Text

2004 - Final Operating Reference Examination
	ML041130156
Person / Time
Site:	Fort Calhoun
Issue date:	04/16/2004
From:	Gody A; Operations Branch IV
To:	Ridenoure R; Omaha Public Power District
References
	50-285/04-301 50-285/04-301
	Download: ML041130156 (156)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 1 Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: IC# 1 100% Power BOC Turnover: Diesel Generator DG-1 and Charging Pump CH-1B are out of service. Maintain full power operation.

Event No.

Malf No.

Event Type*

Event Description 1 (0 min)

COP T:F908 I - sec S/G steam flow transmitter output fails low 2 (5 min)

COP T:122H2 I - pri Hot leg RTD fails high (tech spec entry) 3 (15 min)

ORP X10I227 C - sec Heater Drain Pump, FW-5B, trips 4 (20 min)

COP JLB218LL I - pri VCT level transmitter fails low 5 (30 min)

MFP CRD06 1 C - pri CEA drop (tech spec entry) 6 R - pri N - sec T. S. required power reduction 7 (42 min)

ORP X01I392 C - pri CCW pump, AC-3B, trips (tech spec entry) 8 (47 min)

MFP CRD06 5 C - pri Second CEA drops - Manual Reactor Trip Required 9 (55 min)

MFP SGN01A M - all Steam Generator Tube Rupture 10 (preset)

COP RSGH041A C - sec MSIV on ruptured S/G will not close

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 1 Page 2 of 11 Event

Description:

S/G steam flow transmitter output fails low Time Position Applicants Actions or Behavior SEC Respond to S/G-2B level low alarm SEC Identify and communicate lowering FW flow and level in S/G B SRO Direct SEC to take manual control of feedwater (FC-1102 in manual)

SEC Take manual control and restore feedwater level before level lowers to 50% NR on B S/G SEC Identify FR-908 as failed instrument SRO Inform OCC of failure of FR-908 SEC Continue to monitor and control S/G level PRI Monitor primary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 2 Page 3 of 11 Event

Description:

Hot leg RTD fails high (tech spec entry)

Time Position Applicants Actions or Behavior PRI Responds to numerous alarms on CB-4, panel A-20 and CB-1,2,3, panel A4. Reports that Trip Units 1, 9 and 12 on Channel A are tripped PRI/SEC Reviews ARP PRI Checks power, pressure and temperature indications PRI Determines that alarm causes by failed T-hot channel (C/T122H)

SRO Enters T. S. 2.15 and refers to 2.10.4 (5) per ARP (Trip units 1, 9 and 12 on channel A must be bypassed within one hour.

The trip units may remain bypassed for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , at which time they must be placed in the tripped condition. If it is determined that an RTD has failed, the allowable bypass time increases to 7 days after which the reactor must be placed in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

SRO Obtains keys and directs PRI to bypass TUs 1,9 and 12 on affected channel PRI Bypasses TUs 1, 9 and 12 on affected channel SRO Makes notification of failed transmitter and bypassed TUs

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 3 Page 4 of 11 Event

Description:

Heater Drain Pump, FW-5B, trips Time Position Applicants Actions or Behavior SEC Respond to Heater Drain Pump B Overload/Trip Alarm PRI or SEC Refer to ARP SEC Determine that standby Heater drain pump did not start SRO Direct SEC to start standby Heater Drain Pump SEC Start standby Heater Drain Pump, FW-5A SEC Dispatch Operator to check pump status SRO Report Heater Drain Pump Trip to the OCC SEC Monitor Condensate, Heater Drain and Feedwater system PRI Monitor primary plant systems

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 4 Page 5 of 11 Event

Description:

VCT level transmitter fails low Time Position Applicants Actions or Behavior PRI Respond to Volume Control Tank Level LO-LO alarm PRI or SEC Obtain ARP-CB-1,2,3/A2 SRO Direct PRI to check VCT level PRI Report level on channel LIC-219 is normal PRI Report charging pump suction swapped to SIRWT SRO/PRI Determine that level switch failed SRO Direct PRI to manually open LCV-218-2 and close LCV-218-3 PRI Open LCV-218-2 and close LCV-218-3 PRI Monitor and control primary parameters SEC Monitor and control secondary parameters PRI Optional: may place off-normal placard on LCV-218-2 and /or LCV-218-3 switches SRO Notify OCC of failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 5 Page 6 of 11 Event

Description:

CEA drop (tech spec entry)

Time Position Applicants Actions or Behavior PRI Identify event from Dropped Rod and other alarms PRI Determine only one rod has dropped (rod #1, grp 4)

SRO Enter AOP-02 (CEDM Malfunction)

SRO Direct SEC to adjust turbine load to match reactor power SEC Adjust turbine load to match reactor power SRO Direct RO to control pressurizer pressure and level PRI Monitor Pressurizer pressure and level SRO Direct PRI to reset Rod Drop Bistables PRI Reset Rod Drop Bistables SRO Notify Reactor Engineer SRO Enter Tech Sec 2.10.2.

(Reactor power must be reduced to less than 70% within one hour. The CEA must be realigned or declared inoperable within one hour following the power reduction. If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .)

SRO Inform RO and SEC that Tech Specs require a power reduction to less than 70% within one hour SRO Notify system Operations of impending power reduction SEC Continue manual control of S/G level

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 6 Page 7 of 11 Event

Description:

T. S. required power reduction Time Position Applicants Actions or Behavior SRO Direct PRI and SEC to commence power reduction using AOP-05 or OP-4 SRO Direct PRI on method of boration to use. (Options are normal boration, shifting charging pump suction to the SIRWT, or entering AOP-05 (Emergency Shutdown)

PRI Begin boration SEC Reduce turbine load to control RCS Tc.

PRI Monitor and control primary parameters during power reduction SEC Monitor and control secondary parameters during power reduction SRO Contact chemistry to sample RCS due to downpower PRI May contact Aux Building operator about waste tank level for power reduction

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 7 Page 8 of 11 Event

Description:

CCW pump, AC-3B, trips (tech spec entry)

Time Position Applicants Actions or Behavior PRI Respond to numerous CCW alarms on CB-1,2,3 PRI Identify and report CCW pump trip PRI Determine and report auto start failure of backup CCW pumps SRO Direct PRI to manually start a CCW pump PRI Start a CCW pump SRO Direct PRI to monitor CCW pump discharge pressure and flow PRI Verify CCW operating parameters SRO Report CCW pump trip and auto start failures to OCC

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 8 Page 9 of 11 Event

Description:

Second CEA drops - Manual Reactor Trip Required Time Position Applicants Actions or Behavior PRI Respond to alarm. Inform SRO that second CEA has dropped.

SRO Direct PRI to manually trip the reactor.

PRI Manually trip the reactor SRO Following manual or auto reactor trip, direct standard post trip actions SEC Manually ramp down FW regulating valve for B steam generator PRI SEC Perform Standard Post Trip Actions:

Verify control rod insertion, power lowering, negative startup rate

Verify turbine trip and generator trip

Verify electrical status - 4160, D/G, instrument power, 125V DC

Verify instrument air status

Verify CCW and raw water status

Verify RCS inventory control

Verify RCS pressure control

Verify core heat removal

Verify S/G feed

Verify S/G pressure and T-cold

Verify containment conditions

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 9, 10 Page 10 of 11 Event

Description:

Steam Generator A Tube Rupture Time Position Applicants Actions or Behavior PRI Identify and report RCS inventory loss PRI or SEC Report rising radiation levels on RM-054A and/or RM-057 SRO Diagnose tube rupture - enter EOP-04 or EOP-20 SRO Direct RCS cooldown - Thot less than 510°F SEC Cooldown RCS Thot to less than 510°F PRI Identify and verify PPLS SRO SEC Identify most affected steam generator (A)

SRO Direct SEC to isolate steam generator A SEC Isolate steam generator A, Close the following:

HCV-1041A (A MSIV) [will not close]

HCV-1041C (A MSIV bypass)

MS-291 (atmospheric steam safety valve)

FCV-1101 (FW reg valve)

HCV-1105 (FW reg bypass valve)

HCV-1386 (FW header isolation)

HCV-1103 (FW reg block valve)

HCV-1388A (blowdown isolation)

HCV-1388B (blowdown isolation)

HCV-1107A (AFW isolation)

HCV-1107B (AFW isolation)

YCV-1045A (supply to turbine driven AFW pump, FW-10)

Direct the turbine building operator to close:

MS-298 (MSIV packing leakoff)

SEC Report failure of S/G As MSIV to close SRO or SEC Direct Plant Operator to attempt local closure of MSIV

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 9,10 cont Page 11 of 11 Event

Description:

CCW pump, AC-3B, trips (tech spec entry)

Time Position Applicants Actions or Behavior SRO Direct RO to depressurize RCS to less than 1000 psia PRI Depressurize the RCS PRI Maintain subcooling SEC Monitor and control secondary parameters. Block SGLS during cooldown.

PRI Monitor and control primary parameters Scenario ends with RCS cooldown and depressurization in progress and Steam Generator A isolated except for its MSIV

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2 Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: IC #1 100% Power BOC Turnover: Diesel driven AFW pump, FW-54 and charging pump CH-1B are Out of Service.

Maintain power.

Event No.

Malf No.

Event Type*

Event Description 1 (+2 min)

COP T:P910 I - sec PT-910 fails high causing turbine bypass valve to open 2 (+5 min)

COP NCVPCH1 C

C - pri Charging Pump, CH-1C, Trips (tech spec entry) 3 (+10 min)

MFP NIS02D Wide Range NI channel D fails (tech spec entry) 4 (+15 min)

COP T:P103Y I - pri Pressurizer Pressure channel, 103Y, fails low 5 (+20 min)

MFP TUR05F C - sec High turbine vibration caused by inadequate oil cooling 6 (+28 min)

MFP SWD02A SWD02B M - all Loss of Offsite Power 7 (preset)

File ATWAS_P LUS1 M - all ATWS - manual trip required 8 (preset)

RFP AFW10A C - sec Emergency Feedwater Storage Tank line is blocked causing a total loss of Feedwater (once-through cooling required) 9 (20% WR level on both steam generators)

M - all Initiate Once-Through Cooling (Note: Examiner may direct simulator operator to run a file to lower steam generator levels to 20%, once through cooling initiation level, if required for time limitations)

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 1 Page 2 of 9 Event

Description:

PT-910 fails high causing turbine bypass valve to open Time Position Applicants Actions or Behavior SEC Identify rapid decrease in RCS T-cold (VOPT ANN will alarm if uncorrected)

PRI or SEC If alarm is received, then refer to ARP SEC Determine cause as turbine bypass valve being open (red light on CB-10,11)

SRO Direct SEC to take manual control of PCV-910 and close valve SEC Take manual control of PCV-910 and close it SEC Monitor RCS Tc PRI Monitor and control RCS parameters SRO Notify I & C of failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 2 Page 3 of 9 Event

Description:

Charging Pump, CH-1C, Trips (tech spec entry)

Time Position Applicants Actions or Behavior PRI Respond to Charging Pump Off-Normal Annunciator on AI-30 PRI or SEC Refer to ARP PRI Report Charging Pump Trip SRO Direct PRI to Start a charging pump.

PRI Start charging pump, CH-1A.

PRI Direct Auxiliary Building Operator to check status of charging pumps and ensure packing cooling pump running for pump that was started PRI Control pressurizer level as needed SRO Enter Technical Specification 2.2.4(1).

(72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO due to 2 charging pumps being inoperable. If 2 charging pumps can not be restored to operability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , then be in hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , less than 300°F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months )

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 3 Page 4 of 9 Event

Description:

Wide Range NI channel D fails (tech spec entry)

Time Position Applicants Actions or Behavior PRI Respond to Nuclear Instrument Channel Inoperative Alarm PRI or SEC Refer to ARP-CB4-A20 SRO Direct PRI to check operation of NIS channels PRI Report failure of WR channel D (NON-OP light lit)

SRO Optional : may refer to AOP-15 (not required at this power level)

SRO Optional: May direct PRI to bypass channel D SUR trip PRI If directed, bypass channel D SUR trip SRO Enter Technical Specification 2.15 (7 day LCO because WR channel D provides the input to AI-212 on the alternate shutdown panels)

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 4 Page 5 of 9 Event

Description:

Pressurizer Pressure channel, 103Y, fails low Time Position Applicants Actions or Behavior PRI Respond to PZR Pressure Off Normal Hi-Lo Channel Y alarm on CB-1,2,3 A4 PRI or SEC Refer to ARP PRI Identify deviation between pressurizer pressure channels.

SRO Direct PRI to swap controlling channels or to take manual control of pressurizer pressure.

PRI Switch controlling channel to channel 103X or take manual control of pressurizer pressure.

PRI Monitor and maintain proper pressurizer pressure.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 5 Page 6 of 9 Event

Description:

High turbine vibration caused by inadequate oil cooling Time Position Applicants Actions or Behavior PRI or SEC Respond to plant computer alarm for high turbine vibration SEC Report recorder indication of rising vibration on bearing #6, 7 mills and rising SRO Enter AOP-26 SEC Report vibration greater than 8 mills SRO Direct power reduction SEC Reduce turbine load PRI Control reactivity during load reduction SEC Report turbine vibration below 8 mills SRO Direct PRI and SEC to maintain power SRO or SEC Dispatch Turbine Building Operator to check turbine cooling SRO or SEC Upon receiving report of high lube oil temperature, direct Turbine Building Operator to raise cooling water flow.

SEC Continue to monitor vibration levels

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 6, 7 Page 7 of 9 Event

Description:

Loss of Offsite Power with ATWS Time Position Applicants Actions or Behavior PRI Determine and communicate that the reactor failed to trip.

SRO Direct PRI to manually trip the reactor PRI Push CB-4 manual Reactor Trip Pushbutton.

SEC Determine and communicate that Trip did not actuate.

SRO Direct the PRI and SEC to initiate RPS panel (AI-31) trip and DSS trip.

SEC Operate DSS Trip.

SRO Direct PRI or SEC to open Clutch Power Supply Breakers PRI or SEC Open Clutch Power Supply Breakers PRI Optional: May initiate Emergency Boration PRI Determine and communicate that the rods have inserted.

SRO Direct PRI and SEC to take Standard Post Trip Actions (SPTAs).

PRI SEC Perform Standard Post Trip Actions:

Verify control rod insertion, power lowering, negative startup rate

Verify turbine trip and generator trip

Verify electrical status - 4160, D/G, instrument power, 125V DC

Verify instrument air status

Verify CCW and raw water status

Verify RCS inventory control

Verify RCS pressure control

Verify core heat removal

Verify S/G Feed-Report loss of feedwater

Verify S/G pressure and T-cold

Verify containment conditions PRI Restart charging pump, CH-1A SRO Verify completion of SPTAs

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 8 Page 8 of 9 Event

Description:

Emergency Feedwater Storage Tank line is blocked causing a total loss of Feedwater (once-through cooling required)

Time Position Applicants Actions or Behavior SEC Determine and communicate Loss of All Feedwater.

SRO Direct SEC to attempt to restore feedwater flow.

SEC Start motor driven AFW pump (FW-6).

SEC Start turbine driven AFW pump (FW-10).

SEC Report AFW flow can not be established.

SEC Enter EOP-06 or EOP-20 SRO Direct SEC to isolate blowdown.

SEC Isolate blowdown SRO Direct SEC to monitor S/G level for Once Through Cooling.

SEC Report when WR level is approaching 20% on both S/Gs

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 9 Page 9 of 9 Event

Description:

Initiate Once Through Cooling Time Position Applicants Actions or Behavior SRO Enter EOP-20/HR-4.

SRO Direct PRI to initiate Once Through Cooling.

PRI Open all HPSI loop injection valves.

HCV-311

HCV-312

HCV-314

HCV-315

HCV-317

HCV-318

HCV-320

HCV-321 PRI Start all three HPSI pumps and ensure charging pump.CH-1A is running PRI Open Both PORVs PRI Verify PORVs have opened.

PRI Report Once Through Cooling is initiated.

SRO Direct PRI and SEC to monitor parameters.

PRI Monitor primary parameters.

SEC Monitor secondary parameters.

Scenario ends with Once-Through Cooling in progress.

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 3 Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: IC# 7 BOC 50% Power, FW-54 Out of Service Turnover: Diesel driven FW pump, FW-54 is out of service. Maintain power Scenario objective: Evaluate ISRO candidates in the primary and secondary positions with a surrogate acting as SRO Event No.

Malf No.

Event Type*

Event Description 1 (+2 min)

COP T:L101Y I - pri Controlling pressurizer level channel, 101Y, fails low 2 (+7 min)

COP T:L906Y I - sec Steam generator RC-2B level channel, 906Y, fails high 3 (+13 min)

MFP RCP09B C - pri Reactor Coolant Pump, RC-3B, lower seal failure 4 (+18 min)

COP T:P210 I - pri Letdown pressure transmitter PT-210 fails low 5 (+24 min)

MFP RCP10B Reactor Coolant Pump, RC-3B, middle seal failure 6

R - pri N - sec Emergency shutdown 7 (+35 min)

RFP BCW10A C - sec Running Bearing water pump, AC-9A, trips 8 (+40 min)

MFP RCS01C 0.2%

M - all Loss of Coolant Accident 9 (preset)

MFP EHC02 C - sec Turbine trip failure 10 (preset)

File HPSI-LOOP-INJ-PULL C - pri HPSI loop injection valves fail to open

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 1 Page 2 of 10 Event

Description:

Controlling pressurizer level channel, 101Y, fails low Time Position Applicants Actions or Behavior PRI Respond to Low Level alarm PRI Identify and report failure of pressurizer level instrument SRO Direct PRI to transfer control channels or take manual control of controlling channel PRI Transfer control channel or take manual control of level PRI Monitor and control pressurizer level SRO Direct PRI to select X channel on the low level heater cutout switch PRI Select X channel on low level heater cutout switch SEC Monitor secondary parameters SRO Notify OCC of instrument failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 2 Page 3 of 10 Event

Description:

Steam generator RC-2B level channel, 906Y, fails high Time Position Applicants Actions or Behavior SEC Responds to Feedwater Control Steam Generator RC-2B Level Hi alarm PRI or SEC Obtain ARP-CB-4/A8 and determines actions SEC Check S/G level channels to determine failed channel SEC Identify regulating valve FCV-1102 is closed SRO Direct SEC to take manual control of FCV-1102 SEC Takes manual control of FCV-1102 Aux controller and opens valve to control level SRO Notifies OCC of failure PRI Monitors primary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 3 Page 4 of 10 Event

Description:

Reactor Coolant Pump, RC-3B, lower seal failure Time Position Applicants Actions or Behavior PRI Identify and communicate high seal leakage from alarms PRI or SEC Refer to alarm response procedure SRO Enter AOP-35 PRI Monitor RCP seal pressures and determine that the lower seal on RCP B has failed SRO Direct primary operator to continue to monitor seal parameters PRI Monitor RCP seal parameters PRI or SEC Raise seal cooling water flow to RC-3B SRO Notify OCC of the seal failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 4 Page 5 of 10 Event

Description:

Letdown pressure transmitter PT-210 fails low Time Position Applicants Actions or Behavior PRI Respond to Intermediate Letdown Pressure Alarm PRI Determine and communicate loss of letdown flow due to PCV-210 being closed SRO Direct PRI to isolate letdown PRI Isolate letdown SRO Direct PRI to take manual control of PCV-210 and reestablish letdown flow per OI-CH-1 PRI Take manual control of PCV-210 and reestablish letdown flow.

SRO Notify OCC of PC-210 failure PRI Monitor and control letdown SEC Monitor secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 5 Page 6 of 10 Event

Description:

Reactor Coolant Pump, RC-3B, middle seal failure Time Position Applicants Actions or Behavior PRI Monitor RCP seal pressures and determine that the lower and middle seals on RCP B have failed SRO Direct Emergency Shutdown and enter AOP-05 (Emergency Shutdown)

SEC Monitor secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 6 Page 7 of 10 Event

Description:

Emergency shutdown Time Position Applicants Actions or Behavior SRO Enter AOP-05 (Emergency Shutdown) - Direct Emergency Shutdown SRO Notify System Operations of Power Decrease SRO Direct PRI to begin boration using SIRWT PRI Switch charging pump suction from the VCT to the SIRWT PRI Direct SEC to control RCS cold leg temperature by reducing turbine load SEC Reduce turbine load to control cold leg temperature SRO Direct PRI to operate control rods to control ASI PRI Operate Control Rods to control ASI PRI Monitor and control primary parameters SEC Monitor and control RCS cold leg temperature and secondary parameters SRO Continue to coordinate PRI and SEC actions during power reduction

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 7 Page 8 of 10 Event

Description:

Running Bearing water pump, AC-9A, trips Time Position Applicants Actions or Behavior SEC Respond to Cooling Water Pressure Low alarm SEC Report that AC-9A tripped SRO Direct SEC to start AC-9B SEC Start AC-9B SRO Direct SEC to verify operation of air compressor SEC Verify operation of air compressors (CA-1C stops and restarts)

SRO May enter AOP-20

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 8, 9 Page 9 of 10 Event

Description:

Loss of Coolant Accident with turbine trip failure Time Position Applicants Actions or Behavior PRI Identify and communicate lowering of pressurizer level and pressure.

SRO May direct RO to manually trip the reactor.

PRI Manually trip the reactor if directed by SRO.

SRO Direct Standard Post Trip Actions (SPTAs)

PRI Perform Standard Post Trip Actions:

Verify control rod insertion, power lowering, negative startup rate SEC Perform Standard Post Trip Actions:

Verify turbine and generator trip

Determines that stop and intercept valves have not closed

Manually trips the turbine

Place both EHC pumps in pullout SEC Report that turbine did not trip PRI and SEC Continue Standard Post Trip Actions:

Verify electrical status - 4160, D/G, instrument power, 125V DC

Verify instrument air status

Verify CCW and raw water status

Verify RCS inventory control

Verify RCS pressure control

Verify core heat removal

Verify S/G feed

Verify S/G pressure and T-cold

Verify containment conditions SEC Closes both MSIVs if steam generator pressure lowers to 500 psia PRI Secure 1 RCP in each loop at 1350 psia.

PRI Secure remaining RCPs on loss of NPSH SRO Transition to EOP-03 (LOCA).

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 3 Event No.: 10 Page 10 of 10 Event

Description:

HPSI loop injection valves fail to open Time Position Applicants Actions or Behavior PRI Monitor for automatic PPLS actuation.

PRI Determine and report that HPSI loop injection valves did not open.

SRO Direct PRI to manually open HPSI loop injection valves PRI Manually open HPSI loop injection valves PRI Verify and report meeting HPSI flow criteria.

Scenario ends with HPSI flow in progress

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 4 (spare)

Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: IC#1 100% Power BOC Ensure FW-5B and FW-5C are the running Heater Drain Pumps.

Turnover: LPSI pump SI-1B is Out of Service for bearing replacement Event No.

Malf No.

Event Type*

Event Description 1 (+3 min)

MFP NIS03F I - pri Power range nuclear instrumentation channel C fails (tech spec entry) 2 (+10 min)

COP T:F1101 I - sec FW flow channel on RC-2A fails low 3 (+15 min)

MFP DSG06A C - sec Diesel Generator, D/G-1, radiator leak (tech spec entry) 4 (+25 min)

COP T:T2897 I - pri Letdown HX CCW outlet temperature transmitter fails low 5 (+30 min)

MFP SWD02B C -sec Loss of 161 KV 6 (+40 min)

MFP MSS01B 25%

300 sec ramp M - all Steam line break inside containment 7 (preset)

RFP CWS10N C -sec CW-1C breaker fails to trip preventing D/G-2 breaker from closing 8 (preset)

MFP ESF02A ESF 02B C - pri CPHS fails to actuate

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 1 Page 2 of 9 Event

Description:

Power range nuclear instrumentation channel C fails (tech spec entry)

Time Position Applicants Actions or Behavior PRI Identify the failure from numerous alarms on CB-4, panel A20 and Trip Units 9 and 12 on channel C SRO Reference AOP-15 SRO Enters Technical Specification 2.15 (Trip units 1, 9 and 12 on channel C must be bypassed within one hour.

The trip units may remain bypassed for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , at which time they must be placed in the tripped condition. If it is determined that a nuclear detector has failed, the allowable bypass time increases to 7 days after which the reactor must be placed in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

SRO Obtain the keys and direct the PRI to place the 1, 9 & 12 trip units on C RPS channel in bypass PRI Place 1, 9 and 12 trip units in bypass SEC Enter channel bypass in control room log SEC Monitor Secondary Parameters SRO Notify OCC of instrument failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 2 Page 3 of 9 Event

Description:

FW flow channel on RC-2A fails low Time Position Applicants Actions or Behavior SEC Respond to S/G-2B level low alarm SEC Identify and communicate rising FW flow and level in S/G A and lowering level in S/G B SRO Direct SEC to take manual control of feedwater SEC Take manual control and restore feedwater level SEC Identify FT-1101 as the failed instrument or channel SRO Inform OCC of failure of FT-1101 SEC Continue to monitor and control S/G level PRI Monitor primary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 3 Page 4 of 9 Event

Description:

Diesel Generator, D/G-1, radiator leak (tech spec entry)

Time Position Applicants Actions or Behavior PRI or SEC Respond to Diesel Trouble Alarm and LS-4, Tank Level Low indicator light PRI or SEC Refer to ARP-AI-30A/A30 PRI or SEC Dispatch Turbine Building Operator to determine status of D/G.

PRI or SEC Inform SRO of report of water leak SRO Direct PRI or SEC operator to disable D/G-1 SRO Enter Technical Specifications 2.7 and 2.0.1(b)

(Technical Specification 2.7 requires that the plant be placed in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . However, Technical Specification 2.0.1 (b) also applies due to D/G-1 (1A3) and SI-1B (1A4) both being inoperable, and requires that the plant be placed in hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Refer to Tech Spec Interpretation 96-13-1)

SRO Direct PRI and SEC to make preparations for plant shutdown SRO Notify Station Management of Tech Spec required shutdown

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 4 Page 5 of 9 Event

Description:

Letdown HX CCW outlet temperature transmitter fails low Time Position Applicants Actions or Behavior PRI Respond to Letdown Heat Exchanger Tube Outlet Temp HI Alarm on CB-1,2,3 panel A2 PRI Determine that TCV-211-2 has repositioned to bypass ion exchangers PRI Determine high temperature due to reduced CCW flow to letdown heat exchanger following closure of TCV-2897 SRO Direct PRI to manually control CCW flow to letdown HX using TCV-2897 PRI Manually control TCV-2897 to restore letdown temperature using TIC-211 for indication SRO May direct PRI to place the ion exchanger back in service by repositioning TCV-211-2 and maintain 100°F - 120°F PRI Reposition TCV-211-2 if directed PRI Monitor primary parameters SEC Monitor secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 5 Page 6 of 9 Event

Description:

Loss of 161 KV Time Position Applicants Actions or Behavior SEC Diagnose loss of 161 KV from annunciators and board indications. Inform SRO SRO Enter AOP-31 and Direct SEC operator SEC Ensure 2 FW pumps, 2 CND pumps and 2 HD pumps are running SEC Ensure Main Generator terminal voltage less than 22,000 volts SEC Ensure FW-2A, FW-4A and FW-5A are operating. Start FW-5A, shutdown 1 other HD pump SEC Verify 480V bus voltage SEC Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 SRO or SEC Direct that signs be placed at switchgear room entrances

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 6, 7, 8 Page 7 of 9 Event

Description:

Steam line break inside Containment, No Power to either vital bus. Failure of CPHS.

Time Position Applicants Actions or Behavior ALL Recognizes that a HELB has occurred in S/G RC-2B:

Lowing pressure in S/G RC-2B.

Initiation of a Steam Generator Low Signal (SGLS).

Lowering RCS Tav.

Raise in feedwater flow until Steam Generator Isolation Signal (SGIS) occurs.

Containment Isolation Actuation Signal (CIAS) due to raising containment pressure.

SRO Directs entry into EOP-00 PRI and SEC Perform Standard Post Trip Actions:

Verify control rod insertion, power lowering, negative startup rate

Verify turbine trip and generator trip

Verify electrical status - 4160, D/G, instrument power, 125V DC SEC Reports no power to busses 1A3 and 1A4 Continue Standard Post Trip Actions

Verify instrument air status

Verify CCW and raw water status

Verify RCS inventory control

Verify RCS pressure control

Verify core heat removal

Verify S/G feed

Verify S/G pressure and T-cold

Verify containment conditions SEC Identify failure of CW-1C breaker to open SEC/SRO Direct EONT to manually trip CW-1C breaker SRO Direct SEC to verify restoration of power to bus 1A4 SEC Verify power to bus 1A4

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 6,7,8 cont Page 8 of 9 Event

Description:

Steam line break inside Containment, No Power to either vital bus. Failure of CPHS.

Time Position Applicants Actions or Behavior PRI Monitor containment pressure and determine that CPHS did not actuate at setpoint SRO Direct PRI to manually actuate CPHS PRI Manually actuate CPHS and verify containment spray flow SRO Enters EOP-05 or EOP-20 SEC Verifies break location in accordance with EOP-20 to mitigate HELB.

PRI Verifies that all containment vent fans (VA-3A, 3B, 7C, 7D) have started and ensures that they are supplied from CCW.

SEC Ensures that SGIS valves have closed (e.g., MSIVs and FWIVs).

PRI Ensures that emergency boration is in progress by directing Aux Building Operator to open HCV-268 and/or close LCV-218-2 SRO/PRI Ensures that SI flow is acceptable PER Attachment 3, Safety Injection Flow vs. Pressurizer Pressure.

PRI SEC Maximizes safety injection and charging flows by operating:

HPSI Pumps SI-2A/B/C LPSI Pumps SI-1A/B Charging Pumps CH-1A/B/C PRI Verifies normal CCW/RW system operation:

2 CCW pumps operating CCW pump discharge pressure > 60 psig 2 RW pumps operating 3 CCW heat exchangers in service RCP cooler valves HCV-438A/B/C are open LSO SEC Confirms that S/G RC-2B is affected S/G by downward trends in steam pressure, S/G level, and RCS Tc.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 4 Event No.: 6,7,8 cont Page 9 of 9 Event

Description:

Steam line break inside Containment, No Power to either vital bus. Failure of CPHS.

Time Position Applicants Actions or Behavior SRO Direct SEC to establish steam flow from intact steam generator prior to dryout of faulted steam generator SEC

`

Establish steam flow from intact steam generator by opening MS-291 before WR level in S/G RC-2B reaches 10%

SRO Directs SEC to Isolate faulted S/G SEC Isolate steam generator B, Close (or ensure SGIS has closed) the following:

HCV-1042A (B MSIV)

HCV-1042C (B MSIV bypass)

MS-292 (atmospheric steam safety valve)

FCV-1102 (FW reg valve)

HCV-1106 (FW reg bypass valve)

HCV-1385 (FW header isolation)

HCV-1104 (FW reg block valve)

HCV-1387A (blowdown isolation)

HCV-1387B (blowdown isolation)

HCV-1108A (AFW isolation)

HCV-1108B (AFW isolation)

YCV-1045B (supply to turbine driven AFW pump, FW-10)

Direct the turbine building operator to close:

MS-298 (MSIV packing leakoff)

SRO Direct PRI to monitor and control RCS pressure to maintain subcooling between 20° and 200°F PRI Monitor and control pressure to maintain subcooling between 20° and 200°F Scenario ends with D/G-2 supplying power to bus 1A4, Containment spray in progress and Steam Generator RC-2B isolated.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 JPM

Title:

Determine Dilution Volume for Power Change Page 1 of 6 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

TDB-II, Figure II.A.2 (R27)

TDB-V.12 (R6)

K/A 2.1.

25 (RO Imp 2.8)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 JPM

Title:

Determine Dilution Volume for Power Change Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

Calculator Safety Considerations:

None Comments:

Use the TDB sections provided for this JPM. The plant TDB may use different figures due to the power uprating.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 JPM

Title:

Determine Dilution Volume for Power Change Page 3 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 JPM

Title:

Determine Dilution Volume for Power Change Page 4 of 6 INITIATING CUE:

The plant has been operating at 80% power for a week due to some limitations on the secondary side. Repairs have been made and power will be raised to 95%.

The CRS has asked you to determine how many gallons of water will be required for the power change.

The ERF computer is not available.

The plant conditions are:

Reactor Power = 80%

RCS Boron Concentration = 512 ppm RCS T-cold is 540°F RCS T-hot is 581°F All CEAs are fully withdrawn Note: Ignore the effect of xenon concentration changes for this calculation.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Determines the boron concentration change for a power increase from 80% to 95% power.

Enters TDB-II, refers to figure II.A.2.

Determines that boron concentration must be lowered approximately 50 ppm, from 512 ppm to 462 ppm 2

Determines the amount of dilution water required.

Enters TDB-V.12 Uses the dilution formula to determine that approximately 3880 gallons of water is required.

Acceptable range is between 3680 - 4080 gallons

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 JPM

Title:

Determine Dilution Volume for Power Change Page 5 of 6 STEP ELEMENT STANDARD GAL WATER = [67250.044 - 52.562 x (T-avg)] Ln (CI/CF)

= [67250.044 - 52.562 x (540+581)/2] Ln (512/462)

= 3883 gal Termination Criteria:

Determination of required dilution volume has been made.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-1 Page 6 of 6 INITIATING CUE:

The plant has been operating at 80% power for a week due to some limitations on the secondary side. Repairs have been made and power will be raised to 95%.

The CRS has asked you to determine how many gallons of water will be required for the power change.

The ERF computer is not available.

The plant conditions are:

Reactor Power = 80%

RCS Boron Concentration = 512 ppm RCS T-cold is 540°F RCS T-hot is 581°F All CEAs are fully withdrawn Note: Ignore the effect of xenon concentration changes for this calculation.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-2 JPM

Title:

Diesel Generator Hot Weather Operability Page 1 of 5 Approximate Time:

10 min Actual Time: _________________

Reference(s):

TDB-III.26A K/A 2.1.32 (RO Imp 3.4)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-2 JPM

Title:

Diesel Generator Hot Weather Operability Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-2 JPM

Title:

Diesel Generator Hot Weather Operability Page 3 of 5 INITIATING CUE:

It is night shift. Both Diesel Generators are operable.

Both are using an Ethylene Glycol solution for cooling.

The forecasted high temperature for tomorrow is 103°F.

The CRS has asked you to determine if the high temperature will affect the operability of the diesel generators. If so, what action could be taken to ensure operability.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refer to TDB-III.26A Enters TDB-III.26.A 2

Determines DG-1 Operability with Ethylene Glycol Coolant Refers to Figure 1 Determines that DG-1 would be inoperable at 103°F.

3 Determines DG-1 Operability if Ethylene Glycol solution was replaced with water.

Refers to Figure 2 Determines that DG-1 would be operable with water coolant. Recommends coolant replacement 4

Determines DG-2 Operability with Ethylene Glycol Coolant Refers to Figure 3 Determines that DG-2 would be operable at 103°F.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-2 JPM

Title:

Diesel Generator Hot Weather Operability Page 4 of 5 Termination Criteria:

DG operability at 103°F has been determined and recommendation made to replace DG-1 coolant with water.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-2 Page 5 of 5 INITIATING CUE:

It is night shift. Both Diesel Generators are operable.

Both are using an Ethylene Glycol solution for cooling.

The forecasted high temperature for tomorrow is 103°F.

The CRS has asked you to determine if the high temperature will affect the operability of the diesel generators. If so, what action could be taken to ensure operability.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-3 JPM

Title:

Determine equipment affected by isolation of Instrument Air Valve Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

P&ID 11405-M 264 sheet 1 P&ID 11405-M 264 sheet 4 K/A 2.2.13 (RO Imp 3.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-3 JPM

Title:

Determine equipment affected by isolation of Instrument Air Valve Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-3 JPM

Title:

Determine equipment affected by isolation of Instrument Air Valve Page 3 of 5 INITIATING CUE:

Maintenance has requested that instrument air valve, IA-525 be isolated for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to repair a small leak. The CRS has asked you to provide him with a written list of equipment that would be affected by isolation of this valve.

START Critical Steps shown in gray STEP ELEMENT STANDARD CUE: Provide candidate with a blank sheet of paper to list the equipment on.

1 Refers to P&ID to determine affected Instrument Air Riser.

Uses P&ID 11405-M 264 sheet 1, to determine that IA-525 isolates riser AY.

2 Refers to P&ID to determine affected equipment.

Uses P&ID 11405-M 264 sheet 4 to determine equipment affected.

3 Provides list of equipment affected.

List includes:

HCV-818B

HCV-2603A

HCV-2604A

HCV-425B

HCV-425D

A/HCV-742

B/HCV-742

C/HCV-742

D/HCV-742

AI-161

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-3 JPM

Title:

Determine equipment affected by isolation of Instrument Air Valve Page 4 of 5 Termination Criteria:

List of affected equipment has been provided.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-3 Page 5 of 5 INITIATING CUE:

Maintenance has requested that instrument air valve, IA-525 be isolated for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to repair a small leak. The CRS has asked you to provide him with a written list of equipment that would be affected by isolation of this valve.

START

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-4 JPM

Title:

RCA Entry and Exit Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

GET-Radiation Worker Training Standing Order G-101 K/A 2.3.1 (RO Imp 2.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-4 JPM

Title:

RCA Entry and Exit Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This JPM will be performed during RCA entrance and exit during conduct of in-plant JPMs.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-4 JPM

Title:

RCA Entry and Exit Page 3 of 5 INITIATING CUE:

You have been directed to enter Room 13 to ensure that blowdown tank transfer pump, FW-34A is operating properly.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Provide Initiating CUE to candidate prior to RCA entry.

1 Review RWP Reads RWP 2

Determine Radiological Conditions in Room 13.

Checks survey maps and/or discusses radiological conditions with RP personnel.

3 Obtains Dosimetry Verify TLD attached to security badge. Obtain EAD.

4 Sign in on appropriate RWP Insert EAD in reader. Scan PID and RWP number 5

Enter RCA RCA entered 6

Enter Room 13 Enters Room 13 As soon as candidate clears shield wall while entering room 13:

CUE: EAD is Alarming on high dose rate

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-4 JPM

Title:

RCA Entry and Exit Page 4 of 5 STEP ELEMENT STANDARD 7

Exits Room and Contacts RP Leaves Room Immediately and Contacts RP CUE: RP will provide coverage for Room 13 entry.

Examiner will act as RP Tech 8

Enter Room 13 with RP Tech Enters room CUE: All parameters for FW-34A are normal 9

Exits Room 13 with RP Tech Exits room Note to Examiner:

In-plant JPMs that are conducted in the RCA may be performed at this time.

Steps 10 and 11 are performed during RCA exit.

10 Monitor for personnel contamination prior to exiting RCA Monitor for contamination using PCM 11 Sign out of RCA Insert EAD in reader, enter PID number and confirm dose Termination Criteria:

RCA has been exited

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO-2004-4 Page 5 of 5 INITIATING CUE:

You have been directed to enter Room 13 to ensure that blowdown tank transfer pump, FW-34A is operating properly.

START

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-1 JPM

Title:

Review Shutdown Margin Calculation Page 1 of 5 Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

TDB-V.9 (R35)

TDB-II (R27)

K/A 2.1.7 (SRO Imp 3.7)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-1 JPM

Title:

Review Shutdown Margin Calculation Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Use provided TDB sections. Plant values may have changed due to power uprating

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-1 JPM

Title:

Review Shutdown Margin Calculation Page 3 of 5 INITIATING CUE:

CEAs 22 and 29 have just been declared inoperable (untrippable) following a surveillance test. The STA has determined that shutdown margin is adequate and has asked you to review his SDM calculation. The plant conditions are as follows:

Reactor Power: 50%

CEA position: GRP 4 @ 100, all other CEAs fully withdrawn Boron concentration: 860 ppm Burnup: 6000 MWD/MTU START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Provide Shutdown Margin Calculation to candidate with initiating cue.

Do NOT give him TDB-II until he identifies the need to use TDB-II.

1 Reviews shutdown margin calculation Determines that least conservative CEA worth was mistakenly used in step 9.c.(2) instead of the most conservative 2

Calculates shutdown margin using corrected values.

Determines that shutdown margin is between 2.93% and 3.33% and is not adequate.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-1 JPM

Title:

Review Shutdown Margin Calculation Page 4 of 5 Termination Criteria:

SRO has determined that shutdown margin is not adequate

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-1 Page 5 of 5 INITIATING CUE:

CEAs 22 and 29 have just been declared inoperable (untrippable) following a surveillance test. The STA has determined that shutdown margin is adequate and has asked you to review his SDM calculation. The plant conditions are as follows:

Reactor Power: 50%

CEA position: GRP 4 @ 100, all other CEAs fully withdrawn Boron concentration: 860 ppm Burnup: 6000 MWD/MTU START

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-2 JPM

Title:

Raw Water Operability Determination Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

TDB III.41 (R1)

Technical Specifications K/A 2.1.12 (SRO Imp 4.0)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-2 JPM

Title:

Raw Water Operability Determination Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-2 JPM

Title:

Raw Water Operability Determination Page 3 of 5 INITIATING CUE:

The plant has entered a Technical Specification LCO due to the inoperability of Raw Water Heat Exchanger AC-1A and Raw Water Pump, AC-10C.

Raw Water Pump, AC-10A has just been declared inoperable. The river conditions are as follows:

River temperature = 64°F River level = 984 feet Determine the applicable Technical Specification and required actions, if any, to be taken.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refers to TDB-III.41 Enters TDB-III-41 2

Refers to Table and Chart number 4 to determine applicable LCO Determines that T.S. 2.0.1 applies with these river conditions 3

Determines Tech Spec. 2.0.1 required Action Statement Plant must be in Hot Shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-2 JPM

Title:

Raw Water Operability Determination Page 4 of 5 Termination Criteria:

Technical Specification 2.0.1 has been entered.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-2 Page 5 of 5 INITIATING CUE:

The plant has entered a Technical Specification LCO due to the inoperability of Raw Water Heat Exchanger AC-1A and Raw Water Pump, AC-10C.

Raw Water Pump, AC-10A has just been declared inoperable. The river conditions are as follows:

River temperature = 64°F River level = 984 feet Determine the applicable Technical Specification and required actions, if any, to be taken.

START

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-3 JPM

Title:

Shift Manager Review of Surveillance Test Results Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

OP-ST-CCW-3002 K/A 2.2.12 (SRO Imp 3.4)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-3 JPM

Title:

Shift Manager Review of Surveillance Test Results Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-3 JPM

Title:

Shift Manager Review of Surveillance Test Results Page 3 of 5 INITIATING CUE:

You are acting as the Shift Manager. OP-ST-CCW-3002, AC-3A Component Cooling Water Pump Inservice Test, has been completed today. The STA has completed his evaluation of the test data and forwarded the test procedure to you for approval. Review the test documentation and approve, if warranted. Take any required actions.

START Critical Steps shown in gray STEP ELEMENT STANDARD CUE: Provide candidate with a partially filled out copy of the surveillance test procedure.

1 Reviews procedure for completion.

Procedure filled in up to point of Shift Manager approval.

2 Reviews the results in and Figure 1.

Determines that the data point was incorrectly plotted on Figure 1. Results are in the High Required Action Range.

3 Applies acceptance criteria Declares AC-3A inoperable

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-3 JPM

Title:

Shift Manager Review of Surveillance Test Results Page 4 of 5 Termination Criteria:

Test results have been reviewed.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-3 Page 5 of 5 INITIATING CUE:

You are acting as the Shift Manager. OP-ST-CCW-3002, AC-3A Component Cooling Water Pump Inservice Test, has been completed today. The STA has completed his evaluation of the test data and forwarded the test procedure to you for approval. Review the test documentation and approve, if warranted. Take any required actions.

START

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-4 JPM

Title:

Determine Primary to Secondary Leak Rate Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

Standing Order G-105 Standing Order O-43 K/A 2.3.11 (SRO Imp 3.2)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-4 JPM

Title:

Determine Primary to Secondary Leak Rate Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-4 JPM

Title:

Determine Primary to Secondary Leak Rate Page 3 of 5 INITIATING CUE:

The plant is operating at 100% power. The RCS chemistry is:

Total RCS Activity = 4.4 µCi/g

RCS Leak Check gas concentration = 3.8 µCi/cc

DEI-131 Activity = 0.02 µCi/g

Boron Concentration = 835 ppm

RM-057 has increased from 1410 cpm to 1525 cpm over the last hour.

The Condenser Evacuation pumps are in recirc mode.

The Shift Manager directs you, the CRS, to estimate the primary to secondary leakrate and determine what actions, if any, are required.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Obtain copy of Standing Order G-105 Obtains copy of Standing Order G-105

2.

Use S.O. G-105 to estimate primary to secondary leakage Estimates leakage between 75 and 80 gpd using G-105.

3 Determine Action level Action level 3 4

Determine required actions

Commence controlled plant shutdown using OP-4

Align condenser evacuation discharge to aux building stack.

5 Obtain copy of Standing Order O-43 Obtains S.O. O-43

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-4 JPM

Title:

Determine Primary to Secondary Leak Rate Page 4 of 5 STEP ELEMENT STANDARD 6

Determine fuel action level Action level 2 7

Determine desired blowdown operation Blowdown Operation should be continued Termination Criteria:

A determination of primary to secondary leakrate and required actions has been performed.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-4 Page 5 of 5 INITIATING CUE:

The plant is operating at 100% power. The RCS chemistry is:

Total RCS Activity = 4.4 µCi/g

RCS Leak Check gas concentration = 3.8 µCi/cc

DEI-131 Activity = 0.02 µCi/g

Boron Concentration = 835 ppm

RM-057 has increased from 1410 cpm to 1525 cpm over the last hour.

The Condenser Evacuation pumps are in recirc mode.

The Shift Manager directs you, the CRS, to estimate the primary to secondary leakrate and determine what actions, if any, are required.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO 2004-5 JPM

Title:

Emergency Plan Classification and PARs Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

EPIP-OSC-1 EPIP-EOF-7 K/A 2.4.41 (SRO Imp 4.1)

K/A 2.4.44 (SRO Imp 4.4)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO 2004-5 JPM

Title:

Emergency Plan Classification and PARs Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Do not perform this JPM before Simulator Scenario Number 1

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO 2004-5 JPM

Title:

Emergency Plan Classification and PARs Page 3 of 5 INITIATING CUE:

A 800 gpm steam generator tube rupture has occurred in RC-2A. EOP-00 and EOP-04 have been entered. The MSIV for RC-2A could not be closed. A plant cooldown is being performed using both steam generators.

The EAGLE output is attached.

The meteorological indications are as follows:

Indicated 10m wind speed - 12 mph, 14 mph

Indicated wind direction - 120°, 128°

Indicated ?T is -1.8°C/100m, -1.6°C/100m

It is raining, 0.4 inches daily total You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.

Complete page 1 of form FC-1188.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refer to Emergency Plan Refer to EPIP-OSC-1 2

Classify the event The event should be classified as a Site Area Emergency per EAL 2.7 (Primary to Secondary Leakage >

40 gpm with an ongoing release) on form FC-1188 3

Determine Protective Action Recommendations Refer to EPIP-EOF-7 and determine that there are no PARs for this situation. Document on form FC-1188

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO 2004-5 JPM

Title:

Emergency Plan Classification and PARs Page 4 of 5 STEP ELEMENT STANDARD 4

Document other items on form FC-1188

Wind from - 120° - 128°

Wind Speed - 12 mph

Precipitation - yes

Stability class - C

There is an airborne radioactive release

Prognosis is unstable

Plant is shutdown Termination Criteria:

Event has been classified and PARs determined

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO-2004-5 Page 5 of 5 INITIATING CUE:

A 800 gpm steam generator tube rupture has occurred in RC-2A. EOP-00 and EOP-04 have been entered. The MSIV for RC-2A could not be closed. A plant cooldown is being performed using both steam generators.

The EAGLE output is attached.

The meteorological indications are as follows:

Indicated 10m wind speed - 12 mph, 14 mph

Indicated wind direction - 120°, 128°

Indicated ?T is -1.8°C/100m, -1.6°C/100m

It is raining, 0.4 inches daily total You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.

Complete page 1 of form FC-1188.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 JPM

Title:

Simultaneous Hot and Cold Leg Injection Page 1 of 6 Location:

Simulator Control Room Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

EOP/AOP Attachment 9 EOP/AOP Attachment 10 K/A 006000 A4.05 (3.9/3.8)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 JPM

Title:

Simultaneous Hot and Cold Leg Injection Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Use JPM set#1 which has HCV-238 failed open This is an alternate path JPM.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 JPM

Title:

Simultaneous Hot and Cold Leg Injection Page 3 of 6 INITIATING CUE:

A LOCA occurred 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. Containment Spray is operating per TSC recommendation. All three HPSI pumps are operating.

The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Do Not provide Attachment 10 to candidate until he makes the transition prior to step 4.

1 Enter EOP/AOP Attachment 9 entered 2

Open at least one of the Charging Pumps HPSI Header Isolation Valves:

HCV-308

HCV-2988 CB-1,2,3 At least one valves control switch to OPEN with RED light lit.

3 Ensure HCV-238 and HCV-239 are closed CB-1,2,3 Determines that HCV-238 will not close. Goes to EOP/AOP 0.

4 Ensure both Charging Isolation valves are open.

HCV-247

HCV-248 CB-1,2,3 RED lights lit GREEN lights off

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 JPM

Title:

Simultaneous Hot and Cold Leg Injection Page 4 of 6 STEP ELEMENT STANDARD 5

Ensure HCV-238 and HCV-239 are closed CB-1,2,3 Control switch to CLOSE GREEN lights lit RED lights off Determines that HCV-238 will not close.

6 Close both Charging Isolation valves:

HCV-247

HCV-248 CB-1,2,3 Control switch to CLOSE GREEN lights lit RED lights off 7

Open at least one of the PZR Auxiliary Spray Isolation Valves

HCV-240

HCV-249 CB-1,2,3 At least one valves control switch to OPEN with RED light lit.

8 Close all of the following HPSI Loop Injection Valves:

HCV-315

HCV-318

HCV-312

HCV-321 AI-30A/B Control Switches to CLOSE (pull out, counter-clockwise) until GREEN lights lit.

9 Close HCV-2987 HPSI Header Isolation Valve AI-30A/B Control Switch to CLOSE GREEN light lit RED light off

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 JPM

Title:

Simultaneous Hot and Cold Leg Injection Page 5 of 6 STEP ELEMENT STANDARD 10 Throttle HPSI Loop Injection Valves until all of the following criteria are satisfied:

Charging flow greater than 140 gpm on FIA-236

Total HPSI flow greater than 140 gpm AI-30A/B Throttle one or more of the following valves:

HCV-314

HCV-317

HCV-311

HCV-311 Greater than 140 gpm total flow on FI-313, FI-316, FI-319 and FI-322 CB-1,2,3 Greater than 140 gpm flow on FIA-236 Note: Plant computer may also be used to verify flows Termination Criteria:

Simultaneous Hot and Cold Leg Injection Established with greater than 140 gpm flow through charging (Hot Leg) and greater than 140 gpm flow through HPSI Header (Cold Legs).

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: jpm-1135 Page 6 of 6 INITIATING CUE:

A LOCA occurred 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. Containment Spray is operating per TSC recommendation. All three HPSI pumps are operating.

The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 1 of 8 Location:

Simulator Control Room Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

EOP/AOP Attachment 17 (R15)

K/A 064000 A4.07 (3.4/3.4)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 2 of 8 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Use JPM setup # 1

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 3 of 8 INITIATING CUE:

A reactor trip from 100% power and loss of offsite power has occurred. EOP-00 immediate actions have been carried out and plant conditions stabilized. DG #1 and DG#2 are running supplying power to busses 1A3 and 1A4. 161 KV is available.

You have been directed to restore offsite power to bus 1A3 using 161 KV per EOP/AOP Attachment 17 START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of EOP/AOP Attachment 17 with the initiating cue.

1 Verify NONE of the following Lockout Relays are tripped:

86/1A13

86/1A33

86/1A3-TFB AI-24 Lockout relays in RESET position (switch handle vertical)

OR CB-20 Verify lockout relay indicating lights lit 2

Ensure both of the following breakers are tripped:

1A13

1A33 CB-20 GREEN lights lit

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 4 of 8 STEP ELEMENT STANDARD 3

Ensure Transfer Switch 43/1A1-1A3 is in Manual CB-20 Switch in Manual position 4

Verify None of the following Lockout relays are tripped:

86A/OPLS

86B/OPLS Determines OPLS lockout relays are tripped AI-30A/B Relays in Trip position AMBER lights OFF 5

Place CHAN A TEST AND BYPASS SW TS-A/OPLS in BYPASS AI-30A Keyswitch in bypass position 6

Place CHAN B TEST AND BYPASS SW TS-B/OPLS in BYPASS AI-30B Keyswitch in bypass position 7

Place all of the following Condenser Evacuation Pump control switches in PULL-TO-LOCK:

FW-8A

FW-8B

FW-8C CB-10,11 All three Condenser Evacuation Pump control switches turned counter-clockwise and pulled out to the PULL-TO LOCK position 8

Reset BOTH of the following lockout relays:

86A/OPLS

86B/OPLS AI-30A 86A/OPLS Lockout relay reset Amber light ON AI-30B 86B/OPLS Lockout relay reset Amber light ON

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 5 of 8 STEP ELEMENT STANDARD CUE: PCMMINT shows 161 KV @ 162.3 volts 9

Ensure Lockout Relay 86/161 is RESET AI-22 Lockout relay in RESET position 10 Ensure all of the following lockout relays are reset:

861/T1A-4

86-2/TIA-4

861/T1A-3

86-2/TIA-3

86X/FT161 AI-25, AI-24, AI-46 Lockout relays in RESET position 11 Synchronize and close at least one of the following breakers:

Breaker 110

Breaker 111 CB-20 Place synch switch in synch position One or both control switches to CLOSE RED light lit 12 Check that T1A3 secondary voltage greater than or equal to 4160V CB-20 Verify voltage on meters 13 Verify TRANS T1A-3 Secondary Low Voltage alarm is clear CB-20, A17, A2 Annunciator window OFF

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 6 of 8 STEP ELEMENT STANDARD 14 Ensure all of the following lockout relays are reset:

86/1A33

86/1A13

86/1A3-TFB AI-24 Lockout relays in RESET position (switch handle vertical)

OR CB-20 Verify lockout relay indicating lights lit 15 Synchronize and close breaker 1A33 CB-20 Place synch switch in synch position Adjust D/G load as necessary Place control switch for breaker 1A33 in CLOSE position then release RED light lit CUE: Diesel Generator #1 load is 280 KW 15 Open Breaker 1AD1 CB-20 Breaker control switch to trip GREEN light lit CUE: Another Operator will shutdown the Diesel-Generator

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 JPM

Title:

Restoration of Offsite Electrical Power Page 7 of 8 Termination Criteria:

Bus 1A3 is power from 161 KV Offsite Power.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0026 Page 8 of 8 INITIATING CUE:

A reactor trip from 100% power and loss of offsite power has occurred. EOP-00 immediate actions have been carried out and plant conditions stabilized. DG #1 and DG#2 are running supplying power to busses 1A3 and 1A4. 161 KV is available.

You have been directed to restore offsite power to bus 1A3 using 161 KV per EOP/AOP Attachment 17 START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 JPM

Title:

Operate the Containment Hydrogen Analyzer Page 1 of 6 Location:

Simulator Control Room Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

EOP-AOP Attachment 16 (R15)

K/A 028000 A1.01 (3.4/3.8)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 JPM

Title:

Operate the Containment Hydrogen Analyzer Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM setup #1

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 JPM

Title:

Operate the Containment Hydrogen Analyzer Page 3 of 6 INITIATING CUE:

A LOCA has occurred and an analysis for hydrogen concentration is required. You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachments and sample the upper level of containment via HCV-820C and HCV-883C.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1

Open HCV-820C AI-65A/B Control switch to OPEN RED light lit 2

Open HCV-883C AI-65A/B Control switch to OPEN RED light lit 3

Place all of the following switches in Override:

HCV-820A/821A

HCV-883A/884A

HCV-820B/821B

HCV-883B/884B AI-43A/B Control switches to ORIDE RED lights lit 4

Place recorders, HR-81A/B in service AI-65A/B Turn recorders on 5

Ensure Range Selector switches are in 0-10%

AI-65A/B Selector switch in 0-10%

position

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 JPM

Title:

Operate the Containment Hydrogen Analyzer Page 4 of 6 STEP ELEMENT STANDARD 6

Place the Hydrogen Analyzer Power On Selector Switches to ANALYZE AI-65A/B Switches to ANALYZE position 7

Ensure the Function Selector Switches are in SAMPLE AI-65A/B Switches in SAMPLE position 8

Press REMOTE selector pushbuttons AI-65A/B Depress pushbuttons 9

Verify the following:

Containment H2 Sampling System Remote/Local Off Normal Annunciator in Alarm

0-10% Range Amber indicating light is ON

The Sample Indicating light is ON AI-65A/B Alarm Window Lit AMBER light lit Light is lit 10 Press Alarm Reset Push buttons AI-65A/B Depress push buttons CUE: 5 minutes have elapsed 11 Obtain hydrogen concentration reading AI-65A/B Report reading from meters

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 JPM

Title:

Operate the Containment Hydrogen Analyzer Page 5 of 6 Termination Criteria:

Containment hydrogen concentration has been determined

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0156 Page 6 of 6 INITIATING CUE:

A LOCA has occurred and an analysis for hydrogen concentration is required. You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachments and sample the upper level of containment via HCV-820C and HCV-883C.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 1 of 9 Location:

Simulator Control Room Approximate Time:

20 minutes Actual Time: _________________

Reference(s):

OP-ST-RPS-0008 K/A 012000 A4.01 (4.5/4.5)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 2 of 9 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM setup #2 Ensure D/G trip links closed

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 3 of 9 INITIATING CUE:

As a portion of the preparations for a Reactor Startup, you, the LO,are directed to verify the operation of the Reactor Protective System manual trip circuits by performing OP-ST-RPS-0008. All prerequisites and initial conditions are met.

Both D/Gs have been Barred over START:

Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of OP-ST-RPS-008 along with initiating cue.

1 Verify BW-20-TS and CW-20-TS switches are CLOSED.

AI-31B AND AI-31C Cue: Switches are CLOSED.

2 Display Y-3466 (Reactor Trip Digital Point) on ERF CRT.

ERF CRT Display DVD or GRA.

NORMAL 3

Ensure Reactor is Reset.

CB-4 Verify Reactor Trip Alarm is CLEAR 4

Push Manual Reactor Trip pushbutton on RPS.

AI-31B/C Push RED button.

5 Verify the following:

CEDM clutch power supply breakers CB-AB and CB-CD are open AI-57 Both breakers mid position

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 4 of 9 STEP ELEMENT STANDARD 6

Clutch power supplies are deenergized AI-3 RED trip light on for each power supply:

PS-1

PS-2

PS-3

PS-4 7

Turbine Trip circuits are actuated AI-31B/C K1, K2, K3 and K4 indicating lights are OFF 8

Diesel Generator Start Circuits are actuated:

D/G-1:

86A/D1 lockout relay tripped

86B/D1 lockout relay tripped

YI-6048B at idle speed D/G-2:

86A/D2 lockout relay tripped

86B/D2 lockout relay tripped

YI-6148B at idle speed AI-30A Relays tripped AMBER lights off Tachometer @ 500 RPM AI-30B Relays tripped AMBER lights off Tachometer @ 500 RPM 9

REACTOR TRIP annunciator in ALARM CB-4, A20, A-7 Alarm panel lit

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 5 of 9 STEP ELEMENT STANDARD 10 ERF Y3466 indicates tripped ERF terminal Y-3466 tripped 11 Sequence of Events Log has printed PC-22 (line printer)

CUE: Post trip review printed 12 RESET and CLOSE Breakers CB-AB and CB-CD.

AI-57 OPEN breaker and then CLOSE.

13 RESET Reactor Trip.

Depress Reactor Trip Reset Button on CB-4 14 Verify the following:

Clutch power supplies are energized.

Turbine trip reset.

Reactor Trip Alarm CLEARS.

Y-3466 RESETS On Panel AI-3 PS-1, 2, 3,& 4 trip lights OFF.

AI-31B (Behind Panel)

K1 & K3 lights lit AI-31C (Behind Panel)

K2 & K4 lights lit.

On Panel CB-4, Alarm A-20 A-7 Resets Y-3466 NORMAL on ERF CRT.

15 RESET:

86A/D1

86B/D1

86A/D2

86B/D2 On Panel AI-30 A/B:

Reset Lockouts AMBER lights lit.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 6 of 9 STEP ELEMENT STANDARD 16 Push Manual Reactor Trip on Main Control Board.

CB-4 Depress RED Trip Button.

17 Attempt to RESET the Reactor.

CB-4 Push Manual Reactor Trip Reset pushbutton. Verify system will NOT reset within

~ 30 seconds TRIP Annunciator does not clear CUE: Operator at AI-3 reports that the trip lamps on the clutch power supplies stayed on for approximately 30 seconds.

18 Reset Reactor Trip.

CB-4 Depress BLACK Reactor Trip Reset Pushbutton.

19 Push Manual Reactor Trip on Main Control Board.

CB-4 Depress RED Trip Button.

20 Verify the following:

M1, 2, 3 and 4 are deenergized.

AI-3 Voltage indicates ZERO for M1, 2, 3 and 4.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 7 of 9 STEP ELEMENT STANDARD 21 Clutch power supply PS 1, 2, 3 and 4 Trip Lights ON.

AI-3 One RED trip light ON for each clutch power supply:

PS-1

PS-2

PS-3

PS-4 22 Turbine Trip Circuit ACTUATED.

Behind AI-31B/C K1, K2, K3 and K4 indicating lights off 23 The Diesel Start Circuit ACTUATED:

86A/D1 Tripped

86B/D1 Tripped

86A/D2 Tripped

86A/D2 Tripped AI-30A/B Verify both diesels are at idle speed Lockout relays Tripped AMBER light out.

24 Reactor trip annunciator operated Reactor Trip Alarm on CB 4.

(A20, A7) 25 Y-3466 is Tripped.

ERF CRT Y-3466 TRIPPED.

26 Post Trip Review is printed.

PC-22 (line printer)

CUE: Post trip review printed 27 RESET the reactor.

CB-4 Push Reactor Trip Reset.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 JPM

Title:

Perform Manual Trip Check Page 8 of 9 STEP ELEMENT STANDARD 28 Verify the following:

On Panel AI-3:

Clutch power supplies are energized.

PS-1, 2,3 & 4 trip lights OFF.

Turbine trip reset.

AI-31B/C (Behind Panel)

K1, K2, K3 and K4 lights ON Reactor Trip Alarm Clears.

CB-4:

Alarm A-20, A-7 Resets.

Y-3466 Resets.

Alarm Point Y-3466 on the ERF CRT reset.

29 RESET:

86A/D1

86B/D1

86A/D2

86B/D2 AI-30A/B Reset Lockout relays AMBER lights lit.

CUE: Another Operator will shutdown the Diesel Generators Termination Criteria:

Reactor Trip circuits have been tested.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0654 Page 9 of 9 INITIATING CUE:

As a portion of the preparations for a Reactor Startup, you, the LO,are directed to verify the operation of the Reactor Protective System manual trip circuits by performing OP-ST-RPS-0008. All prerequisites and initial conditions are met.

Both D/Gs have been Barred over START:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 1 of 7 Location:

Simulator Control Room Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

OI-VA-1, Attachment 8 (rev 49)

K/A 029000 A2.03 (2.7/3.1)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 2 of 7 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM set 2 Alternate Path JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 3 of 7 INITIATING CUE:

The plant is in a refueling shutdown condition. A containment purge permit has been delivered to the Shift Manager by the C/RP group. Maximum purge flow is not to exceed 20,000 SCFM. The Shift Manager has signed the permit and authorized the release.

You, the LO, are to start up a containment purge using VA-24A and VA-32A per OI-VA-1, attachment 8.

Process monitors RM-050, RM-051, RM-052 (aligned to stack) and RM-062 are all operable, VA-3A is running and VA-40B is in service. This is a Step #3 Purge.

All prerequisites are met and OI-VA-1, attachment 8 is complete through step 5. You are to begin at step 6.

START.

Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Provide candidate with a copy of OI-VA-1, Attachment 8

1 Verify the following are closed:

HCV-749

HCV-750

HCV-753

HCV-754

HIC-751 AI-44 GREEN damper position lights lit 2

Ensure the following permissive key switches are in OPEN

HC-742-2C

HC-742-2D

HC-742-1C

HC-742-1D AI-44 Key switches in OPEN position

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 4 of 7 STEP ELEMENT STANDARD 3

Ensure the TOTAL display is selected on QQI-755 AI-60 TOTAL selected 4

Reset QQI-755 AI-60 Push RESET pushbutton 5

Turn on FR-755/6600/6601, Containment Purge Air Flow AI-60 Recorder FR-755 is ON and recording CUE: Recorder chart marking is complete 6

Place HC-745 to HAND AI-44 Switch placed in HAND position 7

Station an Operator to monitor RM-052 and/or RM-062 CUE: Operator has been stationed 8

Place the following valves in OPEN:

PCV-742C

PCV-742D

PCV-742A

PCV-742B

HIC-751 AI-44 Switches on OPEN RED lights lit CUE: Operator monitoring RM-052 and RM-062 reports no change in count rate

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 5 of 7 STEP ELEMENT STANDARD 9

Monitor for change in containment pressure AI-65A/B Cue: PR-785 and PR-786 show steady containment pressure 10 Throttle the following purge fan dampers:

HCV-753

HCV-749 AI-44 Rotate controllers to approximately 10% open 11 Start VA-24A and VA-32A AI-44 VA-24A control switch to start and RED light lit VA-32A control switch to start and RED light lit 12 Adjust following dampers as necessary to the desired flows:

HCV-753

HCV-749

HIC-751 AI-44 Adjust dampers, purge flow must remain below FC-212 maximum release rate.

Containment pressure should remain steady 13 Ensure FI-756 Purge Air DIL Flow is greater than equal to FC-212 Dilution flow value AI-44 Indicated flow greater than FC-212 value CUE: Operator reports that RM-052 and RM-062 indications are rising and approaching the high alarm setpoint

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 JPM

Title:

Start up the Containment Purge System Page 6 of 7 STEP ELEMENT STANDARD 14 Stop VA-32A and VA-24A AI-44 VA-24A control switch to stop and GREEN light lit VA-32A control switch to stop and GREEN light lit 15 Ensure the following dampers are closed:

HCV-753

HCV-754

HCV-749

HCV-750

HIC-751

PCV-742C

PCV-742D

PCV-742A

PCV-742B

FCV-6601B

FCV-6600B

HCV-6602

HCV-6603 AI-44 Control switches in CLOSE GREEN lights lit AI-60 SP-6601 @ zero SP-6601 @ zero Control switches in CLOSE GREEN lights lit Termination Criteria:

Purge has been terminated due to observed rising count rate on RM-052 and RM-062

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0704 Page 7 of 7 INITIATING CUE:

The plant is in a refueling shutdown condition. A containment purge permit has been delivered to the Shift Manager by the C/RP group. Maximum purge flow is not to exceed 20,000 SCFM. The Shift Manager has signed the permit and authorized the release.

You, the LO, are to start up a containment purge using VA-24A and VA-32A per OI-VA-1, attachment 8.

Process monitors RM-050, RM-051, RM-052 (aligned to stack) and RM-062 are all operable, VA-3A is running and VA-40B is in service. This is a Step #3 Purge.

All prerequisites are met and OI-VA-1, attachment 8 is complete through step 5. You are to begin at step 6.

START.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613M JPM

Title:

Shutdown a Reactor Coolant Pump Page 1 of 5 Location:

Simulator Control Room Approximate Time:

5 minutes Actual Time: _________________

Reference(s):

OI-RC-9, Attachment 2 (R49)

K/A 003000 A4.06 (2.9/2.9)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613M JPM

Title:

Shutdown a Reactor Coolant Pump Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM set #2 which has RC-3Ds 90% speed switch failed This is an Alternate Path JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613M JPM

Title:

Shutdown a Reactor Coolant Pump Page 3 of 5 INITIATING CUE:

The reactor is in Hot Shutdown and is being cooled down to go into refueling. The RCS T-cold is 505°F and lowering approximately 30°F per hour.

You, the LO, are directed to shutdown Reactor Coolant Pump RC-3D.

START Critical Steps shown in gray STEP ELEMENT STANDARD 1

Ensure the reactor is shutdown prior to stopping a RCP.

CB-4 Verify all trippable rods are inserted 2

Ensure Zero Power Mode Bypass switches are in Bypass AI-31 A/B/C/D Keys installed and AMBER lights lit 3

Stop Reactor Coolant Pump RC-3D CB-1,2,3 Control switch to AFTER-STOP position and release GREEN light lit 4

Ensure the Oil Lift Pump starts automatically as pump speed lowers.

CB-1,2,3 Determines pump did not start.

Manually starts lift oil pump by placing control switch in START position and verifying RED light on.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613M JPM

Title:

Shutdown a Reactor Coolant Pump Page 4 of 5 STEP ELEMENT STANDARD 5

Holds Lift Oil Pump control switch in the START position If the control switch is released, the lift pump will stop. It should then be returned to the START position.

The control switch should be held in the START position until the zero speed light comes on.

6 Ensure Reverse Rotation Annunciator is clear.

CB-1,2,3, A6 D-5 Annunciator is OFF 7

Confirm Zero Speed light is on CB-1,2,3 RC-3D GREEN light on 8

Confirm RCP tachometer indicates zero CUE: Local Operator reports RC-3D speed is zero rpm.

9 Stop oil lift pump.

CB-1,2,3 Control switch to AFTER-STOP GREEN light lit Termination Criteria:

Reactor Coolant Pump RC-3D is secured

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0613M Page 5 of 5 INITIATING CUE:

The reactor is in Hot Shutdown and is being cooled down to go into refueling. The RCS T-cold is 505°F and lowering approximately 30°F per hour.

You, the LO, are directed to shutdown Reactor Coolant Pump RC-3D.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M JPM

Title:

Raise RCS Pressure with a Steam Bubble in the Pressurizer Page 1 of 6 Location:

Simulator Control Room Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

OI-RC-7, attachment 2 (rev 9)

K/A 010000 A2.03 (4.1/4.2)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M JPM

Title:

Raise RCS Pressure with a Steam Bubble in the Pressurizer Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM setup 3 Alternate path JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M JPM

Title:

Raise RCS Pressure with a Steam Bubble in the Pressurizer Page 3 of 6 INITIATING CUE:

The plant is operating at 100% power when you, the LO, are directed to raise pressure to 2140 psia using manual controls. All prerequisites are met.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

When candidate identifies OI-RC-7, attachment 2 as the proper procedure, provide a copy to him 1

Verify PRC-103Y in MANUAL CB-1,2,3 Controller selected to MANUAL position 2

Ensure Spray Control Switches in AUTO CB-1,2,3 HC-103-1, HC-103-2 in AUTO 3

Ensure Proportional Heater Control in AUTO CB-1,2,3 HC-103-7 and HC-103-8 in AUTO RED lights lit 4

Energize Backup Heaters CB-1,2,3 Place any or all listed to ON with RED lights lit:

225 KW Backup Htrs, Bank 1, Group 1/2/3

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M JPM

Title:

Raise RCS Pressure with a Steam Bubble in the Pressurizer Page 4 of 6 STEP ELEMENT STANDARD

150 KW Backup Htrs, Bank 2, Group 4/5

150 KW Backup Htrs, Bank 3, Group 8/9

225 KW Backup Htrs, Bank 4, Group 10/11/12 5

Increase Proportional Heater Output CB-1,2,3 Move Manual Control lever for PRC-103Y to the left Pressure raised to 2140 psia When pressure raised to 2140 psia, CUE: You are directed to return RCS pressure to 2100 psia.

6 Place Backup Heater Control in Auto or ON CUE: Select AUTO CB1,2,3 Switches in AUTO GREEN and AMBER lights lit 7

Adjust Manual Control Lever to return RCS pressure to Normal Operating Pressure.

CB-1,2,3 PRC-103Y output adjusted to approximately 67%

When RCS pressure reaches 2120 psia, simulator operator will fail PCV-102-1 open 8

Respond to annunciator alarms CB-1,2,3/A4 A-2 and C-4 Refers to ARP CB-1,2,3/A4

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M JPM

Title:

Raise RCS Pressure with a Steam Bubble in the Pressurizer Page 5 of 6 STEP ELEMENT STANDARD 9

Closes block valves HCV-150 and HCV-151 one at a time.

Identifies that PCV-102-1 has opened and ensures that HCV-151 is closed.

CB-1,2,3 Control switch for HCV-151 to CLOSE GREEN light lit Termination Criteria:

Pressure is returning to 2100 psia and PORV PCV-102-1 is isolated by Block valve HCV-151

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0621M Page 6 of 6 INITIATING CUE:

The plant is operating at 100% power when you, the LO, are directed to raise pressure to 2140 psia using manual controls. All prerequisites are met.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 JPM

Title:

Realign Misaligned CEA Page 1 of 6 Location:

Simulator Control Room Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

AOP-02 (R2.1)

K/A 001000 A2.03 (3.5/4.2)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 JPM

Title:

Realign Misaligned CEA Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

JPM set 3 Alternate Path JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 JPM

Title:

Realign Misaligned CEA Page 3 of 6 INITIATING CUE:

The plant is operating at 50% power. During the performance of OP-ST-CEA-0003, CEA Partial Movement Check, a malfunction occurred which resulted in inserting CEA #41 to a position of 90 inches withdrawn. The other CEAs in the group are 110 inches withdrawn.

AOP-02 was entered and the malfunction has been repaired. The CEA has been misaligned for 25 minutes.

You have been directed to realign the CEA with its group using AOP-02,Section III Step 22. Another operator has been assigned to make any required changes in boron concentration.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide a copy of AOP-02 to the candidate with the initiating cue.

1 Determine group that misaligned CEA belongs to.

CEA #41 belongs to group 4 2

Place Rod Control Mode Selector Switch in Manual Individual Position CB-4 Mode Selector Switch in Manual Individual Position 3

Select the group containing the misaligned CEA using the Control Rod Group Selector Switch CB-4 Control Rod Group Selector Switch selected to Group 4

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 JPM

Title:

Realign Misaligned CEA Page 4 of 6 STEP ELEMENT STANDARD 4

Select the misaligned CEA using the Rod Selector Switch for the misaligned group.

CB-4 Group 4 Rod Selector Switch selected to CEA #41 5

Place the Rod Block Bypass Switch in Bypass CB-4 Switch in BYPASS position 6

Operate the Manual Rod Control Switch to move the selected CEA CB-4 Move the IN-OUT-HOLD to the OUT position is short increments (3 inches or less) 7 Monitor the CEA withdrawal CB-4 Verify CEA movement using both Primary (Dial) and Secondary (CRT) indications 8

Terminate CEA movement when the CEA has been realigned with its group.

CB-4 IN-OUT-HOLD switch released Simulator Operator will insert a malfunction that causes an uncontrolled CEA withdrawal.

9 Places the Mode Selector Switch in OFF Position CB-4 Mode Selector Switch in OFF Position

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 JPM

Title:

Realign Misaligned CEA Page 5 of 6 STEP ELEMENT STANDARD 10 Manually Trips the Reactor CB-4 Presses RED Manual Reactor Trip Pushbutton 11 Verifies Reactivity Control Safety Function is satisfied.

CB-4 Verifies:

Trippable CEAs inserted.

Reactor Power is lowering.

Negative startup rate.

Termination Criteria:

Reactor has been manually tripped and Reactivity Control Safety Function is satisfied.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0003 Page 6 of 6 INITIATING CUE:

The plant is operating at 50% power. During the performance of OP-ST-CEA-0003, CEA Partial Movement Check, a malfunction occurred which resulted in inserting CEA #41 to a position of 75 inches withdrawn. The other CEAs in the group are 95 inches withdrawn.

AOP-02 was entered and the malfunction has been repaired. The CEA has been misaligned for 25 minutes.

You have been directed to realign the CEA with its group using AOP-02,Section III Step 22. Another operator has been assigned to make any required changes in boron concentration.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0450 JPM

Title:

Emergency Start of the Diesel Fire Pump Page 1 of 5 Location:

Intake Structure Approximate Time:

5 minutes Actual Time: _________________

Reference(s):

OI-FP-1 Attachment 3 (R53)

K/A 086000 A4.01 (3.3/3.3)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0450 JPM

Title:

Emergency Start of the Diesel Fire Pump Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

Potential tripping hazards Do NOT operate any controls Comments:

Alternate path JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0450 JPM

Title:

Emergency Start of the Diesel Fire Pump Page 3 of 5 INITIATING CUE:

The electric fire pump is out of service. Transformer deluge has activated due to a fire but the diesel fire pump did not start automatically.

You are directed to perform an emergency manual start of the diesel fire pump.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of OI-FP-1 1

Ensure the following are on:

AI-183-CB1, Fire Pump FP-1B Batt 1 Switch

AI-183-CB2, Fire Pump FP-1B Batt 2 Switch AI-183 Battery 1 is ON Battery 2 is ON 2

Place HC/FP-1B-MS control switch to Manual 1 AI-183 Select Manual #1 3

Press HC/FP-1B-1, Crank 1 start button AI-183 Push Crank 1 pushbutton CUE: Engine did not turn over or start 4

Place HC/FP-1B-MS control switch to Manual 2 AI-183 Select Manual #2

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0450 JPM

Title:

Emergency Start of the Diesel Fire Pump Page 4 of 5 STEP ELEMENT STANDARD 5

Press HC/FP-1B-1, Crank 2 start button AI-183 Push Crank 2 pushbutton CUE: Engine turned over but did not start 6

Open FO-169, Fuel Oil Solenoid Valve South side of Engine Turn Knob clockwise to full in position 7

Open FP-161, Pressure control valve bypass valve South side of Engine Cooling water bypass valve to OPEN 8

Engage the starter using either of the two starter contactors North side of Engine Raise lever knob on either:

YS/FP-1B-1

YS/FP-1B-1 CUE: Engine has started and is running Release lever Termination Criteria:

Diesel Fire Pump has been started

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0450 Page 5 of 5 INITIATING CUE:

The electric fire pump is out of service. Transformer deluge has activated due to a fire but the diesel fire pump did not start automatically.

You are directed to perform an emergency manual start of the diesel fire pump.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 1 of 7 Location:

Switchgear Room, Turbine Building and Control Room Approximate Time:

20 minutes Actual Time: _________________

Reference(s):

EOP/AOP Attachment 6 (R15)

K/A 063000 A1.01 (2.5/3.3) This is identified as a risk significant operator action in the Fort Calhoun PRA. Therefore, the FCS importance factor is significantly higher than the values given in NUREG-1122.

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 2 of 7 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This is a Time Critical JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 3 of 7 INITIATING CUE:

The plant has tripped due to a station blackout event.

The CRS has directed you to Minimize DC Loads using EOP/AOP Attachment 6.

Steps 1 through 3 are Time Critical.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: provide copy of EOP/AOP to candidate.

EXAMINER NOTE START TIME ______________

1 Place BOTH of the following Breakers in OFF:

Computer 400 Cycle Cabinet

Emergency Lighting PNL Transfer Switch in OFF Switchgear Room DC Bus 2 EE-8G-CB12 to OFF EE-8G-CB8 to OFF 2

Place Emer Lighting PNL Transfer Switch in OFF Switchgear Room DC Bus 1 EE-8F-CB-11 to OFF 3

Place 125 VDC Panel DC-PNL-1, Breaker 15, in OFF Turbine Building West Wall Breaker #15 to OFF Time Completed __________

Elapsed time must be 15 minutes or less

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 4 of 7 STEP ELEMENT STANDARD Note: The remainder of this JPM is performed in the Control Room and is not time critical.

Inform candidate that the remainder of this JPM is not time critical.

CUE: The turbine has stopped rolling 4

Stop LO-4, DC Oil Pump CB-10,11 LO-4 Control Switch in Pull-Out, RED and GREEN lights OFF.

CUE: Two hours have elapsed 5

Ensure the following are closed:

Main Disconnect I1-1

Circuit #1 AI-53 Feed AI-42A Switches in ON position 6

Place ALL of the following breakers in OFF:

Circuit #2 AI-56 Feed

Circuit #3 AI-100 Feed

Circuit #4 IB -1A Feed

Circuit #5 CB-10,11 Feed

Circuit #7 CB-1,2,3 Feed

Circuit #8 AI-195 Feed

Circuit #9 AI-44 Feed

Circuit #10 AI-58 & AI-59 Feed

Circuit #11 CB-20 Feed AI-42A Breakers in OFF

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 5 of 7 STEP ELEMENT STANDARD

Circuit #12 AI-42 & AI-60 Feed

Circuit #13 CB-4 Feed

Circuit #18 AI-43A & AI-33C Feed 7

Ensure Both of the following breakers are closed:

Main Disconnect I2-1

Circuit #1 AI-53 Feed AI-42B Switches in ON position 8

Place all of the following breakers in OFF:

Circuit #2 AI-50 Feed

Circuit #3 AI-105 & AI-107 Feed

Circuit #4 AI-55 Feed

Circuit #5 AI-101B Feed

Circuit #6 IB -2A Feed

Circuit #7 CB-10,11 Feed

Circuit #8 Nuclear Emergency Feed

Circuit #9 CB-4 Feed

Circuit #10 Fire Emergency Feed

Circuit #11 AI-44 Feed

Circuit #12 AI-187 Feed

Circuit #13 CB-1,2,3 Feed

Circuit #14 AI-195 Feed

Circuit #15 RC Punp Vibr. Sys

Circuit #16 AI-43A & AI-65B Feed

Circuit #17 CB-20 Feed AI-42B All listed breakers in OFF

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 JPM

Title:

Minimizing DC Loads Page 6 of 7 STEP ELEMENT STANDARD 9

Stop LO-12B, DC Seal Oil Pump CB-10,11 LO-12B switch in Pull OUT, GREEN and RED lights OFF Termination Criteria:

DC Loads have been minimized

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0304 Page 7 of 7 INITIATING CUE:

The plant has tripped due to a station blackout event.

The CRS has directed you to Minimize DC Loads using EOP/AOP Attachment 6.

Steps 1 through 3 are Time Critical.

START

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW JPM

Title:

Establish RW Backup Cooling to SI Pumps Page 1 of 6 Location:

SI Pump Room 21 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

AOP-11 (R7)

K/A 076000 A4.04 (3.5/3.5)

JPM Prepared by:

Jerry Koske Date:

2/25/2004 JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW JPM

Title:

Establish RW Backup Cooling to SI Pumps Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

NONE Safety Considerations:

Requires RCA entry Comments:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW JPM

Title:

Establish RW Backup Cooling to SI Pumps Page 3 of 6 INITIATING CUE:

The reactor has been tripped from 100% power. A total loss of CCW has occurred and one train of Safety Injection and Containment Spray Pumps are operating.

You are directed to establish Raw Water backup cooling to SI-3A, SI-1A, SI-2A and SI-2C.

The Control Room has placed the SI Pump AC Valves SIAS Override Switches, HC-2809/11/14/15 and HC-2808/10/12/13, in OVRRD.

START Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide a copy of AOP-11, pages 30-36 to the candidate with the initiating cue.

Note: Keys located in AI-100 room. Some Operators may carry keys.

Establish RW flow to CS Pump SI-3A Room 21 1

Control room closes HCV-2813A/B CUE: Valves are closed 2

Unlock and release the hand jacks from:

HCV-2813C

HCV-2813D Remove locking device and back off valve operator wheel

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW JPM

Title:

Establish RW Backup Cooling to SI Pumps Page 4 of 6 STEP ELEMENT STANDARD 3

Locally open HCV-2813C/D by placing the following 3-way valves in OPEN

IA-HCV-2813C-TV

IA-HCV-2813D-TV Place 3-way instrument air supply valves in the OPEN position.

CUE: Air vents and valve moves to open position Establish RW flow to LPSI Pump SI-1A Room 21 4

Control Room closes HCV-2808A/B CUE: Valves are closed 5

Unlock and release the hand jacks from:

HCV-2808C

HCV-2808D Remove locking device and back off valve operator wheel 6

Locally open HCV-2808C/D by placing the following 3-way valves in OPEN

IA-HCV-2808C-TV

IA-HCV-2808D-TV Place 3-way instrument air supply valves in the OPEN position.

CUE: Air vents and valve moves to open position Establish RW flow to HPSI Pump SI-2A Room 21 7

Control Room closes HCV-2810A/B CUE: Valves are closed 8

Unlock and release the hand jacks from:

HCV-2810C

HCV-2810D Remove locking device and back off valve operator wheel

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW JPM

Title:

Establish RW Backup Cooling to SI Pumps Page 5 of 6 STEP ELEMENT STANDARD 9

Locally open HCV-2810C/D by placing the following 3-way valves in OPEN

IA-HCV-2810C-TV

IA-HCV-2810D-TV Place 3-way instrument air supply valves in the OPEN position.

CUE: Air vents and valve moves to open position Establish RW flow to HPSI Pump SI-2C Room 21 10 Control Room closes HCV-2812A/B CUE: Valves are closed 11 Unlock and release the hand jacks from:

HCV-2812C

HCV-2812D Remove locking device and back off valve operator wheel 12 Locally open HCV-2812C/D by placing the following 3-way valves in OPEN

IA-HCV-2812C-TV

IA-HCV-2812D-TV Place 3-way instrument air supply valves in the OPEN position.

CUE: Air vents and valve moves to open position Termination Criteria:

Raw Water backup cooling is being supplied to the HPSI, LPSI and CS Pumps located in room 21

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0010RW Page 6 of 6 INITIATING CUE:

The reactor has been tripped from 100% power. A total loss of CCW has occurred and one train of Safety Injection and Containment Spray Pumps are operating.

You are directed to establish Raw Water backup cooling to SI-3A, SI-1A, SI-2A and SI-2C.

The Control Room has placed the SI Pump AC Valves SIAS Override Switches, HC-2809/11/14/15 and HC-2808/10/12/13, in OVRRD.

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ML041130156

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