Text

WC-03-2006 - Final Operating Exam
	ML060880360
Person / Time
Site:	Wolf Creek ; (NPF-042)
Issue date:	03/06/2006
From:	; Operations Branch IV
To:	;
References
	Download: ML060880360 (181)
	v • d • e

INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO #1 Revision 1 Week of March 6, 2006

OP-TEST # 1 SCENARIO # 1 Page 2 of 43 Facility: Wolf Creek NRC Scenario No.: 1 Op-Test No.:

1 Source:

New X Bank - Significantly Modified

. Bank - Initial Condition Change.

See page 3 for Examiner/student assignments Initial Conditions: 55% power, B Main Feed Pump (MFP) rolling at 1100 rpm Turnover: _Place 2nd MFP on line, maintain current power for flux map Event No.

Malf.

No.

Event Type*

Event Description 1

N/A N-BOP Place 2 MFP on line nd 2

mPCS02 A

R-ATC Turbine Impulse Pressure AC PT-505 fails low causing control rod insertion.

3 mMSS0 1C2 I-BOP C SG Pressure Instrument fails low, affecting Steam Flow indication and MFP Speed Control.

4 mCCW1 8B C-ATC C-BOP Component Cooling Water System (CCW) Leak in the B Train Safety Loop. Requires removing B Train CCW and ECCS pumps from service.

5 mRCS07 B

M Small Break LOCA, Safety Injection 6

mCCW0 6A r19064B C-ATC A Train CCW pump A trips on SI and the C pump fails to auto start.

7 mPSC10 C

C-ATC Containment Isolation Phase A fails to automatically actuate

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST # 1 SCENARIO # 1 Page 3 of 43 SCENARIO MISCELLANEOUS INFORMATION SCENARIO

SUMMARY

The objective of this scenario is to mitigate a small break Loss Of Coolant Accident, complicated by the loss of one train of Emergency Core Cooling System (ECCS). The scenario begins at 55% power with the crew placing the second Main Feed Pump in service. Two instrument failures occur requiring operator action to stabilize the plant and evaluation of Technical Specifications.

A leak in the operating Component Cooling Water (CCW) train requires swapping to the standby train and subsequent shutdown of the CCW train. Procedural requirements place all ECCS pumps served by the affected train out of service. This will also require the SRO to evaluate Technical Specifications.

Following the small break LOCA, operator actions are required. The running CCW pump in the only available train, trips and the standby pump does not autostart. Containment Isolation Signal Phase A also fails to actuate automatically challenging containment integrity. Both failures can be corrected by manual actions.

CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

SG Levels

RCP Temperatures

RCS and PZR Pressures

PZR Level

Containment Pressure

RCS Tavg OPERATOR ACTIONS TABLE NOTES:

1.

Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2.

Actions required throughout the event are indicated as continuous (cont) in the position column.

3.

Shaded cells indicate procedural entry points.

OP-TEST # 1 SCENARIO # 1 Page 4 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 1 Event

Description:

Place second Main Feed Pump B in service. SYS AE-121 TURBINE DRIVEN MAIN FEED WATER PUMP STARTUP procedure in progress at step 6.2.23.

Time Position Applicant's Actions or Behavior Notes SRO Provide RO a band to maintain for Tavg and Power during pump startup. Direct BOP to place B MFP on line using the procedure.

RO cont Maintain Rx power and Tavg within band provided by SRO BOP Verifies oil temperature > 110 degrees by contacting local operator.

BOP cont Monitor SG levels and running A MFP to ensure secondary remains stable.

BOP Increase MFP speed to 3600 rpm and transfer control to auto.

Perform actions to null the signal match between the GE and Westinghouse controllers.

BOP Contact local operator and verify seal dP.

BOP Increase B MFP speed till it indicates 0-100 rpm above A and place control on the Master Speed Controller.

BOP Inform SRO that the procedure is complete.

Termination Criteria:

The Master Speed Controller is controlling both MFPs. All SG levels are stable at or trending to program level (50%).

OP-TEST # 1 SCENARIO # 1 Page 5 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 2 Event

Description:

Turbine Impulse Pressure AC PT-505 fails low causing control rod insertion.

Time Position Applicant's Actions or Behavior Notes RO Note and Communicate that control rods are stepping in. Place rod control in manual after confirmation that a loss of load is not in progress.

Rods should be taken to manual in time to prevent a Rx Trip.

BOP Confirm that a turbine loss of load is not occurring.

SRO Monitor/acknowledge communications.

Direct above actions be performed if not already done.

RO/BOP Note and communicate that AC PT-505 has failed low.

Monitor for entry into DNB T.S.

Two hours to restore.

SRO Enter and direct OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment D.

RO/BOP Identifies failed channel as AC PT-505.

Ensure rods in manual.

BOP Select out failed channel SRO/RO Conduct reactivity brief with RO to return rods to the pre-event position and restore Tavg. Return rods to Automatic.

BOP Place Steam Dump Interlocks to OFF Set AB PK-507 pot to 7.28 Place Steam Dumps in Steam Pressure Mode.

Place Steam Dump Interlocks to ON SRO Contact Work Week Manager (WWM) for INC assistance in tripping bi-stables and troubleshooting.

BOP Check C-16 Lo Tavg NOT LIT Check HOLD light NOT LIT

OP-TEST # 1 SCENARIO # 1 Page 6 of 43 BOP Place AMSAC in proper state AMSAC is not modeled. Booth Operator will meet BOP at door with cue.

SRO Review and comply with T.S. 3.3.1, Function 18.f, Condition T.

Verify P-13 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Termination Criteria:

Control Rods in Auto.

Tavg within 1 degree of Tref.

T.S. Identified

OP-TEST # 1 SCENARIO # 1 Page 7 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 3 Event

Description:

C SG Pressure Instrument fails low, affecting Steam Flow indication and MFP Speed Control.

Time Position Applicant's Actions or Behavior Notes BOP Note and communicate alarm 110C, C SG Level is decreasing or C MFRV is closing.

BOP Place C MFRV in manual and restore feed flow.

This action should be taken in time to prevent a Rx Trip.

SRO Monitor/acknowledge communications.

Direct above actions be performed if not already done.

SRO Enter and direct Alarm Response ALR 00-110C SRO may enter the OFN directly RO Check SG C instrumentation. Note and communicate that Steam Pressure Channel AB PT-535 has failed low.

Note: Steam Flow is an input to the MFP Speed Control and will force the MFPs to continue slowing down till the affected channel is selected out.

SRO Perform RNO column. Direct BOP to select out failed channel.

SRO Direct BOP to return MFRV to Automatic when SG level is restored.

Should provide a band or value.

BOP cont Restore SG level to program and place MFRV in Auto per SRO directive.

SRO Enter and direct OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment C If SRO entered the OFN directly based on Steam Flow, Attach. A will direct them to Attach. C.

SRO/RO Identify failed channel

OP-TEST # 1 SCENARIO # 1 Page 8 of 43 SRO/BOP Check if channel selected for control.

Place MFRV in manual Select Alternate Channel May have already been completed.

SRO Contact Work Week Manager (WWM) for INC assistance in tripping bi-stables and troubleshooting.

SRO Monitor and comply with T.S.s 3.3.2 Function 1.e., 3.a.(3), 4.d.(1) and (2), 5.c, 6.e, and 7.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to trip Bi-stables.

3.3.3 and 3.3.4 - No Action Required 3.3.6, Table 3.3.6-1, Function 4 3.3.7, Table 3.3.7-1, Function 4 T.S 3.3.2 contains the only required actions.

3.3.6 and 3.3.7 should be referenced, however no actions are required.

SRO/BOP Ensure C MFRV back in auto and controlling SG level.

Termination Criteria:

C SG level stable at or trending to program (50%). C MFRV back in Auto.

T.S.s identified.

OP-TEST # 1 SCENARIO # 1 Page 9 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 4 Event

Description:

Component Cooling Water System (CCW) Leak in the B Train Safety Loop.

Requires removing B Train CCW and ECCS pumps from service.

Time Position Applicant's Actions or Behavior Notes ALL Various CCW Alarms annunciate and clear. Crew should investigate alarms.

At any point, the SRO may enter the OFN directly and the following diagnostics may not be performed.

RO/BOP Recognize Auto make-up has initiated from Demin Water system (AN).

No audible alarm. Crew may not recognize make-up in progress.

RO/BOP Recognize CCW B surge tank level is decreasing.

ALL Annunciator 104D for RHR Pump Room Sump Level high alarms.

SRO Direct Local Operator to be dispatched to investigate sump level alarm.

At some point, the Building Watch will report a leak on CCW Train B Safety Loop.

SRO Enter and Direct OFN EG-004, CCW MALFUNCTIONS.

SRO Direct starting an A Train CCW pump.

RO/BOP Make Announcement and start an A Train CCW pump.

RO/BOP cont Check CCW inventory.

Isolate CCW to Radwaste.

Ensure DI water Make-up.

Start second AN pump.

Cycle B ESW make-up valves to B CCW as required to maintain level between 40 and 60%.

SRO should assign continuous action to one of the board operators.

SRO Identify CCW leak.

(RHR sumps increasing)

Check Location of Leak.

(B Safety Loop)

Building Watch will report leak is on the B Safety Loop and cannot be isolated.

OP-TEST # 1 SCENARIO # 1 Page 10 of 43 SRO Determine Leak not on Service Loop in Containment and go to step 12.

Determine Leak not on Service Loop outside Containment and go to step 19 SRO Direct Service Loop be swapped to A Train CCW and Shutdown B CCW Train.

RO/BOP Swap Service Loop to A Train CCW.

Place both B Train CCW pumps in Pull to Lock (PTL).

Recognize leak cannot be isolated and direct building watch to close EG-V148 for DI water make-up.

Place ECCS pumps in PTL.

CCP SI RHR SRO Stop the B SFP Cooling pump.

Direct board operator to co-ordinate with the Bldg Watch and place SFP Cooling on A CCW Train.

RO/BOP May attempt to re-establish Thermal Barriers to RCPs and restore Radwaste back to service.

SRO Identify Tech Specs.

3.7.7 CCW One Train inoperable, 72 Hours to restore.

3.5.2 ECCS Operating Determine Safety function is not lost and it would be 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore.

May apply or request an evaluation to apply 3.0.6 and not enter 3.5.2.

Termination Criteria:

CCW Service Loop aligned to A Train.

All B Train ECCS pumps and CCW pumps are in PTL.

Tech Specs Identified.

OP-TEST # 1 SCENARIO # 1 Page 11 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 5 Event

Description:

Small Break LOCA, Safety Injection Time Position Applicant's Actions or Behavior Notes SRO/RO BOP Note and communicate RCS pressure is decreasing.

SRO/RO BOP Monitor RCS pressure for entry into DNB Tech. Spec. at < 2220 psig.

T.S. 3.4.1, two hours to restore.

RO As RCS pressure decreases, may energize PZR B/U heaters.

Monitor for DNB T.S.

RO Note and communicate that PZR level is decreasing.

SRO Enter and direct OFN BB-007 RCS Leakage.

RO Checks PZR Level - decreasing.

Increase charging flow.

Isolate Letdown.

SRO/RO Check Charging Pump Suction.

Check PZR pressure - stable.

SRO/BOP Check S/G Tubes - intact.

Dispatch HP

Contact Chemistry.

SRO/RO Fold Out Page criteria are met when charging is maximized, letdown isolated and PZR level continues to decrease OR SRO determines they cannot maintain PZR Pressure.

SRO Direct a Reactor Trip and Initiate Safety Injection. Transition to EMG E-0.

Auto Actuation may occur before the SRO can order manual actuation.

Termination Criteria:

Reactor is tripped and Safety Injection Actuated.

OP-TEST # 1 SCENARIO # 1 Page 12 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 6 and 7 Event

Description:

Upon Reactor trip and Safety Injection, the running CCW pump trips and the standby pump fails to auto start. Containment Isolation Phase A (CIS-A) fails to auto actuate.

Time Position Applicant's Actions or Behavior Notes SRO Enter and Direct actions of EMG E-0, Reactor Trip or Safety Injection.

RO/BOP Perform Immediate Actions of EMG E-0.

RO Verify Rx Trip

Rod Bottom Lights Lit.

Rx Trip and Bypass Bkrs open.

Neutron Flux decreasing (Intermediate Range & Gamma metrics)

Transfer NR-45 recorder to Intermediate Range Verify Vital AC Power

Both NB buses - normal voltage /

aligned to off site power.

Verify SI actuated Determine SI is actuated. Annunciators 30A and 31A are lit.

BOP Verify Turbine trip.

Main Stop valves all closed.

Generator and exciter bkrs open.

SRO At completion of Immediate Actions determine if there are any immediate concerns.

RO Notes that no CCW pump is running in the only available Train and informs SRO.

ALL One person from the crew should recognize adverse containment values have been exceeded and communicate this to the rest of the crew.

Adverse Containment may not occur at this break size.

OP-TEST # 1 SCENARIO # 1 Page 13 of 43 SRO/RO "C"

Start the standby A Train CCW pump.

CRITICAL TASK: The standby pump must be started prior to the end of Attach. F.

SRO/RO Notes that CIS-A, CRVIS and CPIS has failed to actuate on Status Panels SB066X and 66Y.

SRO/RO C

Manually Actuate CIS-A.

CRVIS and CPIS will actuate on the manual CIS-A, operator may actuate CRIVS or CPIS separately prior to the CIS-A.

CRITICAL TASK: The CIS-A signal must be actuated prior to the end of Attach. F.

Only one train is required to be actuated to meet the critical task.

SRO Read steps and confirm Immediate Actions Complete.

SRO /RO Check if SI is required - YES SRO /RO Perform EMG E-0 Attach. F for Automatic Signal verification.

RO C

If not previously started then during performance of Attach. F., start the standby CCW pump RO C

If not previously actuated, then during the performance of Attach. F., actuate CIS-A.

SRO/BOP Verify AFW > 270 Klbm/hr.

Close AC HIS-134 Reduce AFW to 270 Klbm/hr Establish S/G Pressure Control SRO /BOP Check PORV/Block Valves.

Check PZR Spray Valves.

Check PZR Safety Valves.

Check if RCPs should be stopped.

SRO Direct Monitoring Critical Safety Function Status Trees using EMG F-0.

SRO /RO Check if S/Gs are not faulted.

Check if S/G Tubes are intact.

Dispatch HP Check S/G levels - controlled increase SRO/RO Check if RCS Intact in Containment

OP-TEST # 1 SCENARIO # 1 Page 14 of 43 NO Ensure BIT inlet and outlets open.

Transition to EMG E-1 SRO Enter and Direct EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

SRO Conduct Transition Brief for EMG E-1.

SRO/RO Check if RCPs should be stopped.

Depending on the timeline of the crew response, RCP trip criteria may exist. If RCS pressure decreases to < 1400 psig it would require the crew to trip all RCPs.

SRO/BOP Check SG Pressures.

Check SG Levels.

SRO/RO Reset SI.

Reset CIS-A and CIS-B.

Termination Criteria:

The Scenario may be terminated after transition to EMG E-1 and SI is reset.

OP-TEST # SCENARIO #

PAGE 15 OF 43 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT RO Start the Standby CCW pump Prior to the end of EMG E-0, Attach. F.

RO Manually actuate CIS-A Prior to the end of EMG E-0, Attach. F.

Only one train is required to be actuated to meet the critical task However if only one train of CRVIS is actuated the other train has to be isolated within 90 minutes..

OP-TEST # SCENARIO #

PAGE 16 OF 43 INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO # 2 Revision 1 Week of March 6, 2006

OP-TEST # 1 SCENARIO #2 Page 17 of 43 Facility: Wolf Creek Generating Station Scenario No.: 2 (Mod) Op-Test No.: 1 Examiners: __________________________ Operators: __________________________

Initial Conditions: 100% power, Normal Operations Turnover:, A Emergency Diesel Generator (EDG) is Out of Service..

Block Valve BB HV-8000A closed and power removed..

due to PORV blowing fuses..

Event No.

Malf. No.

Event Type*

Event Description 1

mWAT06 A

R-ATC C-BOP Circ Water Pump A trips causing a Main Turbine Setback to 80%.

2 mFWM02 C4 I-BOP C SG Level Channel fails high.

3 P24100C P24100D C-ATC Instrument Air to Containment, KA HV-29, fails closed causing a loss of normal charging and letdown.

4 mRCS02A M

330 gpm Steam Generator Tube Rupture on A 5

P19019B P19028B C-ATC Both Essential Service Water Pumps fail to automatically start on Safety Injection 6

mMSS07D C-BOP D SG Atmospheric Relief Valve fails open on Rx Trip.

7 rPRS07 C-ATC Block Valve BB HV-8000B fails to open, affecting RCS depressurization.

Requires entry into contingency procedure EMG C-33 for SGTR with Loss of Pressure Control.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST # 1 SCENARIO #2 Page 18 of 43 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:

The objective of this scenario is to mitigate a Steam Generator Tube Rupture (SGTR) with a loss of Pressure control requiring the use of a Contingency Procedure..

The SRO will evaluate Technical Specifications for the SG Level channel and the Rod Insertion Limit resulting from the Main Generator Setback. The setback also caused a greater than 15% power change in one hour. This requires T.S. surveillance 3.4.16.2 to be run 2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following the power change.

The scenario begins with a trip of a running Circulating Water Pump causing a Turbine Setback. Following the setback is a failure of a SG level instrument. Both require operator actions to stabilize the plant and the use of Off Normal procedures. Prior to the trip there is a Loss of Instrument Air to Containment, also requiring use of an Off Normal Procedure. The crew will have to mitigate the effects on charging and Pressurizer pressure for the loss of air to Containment.

Post trip failures include both Essential Service Water pumps fail to auto start on the Safety Injection. The operator must start at least one pump prior to the end of the scenario. When the crew prepares to de-pressurize the RCS as part of the SGTR mitigation, the PZR Block valve for the only available PORV fails while in the closed position. With Instrument Air already lost to containment and no available means to de-pressurize the RCS, the crew must transition to EMG C-33, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, contingency procedure.

Success path in EMG C-33 is to secure ECCS pumps.

The following is the expected major procedure flow path:

OFN MA-001, LOAD REJECTION OR TURBINE TRIP

OFN SB-008, INSTRUMENT MALFUNCTIONS

OFN KA-019, LOSS OF INSTRUMENT AIR

OFN BB-07A, STEAM GENERATOR TUBE LEAK

EMG E-0, REACTOR TRIP OR SAFETY INJECTION

EMG E-3, STEAM GENERATOR TUBE RUPTURE

EMG C-33, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

RCS Pressure and Temperatures

SG Levels and Pressures

PZR Level and Pressure

Control Rod Positions

OP-TEST # 1 SCENARIO #2 Page 19 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 1 Event

Description:

Circ Water Pump trip, Main Turbine Setback.

Time Position Applicant's Actions or Behavior Notes RO Notes and Communicates annunciator 08A, Circ Water Pump Trip is in Alarm.

Verifies CWP A has tripped.

SRO Direct placing CWP A handswitch in STOP position to start closing discharge valve.

This action should be performed in time to prevent a Unit trip on low vacuum.

SRO Direct dispatching Site Watch to locally close CWP A discharge valve remaining 25%.

ALL Confirm Setback has occurred.

Generator MW load decreasing.

Control rods inserting in Auto.

SRO Enter and Direct OFN MA-001. LOAD REJECTION OOOR TURBINE TRIP BOP Check Turbine Not Tripped.

Checks Stator Cooling - Normal RO Verify Control Rods inserting in Auto in response to Temperature mis-match.

BOP Checks CWPs - all Running Use RNO Ensure Handswitch in stop and Site Watch dispatched.

Reference plant procedures for Circ Water System Operation.

Should already be performed.

RO Check PZR Pressure and Level stable or trending to program. Make adjustments as required.

BOP Check SG Levels stable or trending to program. Make adjustments as required.

BOP Confirm Load Rejection has stopped.

SRO Recognize that at current core life MTC would be negative.

OP-TEST # 1 SCENARIO #2 Page 20 of 43 BOP Verify SG Atmospherics are closed.

Reset C-7 signal to steam dumps by placing Steam Dump Selector switch in reset and return to Tavg mode.

RO/BOP Close FW HTR Bypass Valve AE HV-038.

Use Open Procedure.

SRO Direct crew to maintain stable plant conditions.

SRO If power decreased to <70%, Contact Work Week Manager (WWM) to request INC assistance.

SRO Refer to Tech Specs.

3.1.6 Control Rod Insertion Limits RIL LO and LO-LO annunciators may alarm. Direct boration of the RCS to restore rods within two hours.

3.2.3 Axial Flux Difference The SRO may direct the RO to borate per the 10% down power pre-shift brief.

SRO/BOP Determine SG Safeties remained closed during load rejection.

SRO Determine Thermal Power change was

>15% in one hour and notify Chemistry for sampling.

T.S. requirement to sample 2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following the transient.

The SRO needs to contact chemistry.

SRO/BOP Reset Load Limiter by slowly reducing Load Potentiometer till the Load Limit light extinguishes.

SRO Contact System Operations for Load Requirements.

Termination Criteria: Unit Stable at approximately 80%, Tech Specs identified.

OP-TEST # 1 SCENARIO #2 Page 21 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 2 Event

Description:

C S/G Controlling Level Channel fails high.

Time Position Applicant's Actions or Behavior Notes BOP Notes and communicates annunciator 00-110B, and that C MFRV is going closed.

Takes manual control of C MFRV and stabilizes level at program level (50%).

Stabilize S/G level to prevent a Rx Trip.

SRO Acknowledges communications, enters and directs Alarm Response (ALR 00-110B)

CRS may enter OFN SB-008 directly.

RO Notes and communicates that level indicator AE LI-553 is failing high.

BOP Manually controls MFRV to establish S/G level at program.

Select out failed channel.

Returns MFRV controller to auto.

SRO Enter and direct actions of OFN SB-008, Instrument Malfunctions, Attach. F.

BOP Confirms failed channel, channel has been selected out, monitors S/G level to ensure proper control.

SRO Contact Work Week Manager (WWM) to have I&C troubleshoot and trip bi-stables.

Recognize channel does affect AMSAC.

OP-TEST # 1 SCENARIO #2 Page 22 of 43 OPERATOR ACTIONS Event 2 Continued SRO Refer to and comply with T.S. Actions.

Table 3.3.1-1 Function 14 T.S. 3.3.1, Condition E Table 3.3.2-1, Functions 5b and 6d.

T.S. 3.3.2, Conditions I and D All are 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to trip bi-stables.

SRO Review Attach. S, determine instrument does not affect T.S. 3.3.3 or 3.3.4 for Post Accident or Shutdown Monitoring.

Termination Criteria:

S/G level stable or trending to 50%.

MFRV back in auto and Tech Specs identified.

OP-TEST # 1 SCENARIO #2 Page 23 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 3 Event

Description:

KA-HV-029, Instrument Air to Containment Isolation valve fails closed.

Time Position Applicant's Actions or Behavior Notes RO/BOP Plant response is approximately 60 seconds after KA HV-029 fails.

PZR Spray valves fail closed.

Letdown Isolates

Charging flow to the RCS isolates.

CCW alarms occur due to flow imbalance.

Letdown HX temperature alarms RO/BOP Identify plant response is indicative of a loss of instrument air.

Identify KA HV-029 has closed.

Dispatch Building Watch to investigate.

SRO/RO Place PZR B/U Heaters in Auto to minimize pressure rise.

SRO Enter and Direct OFN KA-019, LOSS OF INSTRUMENT AIR.

SRO Make Plant Announcement.

Check Instrument Air Pressures.

Ensure can still maintain plant control.

SRO/RO Check PZR Level - stable.

Start A CCP

Establish Alternate Seal Injection.

Stop the NCP

Establish Excess Letdown to the PRT.

Should recognize the need to start an A Train CCW pump prior to starting the CCP.

SRO/BOP Continue procedure steps to check for proper operation of Instrument Air system.

SRO Contact WWM for assistance with KA HV-029.

Termination Criteria:

Charging aligned to Alternate Seal Injection, Excess Letdown in Service.

OP-TEST # 1 SCENARIO #2 Page 24 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 4 Event

Description:

Steam Generator Tube Rupture Time Position Applicant's Actions or Behavior Notes SRO/RO BOP Note and communicate RCS pressure is decreasing.

SRO/RO BOP Monitor RCS pressure for entry into DNB Tech. Spec. at < 2220 psig.

T.S. 3.4.1, two hours to restore.

Monitor for DNB T.S.

RO As RCS pressure decreases, may energize PZR B/U heaters.

BOP Note and Communicates that A SG level is increasing.

RO Note and communicate that PZR level is decreasing.

RO/BOP Note and communicate Annunciator 061A and B, Process Rad Hi and Hi-Hi.

SRO Determine from RM-11 panel that GE RE-92, Condenser Off-gas is in alarm.

SRO Enter and direct OFN BB-07A Steam Generator Tube Leakage.

RO Checks PZR Level - decreasing.

Increase charging flow.

May Re-Start the NCP Isolate Letdown.

RO should increase charging flow and isolate letdown.

SRO/RO Check Charging Pump Suction.

Check PZR pressure - stable.

SRO/BOP Check S/G Tubes - intact.

Dispatch HP

Contact Chemistry.

SRO/RO Fold Out Page criteria is met when charging is maximized and PZR level continues to decrease OR SRO determines they cannot maintain PZR Pressure.

The crew may not perform all steps listed for OFN BB-07A.

OP-TEST # 1 SCENARIO #2 Page 25 of 43 SRO Direct Reactor Trip and Safety Injection.

Transition to EMG E-0 Termination Criteria:

Reactor Tripped and Safety Injection Actuated.

OP-TEST # 1 SCENARIO #2 Page 26 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 5 and 6 Event

Description:

Reactor Trip Safety Injection due to SGTR, ESW pumps fail to start and D SG ARV fails open.

Time Position Applicant's Actions or Behavior Notes SRO Enter and Direct actions of EMG E-0, Reactor Trip or Safety Injection.

RO/BOP Perform Immediate Actions of EMG E-0.

RO Verify Rx Trip

Rod Bottom Lights Lit.

Rx Trip and Bypass Bkrs open.

Neutron Flux decreasing (Intermediate Range & Gamma metrics)

Transfer NR-45 recorder to Intermediate Range Verify Vital AC Power

Both NB buses - normal voltage /

aligned to off site power.

Verify SI actuated

Determine SI is actuated.

Annunciators 30A and 31A are lit.

BOP Verify Turbine trip.

Main Stop valves all closed.

Generator and exciter bkrs open.

SRO At completion of Immediate Actions determine if there are any immediate concerns.

RO Notes that no ESW pump is running in either Train and informs SRO.

SRO/RO C

Start at least one ESW pump.

CRITICAL TASK: Start at least one ESW pump prior to the end of Attach. F.

OP-TEST # 1 SCENARIO #2 Page 27 of 43 BOP Determine Cooldown is continuing, Note and communicate D SG ARV is indicating Open.

SRO / BOP C

Take Manual control and close D ARV.

CRITICAL TASK: D ARV must be manually closed or locally isolated prior to a needless orange path occurring or SG pressures less than 275 psi.

SRO Read steps and confirm Immediate Actions Complete.

SRO / RO Check if SI is required - YES SRO / RO Perform EMG E-0 Attach. F for Automatic Signal verification.

RO C

If not previously started then during performance of Attach. F., start at least one ESW pump.

SRO / BOP Verify AFW > 270 klbm/hr.

Close AC HIS-134 Reduce AFW to 270 klbm/hr Establish S/G Pressure Control May discover D ARV open here.

SRO / BOP cont Monitor Fold Out Page. When A SG level exceeds 6% Narrow Range, Isolate all AFW flow to A SG.

SRO / BOP Check PORV/Block Valves.

Check PZR Spray Valves.

Check PZR Safety Valves.

Check Id RCPs should be stopped.

SRO Direct Monitoring Critical Safety Function Status Trees using EMG F-0.

SRO / BOP Check if S/Gs are not faulted.

Check if S/G Tubes are intact.

Dispatch HP Check S/G levels - controlled increase.

SRO / RO Check BIT Inlet and Outlet valves open.

Transition to EMG E-3 TERMINATION:

Transition to EM E-3,STEAM GENERATOR TUBE RUPTURE.

OP-TEST # 1 SCENARIO #2 Page 28 of 43 Op-Test No.: # 1 Scenario No.: 2 Event No.: 7 Event

Description:

EMG C-33, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL Time Position Applicant's Actions or Behavior Notes SRO Enter and Direct EMG E-3, Steam Generator Tube Rupture.

A Transition Brief is not desired nor required when in SGTR procedures.

SRO/RO Check if RCPs should be stopped. Verify RCS pressure >1400.

SRO/BOP C

Identify A SG is ruptured.

Isolate A SG.

ARV set at 1125

Steamline drain isolated

Blowdown and Sampling isolated

Close MSIV

Ensure Steam Bypass closed

Isolate AFW when Level is >6%.

Critical Task: Isolate steam flow from the ruptured SG in time to prevent a transition to EMG C-31, SUBCOOLED RECOVERY.

SRO/RO Establish SG Pressure Control.

Place Steam Dumps in Steam Pressure Mode.

All Verify Ruptured SG isolated.

Hold Point till MSIV is closed.

SRO/BOP Check Ruptured SG >275 psi RO cont Block Low Steam Line Pressure SI when RCS pressure <1970 psi SRO/BOP Determine Target Conditions Initiate RCS Cooldown

Slowly lower setpoint to open Group 1 Steam Dump Valves

When Tavg <P-12, place Steam Dumps in Bypass interlock

Set Steam Dump Potentiometer to Target Value.

Increase AFW flow to intact SGs BOP cont Monitor cooldown; ensure steam dumps begin closing as target temperature is approached.

OP-TEST # 1 SCENARIO #2 Page 29 of 43 SRO/RO Check PZR PORVs and Block Valves Check PZR Safeties.

Reset SI Reset CIS-A and CIS-B SRO/RO Establish Instrument Air to Containment Recognize can not be performed.

SRO/RO cont Stop both RHR pumps.

RO monitor RCS pressure for restart.

SRO/BOP Check if Cooldown should be stopped.

Ensure steam dumps close when target is reached. Adjust controller to maintain below target.

Check Ruptured SG Pressure stable or increasing.

SRO/RO Check Subcooling >50 degrees SRO/RO Depressurize RCS using spray

Normal Spray not available - RNO SRO/RO Depressurize RCS using PORVs When Attempt is made to open the block valve the breaker will trip.

SRO use RNO SRO/RO Depressurize RCS using Aux Spray in Attach D of EMG E-3.

SRO Attach D, step 1, if KA HV-029 is closed then use RNO.

Transition to EMG C-33, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL>

Termination Criteria:

EMG E-3 completed to Attach D.

Transition to EMG C-33

OP-TEST # 1 SCENARIO #2 Page 30 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 7 Event

Description:

EMG C-33, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL Time Position Applicant's Actions or Behavior Notes SRO Enter and Direct EMG C-33 A Transition Brief is not desired nor required when in SGTR procedures.

SRO/BOP Check Ruptured SG Level <78%

RNO go to step 13 If level has not reached 78% at this time the crew will work through the RNOs of the procedure and eventually end up at step 13.

SRO/RO/

BOP Check if SI can be Terminated.

Subcooling >30 degrees

SG levels or AFW Flow

RVLIS level

Ruptured SG level SRO/RO C

Stop ECCS pumps.

All but one CCP

Stop both SI pumps

Stop both RHR pumps Critical Task: ECCS pumps must be secured prior to the SG Safety on the Ruptured SG lifting due to water solid conditions.

Termination Criteria:

The Scenario may be terminated when all ECCS pumps are secured except for one CCP.

OP-TEST # SCENARIO #

PAGE 31 OF 43 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT RO Start Both ESW pumps.

At Least one ESW pump must be started to supply cooling to an ECCS train prior to the end of EMG E-0 Attach. F.

BOP Close or Isolate D SG ARV Manually close or locally isolate prior to a needless orange path occurring or SG pressures less than 275 psi.

BOP Isolate Ruptured SG Isolate steam flow from the ruptured SG in time to prevent a transition to EMG C-31 RO Secure ECCS pumps.

ECCS pumps must be secured prior to the SG Safety on the Ruptured SG lifting due to water solid conditions.

OP-TEST # SCENARIO #

PAGE 32 OF 43 INITIAL LICENSE EXAM OPERATING TEST # 1 SCENARIO # B/U Revision 0 Week of March 06, 2006

OP-TEST #1 SCENARIO #B/U Page 33 of 43 Facility: Wolf Creek NRC Scenario No.:

B/U Op-Test No.: 1 Revision 0 Source:

New _ Bank - Significantly Modified X Bank - Initial Condition Change____

Initial Conditions: 100% Power, MOL, A MDAFWP is OOS for bearing replacement.

A Safety Injection Pump is OOS for oil change.

Turnover: Maintain current plant conditions. Severe Thunderstorms western Kansas.

Event No.

Malf.

No.

Event Type*

Event Description 1

mPRS0 3A C-ATC Pzr Spray Valve fails full open in Automatic.

2 mEPS0 3F R-ATC N-BOP Rapid Down power due to loss of one 345 Kv line.

3 mMSS1 3

I-BOP Steam Header Pressure Channel fails low. (Affects both MFPs) 4 mFWM 20 M-ALL Main Feed Line break in Turbine Building 5

mAFW 02B C BOP TDAFW pump fails to autostart.

6 IOR P01055 B

C-ATC A CCP fails to Auto Start on Safety Injection.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST #1 SCENARIO #B/U Page 34 of 43 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:

The objective for this scenario is to mitigate a Loss of Heat Sink event by initiating feed and bleed using plant procedures. Initial conditions have one Aux Feedwater (AFW) pump and one Safety Injection (SI) pump out of service for maintenance. The scenario contains a steam header pressure instrument failure and failure of the controller for one PZR spray valve. All will require operator action to prevent a reactor trip.

The SRO will evaluate technical specifications associated with DNB during the Spray Valve Failure and the Projected Degraded Grid Voltage.

The major event is a feed line break in the turbine building and a subsequent loss of the Turbine Driven AFW pump. This places the crew in a red path, Loss of Heat Sink, functional recovery procedure. The crew will meet requirements to initiate bleed and feed to the reactor coolant system (RCS). The crew must realize that the only available high head injection pump did not autostart and manually start it to establish a feed path to the RCS. The scenario terminates when the crew has completed the bleed and feed portion of the functional recovery procedure.

The following is the expected major procedure flow path:

OFN SB-008, INSTRUMENT MALFUNCTIONS

OFN AF-025, UNIT LIMITATIONS

OFN MA-038, RAPID PLANT SHUTDOWN

OFN SB-008, INSTRUMENT MALFUNCTIONS

EMG E-0, REACTOR TRIP OR SAFETY INJECTION

EMG ES-02, REACTOR TRIP RESPONSE

EMG FR-H1, LOSS OF HEAT SINK CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

S/G Wide Range Levels

RCS and PZR pressure

Hot Leg/Incore Temperatures

High head injection flow (BIT)

PZR PORV and block valve status.

RCS Tavg and Turbine Tref

SG NR levels

OP-TEST #1 SCENARIO #B/U Page 35 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: B/U Event No.: 1 Event

Description:

PZR Spray Valve A fails full open in Automatic. BB PCV-455B.

Time Position Applicant's Actions or Behavior Notes RO/BOP/

SRO Note and Communicate that RCS pressure is decreasing.

RO/BOP/

SRO Monitor RCS pressure for entry into DNB Tech. Spec. at < 2220 psig.

T.S. 3.4.1, two hours to restore.

SRO/RO As RCS pressure decreases to < 2220, the crew may energize 2nd set of PZR back-up heaters.

RO Note and communicate A Spray valve is failing open.

Place A spray controller in Manual and close A spray valve.

A spray controller must be placed in Manual and closed in time to prevent a Rx Trip.

SRO Enter and direct OFN SB-008, Instrument Malfunctions, Attachment V.

RO Verify A Spray Valve controller failed open in auto and is now in manual/closed.

SRO Contact WWM to request I&C repair failed channel.

Termination Criteria:

A Spray Valve Controller in manual/closed. RCS pressure stable at or trending to program (2235).

OP-TEST #1 SCENARIO #B/U Page 36 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: B/U Event No.: 2 Event

Description:

Rapid Power Reduction due to Loss of 345 Kv Line and Predicted Degraded Grid Voltage (Cue may be provided from Shift Manager to reduce power at 1% per minute.)

Time Position Applicant's Actions or Behavior Notes SRO Receive call from WESTAR Transmission Services that the Benton Line has failed.

Determine this is an entry condition for OFN AF-025.

SRO Enter OFN AF-025, UNIT LIMITATIONS SRO Determine from OFN, Attach. A, page 3 that maximum generator load is 950 MWE net, (995 MWE gross)

SRO Enter and direct actions of OFN MA-038.

Conduct Reactivity Brief with board operators. Pre-Shift brief for reduction to 90%.

Crew should commence 10%

downpower from pre-shift brief then determine remaining actions.

RO Calculate Boration required.

155 gallons at 15.4 gpm.

SRO/BOP Check AE HV-038 - Closed BOP (Continuous)

Establish 1% per minute power decrease on the Load Set potentiometer.

Press Decrease Load till Load Limit light is out.

Select 1%/Minute ON.

Decrease Loading Rate - ON.

Decrease Load Set, maintain within 200 MW of actual load.

RO (Continuous)

Use rods to maintain Tavg/Tref error between 0 and +5

Energize both PZR B/U heaters.

Borate and adjust rods as necessary to maintain rods above RIL.

RO/BOP

Check PZR PORV / Block Valves

Check PZR Pressure

Check PZR Level

OP-TEST #1 SCENARIO #B/U Page 37 of 43 OPERATOR ACTIONS EVENT 2 Continued.

BOP (Continuous)

Control S/G levels to maintain 45-55%.

SRO Check Reactor Power < 60%. Recognize hold point in procedure SRO Receive call from WESTAR Transmission Services that predicted grid voltage from the model is 98%.

SRO Recognize entry condition to OFN AF-025.

SRO Determine from step 8 to refer to Attach. E of the OFN. Per the note on the Attach.

Declare both Off Site sources in-operable and refer to T.S 3.8.1 SRO Determine T.S. 3.8.1 Condition C applies.

Will have to return A AFW and A SI pumps to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the B AFW and B SI in-operable requiring entry into T.S. 3.0.3.

AND Restore at least one offsite source within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Termination Criteria:

Power Reduction in Progress. Rods have automatically stepped in. T.S. 3.8.1 Condition C identified.

OP-TEST #1 SCENARIO #B/U Page 38 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 3 Event

Description:

Steam Header Pressure Channel fails low. (Affects both MFPs)

Time Position Applicant's Actions or Behavior Notes BOP Notes and communicates that level is decreasing in all four S/Gs.

SRO/BOP Communicate and takes manual control of the Master MFP Speed controller.

Master Speed Controller must be placed in manual and SG levels stabilized in time to prevent a Rx Trip.

RO/BOP Identify Steam Header Pressure channel 507 has failed low.

SRO Enter and direct OFN SB-008, Instrument Malfunctions, Attachment B.

RO/BOP Verify Steam Header Pressure channel malfunction.

Check Steam Dump select switch NOT in Steam Pressure Mode.

BOP (Continuous)

Manually control MFP speed.

Establish dP IAW Figure 1.

(Operator may match steam and feed flows, then adjust MFP speed to maintain FRVs positioned at ~ 80%.)

At 100% power Main Feed header pressure should read

~165 psi higher than S/G pressure.

BOP Place Steam Header Pressure Controller in manual.

SRO Contact WWM to request I&C repair failed channel.

Termination Criteria:

MFP speed controller in manual, all S/G levels stable or trending to program level (50%).

OP-TEST #1 SCENARIO #B/U Page 39 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 4 Event

Description:

Main Feed Line break in Turbine Building.

Time Position Applicant's Actions or Behavior Notes BOP Note and communicate level decreasing in all four S/Gs.

BOP Acknowledge and communicate alarms RO/BOP SRO Note S/G Levels are approaching Rx Trip setpoint.

SRO Direct a Rx Trip or respond to a Rx Trip and enter EMG E-0.

RO Verify Rx Trip

Rod Bottom Lights Lit.

Rx Trip and Bypass Bkrs open.

Neutron Flux decreasing (Intermediate Range & Gamma metrics)

Transfer NR-45 recorder to Intermediate Range Verify Vital AC Power

NB01 normal voltage / off site power.

Determine SI is NOT actuated.

BOP Verify Turbine Trip

Main Stop valves all closed.

Generator and exciter bkrs open.

RO Verify SI NOT required

RCS Press> 1830 PSIG

All S/G Press > 615 psig

Ctmt Press < 3.5 psig

RCS Subcooling > 30 degrees

PZR Level > 6%

OP-TEST #1 SCENARIO #B/U Page 40 of 43 OPERATOR ACTIONS Event 4 (Continued)

SRO Ensure Immediate Actions complete.

Identify any immediate concerns.

BOP Note and Communicate that B AFW pump has tripped and the TDAFW pump has failed to auto start.

SRO/BOP C

Manually start the TDAFW pump.

CRITICAL TASK: The TDAFW pump must be started prior to tripping all RCP in EMG FR-H1, LOSS OF HEAT SINK. Crew may use ALR 00-128B.

SRO/BOP Secure all Condensate Pumps and Heater Drain Pumps after Immediate actions are complete.

Management Expectation is to NOT perform any other actions till the immediate actions are complete. With a feed break in the Turbine Building it is expected to secure running secondary pumps.

SRO/RO BOP Using procedure verify Immediate Actions of EMG E-0 complete SRO Direct Operator to Monitor CSFSTs and Transition to EMG ES-02 from Step 4 RNO.

Termination Criteria: EMG E-0 Immediate Actions completed, transition is made to EMG ES-02.

OP-TEST #1 SCENARIO #B/U Page 41 of 43 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: B/U Event No.: 5 and 6 Event

Description:

Loss of Heat Sink, failure of high head Injection.

Time Position Applicant's Actions or Behavior Notes SRO Conduct Transition Brief for entry to EMG ES-02.

Crew may enter EMG FR-H1 directly based on timing of report of red path.

RO Perform EMG F-0 for CSFST SRO/RO BOP (Continuous)

Monitor CSFST on NPIS computer screen after 1st verification with the procedure.

BOP Note that AFW flow is zero to all S/Gs.

May attempt to open all AFW valves.

Note and report that zero flow is indicated to all S/Gs.

TDAFW pump trips.

SRO Recognize that entry conditions are met for RED path on EMG FR-H1, Loss of Heat Sink. Transition to EMG FR-H1.

After transition to FR-H1 the crew will be watching for Fold Out Page Criteria to go to the steps for Feed and Bleed.

SRO Try to establish AFW Flow.

Determine from Building reports that No AFW pump is available.

If Fold Out page is met the crew will go directly to step 27 and initiate bleed and feed.

BOP Close all AFW valves RO/BOP Reduce heat input to RCS.

Stop all RCPs Turn off all PZR heaters (3)

BOP IF MSIVs are open, align Steam Dumps.

Place PK-507 in Manual, setpoint at 7.28, select Steam Pressure Mode, return PK-507 to auto.

IF MSIVs are closed, then use ARVs.

Ensure ARV setpoints at 1125 psig.

OP-TEST #1 SCENARIO #B/U Page 42 of 43 OPERATOR ACTIONS Events 5 and 6 (Continued)

SRO Verify Condensate/Feedwater systems available.

Based on Building reports, determine the Main Feedwater header is unavailable.

Recognize to use the RNO and this places the crew in a loop from step 1 to step 9.

SRO Conduct Quick Brief with crew.

In a procedure loop till the Fold Out Page is met or meet a step criterion.

Crew Monitor S/G WR levels. As level reaches 26% proceed to step 29 and initiate bleed and feed.

Perform Step for Bleed and Feed.

RO/BOP Stop all RCPs Turn off all PZR heaters May have already performed.

RO Actuate Safety Injection Recognize that B CCP and B SI have tripped and A CCP failed to auto start.

RO (C)

Manually start A CCP.

Checks BIT flow indicated on EM FI-917A.

Ensures Feed Path Established RO/BOP (C)

ARM both Cold Overpressure Protection circuits.

Ensure Both Block Valves open.

Open both PZR PORVs.

Ensures Bleed Path Established RO/BOP Verifies BOTH Block valves and BOTH PORVs are open.

Termination Criteria: Bleed and Feed established per steps 29-33 of EMG FR-H1.

Scenario may be terminated anytime after bleed and feed has been established.

OP-TEST #1 SCENARIO #B/U Page 43 of 43 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT BOP Manually start the TDAFW pump The TDAFW pump must be started prior to tripping all RCP in EMG FR-H1, LOSS OF HEAT SINK.

RO/BOP Initiate SI and manually start A Centrifugal Charging Pump to ensure a Feed path, Bleed and Feed must be established prior to S/G dry out.

(3 S/Gs < 8% WR)

RO/BOP Ensure PORVs/Block valves open for a Bleed path.

Bleed and Feed must be established prior to S/G dry out.

(3 S/Gs < 8% WR)

Administrative RO A1.a JOB PERFORMANCE MEASURE JPM NO: RO A1.a K/A NO: 2.1.20 COMPLETION TIME: 20 Minutes K/A RATING: 4.3 JOB TITLE: RO REVISION: 0 TASK TITLE: Perform STS BG-001, Born Injection Flowpath Verification.

Ability to execute procedure steps.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

Administrative SRO.A.1.a JOB PERFORMANCE MEASURE JPM NO: SRO-A.1.a K/A NO: 2.1.5 COMPLETION TIME: 10 Minutes K/A RATING: 3.4 JOB TITLE: SRO REVISION: 0 TASK TITLE: Shift Staffing, Work Hour Limitations Ability to locate and use procedures and directives related to shift staffing and activities.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

AP 13-001, Guidelines for WCGS Staff Working Hours TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A.1.a Page 1 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1.

Initiating Cues:

You are the Control Room Supervisor and one of the assigned ROs called in sick. You need to find a replacement RO. Assuming today is March 7th (0600), based on their work hour history evaluate whether any of the following 5 ROs could perform safety-related functions until 1900 without advanced approval. Assume the work hours will start at 0630 and 1/2 hour will be considered turnover time. For each candidate indicate whether the answer is yes or no.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide cue sheet.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have determined the correct status for at least 4 of the 5 RO and not select an RO that could not work.

START TIME:

STOP TIME:

SRO A.1.a TASK NUMBER - ELEMENT CUE STANDARD SCORE Page 2 of 3

1.

Provide candidate with completed copy of the initiating cue Candidate should locate procedure AP 13-001, Guidelines for WCGS Staff Working Hours and review JPM initiating cue

2. *Review work hour history and determine that only 2 of the 5 ROs could work without advanced approval.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Pass criteria is 4 of the 5 ROs work hour status being correctly determined and not select an RO that could not work RO1 - no, would work 16.5 hrs straight RO2 - Yes, would work 24 hrs in 48 hrs RO3 - No, would be 17.5 hrs in 24 and less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months between work periods RO4 - Yes, would work 70 hrs in 7 days RO5 - No, would work 24.5 hrs in 48 hrs S U Comments:

SRO A.1.a Page 3 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1.

Initiating Cues:

You are the Control Room Supervisor and one of the assigned ROs called in sick. You need to find a replacement RO. Assuming today is March 7th (0600), based on their work hour history evaluate whether any of the following 5 ROs could perform safety-related functions until 1900 without advanced approval. Assume the work hours will start at 0630 and 1/2 hour will be considered turnover time. For each candidate indicate whether the answer is yes or no.

Operator Feb 28 March 1st March 2nd March 3rd March 4th March 5th March 6th March 7th RO1 0630 -

1900 0630 -

1900 OFF OFF OFF 0700 -

1530 0700 -

1530 On at 0000 RO2 OFF OFF OFF 0630 -

1900 0630 -

1900 RO3 OFF 0630 -

1900 0630 -

1900 OFF OFF 1300-2400 RO4 Off 0630 -

1900 0630 -

2230 0630 -

2030 OFF OFF RO5 0630 -

1900 OFF OFF OFF 0630 -

1900 0630 -

1930

1. RO1

2. RO2

3. RO3

4. RO4

5. RO5

Administrative SRO A.1.b Page 4 of 3 JOB PERFORMANCE MEASURE JPM NO: SRO-A1B K/A NO: 2.1.25 COMPLETION TIME: 20 Minutes K/A RATING: 3.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: Determine Time to Boil and Core Uncovery based on a loss of Shutdown Cooling.

Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN EJ-015 TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A.1.b Page 1 of 26 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Today is March 17th. You are a spare licensed operator in the Control Room for Outage Support. The plant is in Mode 5 with water level in the reactor vessel at 3.5 feet below the vessel flange. Train A Residual Heat Removal (RHR) is in operation cooling the reactor core. Train B RHR System is in Standby. Reactor Coolant System temperature is 180°F. The reactor was shutdown on March 8th after operating at 100% power for the last 100 days.

Initiating Cues: Train A Residual Heat Removal pump tripped. Attempts to start B RHR pump are unsuccessful. The Control Room staff has entered procedures to mitigate the event. The Control Room Supervisor directs you to determine the following using the appropriate procedure:

1. the time to boiling

2. the time to start of core uncovery.

3. the time to complete core uncovery.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have determined from OFN EJ-015, LOSS OF SHUTDOWN COOLING, the answers for the above questions.

START TIME:

STOP TIME:

SRO A.1.b TASK NUMBER - ELEMENT CUE STANDARD SCORE Page 2 of 26

3.

Locate Copy of OFN EJ-015, and step 30.

Must determine that the crew would be in OFN EJ-015 and step 30 refers to the graphs.

4.

Check plant - IN REDUCED INVENTORY CONDITION.

Recognize the initiating cues stated the water level in the reactor vessel is 3.5 feet below the vessel flange.

Answer: YES

5. *Estimate time to boiling using FIGURE 5 Locate Figure 5 of OFN EJ-015.

Recognize it has been 9 days since shutdown and that the vessel is not pressurized. Answer: 14 minutes +/- 1.

6. *Estimate time to onset of core uncovery using FIGURE 6.

Locate Figure 6 of OFN EJ-015.

Recognize it has been 9 days since shutdown. Utilize the ONSET OF CORE UNCOVERY graph line.

Answer: 127 minutes +/- 5.

7. *Estimate time to complete core uncovery using FIGURE 6.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Locate Figure 6 of OFN EJ-015.

Recognize it has been 9 days since shutdown. Utilize the COMPLETE CORE UNCOVERY graph line.

Answer: 268 minutes +/- 5.

S U Comments:

Indicates Critical Task

SRO A.1.b Page 3 of 26 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Today is March 17th. You are a spare licensed operator in the Control Room for Outage Support. The plant is in Mode 5 with water level in the reactor vessel at 3.5 feet below the vessel flange. Train A Residual Heat Removal (RHR) is in operation cooling the reactor core. Train B RHR System is in Standby. Reactor Coolant System temperature is 180°F. The reactor was shutdown on March 8th after operating at 100% power for the last 100 days.

Initiating Cues: Train A Residual Heat Removal pump tripped. Attempts to start B RHR pump are unsuccessful. The Control Room staff has entered procedures to mitigate the event. The Control Room Supervisor directs you to determine the following using the appropriate procedure:

1. the time to boiling

2. the time to start of core uncovery.

3. the time to complete core uncovery.

Administrative SRO A.2 Page 4 of 26 JOB PERFORMANCE MEASURE JPM NO: SRO-A2 K/A NO: 2.2.13 COMPLETION TIME: 15 Minutes K/A RATING: 3.8 JOB TITLE: SRO REVISION: 0 TASK TITLE: Review a Clearance Order for approval and identify the critical errors.

Knowledge of tagging and clearance procedures.

DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

Drawings: M-12EN01, M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04 Procedure: AP 21E-001 CLEARANCE ORDERS TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A2 Page 1 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is Mode 1. You are the Work Controls SRO. Containment Spray Pump B has a developed a serious leak on its discharge flow element EN FE-011. The on shift crew has prepared a Clearance Order and the Shift Manager requests you perform the tagging authority review.

Initiating Cues:

The Control Room Supervisor has sent the clearance over for you to release for hanging.

Review the clearance order and identify three critical errors.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Have copies of the following drawings to replace any marked up by the examinee.

M-12EN01, M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have rejected the clearance order based on the three critical errors.

START TIME:

STOP TIME:

SRO A2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 5

8.

Locates the proper drawings.

May locate in any sequence.

M-12EN01 M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04 S U Comments:

9. *Identifies the 3 critical errors on the clearance order.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Can be identified in any sequence.

1. Breaker listed for BN HV-03 is for BN HV-04.

2. Breaker listed for EN HV-07 is actually the cubicle for a relay and not the breaker.

3. EN V-024, RWST Test line valve is for wrong train. Should be EN V-025.

S U Comments:

SRO A2 Page 3 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is Mode 1. You are the Work Controls SRO. Containment Spray Pump B has a developed a serious leak on its discharge flow element EN FE-011. The on shift crew has prepared a Clearance Order and the Shift Manager requests you perform the tagging authority review.

Initiating Cues:

The Control Room Supervisor has sent the clearance over for you to release for hanging.

Review the clearance order and identify three critical errors.

Administrative SRO A.3 Page 4 of 5 APF 21E-001-01, Rev. 02 WOLF CREEK GENERATING STATION CLEARANCE ORDER Clearance Number: S-EN-9000 Date/Time:Today Component Desired: EN FE-011 Work To Be Done: Shift Manager request Reason For Clearance Requestor Date/Time Tags to be Hung by Estimated Date/Time of completion Fire System(s)

Effected Excessive leakage SM Today N/A Shift Managers Approval To Remove Equipment From Service And Hang Tags Prepared By:

Tagging Authority Review:

Shift Manager:

Date/Time:________/________ Effective Date/Time:________/________

Clearance Order Acceptance Work Order and Step Phone Ext ACAD Date/Tim e

Groun d Tag Issued Clearance Order Release Date/Time Ground Tag Retrnd.

Date/Tim e Ground Removed Shift Managers Approval To Remove Tags Restoration Section Prepared By:

Restoration Review (SR Only):

Shift Manager:

Date/Time:______/______ EOL REVIEWED FOR RETEST:

Special Instructions/Reference Documents/Clearance Order Summary Change To Clearance Form Made?

Yes / No

Administrative SRO A.3 Page 5 of 5 FORM APF 21E-001-02 REV 01 CLEARANCE ORDER CONTINUATION SHEET Clearance Number: S-EN-9000 Page: __1 0f 1 Components Required to Clear Equipment Placement Section Restoration Component Tagged Component Description Position Seq.

Tagged By Verefied By Position Seq. Removed By Verified By EN HIS-09 CTMT SPRAY PUMP B PULL TO LOCK 1

BN HIS-03 RWST to CTMT SPRAY PUMP B CLOSED 2

EN HIS-12 CTMT SPRAY PUMP B DISCHARGE CLOSED 2

EN HIS-07 CTMT SUMP TO CTMT SPRAY PUMP B CLOSED 2

NB0203 STMT SPRAY PUMP B SUPPLY BKR OPEN/

RACKED DOWN 3

NG01AEF2 BN HV-03 SUPPLY BKR Verified OFF 3

NG02BBR1 EN HV-12 SUPPLY BKR Verified OFF 3

NG02BFR1 EN HV-07 SUPPLY BKR Verified OFF 3

BN HV-03 RWST to CTMT SPRAY PUMP B HANDWHEEL CLOSED 4

EN HV-12 CTMT SPRAY PUMP B DISCHARGE HANDWHEEL CLOSED 4

EN V-100 EDUCTOR TO SPRAY PUMP B

CLOSED 4

EN V-024 RWST TEST LINE ISOLATION CLOSED 4

EN V-068 CTMT SPRAY PUMP B DRAIN OPEN 5

EN V-115 CTMT SPRAY PUMP B VENT OPEN 5

Administrative SRO A.3 Page 6 of 5 JOB PERFORMANCE MEASURE JPM NO: SRO-A3 K/A NO: 2.3.1 COMPLETION TIME: 10 Minutes K/A RATING: 3.0 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given a Radiological Survey Map and Radiation Work Permit determine the Radiological conditions and controls required.

Knowledge of 10 CFR: 20 and related facility radiation control requirements DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A3 Page 1 of 3 Staging: Begin this JPM in the hall outside Access Control at the RWP desk.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. You are a spare licensed operator on shift.

Initiating Cues:

The Control Room Supervisor states they have received a sump alarm on the B RHR Pump room sump and asks you to investigate. Given the survey map, determine the RWP that you would use. Evaluate the radiological conditions in the area and provide the requested information to the following questions.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide survey map.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have correctly answered the three questions.

START TIME:

STOP TIME:

SRO A3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 3

10. *Reviews survey map and determines RWP.

RWP 06-005 should be selected S U Comments:

11. *Identify the classification for the room the sump is located in.

High Radiation Area.

Based on the 2 at the doorway to the RHR pump room.

S U Comments:

12. *Determine time till dosimeter will alarm in 300 mr/hour field.

Immediately.

RWP rate setting is 125 mr/hour.

S U Comments:

13. *Identify the areas on the Survey Map that require any special HP controls prior to accessing.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Based on Special Instruction 3# on the RWP.

1. The room itself due to High Radiation Area.

2. The RHR pump seal housing due to Highly Contaminated Area.

3. The RHR pump room sump due to Highly Contaminated Area.

Identify at least two of the three areas.

S U Comments:

Page 3 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. You are a spare licensed operator on shift.

Initiating Cues:

The Control Room Supervisor states they have received a sump alarm on the B RHR Pump room sump and asks you to investigate. Given the survey map, determine the RWP that you would use. Evaluate the radiological conditions in the area and provide the requested information to the following questions.

NOTE: Circle the correct answers or write them down for the following questions and provide the evaluator with your completed paperwork.

1. The area where the sump is located is a:

A) Potential Hot Particle Area B) Contaminated Area C) High Radiation Area D) Radiation Area

2. If you had to access the pump discharge piping immediately in front of the RHR Pump, how long before your dosimeter would alarm.

A) Immediately B) 4 minutes C) 15minutes D) 25 minutes

3. Identify the areas on the Survey Map that require HP notification prior to accessing.

Administrative (Simulator Scenario #1) SRO A.4.1 Page 4 of 5 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: SRO A.4 K/A NO: 2.4.41 COMPLETION TIME: 15 Minutes K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

Knowledge of the emergency action level thresholds and classifications.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A-4.1 Scenario #1 PAGE 1 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the acting Shift Manager.

Initiating Cues:

Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM.. (PIR 2003-2930)

Task Standard:

Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.

START TIME:

STOP TIME:

SRO A-4.1 Scenario #1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 2 of 3

1. *This classification is for Scenario #1

2. *Perform Attachment A of EPP 06-006 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 EAL 3-LRCB1 - Yes 3-LRCB2 - Yes 3-LRCB3 - No 3-LRCB5 - Yes 3-LRCB6 - No 3-LRCB7 - No Alert PAR Perform Attachment A of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 3, 4, 5, 7, and 8 are critical S U Comments:

SRO A-4.1 Scenario #1 PAGE 3 of 3 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the acting Shift Manager.

Initiating Cues:

Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

Administrative (Simulator Scenario #2) SRO A.4.2 PAGE 3 of 3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: SRO A.4 K/A NO: 2.4.41 COMPLETION TIME: 15 Minutes K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

Knowledge of the emergency action level thresholds and classifications.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

SRO A-4 Scenario #2 PAGE 1 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the acting Shift Manager.

Initiating Cues:

Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM.. (PIR 2003-2930)

Task Standard:

Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.

START TIME:

STOP TIME:

SRO A-4 Scenario #2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 2 of 3

2. *This classification is for Scenario #2

2. *Perform Attachment A of EPP 06-006 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 EAL 2-SGTF1 - Yes 2-SGTF2 - No 2-SGTF9 - Yes 2-SGTF10 - No 2-SGTF12 - No ALERT PAR Perform Attachment A of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 4, 5, 7, and 8 are critical S U Comments:

SRO A-4 Scenario #2 PAGE 3 of 3 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the acting Shift Manager.

Initiating Cues:

Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

RO A1.a Page 2 of 19 Simulator Set Up:

IC 30 Use the Fuse/Breaker Remote function and remove power from B BATP (PBG02B)

Use the Fuse/Breaker Remote function and remove power from Excess Letdown Valve BG HV8154A.

Hang DNO Tags on BG HIS-8154A and B BATP Handswitch.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. Boric Acid Transfer Pump B is tagged for out for seal replacement.

The pump breaker is off and its inlet and outlet isolations are tagged closed. Excess Letdown Valve BG HV-8154A has its breaker tagged open due to electrical faults.

Initiating Cues:

The Control Room Supervisor directs you to perform STS BG-001, BORON INJECTION FLOW PATH VERIFICATION.

Except for manual valves listed above, ALL other manual valves are in their normal CKL or Locked Component Log positions.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide STS BG-001 with Cover Sheet completed for Authorization to begin.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have identified the Boration and Letdown Flowpaths for the STS.

START TIME:

STOP TIME:

RO A1.a TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 3 of 19

1.

Review Procedure.

Determine Section 8.1 must be performed for current Mode.

Initial Conditions State Mode 1.

S U Comments:

2. *Perform Step 8.1.1.1 and 8.1.1.2 to verify RWST to RCS flowpath.

If candidate asks for local verification of valve positions can restate Initial Conditions or provide the following positions as required.

OPEN valves BG 8471A BG 8471B BG 8485A BG 8485B BG 8483A BG 8483C BG 8483B BG 8402A BG 8402B EM V-107 EM V-108 EM V-109 EM V-110 Completes Figure 1.

On Panel RL001/2.

Notes that the Blue Placard is on the A Train CCP and should use the B CCP for the line up.

Circles PBG05B in Step 8.1.1.2 See key.

S U Comments:

3. *Perform Step 8.1.1.3 to verify PORVs available.

Completes Figure 4.

At Panel RL021/22 Verifies that both PORV and Block valves are available See key.

S U Comments:

RO A1.a TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 4 of 19

4. *Perform Step 8.1.1.4 to verify Excess Letdown Flow Path Completes Figure 4.

On Panel RL001/2 Recognize BG HV-8154A is Tagged out.

See Key S U Comments:

5. *Perform Step 8.1.2 to verify BAST to RCS flowpath.

If candidate asks for local verification of valve positions, restate Initial Conditions or provide the following positions:

CLOSED Valves:

BG V-8465A BG V-8465B BG V-8475 BG V-166 BG V-173 BG V-172 OPEN Valves:

BG V-8461A BG V-8463 BG V-148 BG V-149 BG V-152 BG V-8471A BG V-8485A BG V-8471B BG V-8485B Completes Figure 2.

Must use A CCP (PBG05A) to complete flow path.

Recognizes B Transfer Pump is not available Recognize same Excess Flow Path can be used.

See Key

6.

Complete Procedure THE JPM IS Complete Record Stop Time.

N/A remaining steps in Procedure.

Sign Cover Sheet and return to the SRO.

S U Comments

RO A1.a Page 5 of 19 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. Boric Acid Transfer Pump B is tagged for out for seal replacement.

The pump breaker is off and its inlet and outlet isolations are tagged closed. Excess Letdown Valve BG HV-8154A has its breaker tagged open due to electrical faults.

Initiating Cues:

The Control Room Supervisor directs you to perform STS BG-001, BORON INJECTION FLOW PATH VERIFICATION.

Except for manual valves listed above, ALL other manual valves are in their normal CKL or Locked Component Log positions.

Administrative RO A.1.b Page 6 of 19 JOB PERFORMANCE MEASURE JPM NO: RO-A1B K/A NO: 2.1.25 COMPLETION TIME: 20 Minutes K/A RATING: 2.8 JOB TITLE: RO REVISION: 0 TASK TITLE: Determine Time to Boil and Core Uncovery based on a loss of Shutdown Cooling.

Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN EJ-015 TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

RO A.1.b Page 1 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Today is March 17th. You are a spare licensed operator in the Control Room for Outage Support. The plant is in Mode 5 with water level in the reactor vessel at 3.5 feet below the vessel flange. Train A Residual Heat Removal (RHR) is in operation cooling the reactor core. Train B RHR System is in Standby. Reactor Coolant System temperature is 180°F. The reactor was shutdown on March 8th after operating at 100% power for the last 100 days.

Initiating Cues: Train A Residual Heat Removal pump tripped. Attempts to start B RHR pump are unsuccessful. The Control Room staff has entered procedures to mitigate the event. The Control Room Supervisor directs you to determine the following using the appropriate procedure:

1. the time to boiling

2. the time to start of core uncovery.

3. the time to complete core uncovery.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have determined from OFN EJ-015, LOSS OF SHUTDOWN COOLING, the answers for the above questions.

START TIME:

STOP TIME:

RO A.1.b TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 3

7.

Locate Copy of OFN EJ-015, and step 30.

Must determine that the crew would be in OFN EJ-015 and step 30 refers to the graphs.

8.

Check plant - IN REDUCED INVENTORY CONDITION.

Recognize the initiating cues stated the water level in the reactor vessel is 3.5 feet below the vessel flange.

Answer: YES

9. *Estimate time to boiling using FIGURE 5 Locate Figure 5 of OFN EJ-015.

Recognize it has been 9 days since shutdown and that the vessel is not pressurized. Answer: 14 minutes +/- 1.

10. *Estimate time to onset of core uncovery using FIGURE 6.

Locate Figure 6 of OFN EJ-015.

Recognize it has been 9 days since shutdown. Utilize the ONSET OF CORE UNCOVERY graph line.

Answer: 127 minutes +/- 5.

11. *Estimate time to complete core uncovery using FIGURE 6.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Locate Figure 6 of OFN EJ-015.

Recognize it has been 9 days since shutdown. Utilize the COMPLETE CORE UNCOVERY graph line.

Answer: 268 minutes +/- 5.

S U Comments:

RO A.1.b Page 3 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Today is March 17th. You are a spare licensed operator in the Control Room for Outage Support. The plant is in Mode 5 with water level in the reactor vessel at 3.5 feet below the vessel flange. Train A Residual Heat Removal (RHR) is in operation cooling the reactor core. Train B RHR System is in Standby. Reactor Coolant System temperature is 180°F. The reactor was shutdown on March 8th after operating at 100% power for the last 100 days.

Initiating Cues: Train A Residual Heat Removal pump tripped. Attempts to start B RHR pump are unsuccessful. The Control Room staff has entered procedures to mitigate the event. The Control Room Supervisor directs you to determine the following using the appropriate procedure:

1. the time to boiling

2. the time to start of core uncovery.

3. the time to complete core uncovery.

Administrative RO A.2 Page 4 of 3 JOB PERFORMANCE MEASURE JPM NO: RO-A2 K/A NO: 2.2.13 COMPLETION TIME: 20 Minutes K/A RATING: 3.6 JOB TITLE: RO REVISION: 0 TASK TITLE: Prepare a Clearance Order to remove a leaking pump from service.

Knowledge of tagging and clearance procedures.

DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

Drawings: M-12EN01, M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04 Procedure: AP 21E-001 CLEARANCE ORDERS TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

RO A2 Page 1 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is Mode 1. Containment Spray Pump B has a developed a serious leak on its discharge flow element EN FE-011.

Initiating Cues:

The Control Room Supervisor directs you to identify the isolation boundaries that will be required to remove Containment Spray Pump B from service and isolate EN FE-011. List the components on the clearance order sheet provided in the proper sequence.

Component Names are NOT required.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Have copies of the following drawings to replace any marked up by the examinee.

M-12EN01, M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have designated the correct isolation boundaries.

START TIME:

STOP TIME:

RO A2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 5

12. Locates the proper drawings.

May locate in any sequence.

M-12EN01 M-12BN01, E-13EN01, E-13EN02, E-13EN03, E-13BN04 S U Comments:

13. Identifies the Main Control Board Handswitches See key for proper position.

May list in any sequence.

EN HIS-09, BN HIS-03, EN HIS-12, EN HIS-07

14. *Identifies electrical power supplies.

See key for proper position and breaker number.

Ctmt Spray Pump B BN HV-03 EN HV-12 EN HV-07 S U Comments:

15. *Identifies isolation valves.

See key for proper position.

BN HV-03 EN HV-12 EN V-100 EN V-025 S U Comments:

EN HV-07 is an encapsulated valve and may or may not be listed.

RO A2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 3 of 5

16. *Identifies vent and drain valves.

See key for proper position.

At least one of the valves from each group must be selected.

Drains:

1.

EN V-032

2.

EN V-068

3.

EN V-107 Vents:

EN V-089 EN V-115 EV V-095 S U Comments:

17. *Identifies preferred sequence.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Two critical tasks are associated with the sequence:

1. Spay pump handswitch must be placed in Pull to Lock or the Pump breaker racked out prior to closing suction valves.

2. Vents and drains must be last.

S U Comments:

RO A2 Page 4 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is Mode 1. Containment Spray Pump B has a developed a serious leak on its discharge flow element EN FE-011.

Initiating Cues:

The Control Room Supervisor directs you to identify the isolation boundaries that will be required to remove Containment Spray Pump B from service and isolate EN FE-011. List the components on the clearance order sheet provided in the proper sequence.

Component Names are NOT required.

KEY Page 5 of 5 FORM APF 21E-001-02 REV 01 CLEARANCE ORDER CONTINUATION SHEET Components Required to Clear Equipment Placement Section Restoration Component Tagged Component Description Position Seq.

Tagged By Verified By Position Seq. Removed By Verified By EN HIS-09 CTMT SPRAY PUMP B PULL TO LOCK 1

BN HIS-03 RWST to CTMT SPRAY PUMP B CLOSED 2

EN HIS-12 CTMT SPRAY PUMP B DISCHARGE CLOSED 2

EN HIS-07 CTMT SUMP TO CTMT SPRAY PUMP B CLOSED 2

NB0203 STMT SPRAY PUMP B SUPPLY BKR OPEN/

RACKED DOWN 3

NG02ABF1 BN HV-03 SUPPLY BKR Verified OFF 3

NG02BBR1 EN HV-12 SUPPLY BKR Verified OFF 3

NG02BEF3 EN HV-07 SUPPLY BKR Verified OFF 3

BN HV-03 RWST to CTMT SPRAY PUMP B HANDWHEEL CLOSED 4

EN HV-12 CTMT SPRAY PUMP B DISCHARGE HANDWHEEL CLOSED 4

EN V-100 EDUCTOR TO SPRAY PUMP B CLOSED 4

EN V-025 RWST TEST LINE ISOLATION CLOSED 4

EN V-032 PP & TEST CONNECTION OPEN 5

EN V-068 CTMT SPRAY PUMP B DRAIN OPEN 5

EN V-095 CTMT SPRAY PUMP B SUCTION HEADER VENT OPEN EN V-115 CTMT SPRAY PUMP B VENT OPEN 5

EN V-107 TEST CONNECTION OPEN 5

EN V-089 TEST CONNECTION OPEN 5

Administrative RO A.3 Page 6 of 5 JOB PERFORMANCE MEASURE JPM NO: RO-A3 K/A NO: 2.3.1 COMPLETION TIME: 10 Minutes K/A RATING: 2.6 JOB TITLE: RO REVISION: 0 TASK TITLE: Given a Radiological Survey Map and Radiation Work Permit determine the Radiological conditions and controls required.

Knowledge of 10 CFR: 20 and related facility radiation control requirements DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X

METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

01/03/2006

RO A3 Page 1 of 3 Staging: Begin this JPM in the hall outside Access Control at the RWP desk.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. You are a spare licensed operator on shift.

Initiating Cues:

The Control Room Supervisor states they have received a sump alarm on the B RHR Pump room sump and asks you to investigate. Given the survey map, determine the RWP that you would use. Evaluate the radiological conditions in the area and provide the requested information to the following questions.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide survey map.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have correctly answered the three questions.

START TIME:

STOP TIME:

RO A3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 3

18. *Reviews survey map and determines RWP.

RWP 06-005 should be selected S U Comments:

19. *Identify the classification for the room the sump is located in.

High Radiation Area.

Based on the 2 at the doorway to the RHR pump room.

S U Comments:

20. *Determine time till dosimeter will alarm in 300 mr/hour field.

Immediately.

RWP rate setting is 125 mr/hour.

S U Comments:

21. *Identify the areas on the Survey Map that require any special HP controls prior to accessing.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Based on Special Instruction 3# on the RWP.

1. The room itself due to High Radiation Area.

2. The RHR pump seal housing due to Highly Contaminated Area.

3. The RHR pump room sump due to Highly Contaminated Area.

Identify at least two of the three areas.

S U Comments:

RO A3 Page 3 of 3 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. You are on a tour in the Auxiliary Building.

Initiating Cues:

The Control Room Supervisor states they have received a sump alarm on the B RHR Pump room sump and asks you to investigate. Given the survey map, determine the RWP that you would use. Evaluate the radiological conditions in the area and provide the requested information to the following questions.

NOTE: Circle the correct answers or write them down for the following questions and provide the evaluator with your completed paperwork.

1. The area where the sump is located is a:

A) Potential Hot Particle Area B) Contaminated Area C) High Radiation Area D) Radiation Area

2. If you had to access the pump discharge piping immediately in front of the RHR Pump, how long before your dosimeter would alarm.

A) Immediately B) 4 minutes C) 15minutes D) 25 minutes

3. Identify the areas on the Survey Map that require HP notification prior to accessing.

Simulator S-1 JOB PERFORMANCE MEASURE JPM NO: S -1 K/A NO: 4.5E06EA2.2 COMPLETION TIME: 20 Minutes K/A RATING: 3.5/4.1 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Align Alternate High Head Injection.

Ability to determine and interpret the following as they apply to the (Degraded Core Cooling):

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

DUTY: Operate the Emergency Core Cooling System.

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

EMG FR-C2 TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/13/05

JPM No. S -1 Page 1 of 9 Init IC 174 IC 174 was developed with power removed from B CCP and BG HV8105.

JPM S-2, NB02 de-energized, will be in progress and may affect power indications for some of the B Train components. Only one train is required to satisfy this JPM.

DNO tag the B CCP and put the handswitch in pull-to-lock.

Ensure Blue placard is on B CCP handswitch.

RUN when the evaluators are ready.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

For the evolution required for you to perform, your area of the main control boards will reflect the proper plant conditions. Recognize due to other evaluations in progress, some main control board indications may differ from what you expect.

Initial Conditions: The Plant has experienced a LOCA. The crew is currently performing EMG FR-C2. CCP A has tripped and locked out. CCP B is DNO tagged.

Initiating Cues:

The Control Room Supervisor directs you to perform Attachment A of EMG FR-C2.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide a current copy of EMG FR-C2, Attachment A.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard:

Upon completion of this JPM, the Candidate will have established alternate high head injection per Attachment A of EMG FR-C2.

START TIME:

STOP TIME:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 9

1.

Verify charging pump suction:

At least one charging pump suction from RWST valve is open.

Or Both VCT outlet valves are open.

Step A1 Locate BN HIS-112D on MCB panel RL001/2.

Realize that the switch indicates RED.

Locate BG HIS-112B on MCB panel RL001/2.

Note the GREEN light is illuminated.

S U Comments:

2.

Check any CCPs running.

STEP A2 Locate BG HIS-1A and 2A on MCB panel RL001/2. Realize that A CCP has tripped by the AMBER light lit.

Note that the B CCP is DNO tagged.

Go to the RNO.

S U Comments:

3.

Perform the following:

Manually start the CCPs.

Start the Normal Charging Pump (NCP) on recirculation, if neither CCP can be started.

STEP A2 RNO The Operator may ask permission to reset the handswitch and attempt to start A CCP.

CUE: May perform one attempt to re-start A CCP.

Realize neither CCP can be started.

Locate BG HIS-3 on MCB panel RL001/2.

Rotate the handswitch to the right. Note the RED light is illuminated.

S U Comments:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 3 of 9

4.

Reset safety injection.

STEP A3 Operator may recognize this step has already been performed.

Locate and depress SB HS-42A and SB HS-43A on MCB panel RL001/2.

Operator may use the NPIS screen NORM to check if SI is reset.

S U Comments:

5.

Reset CISA and CISB.

STEP A4 Locate and depress on MCB panel RL017/18:

SB HS-56 SB HS-53 SB HS-55 SB HS-52 S U Comments:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 4 of 9

6.

Establish instrument air to Containment:

Ensure ESW to Air Compressor Valves are open.

Reset and close air compressor breaker reset switches.

Check that instrument air pressure is greater than 105 psig.

Check that the Pressurizer master controller is reading less than a 50% output signal.

Open the Instrument Air Supply Containment Isolation Valve.

STEP A5 Operator may recognize this step has already been performed and only verify actions.

Locate EF HIS-43 and 44 on MCB panel RL019/20. Note that EF HIS-43 indicates RED.

Locate KA HIS-2C and 3C on MCB panel RL023/24. Note both handswitches are reset.

Locate KA PI-40 on MCB panel RL023/24. Note pressure is greater than 105 psig.

Locate BB PK-455A on MCB panel RL001/002.

Ensure output signal is less than 50%.

Locate KA HIS-29 on MCB panel RL023/24 and note the RED light is illuminated.

S U Comments:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 5 of 9

7.

Establish the normal charging header flow path:

Open the Charging Header Back Pressure Control Valve.

Open the Charging Pumps To Regenerative HX Containment Isolation Valves.

STEP A6 The candidate may dispatch the Auxiliary Building watch to manually open BG HV-8105.If this occurs then -

Cue as Auxiliary Building watch that HP is not available and your dosimeter is alarming on rate.

Locate BG HC-182 on MCB panel RL001/2 and rotate the potentiometer to the full open position.

Note the meter reads 100%.

Locate BG HIS-8105 and 8106 on MCB panel RL001/2. Depress the OPEN pushbutton for BG HIS-8106 and note RED light is illuminated.

No power is available to BG HIS-8105.

Go to the RNO.

S U Comments:

8.

Go to Step A11, if flow path through normal charging header cannot be established.

STEP A6 RNO Proceed to Step A11.

S U Comments:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 6 of 9

9.

Open the Bit inlet valves.

STEP A11 If candidate dispatches the Auxiliary Building watch to check open EM HV-8803B - Cue: HP is not available and your dosimeter is alarming on rate.

Locate EM HIS-8803A and B on MCB panel RL017/18. Note the RED light is illuminated for EM HIS-8803A.

Examinee may use the NPIS computer to verify EM HV-8803B is open, if power is not available.

S U Comments:

10. Open the BIT outlet valves.

STEP A12 If candidate dispatches the Auxiliary Building watch to check open EM HV-8801B - Cue: HP is not available and your dosimeter is alarming on rate.

Locate EM HIS-8801A and B on MCB panel RL017/18. Note the RED light is lit on 8801A handswitch. Examinee may use the NPIS computer to verify EM HV-8801B is open, if power is not available.

S U Comments:

11. Check if CCP flow through the BIT has been established by checking any CCPs running.

STEP A13 Locate BG HIS-1A and B on MCB panel RL001/2.

Note BG HIS-1A indicates tripped and BG HIS-1B is DNO tagged.

Go to the RNO.

Proceed to Step A15.

S U Comments:

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 7 of 9

12. Check that the NCP is running.

STEP A15 Locate BG HIS-3 on MCB panel RL001/2.

Note the RED light is illuminated.

S U Comments:

13. Establish NCP flow path to the BIT:

Ensure one train of valves from the charging header to the BIT is open.

Open the NCP discharge flow control valve.

Open the CCP discharge flow control valve.

STEP A16 If candidate dispatches the Auxiliary Building watch to check valve status - Cue: BG V-8483A is open and 8483C is closed.

Recognize the blue placard is on BG HIS-2A, which means BG-V8483A is open. Locate EM HIS-8803A on MCB panel RL018. Note the RED light is lit.

Locate BG FK-462 on MCB panel RL001.

Press the MAN pushbutton and then the upper OUTPUT pushbutton to increase until the meter reads >

0%.

Locate BG FK-121 on MCB panel RL001.

Press the MAN pushbutton and then the upper OUTPUT pushbutton to increase until the meter reads >

0%.

S U Comments:

Annunciators for Charging Line Flow Hi/Low will alarm as 462 and 121 are opened.

JPM No. S -1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 8 of 9

14. *Check that flow is indicated on the CCPs to BIT flow meters.

STEP A17 Locate EM FI-917A and B on MCB panel RL017/18. Realize flow is indicated on EM FI-917A.

If little or no flow is indicated the candidate should return to previous step and further increase the controller outputs on BG FK-121 and BG FK-462.

S U Comments:

15. Return to Procedure and Step In Effect.

STEP A18 Acknowledge report.

THE JPM IS COMPLETE.

RECORD STOP TIME ON PAGE 1.

Report task complete.

S U Comments:

Simulator S-2

Indicates Critical Task Page 9 of 9 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

For the evolution required for you to perform, your area of the main control boards will reflect the proper plant conditions. Recognize due to other evaluations in progress, some main control board indications may differ from what you expect.

Initial Conditions: The Plant has experienced a LOCA. The crew is currently performing EMG FR-C2. CCP A has tripped and locked out. CCP B is DNO tagged.

Initiating Cues:

The Control Room Supervisor directs you to perform Attachment A of EMG FR-C2.

Simulator S-2

Indicates Critical Task Page 10 of 9 JOB PERFORMANCE MEASURE JPM NO: S-2 K/A NO: 4.1.055 EA1.07 COMPLETION TIME: 15 Minutes K/A RATING: 4.3/4.5 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Re-energize the affected NB bus from the normal offsite power supply IAW OFN NB-030.

Ability to operate and monitor the following as they apply to a Station Blackout: Restoration of power from offsite DUTY: Station Blackout The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN NB-030 TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/13/05

JPM No. S-2 PAGE 1 of 5 Init IC 174 IC 174 was developed with power removed from NB02 JPM S-1, Alternate High Head Injection, will be in progress.

Hang DNO tags on KJ HS-108A, B EDG start button, and NE HIS-26, D/G output breaker and put handswitch NE HIS-26 in pull-to-lock.

RUN when the evaluators are ready.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

For the evolution required for you to perform, your area of the main control boards will reflect the proper plant conditions. Recognize due to other evaluations in progress, some main control board indications may differ from what you expect.

Initial Conditions: The Plant has experienced a lockout of bus NB02 and control room personnel are performing steps in OFN NB-030, Loss of AC Emergency Bus NB01 (NB02). Electrical Maintenance has repaired the bus lockout and has reset the bus lockout. B EDG was locally secured and DNO tagged during maintenance activities.

Initiating Cues:

The Control Room Supervisor directs you to continue in OFN NB-030, Attachment B, Step B12, RNO b.3, to perform steps required to energize bus NB02 from its normal source of power.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of Attachment B of OFN NB-030, with place keeping marked, to the examinee.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

When Evaluators are ready, go to RUN Task Standard:

Upon completion of this JPM, the Operator will have performed the steps of the procedure necessary to energize NB02 thru XNB02 from its normal offsite source.

START TIME:

STOP TIME:

JPM No. S-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task PAGE 2 of 5

1. When the NB02 bus lockout has been reset, continue with Step B13.

STEP B12, RNO b.3)

Realize the initiating condition stated the bus lockout has been reset.

Proceed to Step B13.

Operator may observe annunciator 21A is not illuminated.

S U Comments:

2. Check if the B emergency diesel generator is running.

STEP B13 Realize the initial conditions stated the B EDG was secured.

Proceed to the RNO.

S U Comments:

3. Go to Step B16 for normal offsite power, if the CRS directs that NB02 be energized from a source other than the emergency diesel generator.

STEP B13, RNO Realize the CRS directed to energize bus NB02 from its normal source of power.

Proceed to Step B16.

S U Comments:

JPM No. S-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task PAGE 3 of 5

4. Verify the normal offsite power supply is available:

Annunciator 00-022A ESF transformer XNB02 STEP B16 Locate annunciator window 22A. Note the window is clear.

Locate NB HIS-1 on MCB panel RL015/16.

Note that the GREEN light is lit for open breaker.

Proceed to RNO b.

S U Comments:

5. Perform the following:

Close 13.8 kV XMR01 to XNB02 breaker PA0201, if the PA02 lockout relay is reset.

Go to Step B17, if ESF transformer XNB02 can be energized.

STEP B16, RNO b.

Locate NB HIS-1 on MCB panel RL015/16.

Rotate the handle to the right to close.

Note ESF transformer XNB02 is energized.

Proceed to Step B17.

S U Comments:

JPM No. S-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task PAGE 4 of 5

6. Re-energize bus NB02 from its normal offsite power supply:

Place NB02 normal supply sync. Transfer switch to the ON position.

Close NB02 normal supply breaker.

Place NB02 normal supply sync. Transfer switch to OFF.

Check that bus NB02 is energized.

STEP B17 Acknowledge report.

THE JPM IS COMPLETE.

RECORD STOP TIME ON PAGE 1.

Locate NB HS-8 on MCB panel RL015/16. Rotate the handle to the right to the ON position.

Locate NB HIS-4 on MCB panel RL015/16.

Rotate the handle to the right to close the breaker.

Locate NB HS-8 on MCB panel RL015/16. Rotate the handle to the left to the OFF position.

Locate NB EI-2 on MCB panel RL015/16. Note voltage is displayed on the meter or that NB ZL-6 white light is illuminated for NB02.

Report that NB02 is energized.

S U Comments:

Simulator S-3 SRO

Indicates Critical Task PAGE 5 of 5 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

For the evolution required for you to perform, your area of the main control boards will reflect the proper plant conditions. Recognize due to other evaluations in progress, some main control board indications may differ from what you expect.

Initial Conditions: The Plant has experienced a lockout of bus NB02 and control room personnel are performing steps in OFN NB-030, Loss of AC Emergency Bus NB01 (NB02). Electrical Maintenance has repaired the bus lockout and has reset the bus lockout. B EDG was locally secured and DNO tagged during maintenance activities.

Initiating Cues:

The Control Room Supervisor directs you to continue in OFN NB-030, Attachment B, Step B12, RNO b.3, to perform steps required to energize bus NB02 from its normal source of power.

Simulator S-3 SRO

Indicates Critical Task PAGE 6 of 5 JOB PERFORMANCE MEASURE JPM No. S-3 (SRO)

K/A NO: 4.2068 AK3.09 COMPLETION TIME: 15 Minutes K/A RATING: 3.7/4.4 and 3.9/4.4 JOB TITLE: SRO REVISION: 0 TASK TITLE: Establish Plant Control From The ASP Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: Transfer of the following to local control: charging pumps, charging header flow control valve, PZR heaters, and boric acid transfer pumps DUTY: Control Room Evacuation The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN RP-013, Control Room Not Habitable TOOLS/EQUIPMENT:

None PREPARER:

DATE:

12/2/2005

JPM NO:

S-3 (SRO)

Page 1 of 8 INIT IC 175 Read to Performer:

Initial Conditions: You are the Control Room Supervisor. The Control Room has been evacuated due to toxic fumes in accordance with OFN RP-013. You have completed step 6 and are arriving at the Auxiliary Shutdown Panel.

Initiating Cues:

In accordance with OFN RP-013, step 7, take control of the Plant and supervise Plant shutdown. The NCP is in service.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide the Candidate with an information only copy of OFN RP-013, Control Room Not Habitable.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

When evaluators are ready:

Task Standard:

Upon completion of this JPM, the Candidate will have taken control of the Plant from the Auxiliary Shutdown Panel, established AFW control, taken action to control the Plant cooldown, and taken action to restore pressurizer level.

START TIME:

STOP TIME:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 2 of 8

16. *At the ASP, Transfer Controls For Aux Feedwater System And Atmospheric Reliefs To Local STEP 7 On RP118A, locate and select to local:

AL HS-9 AL HS-6 AL HS-1 AL HS-3 AL HS-8 AL HS-11 On RP118B, locate and select to local:

AL HS-10 AL HS-5 AL HS-2 AL HS-4 AL HS-7 AL HS-12 FC HS-313 S U Comments:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 3 of 8

17. Operate Available Equipment From the ASP, As Necessary, To establish Stable Plant Conditions STEP 8 Monitor Plant parameters.

S U Comments:

18. On Shift Personnel Establish Communications With ASP From Designated Areas STEP 9 CUE:

All On Shift Personnel Have Established Communications S U Comments:

19. Check Neutron Flux -

DECREASING SE NI-61X SE NI-61Y STEP 10 On RP118A, locate SE NI-61X and Y. Note flux decreasing S U Comments:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 4 of 8

20. Turbine Building Operator, Check Site Power - AVAILABLE STEP 11 When called, CUE:

Breakers PA0110 and PA0202 are closed.

PA01 and PA02 Voltage Is Normal.

Contact the Turbine Building Operator at PA01/PA02 S U Comments:

21. *Check RCS Cold Leg Temperatures -

STABLE AT 561°F OR TRENDING TO 561°F STEP 12 NOTE: It is not necessary to check all indicators On RP118A, locate BB TI-433X BB TI-443X BB TI-423X On RP118B, locate BB TI-413X Note temperature is less than 561°F and trending lower. Perform the RNO.

S U Comments:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 5 of 8

22. IF temperature less than 561°F AND decreasing, THEN Stop dumping steam

*IF cooldown continues, THEN control total feed flow to limit RCS cooldown. Maintain greater than 270,000 lbm/hr until NR level greater than 6% on at least one SG STEP 12 RNO Locate AB ZL-1B and 3B on RP118A and AB ZL-2B and 4B on RP118B.

Note green lights only illuminated.

Candidate may use TDAFW or MDAFW valves.

On RP118A, locate AL HK-6B, 8B, 9B, 11B and on RP118B, locate AL HK-10B, 5B, 7B, and 12B. Take each out of lock detent open and actuate to the left while monitoring total AFW flow on AL FI-1B, 2B, 3B, and 4B for a total of between 270K and 300K LBM/HR.

S U Comments:

23. Check SG Levels:

Narrow range level in at least one SG -

GREATER THAN 6%

STEP 13 Locate AE LI-528X and AE LI-548X on RP118A, and AE LI-517X and AE LI537X on RP118B.

S U Comments:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 6 of 8

24. Check PZR level control Dispatch an operator to control charging flow locally.

Check PZR level >17%

STEP 14 If SRO contacts building watch to determine which charging pump is running, CUE: The NCP is running.

When directed, CUE:

I am standing by at BG FCV-462 Contact spare operator and dispatch to BG FCV-462.

On RP118A, locate BB LI-459B. On RP 118B, locate BB LI-460B. Note level is <17% on both meters. Perform the RNO.

S U Comments:

25. Perform the following:

*Check letdown isolation. IF letdown is NOT isolated, THEN isolate letdown.

*Check PZR Heaters Are -OFF STEP 14.b. RNO

On RP118A, locate BB HIS-8149CB and BB HIS-8149BB. Note red light only on HIS-8149BB. Depress the close PB and note green light only illuminated.

On RP118B, locate BB HIS-8149AB. Note green light only illuminated.

On RP118A, locate BB HIS-52A. Note red light and white light illuminated and actuate switch to the OFF position. Note green light only illuminated.

On RP118B, locate BB HIS-52B. Note red light and white light illuminated and actuate switch to the OFF position. Note green light only illuminated.

S U Comments:

JPM NO: S-3 (SRO)

TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 7 of 8

26. Control Charging To Restore PZR Level STEP 14.b. RNO (cont)

When contacted to increase charging locally, CUE: Opening BG FK-462.

Contact Operator at Charging Flow Control Valve to increase charging.

S U Comments:

27. Check PZR Level Control and PZR Pressure Steps 15 and 16 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Candidate will continue through remaining steps to ensure plant is stable.

The JPM may be terminated at any time.

S U Comments:

Simulator S3

Indicates critical task Page 8 of 8 Initial Conditions: You are the Control Room Supervisor. The Control Room has been evacuated due to toxic fumes in accordance with OFN RP-013. You have completed step 6 and are arriving at the Auxiliary Shutdown Panel.

Initiating Cues:

In accordance with OFN RP-013, take control of the Plant and supervise Plant shutdown. The NCP is in service.

Simulator S3

Indicates critical task Page 9 of 8 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 302-S K/A NO: 3.3 006 A1.13 COMPLETION TIME: 25 Minutes K/A RATING: 3.5/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Fill an SI Accumulator - Mode 3 Ability to predict and/or monitor changes in parameters: Accumulator pressure (level, boron concentration)

DUTY: Emergency Core Cooling System (ECCS)

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

02/06/2006

JPM N0. S-3 PAGE 1 of 6 IC 175 Set asisal(3)=51100 Set asisag(3)=1000 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.

Initiating Cues:

The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run. Safety Injection Pump discharge relief valves are expected to lift upon pump start.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of SYS EP-200 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard:

At the completion of this JPM, the Examinee will have increased SI Accumulator "C" level to 55% - 58% using B Safety Injection Pump.

START TIME:

STOP TIME:

JPM N0. S-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 2 of 6

1. Perform Prerequisites.

5.1 - 5.3 5.4 Ensure cooling to desired SI pump.

5.5 Check both SI Train A and B are operable Cue from CRS: BOTH Trains are operable.

Steps 5.1 - 5.3 should be N/A Verifies B CCW Train has a running pump.

Initial step.

S U Comments:

2. Procedure 6.1.1 Check accumulator pressure 6.1.2 Record RCS Pressure 6.1.3 Depressurize RHR header if desired.

Open EJ HIS-8890A or 8890B Ensure EM HIS-8964 Open Ensure EM HIS-8871 open.

6.1.4 Using SI Pump A Locate EP PI-964 and EP PI-965 on RL017/18.

Determine pressure is less than 619 psig. N/A the step.

Locate RCS or PRZR pressure indication on RL001/2. Record the pressure.

Locate EJ HIS 8890A or B and open one valve.

N/A the other valve.

Check open.

Recognize the Initiating Cue stated B SIP is to be used. N/A the step.

S U Comments:

JPM N0. S-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 3 of 6

3. Procedure 6.1.5 Using SI Pump B

1. Ensure EM HIS 8814B -

OPEN

2. Ensure BN HIS 8813 -

OPEN

3. *Close EM HIS-8821B

4. *Start SI Pump B

5. *Open EM HIS 8821B Ensures Red Lite lit on EM HIS-8814B.

Ensures Red Lite lit on BNIS-8813 Recognizes initial cue was that reliefs are expected to lift. *The critical step is to inform the CRS that T.S. 3.5.2 must be entered prior to closing the valve. Press close button and observe Green Lite lit and Red Lite out.

Rotate EM HIS-5 to Start; observe Red Lite lit and Green Lite out.

While not critical Mgmt expectations are to make a plant announcement prior to start and to have a NPIS screen displaying pump parameters for the B SI pump.

Presses open on EM HIS 8821B. Observe Red Lite lit and Green Lite out. Informs CRS that T.S. 3.5.2 can be exited.

S U Comments:

JPM N0. S-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 4 of 6

4. Fill Accumulator

6.1.6 Open EM HIS-8888 6.1.7 for Accumulator A and 6.1.8 for Accumulator B.

6.1.9 Fill Accumulator C

1. Record highest level

2. *Open EP HIS-8878C

3. *Fill to 55 - 58%

and close EP HIS-8878C.

4. Record level change.

Presses open on EM HIS 8888. Observe Red Lite lit and Green Lite out.

Steps 6.1.7 and 6.1.8 were marked N/A by the CRS prior to starting.

Locate EP LI-954 or EP LI-955 on RL017/18.

Record level.

Presses open on EM HIS 8888. Observe Red Lite lit and Green Lite out.

Monitor level and close EP HIS-8878C when between 55 - 58%.

The critical step is not to exceed 77.8% which would make the Accumulator inoperable.

Record level change for accumulator "C". Final -

initial. Should be from 15 to 18%.

S U Comments:

JPM N0. S-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 5 of 6

5. Continue Procedure 6.1.11 Close EM HIS-8888 6.1.12 Run SI pump for 5-10 minutes.

6.1.13 Stop SI Pump B.

6.1.14 Ensure valves closed.

EJ HIS-8890A EJ HIS-8890B 6.1.15 Ensure valves open.

EM HIS-8964 EM HIS-8871 6.1.16 Check for Chemistry need to sample.

6.1.17 Secure Pump Room Cooler.

6.1.18 Section 6.1 complete.

If asked cue: Leakage is not present.

As CRS cue:

SYS EJ-323 is in effect.

Leave valves open.

Acknowledge request.

Respond as Turbine Watch: B SI Pump Room Cooler is secured.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Press close button on EM HIS-8888 and observe Green Lite lit and Red Lite out.

Initial Conditions stated leakage was not present.

Rotate EM HIS-5 to Stop; observe Red Lite out and Green Lite lit.

While not critical, Mgmt expectations are to make a plant announcement when securing B SI pump.

Press Close on valve opened in step 6.1.3.

Ensures Green Lite lit and Red Lite out.

Ensures Red Lite lit and Green Lite out.

N/A the step.

Contacts Turbine Building Operator to stop fan at breaker for B room. (NG02ACF3)

Initial and Date step.

S U Comments:

SIMULATOR S-4

CRITICAL STEP PAGE 6 of 6 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.

Initiating Cues:

The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run.. Safety Injection Pump discharge relief valves are expected to lift upon pump start.

SIMULATOR S-4

CRITICAL STEP PAGE 7 of 6 JOB PERFORMANCE MEASURE JPM NO: S-4 K/A NO: 4.2.060AA1.02 COMPLETION TIME: 20 Minutes K/A RATING: 2.9/3.1 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Manually Actuate CRVIS and FBIS.

Ability to operate and / or monitor the following as they apply to the Accidental Gaseous Radwaste:

Ventilation system DUTY: Monitor the ESFAS System.

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN SP-010, Accidental Radioactive Release TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/12/05

JPM No. S-4 Page 1 of 10 Init IC 175 Key 1 to actuate Rad Monitors RUN Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. Annunciator 61A and 61B are in alarm. Fuel Handling is not in progress.

Initiating Cues:

The Control Room Supervisor directs you to perform OFN SP-010, Accidental Radioactive Release.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide a current copy of OFN SP-010.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Operator will have manually actuated CRVIS and FBIS and manually aligned two FBIS components that failed to automatically align.

START TIME:

STOP TIME:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 2 of 10

28. Check Listed Gaseous Monitors - ANY HI-HI ALARM ACTUATED.

GG RE-27(3)

GG RE-28(3)

STEP 1 Go to the RM11 Panel.

(SP056A) Note GG RE-27 and GG RE-28 are indicating HI-HI (Red).

S U Comments:

29. Check If Control Room Ventilation Isolation is required:

a. HI-HI alarm on any of the following monitors

- ACTUATED.

GG RE-27 GG RE-28 STEP 2 Note that GG RE-27 and GG RE-28 are both in HI-HI (Red).

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 3 of 10

30. *Verify Control Room Ventilation Isolation:

a. Check ESFAS status panel CRVIS section

- ALL WHITE LIGHTS LIT.

Red Train Yellow Train STEP 3.a Go to SA066X and Y panels on RL017/18.

Note no status lights for CRVIS are lit and go to RNO.

S U Comments:

31. Perform the following:

If CRVIS has not actuated, then manually actuate CRVIS.

If any CRVIS component is not properly aligned, then manually align the component.

If neither train of CRVIS is in service, then establish one in service.

If only one train of CRVIS can be placed in service, then within 90 minutes isolate out of service train.

STEP 3.a. RNO

Critical step is to actuate at least one train. Per procedure the candidate should actuate both trains.

Locate and depress SA HS-9 and SA HS-13 on MCB panel RL017/18.

Locate SA066X and SA066Y on RL017/18.

Note upper status lights for CRVIS - All WHITE Note that both trains are in service.

If only one train is actuated then the candidate needs to state that the other train has to be isolated within 90 minutes.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 4 of 10

32. Ensure the Control Room outer door is closed.

STEP 3.b When Candidate moves to check outer door, CUE:

Outer door is closed.

Check outer door.

S U Comments:

33. Check if Containment Purge should be isolated:

a. HI-HI alarm on any of the following monitors -

ACTUATED GT RE-22 GT-RE-31 ST RE-32 GT RE-33 STEP 4 Go to the RM11 panel (SP056A) and note that none of the designated monitors is in alarm and go to Step 5.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 5 of 10

34. *Check if Fuel Building should be isolated:

a. HI-HI alarm on any of the following monitors has ACTUATED.

GG RE-27 GG RE-28

b. Check ESFAS status panel FBIS section -

ALL WHITE LIGHTS LIT.

STEP 5 Realize that GG RE-27 and GG RE-28 are both in HI-HI (Red).

Locate SA066X and SA066Y on MCB panel RL017/18. Note no white lights lit for FBIS section and perform the RNO.

S U Comments:

8. Perform the following:

*If FBIS has not actuated, then manually actuate FBIS.

*If any FBIS component is not properly aligned, then manually align component. Refer to ATTACHMENT B.

STEP 5.b. RNO

Critical step is to actuate at least one train. Per procedure the candidate should actuate both trains.

Locate and depress SA HS-10 and SA HS-14 on MCB panel RL017/18.

Locate SA066X and SA066Y on MCB panel RL017 and note all white lights not actuated on SA066X and Y for FBIS.

Go to ATTACHMENT B.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 6 of 10

9. *Ensure Emergency Exhaust Fans are running.

CGG02A CGG02B

10. *Ensure the Fuel Building To Emergency Filter Units dampers are open.

GG HZ-40 dampers GG-D025 GG HZ-43 dampers GG-D018 Step B1 and Step B2.

Candidate may stop when they note that upper tier white lights are lit for FBIS on SA066X and Y. If so, the rest of the steps may be marked N/A THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1.

Critical step is to ensure at least one train is completely aligned. Must start the non-running fan OR open the closed valve. Per procedure the candidate should actuate both trains.

Locate GG HIS-15A and 21A on MCB panel RL020.

Note that GG HIS-21A indicates red light lit.

Note that GG HIS-15A indicates green light only. Actuate GG HIS-15A to the run position and note red light only illuminated.

Locate GG HIS-40 and 43 on MCB panel RL020. Note green light only illuminated for GG HZ-43. Depress the OPEN pushbutton for GG HZ-43 and note red light only illuminated.

May note the upper level white lights lit on panel SA066X and Y for FBIS.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 7 of 10

11. Ensure the Fuel Building Air Supply Fans are stopped.

SGG01A SGG01B STEP B3.

Locate GG HIS-38A and 39A on MCB panel RL020 and note green lights only illuminated.

S U Comments:

12. Ensure the Fuel Building Air Supply Fan Discharge Dampers are closed.

GG HZ-38 dampers GG-D5 GG HZ-39 dampers GG-D6 STEP B4.

Damper indication is integral to the fan handswitch.

Locate GG HIS-38A and 39A and note the damper green lights only illuminated.

S U Comments:

13. Ensure the Fuel Building Air Inlet Dampers are closed.

GG RZ-36 dampers GG-D3 GG RZ-37 dampers GG-D4 STEP B5.

Locate GG HIS-36A and 37A on MCB panel RL020 and note green lights only illuminated.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 8 of 10

14. Ensure the Spent Fuel Pool Discharge to Auxiliary Building damper is closed.

GG HZ-42 damper GG-D32 STEP B6.

Locate GG HIS-42 on MCB panel RL020 and note green light only illuminated.

S U Comments:

15. Ensure the Fuel Building Exhaust to Auxiliary Building Ventilation damper is closed.

GL HZ-62 damper GL-D58 STEP B7.

Locate GL HIS-62 on MCB panel RL020 and note green light only illuminated.

S U Comments:

JPM No. S-4 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step Page 9 of 10

16. Align other ventilation systems discharging to the Unit Vent:

Ensure the Access Control Exhaust Fans are stopped.

GK HIS-47 for CGK02A

GK HIS-49 for CGK02B Ensure the Main Steam Enclosure Exhaust Fans are stopped.

GF HIS-17 for CGF03a

GF HIS-18 for CGF03B Ensure Aux/Fuel Normal Exhaust Fans are in slow speed.

GL HIS-30 for CGL03A

GL HIS-31 for CGL03B STEP B8.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1.

Locate GK HIS-47 and 49 on panel RP068.

Note green lights only illuminated.

Locate GF HIS-17 and 18 on panel RP068.

Note red light illuminated on GF HIS-17. Rotate the switch to the stop position and note green light only illuminated.

Operator should note that this causes an AUTO start of GF HIS-18 and rotate that switch to the stop position and note green light only illuminated.

Locate GL HIS-30 and 31 on MCB panel RL020. Note both indicate fast speed.

Select slow on each handswitch and note slow red light illuminated on each.

S U Comments:

SIMULATOR S-5

Indicates Critical Step Page 10 of 10 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. Annunciator 61A and 61B are in alarm. Fuel Handling is not in progress.

Initiating Cues:

The Control Room Supervisor directs you to perform OFN SP-010, Accidental Radioactive Release.

SIMULATOR S-5

Indicates Critical Step Page 11 of 10 JOB PERFORMANCE MEASURE JPM NO: S-5 K/A NO: 3.8 029 A1.03 COMPLETION TIME: 10 Minutes K/A RATING: 3.0/3.3 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Start Up the Containment Mini Purge.

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Containment Purge System controls including: Containment pressure, temperature, and humidity DUTY: Operate Plant Service Systems The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

SYS GT-120, CONTAINMENT MINI PURGE SYSTEM OPERATIONS TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/12/05

JPM No. S-5 PAGE 1 of 4 INIT IC 176 RUN Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator, the plant is stable in Mode 2. Outside temperature is 70°F. A gaseous release permit has been issued and is complete to the point of starting the release.

Initiating Cues:

The Control Room Supervisor directs you to place the Containment Mini Purge Exhaust System in operation using section 6.1 of SYS GT-120. The prerequisites of SYS GT-120 have been verified and signed off.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of SYS GT-120.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Operator will have started up the Containment Mini Purge Exhaust System.

START TIME:

STOP TIME:

JPM No. S-5 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 2 of 4

1. Record the time and date the purge must be initiated from the permit.

STEP 6.1.1 Examiner provides a time that is two hours after the start of the JPM and todays date.

Enter the time and date provided in the procedure.

S U Comments:

2. Align the Containment Purge dampers:

*Open CTMT PURGE EXH DAMPER.

GT HIS-29

*Open CTMT PURGE EXH DAMPER.

GT HIS-28

Open CTMT MINI PURGE EXH OUTER CTMT ISO.

GT HIS-12 Record time and date dampers are opened.

STEP 6.1.2 Locate GT HIS-29 on RL019/20, depress the OPEN pushbutton, and note red light only illuminated.

Locate GT HIS-28 on RL019/20, depress the OPEN pushbutton, and note red light only illuminated.

Locate GT HIS-12 on RL019/20, depress the OPEN pushbutton, and note red light only illuminated.

Record time and date.

S U Comments:

JPM No. S-5 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 3 of 4

3. *Start the Containment Mini Purge Exhaust fan and verify its discharge damper opens.

GT HIS-20 AND GT HZ-20 STEP 6.1.3 Locate GT HIS-20 and GT HZ-20 on MCB panel RL019/20. Rotate handswitch to the right. Note the RED light lit for the fan and the RED light lit for the damper.

S U Comments:

4. Open the Containment Mini Purge Exhaust Inner Containment Iso and record the time and date opened.

*GT HIS-11 Time and date STEP 6.1.4 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Locate GT HIS-11 on MCB panel RL019/20.

Depress the OPEN pushbutton. Note the RED light is illuminated.

Record time and date opened.

S U Comments:

Simulator S-6

Indicates Critical Step PAGE 4 of 4 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator, the plant is stable in Mode 2. Outside temperature is 70°F. A gaseous release permit has been issued and is complete to the point of starting the release.

Initiating Cues:

The Control Room Supervisor directs you to place the Containment Mini Purge Exhaust System in operation using section 6.1 of SYS GT-120. The prerequisites of SYS GT-120 have been verified and signed off.

Simulator S-6

Indicates Critical Step PAGE 5 of 4 JOB PERFORMANCE MEASURE JPM NO: S-6 K/A NO: 4.2.005 AA1.01 COMPLETION TIME: 30 Minutes K/A RATING: 3.6/3.4 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Perform OFN SF-011 to realign a misaligned rod Ability to operate and / or monitor the following as they apply to the Inoperable / Stuck Control Rod:

CRDS DUTY: Monitor Reactivity The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

OFN SF-011, Realignment Of Dropped, Misaligned Rod(s), And Control Group Malfunctions TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/13/05

JPM No. S-6 PAGE 1 of 9 IC 176 Set rods per RBU, adjust rods two steps out then two steps in to ensure step counters are working.

Reset IC 176 From the Actions screen select Remote Function rCRF01. Use when candidate contacts INC.

Do not go to RUN until just before JPM begins so Tavg does not become an issue during the JPM.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator. Control rod M12 has been misaligned for twenty minutes. The reactor is stable at 80% power. The problem causing the misaligned rod has been corrected.

Initiating Cues:

The Control Room Supervisor directs you to realign rod M12 per step 20 of OFN SF-011. All notifications have been made in compliance with the note prior to step

20. INC and the Aux Building Watch are standing by in the Rod Drive MG Set Room.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of OFN SF-011.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM the Operator will have placed rod M12 in proper alignment in accordance with OFN SF-011.

START TIME:

STOP TIME:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 2 of 9

5. Check If Rod Can Be Moved At Normal Rate.

Misaligned less than 12 steps OR Misaligned for less than one hour STEP 20 On RL021/22, Monitor DRPI and note the rod is misaligned by more than 12 steps Note the initiating cue stated the rod has been misaligned for 20 minutes Determine rod can be moved at normal rate.

S U Comments:

6. Prepare To Realign Rod

*Place rod bank AUTO/MANUAL selector switch to the bank with misaligned rod STEP 21.a On RL003/4, rotate SE HS-9 to Bank D position CBD.

S U Comments:

7. Prepare To Realign Rod Direct INC to locally verify rod bank selected by SE HS-9 is aligned properly by light indications on associated cabinets Step 21.b When contacted as INC, CUE:

Light indication is that rod bank D is selected.

Contact INC and request they locally verify that light indication denotes control bank D is selected S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 3 of 9

8. Prepare To Realign Rod

*At RL003, record position of group step counter for group containing misaligned rod STEP 21.c At RL003/4, locate step counter for control group D, note and record the position is 175 S U Comments:

9. Prepare To Realign Rod

*IF rod is misaligned high with respect to other rod in group THEN insert rods in misaligned bank until next set of DRPI LEDS - LIT STEP 21.d Determine from DRPI indication that rod is misaligned High.

On RL003/4, locate SF HS-2 controller. Move controller to the IN position while monitoring DRPI on RL022.

Release SF HS-2 when next set of LEDs lights.

S U Comments:

10. Prepare To Realign Rod IF rods are misaligned low with respect to other rods in group, THEN perform the following:

STEP 21.e Realize step is NA S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 4 of 9

11. Prepare To Realign Rod

*At lift coil disconnect panel, place all lift coil disconnect switches for other rods in affected bank to ROD DISCONNECTED position.

STEP 21.f Locate panel labeled Control Rod Disconnect Switch Box, on north wall behind Control Boards.

Pull out on and move switch D4, D12, M4, and H8 to the ROD DISCONNECTED position (UP).

S U Comments:

12. Prepare To Realign Rod

*At RL003, record position of group step counter for group misaligned.

STEP 21.g At RL003/4, locate step counter for control group D, note and record the position is 170 S U Comments:

13. Adjust Turbine Load As Necessary To Maintain Tavg Within 3°F of Tref.

STEP 22 As CRS, CUE:

The rest of the crew will control Tavg.

Booth Operator will control Turbine Load.

S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 5 of 9

14. Realign Misaligned Rod To Associated Group Position Check misaligned rod -

IN SHUTDOWN GROUP At Pulse-to-Analog Converter cabinet, hold AUTO-MANUAL switch in MANUAL STEP 23.a and RNO NOTE: Booth Operator action:

rCRF01, Manual Realize misaligned rod is in Control Group and perform the RNO.

Contact INC personnel at the Pulse-to-Analog Converter Cabinet and instruct them to hold the switch in MANU AL S U Comments:

15. *Realign misaligned rod to associated group position STEP 23.b On RL003/4, locate SF HS-2 controller. Move controller to the IN position while monitoring DRPI and the rod demand step counter for Bank D. Release SF HS-2 when DRPI indicates all rods aligned.

S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 6 of 9

16. Check misaligned rod -

IN SHUTDOWN GROUP At Pulse-to-Analog converter cabinet, release AUTO-MANUAL switch STEP 23.c and RNO NOTE: Booth Operator action:

rCRF01, AUTO Realize the rod is in a Control Group and perform RNO.

Contact INC personnel at cabinet and instruct them to release the switch S U Comments:

17. Reset Misaligned Rod

*At lift coil disconnect panel, place all lift coil disconnect switches for affect bank to ROD CONNECTED position STEP 24.a Locate panel on north wall. Pull out on and move switch D4, D12, M4, and H8 to the ROD CONNECTED position (DOWN).

S U Comments:

18. Reset Misaligned Rod

*At RL003, open window and reset affected group step counter by hand to position recorded in Step 21.g STEP 24.b On RL003, open the window for CBDA and reset counter to 170 S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 7 of 9

19. Reset Misaligned Rod

*On RL003, reset rod control urgent failure alarm.

STEP 24.c On RL003/4, locate and depress SF HS-4.

Acknowledge urgent failure alarm and note the annunciator goes out.

S U Comments:

20. Verify proper operation of affected rods by moving affected rods 6 steps in each direction.

STEP 24.d On RL003/4, locate SF HS-2 controller. Move controller to the OUT position while monitoring DRPI and the rod demand step counter for Bank D. Release SF HS-2 when step counter indicates 6 steps out.

Verify proper response on DRPI.

On RL003/4, locate SF HS-2 controller. Move controller to the IN position while monitoring DRPI and the rod demand step counter for Bank D. Release SF HS-2 when step counter indicates 6 steps in.

Verify proper response on DRPI.

S U Comments:

JPM No. S-6 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Step PAGE 8 of 9

21. Move affected group to position recorded in Step 21.c STEP 24.e On RL003, locate SF HS-2 controller. Move controller to the OUT position while monitoring DRPI and the rod demand step counter for Bank D. Release SF HS-2 when step counter indicates 175. Verify proper response on DRPI.

S U Comments:

22. *Place ROD BANK AUTO/MAN SEL switch in MAN position Determine group step counters are the same, have INC check master cycler on 4 or 5.

Perform STN RJ-001 STEP 24.f When INC is contacted cue: Bank D is selected.

After candidate selects manual on rod control Cue: Master Cycler binary counter is on 4.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 On RL003/4, locate SE HS-9. Rotate switch from bank D position to MAN position.

When candidate reaches step to perform STN RJ-001 the JPM may be terminated.

S U Comments:

Simulator S-7

Indicates Critical Step PAGE 9 of 9 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator. Control rod M12 has been misaligned for twenty minutes. The reactor is stable at 80% power. The problem causing the misaligned rod has been corrected.

Initiating Cues:

The Control Room Supervisor directs you to realign rod M12 per step 20 of OFN SF-011. All notifications have been made in compliance with the note prior to step

20.

INC and the Aux Building Watch are standing by in the Rod Drive MG Set Room.

Simulator S-7

Indicates Critical Step PAGE 10 of 9 JOB PERFORMANCE MEASURE JPM NO: S-7 K/A NO: 3.5.026 K4.01 COMPLETION TIME: 15 Minutes K/A RATING: 4.2/4.3 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Align Containment Spray System for recirculation IAW EMG ES-12.

Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:

Source of water for CSS, including recirculation phase after LOCA DUTY: Monitor and Operate Containment Spray.

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

EMG ES-12 TOOLS/EQUIPMENT:

NONE PREPARER:

DATE:

12/13/05

JPM No. S-7 Page 1 of 4 INIT 177 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator. The Plant experienced a large break LOCA. The crew has progressed through EMG E-0, E-1, and have transitioned to EMG ES-12 where they are holding at step 12.

Initiating Cues:

The Control Room Supervisor directs you to perform Step 12 and 13 of EMG ES-12, as necessary.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of EMG ES-12, Steps 12 and 13.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Operator will have aligned the Containment Spray System for recirculation.

START TIME:

STOP TIME:

JPM No. S-7 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 4

23. Check if the Containment Spray System should be aligned for recirculation:

Containment Spray Pumps - ANY RUNNING.

RWST level - LESS THAN 12%.

STEP 12 Locate EN HIS-3 and 9 on MCB panel RL017/18. Note RED light only is illuminated.

Locate BN LI-930, 931, 932, and 933 on MCB panel RL017/18. Note all indicators indicate less than 12%. Locate annunciator 47C and note it is illuminated.

S U Comments:

24. Align the Containment Spray System for recirculation:

*Open both Containment Recirculation Sump to Containment Spray Pump valves.

STEP 13 Locate EN HIS-1 and 7 on MCB panel RL017/18. Depress the OPEN pushbutton and note red light only is illuminated on EN HIS-1.

Note no indication on EN HIS-7.

Go to the RNO.

S U Comments:

JPM No. S-7 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 3 of 4

25. *If either valve cannot be opened, then stop the associated Containment Spray pump.

STEP 13.a. RNO Locate EN HIS-9 on MCB panel RL017/18.

Rotate the handswitch left to the OFF position.

Note green light only illuminated.

The critical step is to secure the B pump prior to cavitation. At 6%

RWST level the RWST Empty alarm is actuated and the fold out page requires securing all pumps taking suction from the RWST.

Report Containment Spray pump B has been secured.

S U Comments:

26. *Close both RWST to Containment Spray pump valves.

STEP 13.b.

Acknowledge Report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Locate EN HIS-3 and 4 on MCB panel RL017/18. Depress the CLOSE pushbutton on both handswitches.

Note green light only illuminated.

Report Steps 12 and 13 are complete.

S U Comments:

Simulator S-8

Indicates Critical Task Page 4 of 4 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Reactor Operator. The Plant experienced a large break LOCA. The crew has progressed through EMG E-0, E-1, and have transitioned to EMG ES-12 where they are holding at step 12.

Initiating Cues:

The Control Room Supervisor directs you to perform Step 12 and 13 of EMG ES-12, as necessary.

Simulator S-8

Indicates Critical Task Page 5 of 4 JOB PERFORMANCE MEASURE JPM NO: S-8 K/A NO: 4.5.005EK3.2 COMPLETION TIME: 15 Minutes K/A RATING: 3.7/4.1 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Establish Feed Flow to SG Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink): Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

DUTY: Response To Loss Of Secondary Heat Sink The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X

PLANT CLASSROOM METHOD OF PERFORMANCE:

SIMULATED PERFORMED X

REFERENCES:

EMG FR-H1, Response To Loss Of Secondary Heat Sink TOOLS/EQUIPMENT:

PREPARER:

DATE:

12/6/2005

JPM No. S-8 Page 1 of 6 INIT IC 177 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Balance of Plant Operator. The Plant is experiencing a post trip loss of heat sink. Attempts to establish feed flow to the SGs with any Aux Feedwater pump per EMG FR-H1 have been unsuccessful. The crew has just completed step 10 to establish Feedwater Control.

Initiating Cues: The CRS assigns you to begin with step 11 of EMG FR-H1 and attempt to establish feed to Steam Generator B. The Turbine Building operator is standing by.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the Candidate with an information only copy of EMG FR-H1.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

When evaluators are ready: Go to RUN Task Standard:

Upon completion of this JPM, the Candidate will have commenced feeding B SG from a condensate pump.

START TIME:

STOP TIME:

JPM No. S-8 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 2 of 6

35. Check Both Main Feedwater Pumps -

Tripped

36. Ensure Low Pressure Heater Condensate Iso Valves - AT LEAST ONE SET OPEN

37. MSIVs - AT LEAST ONE OPEN AB HIS-14 AB HIS-17 AB HIS-11 AB HIS-20 STEPS 11, 12 and 13 Checks Red Light illuminated on both handswitches or Both MCB Annunciators lit.

Locate Heater Iso valves and Bypass Valve on RL023/24 and determine the heater Iso valves are open by noting red lights on

1. AD ZL-55 Or

2. AD ZL-43 Or

3. AD ZL-30 Recognize all four MSIVs are open on RL025/26.

S U Comments:

JPM No. S-8 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 3 of 6

38. Start one Turbine Driven Main Feedwater Pump.

Actuate both MFP FWIS Block Switches Place Both MFP Speed Control in Manual.

Place Both MFP speed potentiometers at zero speed Ensure SI Reset

*Reset BOTH MFP Trip Circuits.

Step 14 and RNO At RP068, place FC HIS-510 and FC HIS-1510 in Block Position.

At RL005/6, Place FC HIS-88 and FC HIS-188 in Manual.

At RL005/6, place both MFP speed pots to zero.

Ensure SI reset by verifying alarms 30A and 31 A not lit, or reset using SB HIS-42A and 43A on RL001/2.

Attempt to reset both MFPs. Recognize MFPs will not reset and perform RNO for step

14.

Go to Step 17 S U Comments:

JPM No. S-8 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 4 of 6

4. Start Motor Driven Main Feed Pump.

Ensure PB04 is energized.

Open Suction/Discharge valves.

Local vent using AE-V344 and locally close BM-V185.

Start the MD MFP.

Fill and vent seal cooler as resources permit.

STEP 17 Acknowledge request and CUE: Pump is vented and BM-V185 is closed.

Acknowledge request, CUE: Will fill and vent seal cooler using SYS AE-122.

Verifies power to pump by checking pump indication or verifying PB04 power.

Press Open on push button AE HS-103.

Verifies suction and discharge valves indicate open.

Dispatch local operator.

Places AE HIS-104 to the START position.

Verify red light lit and green light out. May see flow indicated.

Dispatch local operator.

JPM No. S-8 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates Critical Task Page 5 of 6

39. Control Main Feedwater Flow To At Least One SG:

*Open main feedwater reg bypass valve OR

*Open main feedwater reg valve STEP 18 If the Candidate asks the CRS which valves and which SG to use, CUE:

Use the Bypass valve and feed SG B.

Per the Caution flow should be established slowly.

Locate AE LK-560 on RL005/6. Depress the Manual PB and depress the raise PB until dual indication is observed.

S U Comments:

40. Check SG Levels Bleed and Feed - NOT ESTABLISHED Check narrow range level in at least one SG

- GREATER THAN 6%

Perform RNO STEP 19 and RNO When candidate checks level increasing and feed flow established, CUE THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Realize bleed and feed not in progress Locate level indicators on RL025/26 and check level in SG B. Performs RNO.

Checks Core Exit TCs stable or decreasing.

Checks Wide Range Level in B SG increasing.

Maintains feed flow to B SG S U Comments:

JPM No. S -1 Page 6 of 9 Initial Conditions: You are the Balance of Plant Operator. The Plant is experiencing a post trip loss of heat sink. Attempts to establish feed flow to the SGs with any Aux Feedwater pump per EMG FR-H1 have been unsuccessful. The crew has just completed step 10 to establish Feedwater Control.

Initiating Cues: The Control Room Supervisor assigns you to begin with step 11 of EMG FR-H1 and attempt to establish feed to Steam Generator B. The Turbine Building operator is standing by.

In Plant P-1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-P K/A NO: 002 A2.01 COMPLETION TIME: 20 Minutes K/A RATING: 4.3/4.4 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of coolant inventory DUTY: Reactor Coolant System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE:

SIMULATED X PERFORMED

REFERENCES:

EMG C-0, Loss Of All AC Power TOOLS/EQUIPMENT: NONE PREPARER:

DATE:

02/06/2006

JPM No. P-1 PAGE 1 of 4 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.

Initiating Cues:

The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.

DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide the operator with a copy of EMG C-0, Step 15.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM.. (PIR 2003-2930)

Task Standard:

Upon completion of this JPM, the Candidate will have isolated the valves from the RCP seals.

START TIME:

STOP TIME:

JPM No. P-1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 2 of 4

1. Dispatch personnel to locally close valves to isolate RCP seals

*Seal Water Return Containment Isolation Valve BG HV-8100

*Seal Water Injection Filters Inlet Isolations BG-V101 BG-V105 As operator describes opening valve cue:

Clutch Lever is engaged Stem is insertting.

Handwheel stops turning.

Valve is turning in the clockwise direction.

Valve will not turn any more. Stem is totally inserted.

Valve is turning in the clockwise direction.

Valve will not turn any more. Stem is totally inserted Go to BG HV-8100 at Aux Building, 2000 level, South Penetration Room. Gently engage clutch lever while turning the handwheel in a clockwise direction.

The declutch lever may be released once it engages. Continue turning the handwheel clockwise till the stem is fully inserted and the handwheel stops turning.

Go to BG V101 at Aux Building, 2000 level, RX Coolant Filter/Seal Injection Filter A Valve Room. Rotate the valve operator in the clockwise direction and note the position of the stem.

Go to BG V105 at Aux Building, 2000 level, RX Coolant Filter/Seal Injection Filter B Valve Room. Rotate the valve operator in the clockwise direction and note the position of the stem S U Comments:

S U Comments:

JPM No. P-1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

CRITICAL STEP PAGE 3 of 4

*CCW Return From RCS Isolation Valve EG HV-61 Contact Control Room and Report step complete STEP 15 As operator describes opening valve cue:

Clutch Lever is engaged Stem is inserting.

Handwheel stops turning.

Acknowledge report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Go to the EG HV-61 at the Aux Building, 2000, North Penetration Room.

Gently engage clutch lever while turning the handwheel in a clockwise direction. The declutch lever may be released once it engages.

Continue turning the handwheel clockwise till the stem is fully inserted and the handwheel stops turning..

Call Control Room and report step 15 complete.

S U Comments:

JPM No. P-1 PAGE 4 of 4 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.

Initiating Cues:

The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.

DO NOT OPERATE ANY EQUIPMENT IN THE PLANT

In Plant JPM P-2 PAGE 4 of 4 JOB PERFORMANCE MEASURE JPM NO: P-2 K/A NO: 4.2 068 AA2.05 COMPLETION TIME: 15 Minutes K/A RATING: 4.2/4.3 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Turbine Building Operator OFN RP-017 Ability to determine and interpret the following as they apply to the Control Room Evacuation:

Availability of heat sink DUTY: Perform OFN RP-017, Control Room Evacuation The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE:

SIMULATED X PERFORMED

REFERENCES:

OFN RP-017, Control Room Evacuation, Attachment B.

TOOLS/EQUIPMENT:

PREPARER:

DATE:

11/30/2005

JPM NO:

P-2 Page 1 of 6 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

NO EQUIPMENT WILL BE OPERATED IN THE PLANT - SIMULATE ONLY Staging:

Have the candidate go to the 2047 level of the Communications Corridor, outside the Control Room and then provide the initiating cue.

Read to Performer:

Initial Conditions: You are an extra licensed operator on shift. You are designated as the operator to perform the Turbine Building Actions for OFN RP-017, CONTROL ROOM EVACUATION.

Initiating Cues: You hear the following gaitronics announcement: Reactor Trip, Evacuating the Control Room due to fire, entering OFN RP-017.

This is a timed JPM.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide the Candidate with a training only copy of OFN RP-017, Attachment B during the completion of element 2.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM, the Candidate will have simulated tripping the RCPs from their PA01 and PA02 breakers and simulated tripping the turbine at either PG Load Centers PG11 and PG12 or at the EHC skid.

START TIME:

Phase A Actions Complete Time:

JPM NO:

P-2 Page 2 of 6 STOP TIME:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 3 of 6

1.

Obtain Arc Face Shield and Lab Coat.

After the candidate locates the locker and simulates opening the locker, CUE:

Face Shield and Lab Coat are in hand.

Locate the Emergency Locker located on the 2033 level near columns TE and T-3. Key to the locker is on Turbine Bldg Operator Key Ring.

Operations Expectations is to have a face shield and FR clothing (Lab Coat) prior to operating 13.8 Kv breakers.

2. *Locally Trip RCPs.

PA0107 for RCP A -

TRIPPED

PA0108 for RCP B -

TRIPPED

PA0205 for RCP C -

TRIPPED

PA0204 for RCP D -

TRIPPED STEP B1 As each handswitch is rotated to the left, CUE; Noise of breaker opening Green light only is illuminated.

Record this time.

CUE : This is the end of the Phase A time critical portion of this JPM, continue with the procedure actions.

Locate Breaker PA0107, PA0108, PA0205, and PA0204 cubicles in turn and simulate rotating the trip handle to the left.

Note sound of breaker opening and green light only illuminated.

Phase A actions must be completed within 5 minutes.

For the performance of the JPM the time limit is 10 minutes.

S U Comments:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 4 of 6

3.

Obtain A Copy Of This Procedure.

STEP B2 After the candidate locates the locker and simulates opening the locker, CUE:

Procedure is in hand.

Provide the candidate with an information only copy of OFN RP-017, Attachment B.

Locate the Emergency Locker located on the 2033 level near columns TE and T-3. Key to the locker is on Turbine Bldg Operator Key Ring.

S U Comments:

4.

Perform the following

Obtain radio and flashlight

Obtain pocket ion chambers and TLDs

Select Channel 1 on the radio STEP B3 CUE: Equipment is in hand and the radio is selected to channel 1 Simulated removing equipment from locker:

Radio and flashlight

Pocket ion chambers

Simulated selecting channel 1 on the radio S U Comments:

5.

Inform SRO that Phase A actions are complete STEP B4 Acknowledge report Simulate calling Aux Shutdown Panel on channel 1 and report Phase A actions are complete S U Comments:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 5 of 6

6.

On PK41 OPEN breaker for DC control power to PA01 STEP B5

7.

On PK62 OPEN breaker for DC control power to PA02 STEP B6 Cue: Simulate Entry CUE: PK4103 is OFF CUE: PK6204 is OFF Candidate should state that Security be contacted prior to entry of cage area.

Have Candidate discuss location of panels.

Go to the security cage surrounding PK1 & PK2 on level 2033 Turbine Bldg NW. Indicate entry is required using the high security key to open PK4103.

Go to the security cage surrounding PK1 & PK2 on level 2033 Turbine Bldg NW. Indicate entry is required using the high security key to open PK6204.

S U Comments:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 6 of 6

8.

Verify Turbine Trip STEP B7 When the candidate indicates they are checking the position of Main Turbine Stop Valves 1, 2, 3, or 4. If the turbine is operating (stop valves open), CUE:

The valves are as you actually see them now.

If the turbine should happen to be actually out of operation (stop valves closed), CUE The transducer rod is extended upward toward the valve body Go to the Main Stop Valves on the 2033 level SE part of bldg just outside the Main Lube Oil Room and note the valves are not closed by noting the transducer rod is extended along the side of the valve stem.

(The valve stem is not extended down out of the valve body)

Realize the turbine is not tripped and perform the RNO S U Comments:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 7 of 6

9. *Locally trip turbine by either:

Trip both EHC Pumps OR

Open Hyd Fluid Return Coolers Bypass Valve STEP B7 RNO CUE:

Noise is heard, breaker indicates open Noise is heard, breaker indicates open OR Valve operator is turning to the left.

Threads are retracting.

Valve will no longer turn left.

Critical step is to trip both pumps OR open the bypass valve.

EITHER Locate PG1105 on 2016 level, south end of Turb Building. Depress trip PB and open the racking window for the breaker.

AND Locate PG1205 on 2016 level, south end of Turb Building. Depress trip PB and open the racking window for the breaker.

OR Locate CH FV-1 above head level on west side of EHC skid, 2000 level on SE side of Turb Building. Simulated rotating the valve operator to the left.

S U Comments:

JPM NO: P-2 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 8 of 6

10. Ensure AL HV-36 CST to Turbine Driven AFP Suction Iso Valve is OPEN

Contact SRO to ensure breaker is off CUE:

Breaker NG03CEF4 is NOT open yet THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Use radio to contact ASP for the status of the breaker Perform the RNO and do not continue at this time When candidate states they cannot continue terminate the JPM.

S U Comments:

JPM NO: P-2 Page 9 of 6 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

NO EQUIPMENT WILL BE OPERATED IN THE PLANT - SIMULATE ONLY Read to Performer:

Initial Conditions: You are an extra licensed operator on shift. You are designated as the operator to perform the Turbine Building Actions for OFN RP-017, CONTROL ROOM EVACUATION.

Initiating Cues: You hear the following gaitronics announcement: Reactor Trip, Evacuating the Control Room due to fire, entering OFN RP-017.

This is a Time Critical JPM.

In Plant JPM P-3 Page 10 of 6 JOB PERFORMANCE MEASURE JPM No. P-3 K/A NO: 4.1E055EK3.02 COMPLETION TIME: 15 Minutes K/A RATING: 4.3/4.6 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Align the Fire Protection System to the CST SAFETY FUNCTION: 4 DUTY: Operate Auxiliary Feedwater System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE:

DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE:

SIMULATED X PERFORMED

REFERENCES:

EMG C-0 TOOLS/EQUIPMENT:

PREPARER:

DATE:

12/2/2005

JPM NO: P-3 Page 11 of 23 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

NO EQUIPMENT WILL BE OPERATED IN THE PLANT - SIMULATE ONLY Initial Conditions: A loss of all AC power has occurred while in Mode 1. The Control Room Operators are at step 27 of C-0, Loss of All AC Power and CST to AFP suction pressure is low.

Initiating Cues:

The Control Room Supervisor directs you to manually align the Fire Protection System to the CST per EMG C-0, Step 27 RNO.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Provide an information only copy of C-0, Step 27.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930).

Task Standard:

Upon completion of this JPM the Operator will have installed a jumper hose between the Fire Protection System header and the condensate reject to CST header flush connection.

START TIME:

STOP TIME:

JPM NO: P-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 12 of 23

11. *Locally close

AP-V006, Condensate Reject Iso

AD-V121, Condensate Valve Outlet Iso.

BM-V153, SG Blowdown to CST Inlet Isolation STEP 27 RNO a.

CUE: Chain is removed. Stem is retracting. Valve will no longer turn in the clockwise direction.

Stem is retracting.

Valve will no longer turn in the clockwise direction.

Stem is retracting.

Valve will no longer turn in the clockwise direction.

Locate valve in the CST Valve Room. Simulate removing the lock and chain. Rotate the handwheel in the clockwise direction.

Monitor that the stem is retracted and the valve will not longer rotate in the clockwise direction.

Locate valve in the Turbine Building SE of Condenser. Simulate rotating the handwheel in the clockwise direction.

Monitor that the stem is retracted and the valve will no longer rotate in the clockwise direction.

Locate valve in the Turbine Building SE of Condenser. Simulate rotating the handwheel in the clockwise direction.

Monitor that the stem is retracted and the valve will not longer rotate in the clockwise direction.

S U Comments:

JPM NO: P-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 13 of 23

12. *Obtain flange from AFW Emergency Locker STEP 27 RNO b.

Provide photo of locker contents.

CUE: The flange is in hand.

Locate Emergency Locker outside the Aux Boiler room main door.

Simulate removing the break away lock and removing the flange.

Have Candidate point out the flange.

S U Comments:

JPM NO: P-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 14 of 23

13. *Connect the fire hose between:

KC-V278

Flush connection next to AP-V006 STEP 27 RNO c.

CUE: Hose is in hand.

CUE: The hose is threaded on the valve and the coupling is snug.

CUE: The adapter is bolted to the flange.

CUE: The fire hose is threaded to the adapter.

Simulate obtaining a 2 1/2 fire hose from a hose house or the Brigade Locker.

Locate the valve in the SE stairwell of the Turbine Bldg. Simulate placing the female end on the FP valve and turning the coupling clockwise until tight.

Locate the flush connection next to AP-V006, remove the blank, and install the adapter.

Attach the fire hose to the adapter.

Candidate may state they would contact Security for the propped open door.

S U Comments:

JPM NO: P-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 15 of 23

14. Ensure diesel driven fire pump is running.

STEP 27 RNO d.

CUE: Diesel driven fire pump is running Simulate using a hand held radio and contact the Control Room and notify them to start the diesel driven fire pump.

S U Comments:

15. *Pressurize the fire hose.

STEP 27 RNO e.

CUE: Valve will no longer turn.

If asked, CUE: The hose has become solid to the touch and shows indication of being charged.

Actuate KC-V278 in the counter clockwise direction.

May note hose distends because of system pressure.

S U Comments:

JPM NO: P-3 TASK NUMBER - ELEMENT CUE STANDARD SCORE

Indicates critical task Page 16 of 23

16. *Locally add water to CST.

a. Open AP-V006 STEP 27 RNO f.

CUE: Handwheel is turning counter clockwise. Stem is rising. Handwheel will no longer turn.

If contacted, CUE: Go on with other duties, we will monitor CST level.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Open AP-V006 by actuating the handwheel in the counter clockwise direction. Check for rising stem.

Should contact Control Room for further instructions.

S U Comments:

JPM NO: P-3 Page 17 of 23 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

NO EQUIPMENT WILL BE OPERATED IN THE PLANT - SIMULATE ONLY Initial Conditions: A loss of all AC power has occurred while in Mode 1. The Control Room Operators are at step 27 of C-0, Loss of All AC Power and CST to AFP suction pressure is low.

Initiating Cues:

The Control Room Supervisor directs you to manually align the Fire Protection System to the CST per EMG C-0, Step 27 RNO.

Person / Time
ML060880360
Site:	Wolf Creek (NPF-042)
Issue date:	03/06/2006
From:	Operations Branch IV
To:
References
Download: ML060880360 (181)
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ML060880360

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