODE Switch and simulated placing it in the PWR FLOW
| |
| | |
| TEST position.
| |
| ____ EVALUATOR CUE:
| |
| After candidate located/identified and
| |
| | |
| simulated placing the Mode Switch in the PWR FLOW
| |
| | |
| TEST position, notify him that the switch is in the PWR FLOW
| |
| | |
| TEST position.
| |
| ____5.
| |
| 7.13.5 Verify METER FUNCTION Switch is in AVERAGE Candidate located/identified the METER FUNCTION Switch and verified it in the
| |
| | |
| AVERAGE position.
| |
| ____ EVALUATOR CUE
| |
| : After candidate located/identified the METER FUNCTION switch, notify the candidate that the METER FUNCTION switch is
| |
| | |
| in the AVERAGE position.
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 8 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| CAUTION IF the Bypass Pushbutton is depressed, the APRM will come out of bypass, and may cause a Half Scram
| |
| | |
| Robust Barriers shall be utilized to prevent depressing the Bypass
| |
| | |
| Pushbutton NA No action required. This is a procedure caution.
| |
| *____6.
| |
| 7.13.6 Depress and hold the SETDOWN TEST Pushbutton Candidate located/identified the SETDOWN TEST pushbutton, simulated depressing and simulated maintaining the pushbutton depressed.
| |
| ____ *____7.
| |
| 7.13.7 Adjust POWER Control for an indication of 8% power on the APRM Front Panel
| |
| | |
| Meter Candidate has located/identified the POWER Control and simulated adjusting to obtain a
| |
| | |
| reading of 8% power on the APRM Front Panel
| |
| | |
| Meter ____ EVALUATOR CUE:
| |
| After the candidate has simulated
| |
| | |
| adjustment of the POWER
| |
| | |
| Control, notify him that the
| |
| | |
| APRM B Front Panel Meter indicates 8%.
| |
| ____8.
| |
| 7.13.8 Momentarily press the Trip Reset Pushbutton Candidate has located/identified the Trip Reset pushbutton and simulated momentarily
| |
| | |
| depressing the button.
| |
| ____ ____9.
| |
| 7.13.9 Verify Status Light UPSCALE ALARM is OFF Candidate has located/identified the UPSCALE ALARM and verified it is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After candidate has located the
| |
| | |
| UPSCALE ALARM light, notify
| |
| | |
| him that the light is OFF.
| |
| NOTE NOTE: Expected Trip Value = 12%
| |
| NA No action required. This is a procedure note.
| |
| *___10.
| |
| 7.13.10 Adjust Power Control until Status Light UPSCALE ALARM, just comes on Candidate has located/identified the POWER Control and simulated adjusting until the UPSCALE ALARM light comes on and then stops the simulated adjustment.
| |
| ____ EVALUATOR CUE:
| |
| After the candidates begins the simulated
| |
| | |
| adjustment, notify the candidate
| |
| | |
| that the UPSCALE ALARM
| |
| | |
| light is ON.
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 9 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| NOTE NOTE: Check that the alarm came in due to Setdown limits being in effect NA No action required. This is a procedure note.
| |
| *___11.
| |
| 7.13.11 Check UPSCALE ALARM came on before 15% on the Front Panel Meter Candidate has located/identified the APRM Front Panel Meter and verified that the UPSCALE ALARM light illuminated before 15%.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate locates the APRM
| |
| | |
| Front Panel Meter, notify him that the meter indicates 12%
| |
| ____12.
| |
| 7.13.12 Verify Status Light UPSCALE NEUTRON is OFF Candidate has located/identified the UPSCALE NEUTRON light and verified it is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate locates the UPSCALE
| |
| | |
| NEUTRON LIGHT notify him
| |
| | |
| that the light is OFF.
| |
| NOTE NOTE: Expected Trip Value = 15%.
| |
| NA No action required. This is a procedure note.
| |
| *___13.
| |
| 7.13.13 Raise Power Control until Status Light UPSCALE NEUTRON, just comes on Candidate has located/identified the POWER Control and simulated adjusting until the UPSCALE NEUTRON light comes on and then stops the simulated adjustment.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate begins the simulated
| |
| | |
| adjustment, notify the candidate
| |
| | |
| that the UPSCALE NEUTRON
| |
| | |
| light is ON.
| |
| *___14.
| |
| 7.13.14 Check UPSCALE NEUTRON came on before 20% on the Front Panel Meter Candidate has located/identified the APRM Front Panel Meter and verified that the UPSCALE NEUTRON light illuminated before 20%.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate locates the APRM
| |
| | |
| Front Panel Meter, notify him that the meter indicates 15%
| |
| ____15.
| |
| 7.13.15 Adjust Power Control for an indication of 8% on the Front Panel Meter Candidate has located/identified the POWER Control and simulated adjusting until the Front
| |
| | |
| Panel Meter indicates 8%.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate begins simulated adjustment of the Power
| |
| | |
| Control, notify the candidate
| |
| | |
| that the APRM Front Panel Meter indicates 8%.
| |
| ____16.
| |
| 7.13.16 Release the SETDOWN TEST Pushbutton Candidate has simulated release of the SETDOWN TEST pushbutton. ____
| |
| | |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 10 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| *___17.
| |
| 7.13.17 Momentarily press the Trip Reset Pushbutton Candidate simulated momentary depressing of the Trip Reset pushbutton. ____
| |
| ____18.
| |
| 7.13.18 Check Status Light UPSCALE ALARM is OFF Candidate has verified the UPSCALE ALARM light is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After candidate locates/identifies the
| |
| | |
| UPSCALE ALARM light, notify
| |
| | |
| him that the light is OFF.
| |
| ____19.
| |
| 7.13.19 Check Status Light UPSCALE NEUTRON is OFF Candidate has verified the UPSCALE NEUTRON light is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After candidate locates/identifies the
| |
| | |
| UPSCALE NEUTRON light, notify him that the light is OFF.
| |
| NOTE NOTE: All switches, status lights, test connections, and adjustments are to be made at H13-P670, APRM B unless
| |
| | |
| otherwise noted NA No action required. This is a procedure note.
| |
| 7.14 Restoration of APRM B NA No action performed in this step.
| |
| Actions follow below.
| |
| *___20.
| |
| 7.14.1 Place MODE Switch to OPERATE Candidate located/identified and simulated placing the switch to the OPERATE position.
| |
| ____ EVALUATOR CUE:
| |
| After candidate locates/identifies the MODE switch, notify him that it
| |
| | |
| is in the OPERATE position.
| |
| ____21.
| |
| 7.14.2 Momentarily press the Trip Reset Pushbutton Candidate located/identified and simulated momentarily depressing the Trip Reset
| |
| | |
| Pushbutton.
| |
| ____ 7.14.3 Verify the following:
| |
| NA No action performed in this step.
| |
| Actions follow below.
| |
| ____22.
| |
| 7.14.3.1 Status Light UPSCALE ALARM, is off Candidate located/identified and verified the UPSCALE ALARM light is off.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate located/identified the
| |
| | |
| UPSCALE ALARM light, notify
| |
| | |
| him that the light is OFF.
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 11 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| ____23.
| |
| 7.14.3.2 Status Light UPSCALE NEUTRON, is off Candidate located/identified and verified the UPSCALE NEUTRON light is off.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate located/identified the
| |
| | |
| UPSCALE NEUTRON light, notify him that the light is OFF.
| |
| ____24.
| |
| 7.14.3.3 Status Light UPSCL THERM TRIP, is off Candidate located/identified and verified the UPSCALE THERMAL TRIP light is off.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate located/identified the
| |
| | |
| UPSCALE THERMAL TRIP
| |
| | |
| light, notify him that the light is
| |
| | |
| OFF. ____25.
| |
| 7.14.3.4 Status Light INOP, is off Candidate located/identified and verified the INOP light is off.
| |
| ____ EVALUATOR CUE:
| |
| After the candidate located/identified the
| |
| | |
| INOP light, notify him that the
| |
| | |
| light is OFF.
| |
| ____26.
| |
| 7.14.4 Verify APRM B MODE Switch to OPERATE Candidate located/identified and verified the APRM B MODE Switch is in OPERATE.
| |
| ____ EVALUATOR CUE:
| |
| If requested by the candidate, perform the Independent
| |
| | |
| Verification steps at 7.14.4
| |
| *___27.
| |
| 7.14.5 At H13-P680, place C51B-S6, NEUTRON MONITOR BYPASS Switch
| |
| | |
| to the proper position for current plant
| |
| | |
| conditions Candidate located/identified the joystick on H13-P680 and simulated removing it from the APRM
| |
| | |
| B position and returning it to the center position.
| |
| ____ EVAULATOR CUE:
| |
| If requested as CRS, notify the
| |
| | |
| candidate the proper position
| |
| | |
| for APRM B for current plant
| |
| | |
| conditions is "Not Bypassed"
| |
| | |
| 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.
| |
| ____28.
| |
| 7.14.6 Check that no RPS Half-Scrams have occurred Candidate verified no RPS Half Scram occurred by verifying the RPS status lights on H13-P680 are illuminated OR by verifying the RPS status
| |
| | |
| lights on H13-P691, P692, P693 and P694 are illuminated.
| |
| ____ EVALUATOR CUE:
| |
| Notify candidate that no RPS Half
| |
| | |
| Scrams occurred.
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 12 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| ____29.
| |
| 7.14.7 Check that no single rod scrams have occurred Candidate verified no single rod scrams occurred.
| |
| ____ EVALUATOR CUE:
| |
| Notify candidate that no single rod
| |
| | |
| scrams occurred.
| |
| 7.14.8 Check the following NA No action performed in this step.
| |
| Actions follow below.
| |
| ____30.
| |
| 7.14.8.1 Status Light on H13-P680, BYPASS, is off. Candidate located/identified and verified that the Bypass lights for APRM B below the full core
| |
| | |
| display is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After candidate locates/identifies the Bypass light for APRM B below
| |
| | |
| the full core display, notify him
| |
| | |
| that the light is OFF.
| |
| ____31.
| |
| 7.14.8.2 Status Light on H13-P670, BYPASS for APRM B, is off Candidate located/identified and verified that the Bypass lights for APRM B at H13-P670 is OFF.
| |
| ____ EVALUATOR CUE:
| |
| After candidate locates/identifies the
| |
| | |
| Bypass light for APRM B at
| |
| | |
| H13-P670, notify him that the
| |
| | |
| light is OFF.
| |
| NOTE Check the APRM is functioning before going to another.
| |
| NA No action required. This is a procedure note.
| |
| 7.14.9 Perform the following NA No action performed in this step.
| |
| Actions follow below.
| |
| ____32.
| |
| 7.14.9.1 Verify METER FUNCTION Switch in AVERAGE Candidate located/identified the METER FUNCTION switch and verified it was in the
| |
| | |
| AVERAGE position.
| |
| ____ EVALUATOR CUE
| |
| : After candidate locates/identifies the METER FUNCTION switch notify him that the switch is in
| |
| | |
| the AVERAGE position.
| |
| ____33.
| |
| 7.14.9.2 Record instrument readings Candidate recorded the readings for APRM B &
| |
| F. ____ EVALUATOR CUE:
| |
| When the candidate locates the Front
| |
| | |
| Panel Meters for APRM B & F, notify him that the readings are:
| |
| APRM B 100%
| |
| APRM F 100%
| |
| RJPM-NRC12-C2 RJPM-NRC12-C2
| |
| * Denotes Critical Step Page 13 of 15 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| ____34.
| |
| 7.14.9.3 Check that instrument readings are within 12%. IF greater than 12%, THEN notify OSM/CRS Candidate recognized that the readings were within 12% and took no further action.
| |
| ____ ____35.
| |
| 7.14.10 Notify NCO that surveillance testing of APRM B is complete Candidate notified the NCO that surveillance testing of APRM B was completed.
| |
| | |
| Note: Candidate may state that they will return the Meter Function switch in accordance with OP
| |
| | |
| AID 2001-P-005. This is not required for satisfactory performance of this JPM.
| |
| ____ EVALUATOR CUE:
| |
| As NCO, acknowledge report of the
| |
| | |
| completion of APRM B testing.
| |
| 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 RJPM-NRC12-C2 Page 14 of 15 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 RJPM-NRC12-C2 Page 15 of 15 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) .
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-P1 Revision: 00 Page 1 of 10 TIME CRITICAL 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 RJPM-NRC12-P1 Page 2 of 10 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 Simulate Performance X Actual Performance TESTING METHOD:
| |
| Control Room Simulator In-Plant x COMPLETION TIME:
| |
| 10 MINUTES.
| |
| MAX TIME:
| |
| 10 MINUTES JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| YES EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No SAFETY FUNCTION 2
| |
| RJPM-NRC12-P1 RJPM-NRC12-P1 Page 3 of 10 SIMULATOR SETUP SHEET Task
| |
| | |
| == Description:==
| |
| NA Required Power: NA IC No.: NA Notes: NONE: This JPM is performed in the plant.
| |
| | |
| RJPM-NRC12-P1 RJPM-NRC12-P1 Page 4 of 10 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 RJPM-NRC12-P1
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 hav e 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 RJPM-NRC12-P1
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS WARNING WARNING Due to extreme differential pressure, 123 ft el access doors into the Aux Bldg may be a personnel hazard.
| |
| When operating conditions permit, Aux Bldg access should be from the
| |
| | |
| 95 ft el or 67 ft el.
| |
| N/A This is a procedure warning. No action required. These
| |
| | |
| conditions would be present
| |
| | |
| during an actual event, but not
| |
| | |
| expect during the examination
| |
| | |
| period. It is acceptable to use the
| |
| | |
| 123 ft el access during this
| |
| | |
| examination.
| |
| 5.8 WHEN directed by the CRS, THEN perform Steps 5.8.1 through 5.8.6 NA NOTE Steps 5.8.1 through 5.8.6, in addition to the RCIC lineup steps performed by
| |
| | |
| the ATC operator at the Div I RSS panel, are required to be completed 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. NA This is a procedure note. No action is required.
| |
| * 1.
| |
| | |
| ====5.8.1. Close====
| |
| EHS-MCC2L BKR 6AT, E51-SW63 BRKR 1 ALT DIV I PWR
| |
| | |
| E51-MOVF063 Candidate has located/identified EHS-MCC2L BKR 6AT and simulated placing the breaker
| |
| | |
| handle in the ON position.
| |
| ____
| |
| RJPM-NRC12-P1 RJPM-NRC12-P1
| |
| * Denotes Critical Step Page 7 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 2.
| |
| | |
| ====5.8.2 Close====
| |
| EHS-MCC2L BKR 6AB, E51-SW63 BRKR 2 ALT DIV I PWR
| |
| | |
| E51-MOVF063 Candidate has located/identified EHS-MCC2L BKR 6AB and simulated placing the breaker
| |
| | |
| handle in the ON position.
| |
| ____
| |
| * 3.
| |
| 5.8.3 Open EHS-MCC2D BKR 3C, RCIC
| |
| & RHR STEAM SUPPLY VALVE.
| |
| Candidate has located/identified EHS-MCC2D BKR 3C and simulated placing the breaker
| |
| | |
| handle in the OFF position.
| |
| ____
| |
| * 4.
| |
| 5.8.4 On wall to right side of EHS-MCC2D, close E51-SW63, DIV I ALT PWR
| |
| | |
| SUPPLY E51-MOVF063.
| |
| Candidate has located/identified E51-SW63 and simulated placing the switch in the CLOSED
| |
| | |
| position.
| |
| ____
| |
| * 5.
| |
| 5.8.5 On right side of EHS-MCC2D, place 43-1ICSA02, CONTROL XFER
| |
| | |
| E51-MOVF063 in ALTERNATE and
| |
| | |
| check the following:
| |
| Candidate has located/identified 43-1ICSA02 and simulated placing the switch in the ALTERNATE
| |
| | |
| position.
| |
| ____ 6.
| |
| 5.8.5 W2-1ICSA02, DIV I ALT CONTROL POWER E51-MOVF063 is illuminated.
| |
| Candidate has located/identified W2-1ICSA02 and verified light is illuminated.
| |
| ____ EXAMINER CUE:
| |
| Once the candidate has located W2-1ICSA02, notify him that the
| |
| | |
| light is ON.
| |
| : 7.
| |
| 5.8.5 W1-1ICSA02 NORMAL CONTROL POWER E51-MOVF063 is
| |
| | |
| extinguished Candidate has located/identified W1-1ICSA02
| |
| | |
| and verified light is extinguished.
| |
| ____ EXAMINER CUE:
| |
| Once the candidate has located W1-1ICSA02, notify him that the
| |
| | |
| light is OFF.
| |
| RJPM-NRC12-P1 RJPM-NRC12-P1
| |
| * Denotes Critical Step Page 8 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 8.
| |
| | |
| ====5.8.6 Inform====
| |
| ATC Operator that E51-MOVF063 has been transferred
| |
| | |
| to the Div I Alternate Power. The Div I Remote Shutdown Room number is
| |
| | |
| 2903 Candidate notifies the ATC operator that
| |
| | |
| E51-MOVF063 has been transferred to the Div I
| |
| | |
| Alternate Power.
| |
| ____ EXAMINER CUE:
| |
| Role Play: As ATC operator, accept information regarding
| |
| | |
| transfer of E51-MOVF063 to alternate power. Terminating Cue: E51-MOVF063 has been transferred to alternate power per AOP-0031 Section 5.8
| |
| | |
| COMPLETION TIME: __________
| |
| | |
| RJPM-NRC12-P1 RJPM-NRC12-P1 Page 9 of 10 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 RJPM-NRC12-P1 Page 10 of 10 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-P2 Revision: 0 Page 1 of 13 ALTERNATE PATH 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 RJPM-NRC12-P2 Page 2 of 13 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 Simulate Performance X Actual Performance TESTING METHOD:
| |
| Control Room Simulator In-Plant X COMPLETION TIME: 10 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| All TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| Yes ALTERNATE PATH (FAULTED):
| |
| Yes SAFETY FUNCTION:
| |
| 8 RJPM-NRC12-P2 RJPM-NRC12-P2 Page 3 of 13 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 RJPM-NRC12-P2 Page 4 of 13 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 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 5 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 fi re has occurred in the Auxiliary Boiler/Water Treatment Building. Attempts to start FPW-P1A, Diesel Fire Pump from the Auxiliary Control Room h ave 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 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 6 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS 4.2.2.1 At FPW-MST2, MOTOR DRIVEN
| |
| | |
| FIRE PUMP 2 CONTROLLER, depress START pushbutton to start FPW-P2, MOTOR DRIVEN FIRE
| |
| | |
| PUMP NA No action is required for this step.
| |
| The Initial Conditions indicated
| |
| | |
| that FPW-P2 was unavailable due to power supply damage
| |
| . NOTE The following pump start method is only to be used in an emergency
| |
| | |
| situation.
| |
| NA No action is required. This is a Procedure Note. In addition, the associated step is not required.
| |
| The Initial Conditions indicated
| |
| | |
| that FPW-P2 was unavailable due to power supply damage
| |
| . 4.2.2.2 IF Step 4.2.2.1 does not start FPW-P2, THEN lift the yellow MANUAL EMERGENCY START ONLY handle on FPW-P2, MOTOR DRIVEN FIRE
| |
| | |
| PUMP 2 CONTROLLER, and latch in
| |
| | |
| the raised position
| |
| | |
| NA No action is required for this step.
| |
| The Initial Conditions indicated
| |
| | |
| that FPW-P2 was unavailable due to power supply damage
| |
| . NOTE NOTE MANUAL 1 and MANUAL 2 correspond to manual starting with
| |
| | |
| Bank 1 or Bank 2 respectively.
| |
| | |
| NA No action is required. This is a Procedure Note
| |
| .
| |
| RJPM-NRC12-P2 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 7 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1.
| |
| 4.2.2.3 Place the selector switch on controller FPW-MST1A, DIESEL FIRE PUMP
| |
| | |
| 1A CONTROLLER in MANUAL 1 or
| |
| | |
| MANUAL 2.
| |
| | |
| Candidate has located/identified the proper controls, and simulated manipulation of the
| |
| | |
| selector switch to either MANUAL 1 or
| |
| | |
| MANUAL 2.
| |
| | |
| EVALUATOR CUE
| |
| : After the manipulation has been
| |
| | |
| simulated, notify performer that
| |
| | |
| the "Auto On" light has
| |
| | |
| extinguished.
| |
| 4.2.2.4 Place the selector switch on controller FPW-MST1B, DIESEL FIRE PUMP
| |
| | |
| 1B CONTROLLER in MANUAL 1 or
| |
| | |
| MANUAL 2 NA No action required. FPW-P1B was identified as being tagged out in
| |
| | |
| the initiating cue.
| |
| NOTE NOTE Limit the maximum number of start attempts to six.
| |
| | |
| Do not hold the START pushbutton for greater than 30 seconds.
| |
| | |
| NA No action is required. This is a Procedure Note. 2.
| |
| 4.2.2.5 Depress and hold local START
| |
| | |
| pushbutton for 15 seconds or until
| |
| | |
| engine starts for the following:
| |
| | |
| FPW-P1A, DIESEL DRIVEN FIRE PUMP A
| |
| | |
| Candidate has located/identified the proper controls, and simulated depressing and holding
| |
| | |
| the START pushbutton for 15 seconds
| |
| | |
| EVALUATOR CUE
| |
| : After the performer has simulated
| |
| | |
| depressing the START
| |
| | |
| pushbutton, notify the
| |
| | |
| performer that diesel fire pump
| |
| | |
| fails to crank.
| |
| ______3.
| |
| 4.2.2.6 IF FPW-P1A or FPW-P1B failed to attempt to start due to battery problems, THEN re-perform steps 4.2.2.3 through 4.2.2.5 with the battery
| |
| | |
| bank that was not used. ALTERNATE PATH Candidate has transitioned back to Step 4.2.2.3
| |
| ____
| |
| RJPM-NRC12-P2 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 8 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 4.
| |
| 4.2.2.3 Place the selector switch on controller FPW-MST1A, DIESEL FIRE PUMP
| |
| | |
| 1A CONTROLLER in MANUAL 1 or
| |
| | |
| MANUAL 2.
| |
| | |
| Candidate has located/identified the proper controls, and simulated manipulation of the
| |
| | |
| selector switch to the alternate position.
| |
| .
| |
| 4.2.2.4 Place the selector switch on controller FPW-MST1B, DIESEL FIRE PUMP
| |
| | |
| 1B CONTROLLER in MANUAL 1 or
| |
| | |
| MANUAL 2.
| |
| NA This step is not required. Fire Pump B is tagged out as stated in
| |
| | |
| the initial conditions.
| |
| NOTE NOTE Limit the maximum number of start attempts to six.
| |
| | |
| Do not hold the START pushbutton for greater than 30 seconds.
| |
| NA No action is required. This is a Procedure Note
| |
| . 5.
| |
| 4.2.2.5 Depress and hold local START
| |
| | |
| pushbutton for 15 seconds or until
| |
| | |
| engine starts for the following:
| |
| | |
| FPW-P1A, DIESEL DRIVEN FIRE PUMP A
| |
| | |
| Candidate has located/identified the proper controls, and simulated depressing and holding
| |
| | |
| the START pushbutton for 15 seconds
| |
| | |
| Candidate proceeded to 4.2.2.7
| |
| | |
| EVALUATOR CUE
| |
| : After the performer has simulated
| |
| | |
| depressing the START
| |
| | |
| pushbutton, notify the
| |
| | |
| performer that diesel fire pump
| |
| | |
| fails to crank.
| |
| : 6.
| |
| 4.2.2.7 IF an engine fails to start, THEN Go To Step 4.2.3.
| |
| ALTERNATE PATH Candidate transitions to Step 4.2.3.
| |
| ____
| |
| RJPM-NRC12-P2 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 9 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS NOTE NOTE In the following mode, all other means of stopping the Fire Protection Diesel
| |
| | |
| Engine are disabled, including
| |
| | |
| overspeed protection. The engine
| |
| | |
| continues to run until the Fuel
| |
| | |
| Solenoid Manual Knob is returned to
| |
| | |
| the OUT position.
| |
| | |
| NA No action is required. This is a Procedure Note
| |
| .
| |
| * 7.
| |
| 4.2.3.1 Open FPW-SOV19A,FUEL SUPPLY
| |
| | |
| SOLENOID by turning the knurled manual knob clockwise or IN to open
| |
| | |
| the solenoid.
| |
| | |
| Candidate has located/identified the Fuel Supply Solenoid and simulated turning the knob in the
| |
| | |
| clockwise direction.
| |
| | |
| EVALUATOR CUE
| |
| :Notify the performer that the knob has been rotated fully clockwise and
| |
| | |
| stopped. CAUTION Greater than 50 psig cooling water pressure can damage the Diesel Engine Cooling System. Do not exceed 50 psig cooling water pressure.
| |
| NA No action is required. This is a Procedure Caution.
| |
| * 8.
| |
| 4.2.3.2 Open FPW-V3009, FPW-P1A
| |
| | |
| ENGINE COOLING SYSTEM
| |
| | |
| BYPASS VALVE Candidate has located/identified FPW-V3009 and simulated opening the valve by turning the
| |
| | |
| handwheel in the counter-clockwise direction until handwheel motion stops.
| |
| EVALUATOR CUE
| |
| : Notify the performer that handwheel
| |
| | |
| motion has stopped and the valve stem now appears similar
| |
| | |
| to FPW-V176 (Located just below FPW-V3009)
| |
| * 9.
| |
| 4.2.3.3 Throttle open 2 turns FPW-V179, FPW-P1A ENGINE COOLING
| |
| | |
| SYSTEM BYPASS VALVE Candidate has located/identified FPW-V179 and simulated throttling the valve by turning the
| |
| | |
| handwheel in the counter-clockwise direction for
| |
| | |
| 2 turns.
| |
| EVALUATOR CUE
| |
| : If requested, notify the candidate
| |
| | |
| that FPW-PI27A indicates
| |
| | |
| similar to FPW-PI3A.
| |
| | |
| RJPM-NRC12-P2 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 10 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS 4.2.3.4 Engage the starter per the following:
| |
| NA No action required. Actions follow below. *____10.
| |
| 4.2.3.4.1 Raise the Lever on either of the two starter contactors. FPW-SRT1AA or FPW-SRT1AB, MANUAL START SWITCH "A" FOR PUMP FPW FPW-P1A Candidate has located/identified the starter manual lever and has simulated raising the lever.
| |
| | |
| EVALUATOR CUE
| |
| : After one of the levers has been raised, notify the performer that the
| |
| | |
| engine has started.
| |
| _____11.
| |
| | |
| 4.2.3.4.2
| |
| | |
| Release the Lever for FPW-SRT1AA(BA) or FPW-
| |
| | |
| SRT1AB(BB), MANUAL START SWITCH "A"(B) FOR PUMP FPW-
| |
| | |
| P1A(B) as soon as the engine starts.
| |
| | |
| Candidate has simulated release of the starter manual lever.
| |
| ____ 4.2.3.4.3 IF engine fails to start, THEN repeat steps 4.2.3.4.1 and 4.2.3.4.2 above
| |
| | |
| using the other starter contactor.
| |
| NA No action is required since the engine started in the previous step.
| |
| CAUTION Greater than 50 psig cooling water pressure can damage the Diesel Engine Cooling System. Do not exceed 50 psig cooling water pressure.
| |
| NA No action is required. This is a Procedure Caution.
| |
| | |
| RJPM-NRC12-P2 RJPM-NRC12-P2
| |
| * Denotes Critical Step Page 11 of 13 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *____12.
| |
| 4.2.3.4.4 Throttle open FPW-V179, FPW-P1A
| |
| | |
| ENGINE COOLING SYSTEM
| |
| | |
| BYPASS VALVE as needed to maintain cooling water pressure
| |
| | |
| greater than 40 psig but less than 50
| |
| | |
| psig Candidate located FPW-PI27A & FPW-V179 and turned the handwheel for FPW-V179 until FPW-
| |
| | |
| PI27A indicated >40 psig and < 50 psig.
| |
| | |
| EVALUATOR CUE
| |
| : Prior to manipulation of FPW-V179, FPW-PI27A indicates 32 psig.
| |
| | |
| After the candidate has
| |
| | |
| simulated manipulation of one additional turn of the handwheel 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 RJPM-NRC12-P2 Page 12 of 13 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 RJPM-NRC12-P2 Page 13 of 13 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 Initiating Cues: 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-P3 Revision: 00 Page 1 of 15 TIME CRITICAL 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 RJPM-NRC12-P3 Page 2 of 10 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 Simulate Performance X Actual Performance TESTING METHOD:
| |
| Control Room Simulator In-Plant X COMPLETION TIME: 5 minutes MAX TIME: 5 minutes JOB LEVEL:
| |
| SRO/RO TIME CRITICAL:
| |
| YES EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No RJPM-NRC12-P3 RJPM-NRC12-P3 Page 3 of 10 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 RJPM-NRC12-P3 Page 4 of 10 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 RJPM-NRC12-P3
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 ma y 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 RJPM-NRC12-P3
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS NOTE NOTE If CONTROL POWER MONITOR LIGHTS or LOCAL EMERGENCY
| |
| | |
| CONTROL ALIGNED LIGHTS are off, then continue the procedure until the RSS transfer is complete. The CRS determines when corrective actions can be performed. The Div 1 Remote Shutdown Room number is 2903.
| |
| NA This is a procedure note. No action is required. 5.7 IF a Control Room fire is in progress, THEN initiate a Reactor Scram and a full NSSSS Isolation by directing the ATC Operator to perform the following NA No action required in this step. NOTE If a Main Control Room fire is in progress, then Steps 5.7.1.1 and 5.7.1.2 shall be completed within 5 minutes of scramming the reactor.
| |
| NA This is a procedure note. No action is required.
| |
| ____1.
| |
| | |
| ====5.7.1 Proceed====
| |
| briskly to Control Bldg 116 ft el Div 1 Electrical Protection Assemblies area and perform the following:
| |
| Candidate has arrived at the Div 1 Electrical Protection Assemblies on the Control Building 116 ft el. ____
| |
| | |
| 5.7.1.1 At Control Bldg 116 ft el, place the following Div I Electrical Protection Assemblies in OFF:
| |
| NA Action is performed in bulleted steps below.
| |
| RJPM-NRC12-P3 RJPM-NRC12-P3
| |
| * Denotes Critical Step Page 7 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| *___2.
| |
| | |
| 5.7.1.1 1. C71-S003C Candidate has located/identified C71-S003C and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position.
| |
| *___3.
| |
| 5.7.1.1 2. C71-S003F Candidate has located/identified C71-S003F and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| *___4.
| |
| 5.7.1.1 3. C71-S003A Candidate has located/identified C71-S003A and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| *___5.
| |
| 5.7.1.1 4. C71-S003E Candidate has located/identified C71-S003E and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| | |
| 5.7.1.2 At Control Bldg 116 ft el, place the following Div II Electrical Protection Assemblies in OFF:
| |
| NA Action is performed in bulleted steps below.
| |
| * 6. 1. C71-S003H Candidate has located/identified C71-S003H and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| * 7. 2. C71-S003D Candidate has located/identified C71-S003D and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| | |
| RJPM-NRC12-P3 RJPM-NRC12-P3
| |
| * Denotes Critical Step Page 8 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| * 8. 3. C71-S003G Candidate has located/identified C71-S003G and simulated turning the switch counter clockwise to
| |
| | |
| the OFF position
| |
| * 9. 4. C71-S003B Candidate has located/identified C71-S003B and 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 RJPM-NRC12-P3 Page 9 of 10 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 RJPM-NRC12-P3 Page 10 of 10 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-S1 Revision: 00 Page 1 of 10 ALTERNATE PATH 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 RJPM-NRC12-S1 Page 2 of 10 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME:
| |
| 15 MINUTES.
| |
| MAX TIME:
| |
| 30 MINUTES JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| YES SAFETY FUNCTION 5
| |
| RJPM-NRC12-S1 RJPM-NRC12-S1 Page 3 of 10 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 RJPM-NRC12-S1 Page 4 of 10 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 RJPM-NRC12-S1
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 RJPM-NRC12-S1
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| | |
| ===1.1 Perform===
| |
| the following:
| |
| NA No action performed in this steps. Actions follow below.
| |
| *_____1. Place HVR-AOD22A, ANNULUS MIX SPLY TO SGT in Man Init Candidate located/identified and positioned the HVR-AOD22A, ANNULUS MIX SPLY TO
| |
| | |
| SGT to the Man Init position.
| |
| ____ *_____2. Place HVR-AOD22B, ANNULUS MIX SPLY TO SGT in Man Init Candidate located/identified and positioned the HVR-AOD22B, ANNULUS MIX SPLY TO
| |
| | |
| SGT to the Man Init position.
| |
| ____ *_____3. Depress AUX BLDG TO SGT FLTR A MANUAL INITIATION Candidate located/identified and depressed AUX BLDG TO SGT FLTR A MANUAL
| |
| | |
| INITIATION Pushbutton.
| |
| ____ *_____4. Depress AUX BLDG TO SGT FLTR B MANUAL INITIATION Candidate located/identified and depressed AUX BLDG TO SGT FLTR B MANUAL
| |
| | |
| INITIATION Pushbutton.
| |
| ____ 1.2 Verify the following dampers are closed: NA No action performed in this step.
| |
| Actions follow below.
| |
| ______5. HVR-AOD143, DN STREAM ISOL SUPPLY Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____
| |
| RJPM-NRC12-S1 RJPM-NRC12-S1
| |
| * Denotes Critical Step Page 7 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *_____7. HVR-AOD164, UP STREAM ISOL SUPPLY ALTERNATE PATH Candidate recognized that HVR-AOD164 UP STEAM ISOL SUPPLY failed to isolate 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.
| |
| ____ ______8. HVR-AOD263, SGT UPSTREAM SPLY ISOL Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____ ______9. HVR-AOD264, SGT DNSTREAM SPLY ISOL Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____ _____10. HVR-AOD262, AUX/CNTMT BLDG EXH ISOL Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____ *____11. HVR-AOD214, AUX/CNTMT BLDG EXH ISOL ALTERNATE PATH Candidate recognized that HVR-AOD214, AUX/CNTMT BLDG EXH ISOL failed to isolate
| |
| | |
| 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.
| |
| ____ _____12. HVR-AOD161, ANNULUS PRESS CONT SUCT Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____ _____13. HVR-AOD142, APC UP STREAM DISCH Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____
| |
| RJPM-NRC12-S1 RJPM-NRC12-S1
| |
| * Denotes Critical Step Page 8 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| _____14. HVR-AOD261, APC DN STREAM DISCH Candidate verified the damper closed by verifying the GREEN light is ON and the RED
| |
| | |
| light is OFF.
| |
| ____ _____15. 1.3 Verify both divisions of GTS start.
| |
| Candidate verified the GTS-FN1A and GTS-FN1B are both running by verifying RED
| |
| | |
| 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 a re in service.
| |
| | |
| RJPM-NRC12-S1 RJPM-NRC12-S1 Page 9 of 10 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 RJPM-NRC12-S1 Page 10 of 10 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.
| |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-S2 Revision: 00 Page 1 of 11 ALTERNATE PATH 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 RJPM-NRC12-S2 Page 2 of 11 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
| |
| | |
| Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME: 15 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| Yes SAFETY FUNCTION 1
| |
| RJPM-NRC12-S2 RJPM-NRC12-S2 Page 3 of 11 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 RJPM-NRC12-S2 Page 4 of 11 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 RJPM-NRC12-S2
| |
| * Denotes Critical Step Page 5 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 RJPM-NRC12-S2
| |
| * Denotes Critical Step Page 6 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| | |
| ===5.2 Transferring===
| |
| from Fast Speed to Slow Speed NA No actions performed by this step.
| |
| Actions follow below.
| |
| * 1. 5.2.1. Simultaneously depress B33-C001A and B RECIRC PUMP A and B MOTOR
| |
| | |
| BREAKER 5A and 5B XFER TO
| |
| | |
| LFMG pushbuttons. Candidate simultaneously depressed B33-C001A and B RECIRC PUMP A and B MOTOR BREAKER 5A
| |
| | |
| and 5B XFER TO LFMG pushbuttons.
| |
| | |
| ====5.2.2 Observe====
| |
| the following: NA Actions performed below.
| |
| : 2. 5.2.2.1. Both B33-S001A LFMG MOT BRKR 1A and B33-S001B LFMG MOT
| |
| | |
| BRKR 1B close.
| |
| Candidate verified B33-S001A LFMG MOT BRKR 1A closed.
| |
| | |
| ALTERNATE PATH Candidate recognized that B33-S001B LFMG MOT BRKR 1B failed to close.
| |
| : 3. 5.2.2.2 Both B33-C001A RECIRC PUMP A MOTOR BREAKER 5A and
| |
| | |
| B33-C001B RECIRC PUMP B
| |
| | |
| MOTOR BREAKER 5B open.
| |
| Candidate verified both B33-C001A RECIRC PUMP A MOTOR BREAKER 5A and B33-C001B RECIRC
| |
| | |
| PUMP B MOTOR BREAKER 5B open.
| |
| | |
| RJPM-NRC12-S2 RJPM-NRC12-S2
| |
| * Denotes Critical Step Page 7 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 4. 5.2.2.3 WHEN B33-C001A and B, RECIRC PUMP A and B coast down to approximately 360 - 470 RPM, THEN
| |
| | |
| B33-S001A and B LFMG A and B GEN BRKR 2A and 2B close and pump
| |
| | |
| speeds stabilize near 450 RPM.
| |
| | |
| Candidate verified that B33-S001A LFMG A GEN BRKR 2A closed and pump speed stabilized near 450
| |
| | |
| RPM.
| |
| ALTERNATE PATH Recognized and reported that B33-S001B LFMG B GEN BRKR 2B did not close and pump coasting to 0
| |
| | |
| RPM.
| |
| | |
| EVALUATOR CUE
| |
| : As the CRS, acknowledge the report that
| |
| | |
| Reactor Recirculation Pump B
| |
| | |
| transfer has failed, THEN direct
| |
| | |
| the candidate to perform the
| |
| | |
| actions of AOP-0024 THERMAL
| |
| | |
| HYDRAULIC STABILITY
| |
| | |
| CONTROL Section 5.9.
| |
| | |
| Also, notify the candidate that
| |
| | |
| another operator will perform
| |
| | |
| GOP-0004, SINGLE LOOP
| |
| | |
| OPERATIONS requirements.
| |
| | |
| TRANSITIONING TO AOP-0024 Section 5.9 5.9 IF a single Recirculation Pump Trip occurs, THEN perform the following actions: NA Actions performed below.
| |
| NOTE NOTE: Process computer point B33NA01V is used to determine core flow when one Reactor Recirculation Pump is
| |
| | |
| OFF and the other is in fast speed.
| |
| B33-R613, TOTAL CORE FLOW (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
| |
| | |
| NA This is a procedure note. No action is required.
| |
| RJPM-NRC12-S2 RJPM-NRC12-S2
| |
| * Denotes Critical Step Page 8 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| | |
| ====5.9.1 Enter====
| |
| GOP-0004, Single Loop Operation NA No action required. This task is being performed by another operator.
| |
| : 5.
| |
| | |
| ====5.9.2 Place====
| |
| B33-HYV-F060A (B), FLOW CONT VLV for both loops in
| |
| | |
| MANUAL Candidate verified both loops are in MANUAL as indicated by MANUAL pushbuttons being backlit at
| |
| | |
| B33-K603A & B
| |
| _____
| |
| | |
| ====5.9.3 Perform====
| |
| the following actions for the shutdown loop:
| |
| NA Actions performed below. CAUTION Closure of both suction and discharge valves with seal purge
| |
| | |
| valved in causes high pressures in
| |
| | |
| the isolated loop which can result in damage to the seals. Do not close 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.
| |
| | |
| NA No action required. This is a procedure caution.
| |
| * 6. 5.9.3.1. Close B33-F067A(B), RECIRC PUMP A(B) DISCH VALVE.
| |
| Candidate closed B33-F067B, RECIRC PUMP B DISCH VALVE by depressing the CLOSE push button and verified valve is closed by checking the
| |
| | |
| RED light OFF and the GREEN light ON.
| |
| NOTE: NOTE: Reopening of the Discharge Valve and the FCV following pump coastdown is expected to maintain the shutdown loop temperature within 50°F of the
| |
| | |
| operating loop.
| |
| NA RJPM-NRC12-S2 RJPM-NRC12-S2
| |
| * Denotes Critical Step Page 9 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 7. 5.9.3.2 IF Recirc pump restart is anticipated, THEN perform the following actions: Candidate requested guidance from the CRS regarding pump restart.
| |
| EVALUATOR CUE
| |
| : Inform the candidate that pump restart is not
| |
| | |
| 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 RJPM-NRC12-S2 Page 10 of 11 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 RJPM-NRC12-S2 Page 11 of 11 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
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-S3 Revision: 00 Page 1 of 10
| |
| | |
| 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 RJPM-NRC12-S3 Page 2 of 10 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME: 10 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No SAFETY FUNCTION 3
| |
| RJPM-NRC12-S3 RJPM-NRC12-S3 Page 3 of 10 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 RJPM-NRC12-S3 Page 4 of 10 DATA SHEET References for Development:
| |
| SOP-0011, Rev 027, MAIN STEAM SYSTEM (SYS
| |
| #109) Required Materials:
| |
| SOP-0011, Rev 027, MAIN STEAM SYSTEM (SYS #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 RJPM-NRC12-S3
| |
| * Denotes Critical Step Page 5 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 lin e in accordance with SOP-0011, MAIN STEAM SYSTEM, Section 5.1 RJPM-NRC12-S3 RJPM-NRC12-S3
| |
| * Denotes Critical Step Page 6 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: Section 5.1 denotes isolation of Main Steam Line A with MSL B, C, and D
| |
| | |
| parentheses.
| |
| | |
| Reactor power is limited to less than or equal to 75% RTP with one Main Steam
| |
| | |
| Line out of service.
| |
| | |
| 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.
| |
| | |
| NA No action required. This is a procedure note.
| |
| ______ 1.
| |
| | |
| ====5.1.1 Lower====
| |
| Reactor power to less than or
| |
| | |
| equal to 75%.
| |
| Candidate verified reactor power less than or equal to 75%. ______ 2.
| |
| | |
| ====5.1.2 Perform====
| |
| a slow closure of B21-AOVF028A(B)(C)(D), MSL
| |
| | |
| A(B)(C)(D) OUTBD MSIV as follows: NA No action required. Actions follow below. *_____ 3.
| |
| 5.1.2.1 Place B21-AOVF028A(B)(C)(D), MSL A(B)(C)(D) OUTBD MSIV, Control Switch in OPEN/SLOW
| |
| | |
| TEST Candidate located/identif ied and positioned B21-AOVF028A to the OPEN/SLOW TEST position.
| |
| | |
| RJPM-NRC12-S3 RJPM-NRC12-S3
| |
| * Denotes Critical Step Page 7 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *_____ 4.
| |
| 5.1.2.2. Depress and hold MSL A(B)(C)(D)
| |
| | |
| OUTBD MSIV TEST Pushbutton.
| |
| Candidate located/identified and depressed the MSL A OUTBD MSIV TEST pushbutton and maintained
| |
| | |
| the button in the depressed condition.
| |
| | |
| The following alarms will annunciate
| |
| | |
| and are expected for this evolution:
| |
| | |
| H13-P808-52A-H01 H13-P680-06A-B06
| |
| *_____ 5.
| |
| 5.1.2.3. WHEN B21-AOVF028A(B)(C)(D), MSL A(B)(C)(D) OUTBD MSIV, is
| |
| | |
| fully closed, THEN place the OPEN-SLOW TEST Control Switch
| |
| | |
| in CLOSE When B21-AOVF028A reached the fully closed position indicated by GREEN light ON and RED light
| |
| | |
| OFF, the candidate placed the B21-AOVF028A
| |
| | |
| control switch to the CLOSE position.
| |
| | |
| ______ 6.
| |
| 5.1.2.4. Release MSL A(B)(C)(D) OUTBD MSIV TEST Pushbutton.
| |
| Candidate released the MSL A OUTBD MSIV TEST
| |
| | |
| pushbutton.
| |
| ______ 7.
| |
| | |
| ====5.1.3. Perform====
| |
| a slow closure of B21-AOVF022A(B)(C)(D), MSL
| |
| | |
| A(B)(C)(D) INBD MSIV, as follows:
| |
| NA No action required. Actions follow below. *_____ 8.
| |
| 5.1.3.1 Place B21-AOVF022A(B)(C)(D), MSL A(B)(C)(D) INBD MSIV Control Switch in OPEN/SLOW
| |
| | |
| TEST Candidate located/identified and positioned
| |
| | |
| B21-AOVF022A to the OPEN/SLOW TEST position.
| |
| | |
| *_____ 9.
| |
| 5.1.3.2 Depress and hold MSL A(B)(C)(D)
| |
| | |
| INBD MSIV TEST Pushbutton.
| |
| Candidate located/identified and depressed the MSL A INBD MSIV TEST pushbutton and maintained the
| |
| | |
| button in the depressed condition.
| |
| The following alarms will annunciate and are expected for this evolution:
| |
| | |
| H13-P808-52A-H02 H13-P680-06A-B06
| |
| | |
| RJPM-NRC12-S3 RJPM-NRC12-S3
| |
| * Denotes Critical Step Page 8 of 10 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *____10.
| |
| 5.1.3.3. WHEN B21-AOVF022A(B)(C)(D), MSL A(B)(C)(D) INBD MSIV, is
| |
| | |
| fully closed, THEN place the OPEN-SLOW TEST Control Switch
| |
| | |
| in CLOSE. When B21-AOVF022 reached the fully closed position indicated by GREEN light ON and RED light
| |
| | |
| OFF, the candidate placed the B21-AOVF022A
| |
| | |
| control switch to the CLOSE position.
| |
| | |
| _____11. 5.1.3.4. Release MSL A(B)(C)(D) INBD
| |
| | |
| MSIV TEST Pushbutton.
| |
| Candidate released the MSL A INBD MSIV TEST
| |
| | |
| pushbutton.
| |
| Terminating Cue: The "A" Main Steam Line is isolated in accordance with SOP-0011 Section 5.1.
| |
| | |
| RJPM-NRC12-S3 RJPM-NRC12-S3 Page 9 of 10 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 RJPM-NRC12-S3 Page 10 of 10 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
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-S4 Revision: 00 Page 1 of 12 ALTERNATE PATH 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 RJPM-NRC12-S4 Page 2 of 12 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME: 10 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| YES SAFETY FUNCTION 9
| |
| RJPM-NRC12-S4 RJPM-NRC12-S4 Page 3 of 12 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 RJPM-NRC12-S4 Page 4 of 12 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 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 5 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 Di v 2 with HVK-CHL1B in service with HVK-P1B in accordance with SO P-0066, Control Building HVAC Chilled Water System, Section 5.4.
| |
| RJPM-NRC12-S4 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 6 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 1. 5.4.1 Check that the operating chiller has been running for at least 20 minutes.
| |
| | |
| Candidate verified that the chiller had been running for 3 days per the Initial Conditions NOTE: NOTE: The controls and indications in
| |
| | |
| this section are located at H13-P863, unless otherwise specified.
| |
| | |
| NA No action required. This is a procedure note.
| |
| * 2. 5.4.2 Stop the running Control Building Chilled Water Pump.
| |
| | |
| Candidate turned the HVK-P1A pump control switch
| |
| | |
| to the STOP postion.
| |
| | |
| Note: Several annunciators will be received on H13-P863 when this step
| |
| | |
| is performed.
| |
| : 3. 5.4.3 Verify the running chiller automatically trips. Candidate verified that HVK-CHL1A tripped by observing the red light extinguish and green light on.
| |
| | |
| _____ NOTE: NOTE: Chiller 1B/1D or 1A/1C pre-trip comes in and clears
| |
| | |
| Division I Chilled Water Pumps have a 30 second start time delay NA
| |
| * 4. 5.4.4 Check that the standby chilled water pump starts and its discharge valve opens.
| |
| | |
| ALTERNATE PATH Candidate identified that the HVK-P1B did not start.
| |
| | |
| RJPM-NRC12-S4 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 7 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 5. 5.4.5 IF the standby chilled water pump does
| |
| | |
| not start, THEN go to Step 5.4.7.
| |
| Candidate transitioned to S ection 5.4.7 of SOP-0066.
| |
| EVALUATOR CUE
| |
| : If a report is provided to the CRS concerning the
| |
| | |
| trip, acknowledge the report.
| |
| | |
| TRANSITION TO SECTION 5.4.7 NOTE: NOTE: Steps 5.4.7 thru 5.4.11 resets the chiller logic and places the chiller in
| |
| | |
| standby. A chiller can not be started 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 NA No action required. This is a procedure note.
| |
| : 6. 5.4.7 Check the previously running AHUs and fans have stopped Candidate checked that previously running AHUs
| |
| | |
| have stopped as follows:
| |
| | |
| HVC-ACU1A and 2A Green light ON, Red light OFF and Amber light ON.
| |
| | |
| HVC-FN3A Grren light ON and Red light OFF.
| |
| * 7. 5.4.8 Verify at least 3 minutes has elapsed since chiller was stopped, THEN Reset trips on the previously running AHUs as follows:
| |
| | |
| Candidate waited 3 minutes prior to proceeding.
| |
| * 8. Depress STOP on HVC-ACU1A(B), CR AHU A(B).
| |
| | |
| Candidate depressed STOP on HVC-ACU1A
| |
| | |
| RJPM-NRC12-S4 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 8 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 9. Depress STOP on HVC-ACU2A(B), CONTROL BLDG AHU A(B).
| |
| | |
| Candidate depressed STOP on HVC-ACU2A
| |
| * 10 Place HVC-ACU3A(B), EQPT RM AHU A(B) Switch to STOP then back to
| |
| | |
| AUTO.
| |
| Candidate placed switch for HVC-ACU3A to STOP and then back to AUTO
| |
| _____11.
| |
| 5.4.9 IF when resetting the AHUs in Step 5.4.8, a running AHU trips, THEN depress the LOCKOUT and then the
| |
| | |
| RESET Pushbutton on the tripped AHU to automatically restart the
| |
| | |
| AHU. NA No action required by this conditional step. NOTE: Note: Step 5.4.10 & 5.4.11 Resets the Chilled Water Pump start logic. NA No action required. This is a procedure note.
| |
| : 12.
| |
| 5.4.10. Verify HVK-P1A(B)(C)(D), CHILLED
| |
| | |
| WATER PUMP A(B)(C)(D) Switch for the previously running pump is in STOP.
| |
| | |
| Candidate checked that HVK-P1A switch is in STOP.
| |
| *____ 13.
| |
| 5.4.11. Place HVK-P1A(B)(C)(D), CHILLED
| |
| | |
| WATER PUMP A(B)(C)(D) Switch for the previously running pump to AUTO.
| |
| Candidate placed HVK-P1A switch to AUTO
| |
| | |
| RJPM-NRC12-S4 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 9 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS 5.4.12. Perform the following for the previously
| |
| | |
| running chiller:
| |
| NA No action required. Actions performed below.
| |
| *____14.
| |
| 5.4.12.1 Depress STOP on HVK-CHL1A(B)(C)(D), CONT BLDG
| |
| | |
| CHILLER A(B)(C)(D) Start/Stop/Reset
| |
| | |
| Pushbutton.
| |
| | |
| Candidate depressed STOP pushbutton on HVK-CHL1A
| |
| *___15.
| |
| 5.4.12.2 Depress RESET on HVK-CHL1A(B)(C)(D) Start/Stop/Reset
| |
| | |
| Pushbutton Candidate depressed RESET pushbutton on HVK-CHL1A 5.4.13 Verify the following:
| |
| NA No action required. Actions performed below.
| |
| : 16.
| |
| 5.4.13.1 Standby Chiller starts.
| |
| | |
| Candidate verified that HVK-CHL1A restarted.
| |
| : 17.
| |
| 5.4.13.2 Standby Chiller Recirc Service Water Pump suction valve opens.
| |
| | |
| Candidate verified that SWP-MOV27A opened.
| |
| : 18.
| |
| 5.4.13.3 Standby Chiller Recirc Service Water Pump starts.
| |
| | |
| Candidate verified that SWP-P3A starts EVALUATOR CUE
| |
| : When the candidate makes contact
| |
| | |
| with the Control Building operator to perform Section 5.4.14, notify the
| |
| | |
| candidate as the Control Building
| |
| | |
| 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 RJPM-NRC12-S4
| |
| * Denotes Critical Step Page 10 of 12 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| | |
| RJPM-NRC12-S4 RJPM-NRC12-S4 Page 11 of 12 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 RJPM-NRC12-S4 Page 12 of 12 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: RJPM-NRC12-S5 Revision: 00 Page 1 of 11 ALTERNATE PATH 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 RJPM-NRC12-S5 Page 2 of 11 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME: 10 min. MAX TIME:
| |
| N/A JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| YES SAFETY FUNCTION 2
| |
| RJPM-NRC12-S5 RJPM-NRC12-S5 Page 3 of 11 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 RJPM-NRC12-S5 Page 4 of 11 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 RJPM-NRC12-S5
| |
| * Denotes Critical Step Page 5 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, and you should inform me when you have completed this task.
| |
| Initial Conditions:
| |
| The plant is operating at about 70% power after an inadverten t 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 RJPM-NRC12-S5
| |
| * Denotes Critical Step Page 6 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: NOTE: Precautions 2.9 and 2.10 should be referred to prior to HPCS System
| |
| | |
| shutdown NA No action required. This is a procedure note.
| |
| : 1.
| |
| | |
| ===6.1 Verify===
| |
| E22A-S2, HPCS MANUAL INITIATION collar is in the DISARM
| |
| | |
| position.
| |
| Candidate attempted to rotate Manual Initiation pushbutton collar to the DISARM position or noted that the red indicator mark on the collar is aligned
| |
| | |
| with the DISARM position.
| |
| NOTE: If the HPCS initiation signal is unable to be reset using E22A-S7, HPCS INITIATION RESET Pushbutton, the HPCS Pump can be
| |
| | |
| overridden and stopped. This will prevent an automatic start of the HPCS Pump until the initiation
| |
| | |
| 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.
| |
| | |
| NA No action required. This is a procedure note.
| |
| * 2.
| |
| | |
| ===6.2 Depress===
| |
| E22A-S7, HPCS INITIATION RESET pushbutton and check the white
| |
| | |
| light goes off.
| |
| Candidate depressed HPCS INITIATION RESET pushbutton and verified WHITE light is OFF.
| |
| | |
| RJPM-NRC12-S5 RJPM-NRC12-S5
| |
| * Denotes Critical Step Page 7 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| | |
| ===6.3 Verify===
| |
| closed the following valves:
| |
| NA No action required. Actions follow below. 3.
| |
| 6.3.1 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
| |
| | |
| light indication OFF.
| |
| : 4.
| |
| 6.3.2 E22-F010, HPCS TEST BYPASS VLV TO CST Candidate located/identified and verified E22-F010 is CLOSED by GREEN light indication ON and RED
| |
| | |
| light indication OFF.
| |
| : 5.
| |
| 6.3.3 E22-F011, HPCS TEST RETURN VALVE TO CST Candidate located/identified and verified E22-F011 is CLOSED by GREEN light indication ON and RED
| |
| | |
| light indication OFF.
| |
| * 6.
| |
| 6.3.4 E22-F004, HPCS INJECT ISOL 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 light indication OFF following completion of the
| |
| | |
| valve stroke.
| |
| | |
| RJPM-NRC12-S5 RJPM-NRC12-S5
| |
| * Denotes Critical Step Page 8 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| * 7.
| |
| 6.4 When flow lowers below 625 gpm on E22-R603, HPCS FLOW, verify E22-
| |
| | |
| F012, HPCS MIN FLOW VALVE TO
| |
| | |
| SUPPRESSION POOL opens.
| |
| ALTERNATE PATH Candidate recognized the failure of E22-F012 to open automatically.
| |
| | |
| Candidate manually opened E22-F012 by placing the handswitch in OPEN and verifying RED light ON and
| |
| | |
| GREEN light OFF OR immediately tripped the HPCS pump.
| |
| | |
| ACTION SHOULD OCCUR WITHIN 60 SECONDS
| |
| | |
| Candidate may wait for up to 21 seconds for transmitter saturation to
| |
| | |
| dissipate prior to recognizing failure
| |
| | |
| of E22-F012 (Precaution & Limitation 2.2)
| |
| | |
| NOTE: As a conservative action, an immediate pump trip may be initiated.
| |
| Remaining steps should be performed
| |
| | |
| following the trip.
| |
| | |
| EVALUATOR CUE
| |
| : As CRS acknowledge report of the failure of
| |
| | |
| E22-F012 to open.
| |
| : 5.
| |
| 6.5 If E22-PC003, HPCS LINE FILL PUMP is not running, then start E22-
| |
| | |
| PC003. Candidate verified that E22-PC003 running with RED
| |
| | |
| light ON, GREEN light OFF.
| |
| * 6.
| |
| 6.6 Trip E22-ACB02, HPCS PUMP SUPPLY BRKR.
| |
| Candidate manually opened breaker E22-ACB02 by
| |
| | |
| placing the handswitch to the TRIP position and verified by GREEN light ON, RED light OFF.
| |
| : 7.
| |
| 6.7 When HPCS Pump discharge pressure lowers below 300 psig on E22-R601, HPCS PUMP DISCH PRESSURE, then verify E22-F012, HPCS MIN FLOW
| |
| | |
| VALVE TO SUPPRESSION POOL
| |
| | |
| closes. Candidate checked that E22-F012 auto close when pressure drops below 300 psig by observing GREEN
| |
| | |
| light ON, RED light OFF.
| |
| | |
| RJPM-NRC12-S5 RJPM-NRC12-S5
| |
| * Denotes Critical Step Page 9 of 11 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| : 8.
| |
| 6.8 IF the HPCS DG is operating, THEN shut down the DG per SOP-0052, HPCS Diesel Generator NA No action required. Initial conditions stated that the diesel generator was
| |
| | |
| secured. Terminating Cue: High Pressure Core Spray Pump is shutdown and faulty minimum flow valve was identified. .
| |
| | |
| RJPM-NRC12-S5 RJPM-NRC12-S5 Page 10 of 11 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 RJPM-NRC12-S5 Page 11 of 11 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.
| |
| | |
| RIVER BEND STATION JOB PERFORMANCE MEASURE Number: *RJPM-NRC12-S6 Revision: 00 Page 1 of 16 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 RJPM-NRC12-S6 Page 2 of 16 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 Simulate Performance Actual Performance X TESTING METHOD:
| |
| Control Room Simulator X In-Plant COMPLETION TIME:
| |
| 20 MINUTES.
| |
| MAX TIME:
| |
| 40 MINUTES JOB LEVEL:
| |
| RO/SRO TIME CRITICAL:
| |
| No EIP CLASSIFICATION REQUIRED:
| |
| No PSA RISK DOMINATE:
| |
| No ALTERNATE PATH (FAULTED):
| |
| No SAFETY FUNCTION 4
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6 Page 3 of 16 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 RJPM-NRC12-S6 Page 4 of 16 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 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 5 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) 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 comple ted the task successfully, the objective for this JPM will be sati sfied, 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 bee n flushed and warmed for Shutdown Cooling operation. The system has been filled and vented.
| |
| | |
| E12-MOV64A is de-energized and Administrativ e 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 Coo ling Mode in accordance with SOP-0031 Section 4.4.9 and continuing through 4.4.9.17.
| |
| | |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 6 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^)
| |
| PERFORMANCE STEP STANDARD S/U COMMENTS CAUTION CAUTION: If adequate core circulation is not maintained, Reactor coolant temperature indication is not accurate.
| |
| 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 NA No action required. This is a procedure caution.
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 7 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: NOTE: In Mode 5, during startup or line up changes of shutdown cooling, stop fuel movement in the upper cavity and
| |
| | |
| ensure that all bundles are placed in
| |
| | |
| their proper storage locations. This prevents the possibility of a suspended
| |
| | |
| fuel bundle during a concurrent loss of
| |
| | |
| cavity level.
| |
| 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.
| |
| NA No action required. This is a procedure note.
| |
| | |
| 4.4.9.1 IF any of the following RHR Shutdown Cooling interlocks are to be
| |
| | |
| bypassed, THEN obtain senior plant management review and approval and verify contingency methods are in place to supply sufficient makeup
| |
| | |
| water if a draining event occurs while
| |
| | |
| the SDC interlocks are bypassed:
| |
| NA EVALUATOR CUE:
| |
| If asked at the CRS, notify the candidate that the listed Shutdown Cooling interlocks will not be bypassed.
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 8 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: Only one Shutdown Cooling Isolation Valve is required to be operable.
| |
| | |
| Opening the power supply breaker or
| |
| | |
| lifting leads on one valve per
| |
| | |
| approved procedures to prevent system isolation and loss of SDC during maintenance or testing is permissible. NA No action required. This is a procedure note.
| |
| Low reactor water level isolation of E12-F008, RHR SHUTDOWN
| |
| | |
| COOLING OUTBD ISOL VALVE and E12-F009, RHR SHUTDOWN
| |
| | |
| COOLING INBD ISOL VALVE.
| |
| NA No action performed by this step.
| |
| Interlocks will not be bypassed. Interlocks between E12-F004, RHR PUMP SUP PL SUCTION VALVE
| |
| | |
| and E12-F006, RHR PUMP SDC
| |
| | |
| SUCTION. NA No action performed by this step.
| |
| Interlocks will not be bypassed
| |
| . ______1. 4.4.9.2 On H13-P601, verify less than 135 psig Reactor Pressure as indicated on
| |
| | |
| B21-R623A(B), RX
| |
| | |
| LEVEL/PRESSURE RECORDER
| |
| | |
| A(B). Candidate located/identified B21-R623A(B), RX LEVEL/PRESSURE RECORDER A(B)and
| |
| | |
| verified reactor pressure is less than 135 psig
| |
| ____ 4.4.9.3 Verify closed the following NA No action performed in this step.
| |
| Actions follow below.
| |
| ______2. 4.4.9.3.1 E12-F004A(B), RHR PUMP A(B)
| |
| | |
| SUP PL SUCTION VALVE Candidate located/identified E12-F004A and verified it closed by the GREEN light indicating
| |
| | |
| ON and the RED light indicating OFF.
| |
| ____
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 9 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| ______3. 4.4.9.3.2 E12-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL Candidate verified E12-F064A closed by information provided in Initial Conditions.
| |
| ____ ______4. 4.4.9.3.3 E12-F024A(B), RHR PUMP A(B)
| |
| TEST RTN TO SUP PL Candidate located/identified E12-F024A and verified it closed by the GREEN light indicating
| |
| | |
| ON and the RED light indicating OFF.
| |
| ____ ______5. 4.4.9.3.4 E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST Candidate located/identified E12-F037A and verified it closed by the GREEN light indicating
| |
| | |
| ON and the RED light indicating OFF.
| |
| ____ ______6. 4.4.9.3.5 E12-F048A(B), RHR A(B) HX BYPASS VALVE.
| |
| Candidate located/identified E12-F048A and verified it closed by the GREEN light indicating
| |
| | |
| ON and the RED light indicating OFF.
| |
| ____ ______7. 4.4.9.3.6 E12-F011A(B), RHR A(B) HX CNDS FLUSH TO SUP PL.
| |
| Candidate located/identified E12-F011A and verified it closed by the GREEN light indicating
| |
| | |
| ON and the RED light indicating OFF.
| |
| ____ _____8.
| |
| 4.4.9.4 Place in OFF and initiate administrative controls for
| |
| | |
| EHS-MCC2E(2F) BKR 5C(7B),
| |
| C002A(B) DISCH MIN FLOW
| |
| | |
| VALVE Candidate verified administrative controls on EHS-MCC2E BKR5C for C002A DISCH MIN FLOW VALVE by information provided in
| |
| | |
| Initial Conditions.
| |
| ____ 4.4.9.5 IF Standby Service Water is supplying service water loads, THEN on H13-P870, verify closed SPC-AOV16, SPC HX SW DISCH VLV.
| |
| NA No action required for this conditional step. Normal Service
| |
| | |
| Water is in service.
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 10 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: NOTE: Two Standby Service Water Pumps are required in each loop when operating the Standby Service Water System for heat removal through the
| |
| | |
| RHR Heat Exchangers.
| |
| NA No action required. This is a procedure note.
| |
| *_____9. 4.4.9.6 On H13-P870, throttle open E12-F068A(B), RHR HX A(B) SVCE WTR RTN to establish less than or equal to 5800 gpm flow as indicated
| |
| | |
| on H13-P601, E12-R602A(B), RHR HX A(B) SVCE WTR FLOW.
| |
| Candidate located/identified E12-F068A and throttled open the valve to establish less than or equal to 5800 gpm as indicated on H13-P601, E12-R602A.
| |
| | |
| Note that valve control switch and flow indicator are on different
| |
| | |
| panels and may require the
| |
| | |
| candidate to make several trips
| |
| | |
| across the room to accomplish this
| |
| | |
| step. _____10. 4.4.9.7 Verify Step 4.4.2 has been performed.Candidate verified step 4.4.2 complete by requesting the status of Electrical Maintenance PM Task to re-land the thermal overload/loss of
| |
| | |
| power annunciator leads for E12-F009, RHR SHUTDOWN COOLING INBD ISOL VALVE.
| |
| EVALUATOR CUE:
| |
| When requested, as Electrical
| |
| | |
| Maintenance, notify the
| |
| | |
| candidate that the thermal overload/loss of power
| |
| | |
| annunciator lead for E12-F009
| |
| | |
| has been re-landed.
| |
| _____11. 4.4.9.8 At H13-P601, depress B21H-S32(33), OUTBD(INBD)
| |
| | |
| ISOLATION SEAL-IN RESET
| |
| | |
| Pushbutton.
| |
| Candidate located/identified AND depressed B21H-S32(33) OUTBD(INBD) ISOLATION
| |
| | |
| SEAL-IN RESET PUSHBUTTON on H13-P601.
| |
| _____12. 4.4.9.9 At H13-P601, check RHR ISOLATION Status Lights are ON
| |
| | |
| for E12-F008 and E12-F009. Candidate located/ identified and verified the RHR ISOLATION Status Lights are ON for
| |
| | |
| E12-F008 and E12-F009 on H13-P601.
| |
| | |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 11 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| _____13. 4.4.9.10 In the Div 1 RSS Room at C61-PNL001, verify E12-MOVF008
| |
| | |
| ENABLE/DISABLE Switch is in
| |
| | |
| ENABLE. Candidate verified E12-MOVF008 ENABLE/DISABLE Switch is in ENABLE by
| |
| | |
| contacting the Control Building operation to
| |
| | |
| request status.
| |
| EVALUATOR CUE:
| |
| When requested, as Control Building
| |
| | |
| operator, notify the candidate
| |
| | |
| that E12-MOVF008 ENABLE/DISABLE switch in
| |
| | |
| ENABLE. CAUTION CAUTION: Opening the Shutdown Cooling Isolation Valves with portions of the RHR piping empty, a significant
| |
| | |
| lowering in reactor level can occur.
| |
| | |
| Do not open the Shutdown Cooling Isolation Valves unless the RHR
| |
| | |
| piping including suction lines is completely filled.
| |
| NA No action required. This is a procedure caution.
| |
| 4.4.9.11 Verify open the following:
| |
| NA No action required. Actions follow below. _____14. 4.4.9.11.1 E12-F010, RHR SDC MAN ISOL VLV Candidate located/identified and verified E12-F010 open by checking RED indicating light
| |
| | |
| ON and GREEN indicating light OFF.
| |
| _____15. 4.4.9.11.2 E12-F009, RHR SHUTDOWN COOLING INBD ISOL VALVE Candidate located/identified and verified E12-F009 open by checking RED indicating light
| |
| | |
| ON and GREEN indicating light OFF.
| |
| _____16. 4.4.9.11.3 E12-F008, RHR SHUTDOWN COOLING OUTBD ISOL VALVE Candidate located/identified and verified E12-F008 open by checking RED indicating light
| |
| | |
| ON and GREEN indicating light OFF.
| |
| | |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 12 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| _____17. 4.4.9.11.4 E12-F006A(B), RHR PUMP A(B)
| |
| SDC SUCTION VALVE Candidate located/identified and verified E12-F006A open by checking RED indicating
| |
| | |
| light ON and GREEN indicating light OFF.
| |
| _____18. 4.4.9.11.5 E12-F047A(B), RHR A(B) HX INLET VALVE Candidate located/identified and verified E12-F0047A open by checking RED indicating
| |
| | |
| light ON and GREEN indicating light OFF.
| |
| *___19. 4.4.9.12 & NOTE Verify open one of the following: E12-F053A(B), RHR PUMP A(B)
| |
| SDC INJECTION VALVE NOTE:
| |
| Flow can be diverted to the refueling cavity sparger only if the Drywell and RPV heads are removed and in
| |
| | |
| shutdown cooling E12-F037A(B), RHR A(B) TO UPPER POOL FPC ASSIST Candidate recognized that in Mode 4, the only viable path is through E12-MOV-F053A.
| |
| | |
| Candidate located/identified and opened E12-
| |
| | |
| MOVF053A by holding the control switch in the
| |
| | |
| OPEN position and by verifying the GREEN
| |
| | |
| indicating light OFF and the RED indication light
| |
| | |
| ON.
| |
| | |
| *____20. 4.4.9.13 Close E12-F003A(B), RHR A(B) HX OUTLET VALVE Candidate located/identified and closed E12-F003A by placing the control switch in the
| |
| | |
| CLOSE position and verifying the GREEN
| |
| | |
| incidating light ON and the RED indicating light
| |
| | |
| OFF. _____21. 4.4.9.14 Verify the respective cubicle unit cooler is in service Candidate verified HVR-UC6 in service from initial conditions OR from indicating lights on H13-P870.
| |
| | |
| HVR-UC6 is indicated running by RED
| |
| | |
| indicating light ON and GREEN indicating light
| |
| | |
| OFF.
| |
| RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 13 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS CAUTION CAUTION: Failure to establish greater than 1100 gpm within 25 seconds of pump start may cause pump damage from operation with less than minimum flow requirement. Do not allow more than 25 seconds to elapse before establishing greater than 1100 gpm NA No action required. This is a procedure caution.
| |
| NOTE NOTE: The initiation of Shutdown Cooling with the reference leg backfill system out of service can result in more
| |
| | |
| pronounced notching of indicated
| |
| | |
| reactor level requiring reactor level trends to be monitored more closely.
| |
| NA No action required. This is a procedure note.
| |
| *____22. 4.4.9.15 Start E12-C002A(B), RHR PUMP A(B) and IMMEDIATELY throttle open E12-F048A(B), RHR A(B) HX
| |
| | |
| BYPASS VALVE to obtain greater than or equal to 2000 gpm and less than or equal to 3000 gpm.
| |
| Candidate located/identified and started E12-C002A by placing the control switch to the
| |
| | |
| CLOSE position and verified RED indicating
| |
| | |
| light ON and GREEN indicating light OFF.
| |
| | |
| AND Candidate located/identified and opened E12-F048A to obtain 2000-3000 gpm on E12-R603A RHR A LOOP FLOW meter.
| |
| | |
| The following alarm will annunciate and is expected for this
| |
| | |
| evolution: H13-P680-19A-F07 RJPM-NRC12-S6 RJPM-NRC12-S6
| |
| * Denotes Critical Step Page 14 of 16 ^ Denotes Sequence Critical (must be performed after previous step marked ^) PERFORMANCE STEP STANDARD S/U COMMENTS
| |
| *____23. 4.4.9.16 Establish a stable flow of greater than or equal to 4000 gpm and less than or equal to 5000 gpm by throttling E12-
| |
| | |
| F048A(B), RHR A(B) HX BYPASS
| |
| | |
| VALVE Candidate located/identified and continued to open E12-F048A to obtain 4000-5000 gpm on E12-R603A RHR A LOOP FLOW meter.
| |
| *____24. 4.4.9.17 Throttle open E12-F003A(B), RHR A(B) HX OUTLET VALVE to approximately 10 PERCENT as
| |
| | |
| indicated on E12-R611A(B), HX
| |
| | |
| A(B) OUTLET VLV POS Candidate located/identified and throttle open E12-F003A to approximately 10 percent as
| |
| | |
| indicated on E12-R611A, HX A 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 RJPM-NRC12-S6 Page 15 of 16 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 RJPM-NRC12-S6 Page 16 of 16 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.}}
| |
