ML052270331

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NRC - Proposed Jpms for the Palisades Initial Examination - May 2005
ML052270331
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/23/2005
From: Palagi B
NRC/RGN-III/DRS/OLB
To:
Nuclear Management Co
References
50-255/05-301 50-255/05-301
Download: ML052270331 (95)


Text

PROPOSE NRC DEVELOPED JPMs Administrative Job Performance Measure Conduct of Operations Ability to Apply Technical Specifications and Determine Reportability Requirements for an Event TITLE: Determine All of the Applicable Tech. Specs that apply to a given plant occurrence during all applicable reporting requirements.

Evaluation Location: Simulator Control Room Plant Classroom X Projected Time: 30 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! The plant was initially operating at steady state 100% power.

! Both S/G Feedwater pumps tripped and No Operator Actions were taken.

! S/G water level then decreased to the point that the Auxiliary Feedwater Pumps started

! The P-8A Auxiliary Feedwater pump started but subsequently tripped due to unknown reasons

! P-8C AFW Pump is in service providing 165 gpm flow to each S/G.

Initiating Cue:

Determine all of the Technical Specification entry condition(s) that apply due to the initial set of conditions and determine any applicable reportability requirement(s) to regulatory agencies.

EVALUATION CHECKLIST Task Standard:

The applicant will identify the correct Technical Specifications ( 3.7.5 Cond. A ) that must be entered for the given set of conditions and determine that the automatic start of the Auxiliary Feedwater System is reportable per 50.72(b)(3)(iv)(A) or 50.72(b)(3)(iv)(B)(6). The applicant must also realize that the Reactor tripped on Low S/G Level and that the Reactor Trip is reportable per 50.72(b)(2)(iv)(B) or 50.72(b)(3)(iv)(B)(1).

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Determine that Tech Spec Determine that Tech Spec S/U 3.7.5 applies, specifically 3.7.5 Cond A applies for the Cond. A for the failure of failure of P-8A, Aux.

P-8A, Aux. Feedwater Pump Feedwater Pump

  • 2) Determine that the Determine that the automatic S/U automatic Aux. Feedwater Aux. Feedwater pump start is pump start is from a valid from a valid signal and that signal and that this is this is reportable per reportable per 50.72(b)(3)(iv)(A) or 50.72(b)(3)(iv)(A) or 50.72(b)(3)(iv)(B)(6) and 50.72(b)(3)(iv)(B)(6) and requires an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report.

requires an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report.

  • 3) Determine that the Determine that the Reactor S/U Reactor tripped on low S/G tripped on low S/G level and level and that this is that this is reportable per reportable per 50.72(b)(2)(iv)(B) and is an 4 50.72(b)(2)(iv)(B) and is an hour report.

4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report.

4) Determine that the Rx Determine that the Rx Trip and S/U Trip and Aux. Feedwater Aux. Feedwater Actuation is Actuation is reportable in a reportable in a LER within 60 LER within 60 days per days per 50.73(a)(2)(iv)(A) or 50.73(a)(2)(iv)(A) or 50.73(a)(2)(iv)(B)(1) & (6) 50.73(a)(2)(iv)(B)(1) & (6)

STOP TIME:

Terminate JPM when applicant indicates that he has completed the task CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * )

before the element number. All Elements of this JPM are Critical.

GENERAL

REFERENCES:

6. Technical Specification 3.7.5 Auxiliary Feedwater System
7. Operations Reportability Binder GENERAL TOOLS AND EQUIPMENT:

None COMMENTS:

Initial Conditions The following plant conditions exist:

! The plant was initially operating at steady state 100% power.

! Both S/G Feedwater pumps tripped and No Operator Actions were taken.

! S/G water level then decreased to the point that the Auxiliary Feedwater Pumps started

! The P-8A Auxiliary Feedwater pump started but subsequently tripped due to unknown reasons

! P-8C AFW Pump is in service providing 165 gpm flow to each S/G.

Initiating Cue:

Determine all of the Technical Specification entry condition(s) that apply due to the initial set of conditions and determine any applicable reportability requirement(s) to regulatory agencies.

Administrative Job Performance Measure Conduct of Operations Ability to Locate and Use Procedures and Directives Related to Shift Staffing and Activities TITLE: Determine the Shift Staffing Requirements following an illness.

Evaluation Location: Simulator Control Room Plant Classroom X Projected Time: 15 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! The plant is operating at steady state 100% power.

! It is night shift on Christmas Day.

! The Operations Manager has authorized maximizing time off during Christmas Eve and Christmas Day.

! ONLY the SE / STA is qualified as STA.

! The shift complement at the beginning of the night shift (0000) was:

Shift Manager Control Room Supervisor Shift Engineer/Shift Technical Advisor Reactor Operators - 2 Auxiliary Operators- 4 Radiation Safety Technician - 1 ( EMT )

Required number of Security personnel

! At 0300 the Shift Technical Advisor is taken to the hospital by the Radiation Safety Technician due to an allergic reaction to something he has eaten.

Initiating Cue:

You are the Shift Manager. You need to determine if staffing requirements are met?

Explain your decision and required actions, if any.

EVALUATION CHECKLIST Task Standard:

The applicant will determine that the applicable Plant Staffing Levels are not met due to the illness of the Shift Technical Advisor (STA) and the fact that the only Radiation Safety Technician is no longer onsite. These conditions require that another active STA qualified individual replace the ill Shift Technical Advisor within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and another Radiation Safety Technician must arrive onsite within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as well.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Determine that Determine that Tech Spec S/U Tech Spec and Admin manning is NOT met staffing is NOT met
  • 2) Explain the Required to have one STA S/U minimum manning qualified individual on required shift per Tech Specs.

Another STA qualified individual must be onsite within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Since the only Radiation Safety Technician took the SE/STA to the hospital the minimum staffing requirement of 1 Radiation Safety Technician is not met and another Radiation Safety Technician must arrive onsite within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

STOP TIME:

Terminate JPM when applicant indicates that he has completed the task

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number. All Elements of this JPM are Critical.

GENERAL

REFERENCES:

2. Palisades Administrative Procedure 4.00, Operations Organization, Responsibilities and Conduct
3. 10 CFR Part 50.54
3. Technical Specifications GENERAL TOOLS AND EQUIPMENT:

None COMMENTS:

Initial Conditions The following plant conditions exist:

! The plant is operating at steady state 100% power.

! It is night shift on Christmas Day

! The Operations Manager has authorized maximizing time off during Christmas Eve and Christmas Day

! ONLY the SE/STA is qualified as STA

! The shift complement at the beginning of the night shift (0000) was:

Shift Manager Control Room Supervisor Shift Engineer/Shift Technical Advisor Reactor Operators - 2 Auxiliary Operators- 4 Radiation Safety Technician - 1 ( EMT )

Required number of Security personnel

! At 0300 the Shift Engineer/Shift Technical Advisor is taken to the hospital by the Radiation Safety Technician due to an allergic reaction to something he has eaten.

Initiating Cue:

You are the Shift Manager. You need to determine if staffing requirements are met?

Explain your decision and required actions, if any.

Administrative Job Performance Measure Equipment Control Knowledge of Tagging and Clearance Procedures TITLE: Determine the Mechanical and Electrical isolations points that must be tagged when removing the HP Safety Injection Pump P-66A from service.

Evaluation Location: Simulator Control Room Plant Classroom X Projected Time: 30 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The High Pressure Safety Injection Pump P-66A is required to be taken Out of Service for replacement of its mechanical seal. Computer based tagging is down and a paper-based tagging order has been prepared.

Initiating Cue:

You are to review a paper-based tagging order for the High Pressure Safety Injection Pump, P-66A, to verify sequence, components, and positions are correct and make changes if required. After completion of your review, sign for Approved By and return it for Review.

EVALUATION CHECKLIST Task Standard:

Identify the mistakes made on the Paper-Based Tagging for the High Pressure Safety Injection Pump P-66A. The applicant will determine that the pumps suction valve should not be closed before the pumps discharge valve. The applicant will determine that the pump casing vent valve needs to be open. Finally, the applicant will determine that the CC outlet isolation must also be added to perform work on the pumps mechanical seal.

TASKS: STANDARDS: RESULTS:

Start Time:

Cue: If asked, hand the applicant a blank copy of a tagging form from the procedure so that they can make corrections.

  • 1) Determine that the pump Determine that the pump S/U Suction Vlv should be closed Suction Vlv should be closed after the Discharge Vlv after the Discharge Vlv
  • 2) Determine that the pump Determine that the pump S/U casing vent MV-ES3287 casing vent MV-ES3287 needs to be opened instead of needs to be opened.

closed as listed.

  • 3) Determine that the CC Determine that the CC outlet S/U outlet isolation needs to be isolation needs to be Closed to Closed to the pumps the pumps Mechanical Seal Mechanical Seal CC-157 or CC-157 or CC-199 CC-199 STOP TIME:

Terminate JPM when applicant indicates that he has completed the task CRITICAL ELEMENTS:

Critical Elements are denoted with an asterisk ( * ) before the element number. All Elements of this JPM are Critical.

GENERAL

REFERENCES:

1. Palisades Administrative Procedure 4.10, Personnel Portective Tagging
2. Palisades P&ID drawings
3. Palisades Electrical drawings GENERAL TOOLS AND EQUIPMENT:

None COMMENTS:

Initial Conditions The High Pressure Safety Injection Pump P-66A is required to be taken Out of Service for replacement of its mechanical seal. Computer based tagging is down and a paper-based tagging order has been prepared.

Initiating Cue:

You are to review a paper-based tagging order for the High Pressure Safety Injection Pump, P-66A, to verify sequence, components, and positions are correct and make changes if required. After completion of your review, sign for Approved By and return it for Review.

Administrative Job Performance Measure Radiation Control Knowledge of 10CFR 20 and Related Facility Radiation Control Requirements TITLE: Determination of Radiological Dose Limits Will Be Exceeded Evaluation Location: Simulator Control Room Plant Classroom X Projected Time: 30 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The conditions under which this task is to be performed are as follows:

! A power reduction from 100% to 10% has been performed.

! The Shift Manager has directed you to determine if either Worker 1 or Worker 2 can perform a containment entry to inspect the D Primary Coolant Pump, P-50D, seal area for leakage.

! The transit route dose rate is < 2 mR/hr except as noted on the provided survey maps.

! Rad Protection has determined the lowest dose route is that which is marked on the survey maps.

! Rad Protection estimates that it will take 20 seconds each way to pass through the field of the Regenerative Heat Exchangers.

! Ops estimates that it will take 5 minutes at the PCP seal area for the inspection.

! Ops estimates that it will take 20 minutes inside Containment including the transit time and the inspection time.

! Worker 1 and Worker 2 have accumulated 1700 mR and 1680 mR respectively so far this year.

! A pre-job brief has already been performed Initiating Cue:

Your task is to determine if either Worker 1 or Worker 2 can perform this containment entry to inspect the P-50D PCP seal area, and to report the total accumulated dose each worker would have if they performed the inspection.

EVALUATION CHECKLIST Task Standard:

The applicant will determine that Worker 1 should receive 317.5 mR during this job which will result in him/she exceeding the allowable annual dose limit of 2000 mR. The applicant will also determine that Worker 2 will not exceed the annual dose limit imposed by the plant.

TASKS: STANDARDS:

RESULTS:

Start Time:

1) Calculate dose Calculate dose received S/U received passing to be 50 mR for each through Regen Hx time the Regen Hx is radiation field. passed for a total of 100 mR per worker (once (9000mR/hr)(1hr/3600s)(20s/trip)(2trips)=100 going to the PCP and mR once coming back from PCP after inspection).
2) Calculate dose Calculate dose received S/U received near P-50D to be 217 mR per PCP worker at PCP for the inspection.

(2600 mR/hr)(5 m)(1hr/60m) = 217 mR Calculate dose received S/U

3) Calculate dose to be < 0.5 mR per received for transit worker for transit time inside containment within cnmt.

(<2 mR/hr)(15 m)(1 hr/60m) = < 0.5 mR

4) Calculate total dose received by each worker Calculate total dose S/U during inspection received by each worker during inspection of 100mR + 217mR + 317.5mR 0.5mR = 317.5 mR
5) Calculate total dose each worker has Calculates accumulated S/U accumulated. dose received after Worker 1 317.5mR + 1700mR = inspection to be 2017.5mR 2017.5mR and Worker 2 317.5mR + 1680mR = 1997.5mR 1997.5mR
  • 6) Determine that the Determines Worker 1 S/U annual admin dose limit will exceed annual dose will be exceeded by limit if allowed to Worker 1 but not be perform inspection Worker 2 2017.5mR > 2000mR Cue: Is there any way possible for worker 1 to complete this task?
7) Informs the Shift Informs the Shift S/U Manager that the admin Manager that the admin dose limit would be dose limit would be exceeded by one of the exceeded by one of the workers but not by the workers but not by the other other. A dose extension will have to be obtained to allow Worker 1 to perform this task. No extension necessary for Worker 2.

STOP TIME:

Terminate JPM when Shift Manager has been informed of dose assessment.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the Element number.

GENERAL

REFERENCES:

1. Palisades Health Physics Procedure 11.1, Processing RWPs and ALARA Reviews
2. 10 CFR 20
3. Survey Map of path taken to P-50D GENERAL TOOLS AND EQUIPMENT:

None COMMENTS:

Initial Conditions The conditions under which this task is to be performed are as follows:

! A power reductions to 10% has been performed.

! The Shift Manager has directed you to determine if either Worker 1 or Worker 2 can perform a containment entry to inspect the D Primary Coolant Pump, P-50D, seal area for leakage.

! The transit route dose rate is < 2 mR/hr except as noted on the provided survey maps.

! Rad Protection has determined the lowest dose route is that which is marked on the survey maps.

! Rad Protection estimates that it will take 20 seconds each way to pass through the field of the Regenerative Heat Exchangers.

! Ops estimates that it will take 5 minutes at the PCP seal area for the inspection.

! Ops estimates that it will take 20 minutes inside Containment including the transit time and the inspection time.

! Worker 1 and Worker 2 have accumulated 1700 mR and 1680 mR respectively so far this year.

! A pre-job brief has already been performed Initiating Cue:

Your task is to determine if either Worker 1 or Worker 2 can perform this containment entry to inspect the P-50D PCP seal area, and to report the total accumulated dose each worker would have if they performed the inspection.

Administrative Job Performance Measure Emergency Plan Knowledge of Emergency Action Level Thresholds &

Classifications (THIS JPM WITHHELD FROM ADAMS PACKAGE FOR SECURITY REASONS)

Control Room Systems Job Performance Measure Reactivity Control TITLE: Initiate Emergency Manual Boration due to multiple stuck Control Rods Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 10 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! Reactor Tripped from 100% power.

! Emergency Operating Procedure EOP-1.0, Standard Post Trip Recovery procedure is in progress

! Five Control Rods did not fully insert into the core following the Rx Trip

! Bus 1D is not available due to a bus fault Initiating Cue:

The Control Room Supervisor has directed you to Emergency Borate per step 1.c.1 of EOP-1.0, Standard Post Trip Recovery procedure using SOP-2A, Chemical and Volume Control System procedure.

EVALUATION CHECKLIST Task Standard:

The applicant will establish Gravity Feed to the suction of the operating charging pumps per SOP-2A Attachment 14 Emergency Manual Boration.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP-2A, When applicant indicates where S/U Chemical and Volume Control to find current copy of System procedure procedure provide a copy of Attatchment 14 Emergency SOP-2A, Chemical and Volume Manual Boration. Control System procedure Attatchment 14 Emergency Manual Boration.
2) Step 1.0 Ensure charging Ensure charging flow is > 33 S/U flow is > 33 gpm. gpm
3) Step 2.a Determine that Determine that Bus 1D is not S/U Bus 1D is not available and available and that Boric Acid that Boric Acid Pumps are Pumps are unavailable unavailable
4) Step 2.b Determine that Determine that Bus 1C is S/U Bus 1C is Energized and that Energized and that Gravity Feed Gravity Feed can be can be established established
  • 5) Step 2.b.1 Open the Open the following Boric Acid S/U following Boric Acid Tank Tank Gravity Feed Isol Valves Gravity Feed Isol Valves MO-2169 MO-2169 MO-2170 MO-2170
  • 6) Step 2.b.2 Close the Boric Close the Boric Acid Blender S/U Acid Blender Outlet Control Outlet Control Valve CV-2155 Valve CV-2155
  • 7) Step 2.b.3 Close the VCT Close the VCT Outlet Isol S/U Outlet Isol Valve MO-2087 Valve MO-2087
8) Step 2.b.4 Verify Closed Verify Closed SIRW Tank to S/U SIRW Tank to Charging Charging Pump Isol Valve MO-Pump Isol Valve MO-2160 2160
9) Step 2.b.5 is not applicable Step 2.b.5 is not applicable S/U because Y01 is energized because Y01 is energized
10) Step 2.b.6 Verify Verify Charging Flow is > 33 S/U Charging Flow is > 33 gpm as gpm as indicated by FIA-0212, indicated by FIA-0212, Charging Line Flow Indicator Charging Line Flow Indicator Alarm Alarm

Cue: 45 minutes have elapsed and the CRS directs you to secure Emergency Boration per EOP Supplement 40, Charging Pump Suction Alignment"

11) Step 1.1 of EOP Open Charging Pumps Suction S/U Supplement 40 Open VCT Outlet Valve MO-2187 Charging Pumps Suction VCT Outlet Valve MO-2187
12) Step 1.2 is not applicable Step 1.2 is not applicable since S/U since neither Boric Acid neither Boric Acid Pumps are Pumps are running running
13) Step 1.3 Close the Boric Close the Boric Acid Pump S/U Acid Pump Feed Valve Feed Valve MO-2140 and MO-2140 and Gravity Feed Gravity Feed Valves MO-2169 Valves MO-2169 & MO-2170 & MO-2170
14) Step 1.4 Verify Closed Closed Charging Pumps Suction S/U Charging Pumps Suction from from SIRWT MO-2160 SIRWT MO-2160
15) Step 1.5 Operate each Operate each Charging Pump S/U Charging Pump for at least for at least five minutes start a five minutes start a non- non-running charging pump per running charging pump per SOP-2A, Chemical and Volume SOP-2A, Chemical and Control System procedure.

Volume Control System procedure.

Cue: When Applicant indicates that he needs to swap charging pumps state that Another Operator will complete that task and indicate the JPM is complete STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

14. SOP-2A, Chemical and Volume Control System procedure Attachment 14
15. SOP-2A, Chemical and Volume Control System procedure GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The following plant conditions exist:

! Reactor Tripped from 100% power.

! Emergency Operating Procedure EOP-1.0, Standard Post Trip Recovery procedure is in progress

! Five Control Rods did not fully insert into the core following the Rx Trip

! Bus 1D is not available due to a bus fault Initiating Cue:

The Control Room Supervisor has directed you to Emergency Borate per step 1.c.1 of EOP-1.0, Standard Post Trip Recovery procedure using SOP-2A, Chemical and Volume Control System procedure.

Control Room Systems Job Performance Measure Primary Coolant System Inventory Control TITLE: Establish the Containment Sump as the ECCS suction source following a Large Break Loss of Coolant Accident Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 20 Min.

Alternate Path X Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions

The following plant conditions exist:

! A Large Break Loss of Coolant Accident has occurred

! SIRWT level is at 3% and decreasing

! PRE-RAS Actions have been performed Initiating Cue:

The Control Room Supervisor has tasked you with performing the POST-RAS Actions associated with EOP Supplement 42 step 2.0.

EVALUATION CHECKLIST Task Standard:

The applicant will demonstrate the ability to obtain and use EOP Supplement 42, POST-RAS Actions to re-align the ECCS flow paths to the Containment Sump.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of When applicant indicates S/U EOP Supplement 42, where to find current copy POST-RAS Actions of procedure provide a copy EOP Supplement 42
  • 2) When SIRWT level Start Step 2 of EOP S/U lowers to < 2% perform Supplement 42, POST-step 2 of EOP RAS Actions when Supplement 42, POST- SIRWT is <2%

RAS Actions

  • 3) Step 1a Ensure Both LPSI P-67B must be S/U LPSI Pumps trip manually tripped. P-67A trips automatically
4) Step 1b Check Open CV-3030 does not auto S/U Both Containment OPEN but CV-3029 is Sump Isolation Valves Open CV-3030 CV-3029
  • 5) Step 1.b.1)a) Stop Stop the following S/U the following pumps: pumps:

P-66B HPSI Pp P-66B HPSI Pp P-54B CS Pp P-54B CS Pp P-54C CS Pp P-54C CS Pp

6) Step 1.b.1)b) Check CV-3001 closed S/U Closed Containment automatically Spray Valve CV-3001
7) Step 1c Ensure Both Both SIRWT Isolation S/U SIRWT Isolation Valves Close Valves Close: automatically CV-3031 CV-3031 CV-3057 CV-3057
8) Step 1d Ensure Both Both SI pump S/U SI pump Minimum Minimum Flow Stop Flow Stop Valves are Valves are Closed Closed CV-3027 CV-3027 CV-3056 CV-3056
9) Step 1e Ensure Both CV-0826 is Open S/U CCW Hx SW outlet CV-0823 is Open valves Open:

CV-0826 CV-0823

10) Step 1f Ensure Both Both CCW Hx TCVs S/U CCW Hx TCVs Closed:

Closed: CV-0822 CV-0822 CV-0821 CV-0821

11) Step 1g.1 Ensure at Check that CS Pp P- S/U least 1 CS pump 54A and HPSI Pp P-operating for each 66A are operating operating HPSI
12) Step 1g.2 Open Verify Open CV-3071 S/U HPSI Subcooling Valve HPSI Subcooling Valve for operating HPSI Pp for P-66A
13) Step 1.h If any No action required S/U HPSI pump is operating with HPSI subcooling valve closed, then stop pump
14) Step 1i.1 If only 1 Check that CS Pp P- S/U CS Pp is operating 54A and HPSI Pp P-Ensure only 1 HPSI Pp 66A are operating is operating
  • 15) Step 1i.2 Place Place HS-3001C to S/U HS-3001C to Bypass Bypass (key 397)

(key 397)

16) Ensure CV-3001 Ensure CV-3001 S/U Closed Closed
17) Inform CRS that Inform CRS that CV- S/U CV-3030 is closed and 3030 is closed ask if he would like it Opened Cue: Attempt to Open CV-3030
  • 18) Step 1j.1a Perform To Open CV-3030. S/U the following to Open Place HS-3001C in CV-3030. Place HS- Bypass (key 397).

3001C in Bypass (key 397).

19) Step 1j.1b Ensure Ensure HS-3001A in S/U HS-3001A in Closed Closed position.

position

  • 20) Step 1j.1c Place Place HS-3030A to S/U HS-3030A to Open Open position (key position (key 147) 147) Valve CV-3030 opens
21) Inform CRS that Inform CRS that CV- S/U CV-3030 is Open and 3030 is Open and ask if ask if he wants he wants additional CS additional CS or HPSI or HPSI pumps pumps running? running?

CUE: As CRS state that CV-3030 is Open but another NCO will start additional CS and HPSI pumps.

Terminate JPM when applicant indicates that he has informed the Control Room Supervisor of the fact that CV-3030 is open and asks if additional CS or HPSI pumps should be started.

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

8. Palisades Emergency Operating Procedure Supplement 42, Pre and Post RAS Actions GENERAL TOOLS AND EQUIPMENT:

None COMMENTS:

Initial Conditions The following plant conditions exist:

! A Large Break Loss of Coolant Accident has occurred

! SIRWT level is at 3% and decreasing

! PRE-RAS Actions have been performed Initiating Cue:

The Control Room Supervisor has tasked you with performing the POST-RAS Actions associated with EOP Supplement 42 step 2.0.

Control Room Systems Job Performance Measure Rx Pressure Control TITLE: Swap Pressurizer Pressure Control channels Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 10 Min.

Alternate Path X Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions

The following plant conditions exist:

! Steady state 100% power

! Pressurizer Pressure Controller PIC-0101B is selected and is in AUTO

! Pressurizer Pressure Controller PIC-0101A is in MANUAL at 50% demand Initiating Cue:

The Control Room Supervisor has asked you to switch Pressurizer Pressure Controllers per SOP-1A for normal rotation of controllers.

EVALUATION CHECKLIST Task Standard:

The applicant will demonstrate the ability to locate and obtain the appropriate copy of SOP-1A, Primary Coolant System procedure for switching Pressurizer Pressure Control Channels. The applicant will then use SOP-1A, Primary Coolant System procedure to switch Pressurizer Pressure Controlling Channels. During the evolution the applicant shall recognize the failure of PIC-0101A failing high by observing its output signal going off-scale high. The applicant will then switch PZR Pressure Channel back to PIC-0101B.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of When applicant indicates S/U SOP-1A, Primary where to find current copy Coolant System of procedure provide a procedure copy of SOP-1A, Primary Coolant System S/U
  • 2) Determine that Review Section 7.2.2 Pzr Section 7.2.2.3 of SOP- Press Control and 1A should be use to determine section 7.2.2.3 alternate Pzr Press needs to be performed Controllers
3) Step 3a Verify PIC- Verify PIC-0101A is in S/U 0101A is in MANUAL MANUAL
4) Step 3b Adjust Adjust output signal on S/U output signal on PIC- PIC-0101A to match 0101A to match output output signal on PIC-signal on PIC-0101B 0101B for bumpless transfer
  • 5) Step 3c Place Place selector switch S/U selector switch 1/PRC- 1/PRC-0101 to PIC-0101 to PIC-0101A 0101A CUE: If asked, state that AUTO CONTROL IS DESIRED
6) Step 3.d.1 Ensure Pzr Ensure Pzr Htr Control S/U Htr Control Channel Channel Selector Selector Switch in Switch in CHAN A & B CHAN A & B
  • 7) Step 3.d.2 Ensure Ensure PIC-0101A S/U PIC-0101A setpoint set setpoint set at desired at desired PCS pressure PCS pressure
  • 8) Step 3.d.3 Adjust Adjust PIC-0101A S/U PIC-0101A output to output to match match indicated Pzr indicated Pzr Press (red Press (red pointer) with pointer) with setpoint setpoint press. (Blue press. (Blue pointer) pointer)
  • 9) Step 3.d.4 Depress Depress the A S/U the A pushbutton on pushbutton on PIC-PIC-0101A to place it 0101A to place it in in AUTO AUTO
10) Step 3e Place PIC-0101B Place PIC-0101B in S/U in MANUAL with 50% MANUAL with 50% output output signal signal NOTE: When PIC-0101A is placed in AUTO control, after approx. 10 seconds, its output will slowly start to fail high ( to 100% output). This will cause Pzr Press to decrease (sprays open, heaters turn off).
  • 11) Applicant should Place PIC-0101A back to S/U recognize the failure by MANUAL and reduce observing the output of PIC- controller output to restore Pzr 0101A failing high. Pzr Press. Press to 2060 psig Off Normal Hi-Lo alarm will also alert Applicant of the problem
12) Inform CRS of the Inform CRS of the problem S/U problem with PIC-0101A and with PIC-0101A and recommend switching back to recommend switching back to PIC-0101B PIC-0101B Cue: Control Room Supervisor directs the Reactor Operator to restore PIC-0101B to Automatic control
13) Step 3a Verify PIC-0101B Verify PIC-0101B is in S/U is in MANUAL MANUAL
  • 14) Step 3b Adjust output Adjust output signal on S/U signal on PIC-0101B to PIC-0101B to desired desired output output Place selector switch
  • 15) Step 3c Place selector 1/PRC-0101 to PIC-0101B S/U switch 1/PRC-0101 to PIC-0101B CUE: IF ASKED STATE THAT AUTO CONTROL IS DESIRED

CUE: If asked Direct RO to place PZR Htr control channel selector switch in Channel B

16) Step 3.d.1 Ensure Pzr Ensure Pzr Htr Control S/U Htr Control Channel Selector Channel Selector Switch in Switch in CHAN B CHAN B
  • 17) Step 3.d.2 Ensure PIC- Ensure PIC-0101B setpoint S/U 0101B setpoint set at desired set at desired PCS pressure PCS pressure
  • 18) Step 3.d.3 Adjust PIC- Adjust PIC-0101B output to S/U 0101B output to match match indicated Pzr Press indicated Pzr Press (red (red pointer) with setpoint pointer) with setpoint press. press. (Blue pointer)

(Blue pointer)

  • 19) Step 3.d.4 Depress the Depress the A pushbutton S/U A pushbutton on PIC- on PIC-0101B to place it in 0101B to place it in AUTO AUTO Terminate JPM when applicant indicates that he has informed the Control Room Supervisor of the problem with PIC-0101A.

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( *)

before the element number.

GENERAL

REFERENCES:

7. Palisades System Operating Procedure SOP-1A, Primary Coolant System
2. Palisades Alarm Response Procedure ARP-4, Pressurizer Pressure Off Normal Hi-Lo GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Critical elements of this JPM were determined to be the selection of the correct procedure to accomplish the task and placing the PIC-0101A control back to MANUAL following the failure.

Initial Conditions The following plant conditions exist:

! Steady state 100% power

! Pressurizer Pressure Controller PIC-0101B is selected and is in AUTO

! Pressurizer Pressure Controller PIC-0101A is in MANUAL at 50% demand Initiating Cue:

The Control Room Supervisor has asked you to switch Pressurizer Pressure Controllers per SOP-1A due to normal rotation of the controllers.

Control Room Systems Job Performance Measure Heat Removal From Rx Core TITLE: Initiate Shutdown Cooling of the Primary Coolant System per SOP-3, Safety Injection and Shutdown Cooling System procedure.

Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 20 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! PCS Pressure is 270 psia.

! PCS Temperature is 290oF.

! Step 7.3.2 of SOP-3, Safety Injection and Shutdown Cooling System procedure is in progress with steps completed through 7.3.2.gg. P-67A has just been shutdown after running for 15 minutes.

! PCP P-50B & C are running to provide mixing flow.

Initiating Cue:

The Control Room Supervisor has asked you to take over SOP-3, Safety Injection and Shutdown Cooling System procedure at step 7.3.2.hh and commence cooling the PCS at a rate of 50oF/Hr. The CRS is obtaining the heat-up / cooldown rates for surveillance PO-2, PCS Heatup/Cooldown Operation. PCS temperature has been constant for the last 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

EVALUATION CHECKLIST Task Standard:

The applicant will demonstrate the ability to obtain and use SOP-3, Safety Injection and Shutdown Cooling System procedure to establish shutdown cooling system operation.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP-3, When applicant indicates S/U Safety Injection and where to find current copy Shutdown Cooling System of procedure provide a copy procedure of SOP-3, Safety Injection and Shutdown Cooling System procedure
  • 2) Start the P-67B LPSI Start the P-67B LPSI pump S/U pump per step 7.3.2.hh

CUE: When P-67B pump parameters have stabilized state that 15 minutes have elapsed

  • 3) 7.3.2.ii SLOWLY OPEN the remaining LPSI S/U OPEN the remaining LPSI injection valves to establish injection valves to establish the following:

the following: 1) Total LPSI flow of 3600-

1) Total LPSI flow of 3600- 4000gpm 4000gpm 2) Balanced flow between
2) Balanced flow between all four injection legs all four injection legs approx. 950 gpm approx. 950 gpm
  • 5) 7.3.2.kk SLOWLY OPEN CV-3025, SDC Hx S/U OPEN CV-3025, SDC Hx outlet to pressurize the SDC outlet to pressurize the SDC Hxs Hxs while observing the following:
1) PZR level
2) SDC Hx inlet pressure

& LPSI pump discharge pressure

  • 6) 7.3.2.ll CLOSE CV- CLOSE CV-3025 when S/U 3025 when PZR level PZR level stabilizes by stabilizes setting HIC-3025A to Manual at 0%
  • 7) 7.3.2.mm OPEN CV- OPEN CV-3055, SDC Hx S/U 3055, SDC Hx Inlet (key Inlet (key 102) 102)
  • 8) 7.3.2.nn OPERATE OPERATE CV-3006 as S/U CV-3006, SDC Hx Bypass follows:

Valve as follows: 1. CHECK FIC-0306 in

1. CHECK FIC-0306 in MANUAL with 0%

MANUAL with 0% output signal (full open) output signal (full open) 2. PLACE CV-3006

2. PLACE CV-3006 keyswitch to AUTO (key keyswitch to AUTO 94)

(key 94) 3. ADJUST FIC-0306 to

3. ADJUST FIC-0306 to establish a flow rate of establish a flow rate of 3400-3600 gpm.

3400-3600 gpm.

9) 7.3.2.oo REQUEST REQUEST Chemistry to S/U Chemistry to sample the sample the PCS for Boron PCS for Boron CUE: Chemistry will sample the PCS for boron concentration.
  • 10) 7.3.2.pp CLOSE CV- CLOSE CV-3031 (key 149) S/U 3031 (key 149) and CV- and CV-3057 (key 150) SI 3057 (key 150) SI Pump Pump Suction SIRWT Suction SIRWT Valves and Valves and PLACE Caution PLACE Caution Tags on Tags on keyswitches keyswitches
  • 11) 7.3.2.qq PLACE LPSI PLACE LPSI pump trip on S/U pump trip on Low Level in Low Level in SIRWT SIRWT handswitches to handswitches to DEFEAT DEFEAT P-67A key 154 P-67A key 154 P-67B key 155 P-67B key 155 CUE: This completes this JPM

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

8. Palisades System Operating Procedure SOP-3, Safety Injection and Shutdown Cooling System procedure GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The following plant conditions exist:

! PCS Pressure is 270 psia

! PCS Temperature is 290oF

! Step 7.3.2 of SOP-3, Safety Injection and Shutdown Cooling System procedure is in progress with steps completed through 7.3.2.gg. P-67A has just been shutdown after running for 15 minutes.

! PCP P-50B & C are running to provide mixing flow Initiating Cue:

The Control Room Supervisor has asked you to take over SOP-3, Safety Injection and Shutdown Cooling System procedure at step 7.3.2.hh and commence cooling the PCS at a rate of 50oF/Hr. The CRS is obtaining the heat-up / cooldown rates for surveillance PO-2, PCS Heatup/Cooldown Operation. PCS temperature has been constant for the last 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Control Room Systems Job Performance Measure Containment Integrity TITLE: Alignment of Containment Air Coolers following fan maintenance.

Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 15 Min.

Alternate Path X New X Modified RCA Low Power Emergency Bank Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! Steady State 100% power

! VHX-1 Cooling Fans V-1A and V-1B are Off with Service Water isolated.

! VHX-4 Cooling Fans V-4A and V-4B are Off with Service Water isolated.

! All Outlet Bypass Valves are properly aligned.

Initiating Cue:

The Control Room Supervisor has directed you to restore the Containment Air Cooling System to its normal alignment.

EVALUATION CHECKLIST Task Standard:

The applicant will demonstrate the ability to obtain a copy of SOP-5, Contaiment Air Cooling and Hydrogen Recombiner System procedure and use it to restore the Contaiment Air Cooling System to operation. The applicant will note low Service Water pressure and start a third Service Water Pump.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP-5, When applicant indicates S/U Contaiment Air Cooling and where to find current copy Hydrogen Recombiner of procedure provide a copy System procedure section of SOP-5, Contaiment Air 7.1.1. Cooling and Hydrogen Recombiner System section 7.1.1 CUE: If asked to start a third Service Water Pump state that If possible operate with two Service Water Pumps.

Note: Order of valve alignment is not critical nor is order of fan starts

2) For VHX-4 Verify Open S/U Verify Open High Capacity High Capacity Inlet Valve Inlet Valve CV-0869 CV-0869

Service Water Pump discharge pressure has been setup low and will decrease when high capacity valves are opened.

  • 3) For VHX-4 Open High Open High Capacity Outlet S/U Capacity Outlet Valve CV- Valve CV-0867 0867
4) For VHX-1 Verify Open Verify Open High Capacity S/U High Capacity Inlet Valve Outlet Valve CV-0862 CV-0862
  • 5) For VHX-1 Open High Open High Capacity Outlet S/U Capacity Outlet Valve CV- Valve CV-0861 0861

< 55 psig

7) Obtain SOP-15 Service Obtain SOP-15 Service Water S/U Water Pump procedure Pump procedure
8) Notify Chemistry to Notify Chemistry to S/U recalculate mixing basin recalculate mixing basin discharge flow volume. discharge flow volume.

CUE: CRS will notify Chemistry of P-7C start so they can recalculate mixing basin discharge flow volume.

  • 9) Dispatch AO to OPEN P- Dispatch AO to OPEN P-7C S/U 7C discharge valve MV- discharge valve MV-SW104 SW104 and Check P-7C and Check P-7C motor oil motor oil levels. levels.

CUE: MV-SW104 is Open and P-7C motor oil levels are normal.

10) REMOVE P-7C from REMOVE P-7C from standby S/U standby by placing Control by placing Control Switch to Switch to TRIP TRIP
  • 11) START P-7C to increase START P-7C to increase S/U Service Water Header Service Water Header Pressure. Pressure CUE: AO states that Local discharge pressure is 73 psig and packing leakoff is not excessive.
12) Verify Service Water Verify Service Water Header S/U Header Pressure increases to > Pressure increases to > 55psig 55psig
  • 13) For VHX-1 Start fan V- Start fan V-1A S/U 1A
  • 14) For VHX-1 Start fan V- Start fan V-1B S/U 1B
  • 15) For VHX-4 Start V-4A Start fan V-4A S/U
  • 16) For VHX-4 Start V-4B Start fan V-4B S/U STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

9. Palisades System Operating Procedure SOP-5, Containment Air Cooling and Hydrogen Recombiner procedure

GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The following plant conditions exist:

! Steady State 100% power

! VHX-1 Cooling Fans V-1A and V-1B are Off with Service Water isolated.

! VHX-4 Cooling Fans V-4A and V-4B are Off with Service Water isolated.

! All Outlet Bypass Valves are properly aligned.

Initiating Cue:

The Control Room Supervisor has directed you to restore the Containment Air Cooling System to its normal alignment.

Control Room Systems Job Performance Measure Electrical TITLE: Transfer Electrical Power Source from Startup Power to Safeguards/Station Power.

Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 10 Min.

Alternate Path New X Modified RCA Low Power Emergency Bank Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The plant is operating at 100% reactor power with all systems aligned for normal operation.

Initiating Cue:

The Control Room Supervisor has directed you to transfer the power supply for buses 1C, 1D, & 1E from Startup Power to Safeguards/Station Power.

EVALUATION CHECKLIST Task Standard:

The applicant will use SOP-30, Station Power procedure to transfer power supply for buses 1C, 1D, & 1E from Start-up Power to Safeguards/Station Power.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP- When applicant indicates S/U 30, Station Power procedure where to find current copy of procedure provide a copy of SOP-30, Station Power
2) Check Safeguards/Station Review Sections 7.2.3 & S/U Power supply Bkrs 152- 7.2.4 and check Bkr 401 & 152-402 aligned per alignments Section 7.2.3 or 7.2.4 CUE: Breaker 152-401 is Closed &

Breaker 152-402 is Open

3) Check bus 1C, 1D, & 1E Check bus 1C, 1D, & 1E S/U control power lamps LIT control power lamps LIT
4) Check Startup XFMR Check Startup XFMR UV UV aux. relays 127X-5 and aux. relays 127X-5 and S/U 127X-6 reset. 127X-6 reset.
5) Check Station Power Check Station Power XFMR 1-2 trouble lamp XFMR 1-2 trouble lamp S/U functional. functional
6) Check voltage on Check voltage on S/U Safeguards Bus Safeguards Bus approximately 2400 V approximately 2400 V
7) Direct AO to Check all Direct AO to Check all S/U relays cut in and targets relays cut in and targets reset on bus and feeder reset on bus and feeder breakers for: breakers for:

Bus 1C Bus 1C Bus 1D Bus 1D Bus 1E Bus 1E CUE: AO reports All relays cut in and targets reset on bus feeder Bkrs

  • 8) Scope and Close Scope and Close S/U Safeguards/Station Power Safeguards/Station Power Incoming Brk for Bus 1C Incoming Brk for Bus 1C 152-105 152-105
9) Verify Startup Power Verify Startup Power S/U Incoming BKR Opens on Incoming BKR Opens on Bus 1C 152-106 Bus 1C 152-106
10) Verify White Springs White Springs Charged S/U Charged lamp lit for 152- lamp lit for 152-105 105
  • 11) Scope and Close Scope and Close S/U Safeguards/Station Power Safeguards/Station Power Incoming Brk for Bus 1D Incoming Brk for Bus 1D 152-203 152-203
12) Verify Startup Power Verify Startup Power S/U Incoming BKR Opens on Incoming BKR Opens on Bus 1D 152-202 Bus 1D 152-202
13) Verify White Springs White Springs Charged S/U Charged lamp lit for 152-203 lamp lit for 152-203
  • 14) Scope and Close Scope and Close S/U Safeguards/Station Power Safeguards/Station Power Incoming Brk for Bus 1E Incoming Brk for Bus 1E 152-302 152-302
15) Verify Startup Power Startup Power Incoming BKR S/U Incoming BKR Opens on Opens on Bus 1E 152-303.

Bus 1E 152-303

16) Verify White Springs White Springs Charged lamp S/U Charged lamp lit for 152- lit for 152-302 302
17) When the buses have When the buses have been S/U been transferred Place transferred Place Startup Startup Power Incoming Power Incoming BKR control BKR control switches switches momentarily to Trip momentarily to Trip to to match targets match targets 1C 152-106 1C 152-106 1D 152-202 1D 152-202 1E 152-302 1E 152-302 STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

5. Palisades System Operating Procedure SOP-30, Statio Power procedure GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The plant is operating at 100% reactor power with all systems aligned for normal operation.

Initiating Cue:

The Control Room Supervisor has directed you to transfer the power supply for the 2400 V buses 1C, 1D, & 1E from Startup Power to Safeguards/Station Power.

Control Room Systems Job Performance Measure Plant Service Systems TITLE: Initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System procedure.

Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 20 Min.

Alternate Path X Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! The plant is in Mode 5 with the PCS vented to containment.

Initiating Cue:

The Control Room Supervisor has asked you to initiate a Containment Purge. The CRS has informed you that an AO has been briefed and is standing by awaiting your instructions.

The CRS also informs you that the RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.

EVALUATION CHECKLIST Task Standard:

The applicant will initiate a Containment Purge using SOP-24, Ventilation and Air Conditioning System procedure. After the Containment Purge is started the running main exhaust fan V-6A will trip and V-6B will not start. As a result the release previously started should be isolated. The applicant will have to recognize this and take manual actions to isolate the Containment Purge manually.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP- 6.14 are met. When applicant 24, Ventilation and Air indicates where Conditioning System to find current procedure. copy of procedure
2) Notify the RETS/REMP provide a copy of SOP-Cue: If asked to see the Batch Card inform Candidate that he doesnt need to see it but inform me of the start and stop times of the release so that it can be recorded. 24, Venti lation Supervisor or Duty HP to and Air ensure requirements of HP Conditioning 6.14, Containment Purge, System are met. procedure section 7.2.5.

Cue: The Duty HP indicates that the requirements of HP Notify the

RETS/REMP Supervisor or S/U Duty HP to ensure requirements of HP 6.14, Containment Purge, are met.

S/U

3) Ensure one Main Exhaust Ensure Main Exhaust Fan S/U Fan operating V-6A running
4) Ensure RGEM system is RGEM system is in S/U in operation per SOP-38, operation per SOP-38, Gaseous Process Gaseous Process Monitoring System. Monitoring System per initial conditions (from initiating cue)

Note: Applicant will call AO to verify the following valves are locked closed Cue: CRS indicates that these times have been logged.

5) Ensure the following CV-1807 (key 275)

Test Tap Valves are Locked CV-1808 (key 277)

Closed &Capped CV-1813 (key 273)

MV-VA506 CV-1814 (key 276)

MV-VA508 Ensure the MV-VA505 following Cue: AO Reports that MV-VA506, 508, & 505 are locked closed and capped

  • 6) INSERT key and 7) Record the time the Test Tap OPEN the following Purge valves were opened in the Valves are Supply and Exhaust Control Room Logbook Locked Valves: Closed &

Capped CV-1805 (key 272) MV-CV-1806 (key274) VA506

MV-VA508 MV-VA505 INSERT key and OPEN the following Purge Supply and Exhaust Valves:

CV-1805 (key 272)

CV-1806 (key274)

CV-1807 (key 275)

CV-1808 (key 277)

CV-1813 (key 273)

CV-1814 (key 276)

Record the time the valves were opened in the Control Room Logbook S/U S/U S/U

  • 8) Start Air Room Purge Supply Fan V-46

Note: After Purge Supply Fan is started, the V-6A main exhaust fan will trip and V-6B will not start which requires the cnmt purge to be manually terminated.

9) Exhaust Fan V-6A The Applicant refers to S/U trips. ARP-7, EK-1127, Main Exhaust Fan V-6A or B trip.
10) Per ARP-7, EK- V-6B will not auto or S/U 1127 directs starting manually start.

standby main exhaust fan V-6B

  • 11) Per ARP-7, Secure any radioactive S/U EK1127 secure any waste gas batch per SOP-radioactive waste gas 18A & shutdown any batch per SOP-18A & plant ventilation air flow shutdown any plant per SOP-24 .

ventilation air flow per SOP-24 .

12) Stop Air Room Stop Air Room Supply S/U Supply Fan V-46 Fan V-46
  • 13) Manually Manually CLOSE all S/U CLOSE all OPEN OPEN Purge CIVs Purge CIVs. The CV-1805 (key 272)

Applicant may use CV-1806 (key274)

EOP Supplement 6, CV-1807 (key 275)

Cnmt Isolation as a CV-1808 (key 277) guide CV-1813 (key 273)

CV-1805 (key 272) CV-1814 (key 276)

CV-1806 (key274)

CV-1807 (key 275)

CV-1808 (key 277)

CV-1813 (key 273)

CV-1814 (key 276)

Start Air Room Purge S/U Supply Fan V-46

Note: Candidate may start by securing other ventilation systems but stop JPM when Containment Purge is isolated.

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

2. Palisades System Operating Procedure SOP-24, Ventilation and Air Conditioning System.
2. Palisades Health Physics Procedure HP 6.14, Containment Purge.
3. Palisades System Operating Procedure SOP-38, Gaseous Process Monitoring System
4. Palisades Alarm and Response Procedure ARP-7, EK-1127 Main Exhaust Fan V-6A Trip GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The following plant conditions exist:

! The plant is in Mode 5 with the PCS vented to containment.

Initiating Cue:

The Control Room Supervisor has asked you to initiate a Containment Purge. The CRS has informed you that an AO has been briefed and is standing by awaiting your instructions. The CRS also informs you that the RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.

In-Plant Job Performance Measure Electrical TITLE: Isolate and Locally Start 1-1 Emergency Diesel Generator Evaluation Location: Simulator Control Room Plant X Classroom Projected Time: 30 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

Start-up Transformer 1-2 is not available Safeguards Transformer 1-1 is Not available Fire in the Control Room damages Bus 1C load shed circuits Fire in the Control Room damaged 1-1 D/G control circuits 1-1 D/G is Not Operating Initiating Cue:

Your task per the Control Room Supervisor and Step 5 of ONP-25.2, Alternate Safe Shutdown Procedure is to:

1. Locally Start the 1-1 D/G and energize 2400 VAC bus 1C per ONP-20 and,
2. Locally Close Breakers 152-103( Starting P-7B) and 152-108(Energizing LCC-13)

Contact the Control Room Supervisor prior to powering up any further equipment.

EVALUATION CHECKLIST Task Standard:

The applicant will start and load the P-7B, Service Water Pump and LCC-13 onto the 1-1 D/G after the D/G has been isolated from the Control Room and Locally started per Section 4.3.2.a of ONP-20, Diesel Generator Manual Control .

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of ONP- Obtain a copy of ONP-20, S/U 20, Diesel Generator Diesel Generator Manual Manual Control procedure. Control procedure. (in room between diesel generator rooms)
  • 2) Step 4.3.2.a.1 Trip all Applicant describes S/U breakers on Bus 1C tripping Bkrs electrically electrically or mechanically. by using handswitch or mechanically using the Cue: (Opened electrically) mechanical trip plunger The Green & if applicable, located bottom center of the White status lights are lit bkr inside the cubicle.

& red light is not lit.

(Opened mechanically)

Bkr status flag reads OPEN.

  • 3) Step 4.3.2.a.2 Remove Applicant describes how to S/U Closing Circuit and Close Remove Closing Circuit and Trip Circuit Fuses for and Close and Trip Circuit all Bkrs on Bus 1C Fuses for all Bkrs on Bus EXCEPT 152-103(P-7B), 1C EXCEPT 152-103(P-152-107(D/G 1-1), & 152- 7B), 152-107(D/G 1-1), &

108(Bus 13) 152-108(Bus 13)

Cue: The Bkrs fuse is removedAs each Bkr fuse is removed.

  • 4) Step 4.3.2.a.3 Obtain Applicant describes where S/U the Remote-Local-Transfer to Obtain the RLTS Switch (RLTS) Handles Handles. From cubicle 152-from cubicle 152- 102(Dilution Water Pp) 102(Dilution Water Pp)
5) Step 4.3.2.a.4 Review Att Review Att 2 for effects of S/U 2 for effects of placing D/G placing D/G 1-1 RLTS 1-1 RLTSs in LOCAL switches in LOCAL position. position.
  • 6) Step 4.3.2.a.5 Isolate Isolate D/G 1-1 control S/U D/G 1-1 control circuits by circuits by Placing HS-C22-Placing the RLTSs on D/G RLTS and HS-G20-RLTS Exciter Control Panel (HS- in LOCAL C22-RLTS) and D/G 1-1 Engine Gauge Panel (HS-G20-RLTS) in LOCAL Cue: HS-C22-RLTS and HS-G20-RLTS are in LOCAL S/U
  • 7) Step 4.3.2.a.6 Isolate Isolate Bkr Control Circuits Bkr Control Circuits by by Placing the following Placing the following RLTSs in LOCAL:

RLTSs in LOCAL: HS-152-107RLTS (D/G 1-1)

HS-152-107RLTS (D/G 1-1) HS-152-103RLTS (P-7B)

HS-152-103RLTS (P-7B) HS-152-108RLTS (Bus 13)

HS-152-108RLTS (Bus 13) Cue: HS-152-107RLTS HS-152-103RLTS &

HS-152-108RLTS are in Local

  • 8) Step 4.3.2.a.7 Refer to Remove the Close and Trip S/U Att 3 and Remove the Close Circuit fuses for the following and Trip Circuit fuses for the Bkrs:

following Bkrs: 152-107 D/G 1-1 152-107 D/G 1-1 152-103 P-7B 152-103 P-7B 152-108 Bus 13 152-108 Bus 13 Cue: Close and Trip Circuit fuse is removed for each Bkr

9) Step 4.3.2.a.8 Verify Bkr Verify Bkr status lights are lit S/U status lights are lit for: for:

152-107 D/G 1-1 152-107 D/G 1-1 152-103 P-7B 152-103 P-7B 152-108 Bus 13 152-108 Bus 13 Cue: Bkr status lights are lit for: 152-107 D/G 1-1 152-103 P-7B 152-108 Bus 13

  • 10) Step 4.3.2.a.9.a Start Start D/G 1-1 by Placing S/U D/G 1-1 by Placing Engine Engine Control Switch on Control Switch on Local Local Gauge Board to START Gauge Board to START Cue: Engine Control Switch is in Start and engine is running at 900 rpm, frequency is 60 Hz and voltage is 2.4 KV S/U
  • 11) Step 4.3.2.a.10 Applicant will describe Energize Bus 1C by Locally Closing D/G 1-1 Output Bkr Closing D/G 1-1 Output Bkr 152-107 Locally.

152-107.

Cue: Red and White Bkr status lights are lit and the Green Bkr status light is Out

  • 12) Step 4.3.2.a.11 Applicant will describe S/U Locally Close the Service Closing the Service Water Water Pumps Bkr Pump Bkr 152-103 152-103 P-7B Cue: Red and White Bkr status lights are lit and the Green Bkr status light is Out
  • 13) Step 4.3.2.a.11 Applicant will describe S/U Locally Close the Supply Closing the Supply Bkr to Bkr to Bus 13 152-108 Bus 13 152-108.

Cue: Red and White Bkr status lights are lit and the Green Bkr status light is Out

14) Step 4.3.2.a.12 Verify Verify Service Water Header S/U Service Water Header pressure is > 25 psig on PI-pressure is > 25 psig on PI- 1472 on D/G 1-1 Local 1472 on D/G 1-1 Local Control Panel Control Panel Cue: PI-1472 is reading 30 psig
15) Notify CRS the 1-1 Notify CRS the 1-1 D/G is S/U D/G is running and Service running and Service Water Water Pump P-7B and Bus Pump P-7B and Bus 13 are 13 are energized. energized.

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

2. Palisades Off Normal Procedure ONP-20, Diesel Generator Manual Control
2. Palisades Off Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure GENERAL TOOLS AND EQUIPMENT:

Electrical Safety should be utilized if manually closing Bkrs onto a live 2.4KV Bus COMMENTS:

Initial Conditions The following plant conditions exist:

! Start-up Transformer 1-2 is not available

! Safeguards Transformer 1-1 is Not available

! Fire in the Control Room damages Bus 1C load shed circuits

! Fire in the Control Room damaged 1-1 D/G control circuits

! 1-1 D/G is Not Operating Initiating Cue:

Your task per the Control Room Supervisor and Step 5 of ONP-25.2, Alternate Safe Shutdown Procedure is to:

1. Locally Start the 1-1 D/G and energize 2400 VAC bus 1C per ONP-20 and,
2. Locally Close Breakers 152-103( Starting P-7B) and 152-108(Energizing LCC-13)

Contact the Control Room Supervisor prior to powering up any further equipment.

In-Plant Job Performance Measure Plant Service Systems TITLE: Line-up Fire Protection Water to Aux. Feedwater Pumps P-8A and P-8B.

Evaluation Location: Simulator Control Room Plant X Classroom Projected Time: 10 Min.

Alternate Path New Modified RCA Low Power Emergency Bank X Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! Rx Trip has occurred

! Loss of All Feedwater has occurred

! Normal suction to Auxiliary Feedwater Pumps P-8A, P-8B, & P-8C is not available

! Condensate Storage Tank, T-2 is indicating 0% and the Condensate Storage Tank T-2 Hi-Lo Level alarm is in on low level

! No Aux. Feedwater pumps are in operation Initiating Cue:

Your task per the Control Room Supervisor and EOP-7, Loss of All Feedwater Recovery, is to align P-8A / P-8B suction to Fire Water per EOP Supplement 31, Section 2.0 starting at step 3 through step 10.

EVALUATION CHECKLIST Task Standard:

The applicant will align Fire Protection Water to the P-8A and P-8B Auxiliary Feedwater Pumps using EOP Supplement 31, Supply AFW Pumps From Alternate Sources.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of EOP Obtain a copy of EOP S/U Supplement 31, Supply Supplement 31, Supply AFW Pumps from Alternate AFW Pumps from Sources Alternate Sources
  • 2) Step 2.3 Place K-8 Place K-8 Cooling Water 3- S/U Cooling Water 3-Way Way Valve, MV-FW211 in Valve, MV-FW211 in EMERGENCY position EMERGENCY position (turn vlv handle fully (turn vlv handle fully clockwise) clockwise)

Cue: Vlv handle is in the fully clockwise position

3) Step 2.4 Verify Turbine Verify Turbine Building S/U Building Sump Pumps P- Sump Pumps P-45A and P-45A and P-45B are 45B are operating to operating to maintain maintain expected sump expected sump level level Cue: If asked 1E Bus is energized & sump level is normal
4) Step 2.5 Unlock MV- Unlock MV-FW775, AFW S/U FW775, AFW pumps pumps Supply from Fire Supply from Fire Protection Protection System System Cue: MV-FW775 is unlocked
5) Step 2.6 Throttle Open Throttle Open MV-FW775 S/U MV-FW775 until water until water issues from issues from AFW Pp Supply AFW Pp Supply from FPS from FPS Leak Test Valve Leak Test Valve MV-MV-FW504 FW504 Cue: Water is coming out of MV-FW504"
  • 6) Step 2.7 When water When water issues from S/U issues from MV-FW504 MV-FW504 CLOSE MV-CLOSE MV-FW504 FW504 Cue: MV-FW504 is closed
  • 7) Step 2.8 Open MV-FW775, AFW Pp Supply Open MV-FW775, AFW S/U from FPS Pp Supply from FPS Cue: MV-FW775 is Open
  • 8) Step 2.9 Unlock and Unlock and Open MV- S/U Open MV-FW774 AFW Pp FW774 AFW Pp Supply Supply from FPS from FPS Cue: MV-FW774 is Unlocked and Open
9) Step 2.10 Notify the CRS Notify the CRS that P-8A / S/U that P-8A / P-8B AFW Pps P-8B AFW Pps have Fire have Fire Protection System Protection System water water aligned to them aligned to them Cue: Repeat back the notification and state that the JPM is complete STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

11. Palisades Emergency Operating Procedure EOP-7, Loss of All Feedwater Recovery
2. Palisades Emergency Operating Procedure Supplement EOP-31, Supply AFW Pumps from Alternate Sources GENERAL TOOLS AND EQUIPMENT:
1. Locked Valve Key COMMENTS:

Initial Conditions The following plant conditions exist:

! Rx Trip has occurred

! Loss of All Feedwater has occurred

! Normal suction to Auxiliary Feedwater Pumps P-8A, P-8B, & P-8C is not available

! Condensate Storage Tank, T-2 is indicating 0% and the Condensate Storage Tank T-2 Hi-Lo Level alarm is in on low level

! No Aux. Feedwater pumps are in operation Initiating Cue:

Your task per the Control Room Supervisor and EOP-7, Loss of All Feedwater Recovery, is to align P-8A / P-8B suction to Fire Water per EOP Supplement 31, Section 2.0 starting at step 3 through step 10.

In-Plant Job Performance Measure Containment Integrity TITLE: M-69B Hydrogen Recombiner Start-up per SOP-5, Containment Air Cooling and Hydrogen Recombining System.

Evaluation Location: Simulator Control Room Plant X Classroom Projected Time: 10 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The following plant conditions exist:

! A LOCA is in progress

! Containment Pressure is 24 psia

! All Containment Air Coolers and fans are in service in Emergency Mode

! Pre-Accident Containment temperature was 90oF Initiating Cue:

The Control Room Supervisor is performing step 58 of EOP-4.0, Loss of Coolant Accident Recovery Procedure and he directs you to start the M-69B Hydrogen Recombiner per SOP-5, Containment Air Cooling and Hydrogen Recombining System. All initial conditions and Precautions and Limitations of SOP-5, Containment Air Cooling and Hydrogen Recombining System, are met.

EVALUATION CHECKLIST Task Standard:

The applicant will start and running the M-69B Hydrogen Recombiner per SOP-5, Containment Air Cooling and Hydrogen Recombining System.

TASKS: STANDARDS: RESULTS:

Start Time:

Cue: If asked, another operator will open MCC 9 Feeder Breaker 52-1304.

  • 1) Locate procedure SOP- Locate procedure SOP-5, S/U 5, Containment Air Cooling Containment Air Cooling and Hydrogen Recombining and Hydrogen Recombining System. System.
2) Step 7.2.1.a Ensure at Ensure at least one safety S/U least one safety related CAC related CAC fan is in fan is in service. service. All are in service per initial conditions.

Cue: If asked All CACs are in Emergency Mode

4) Step 7.2.1.c.1 Verify Verify Power Available S/U Power Available lamp lit lamp lit on Hydrogen Recombiner control panel Cue: Power Available C-123 light is lit
5) Step 7.2.1.c.2 Ensure Ensure Power Adjust knob S/U Power Adjust knob is set at is set at 000' 000' Cue: Power Adjust knob is set at 000'
  • 6) Step 7.2.1.c.3 Place Place Power Out Switch to S/U Power Out Switch to ON ON position position Cue: Power Out Switch is ON
7) Step 7.2.1.c.4 Verify Verify Power Out Switch S/U Power Out Switch Red light Red light lit.

lit.

Cue: Power Out Switch red light is lit

8) Step 7.2.1.c.5 Place Place Temp Channel S/U Temp Channel Selector Selector Switch to position Switch to position 1, 2, or 3. 1, 2, or 3.

Cue: Temp Channel Selector Switch is in position 1, 2, or 3"

9) Step 7.2.1.d If Applicant determines that S/U Recombiner is being started Recombiner is Not to be for testing ... started for testing per initiating cue.
10) Step 7.2.1.e.1 S/U Determine the following: From Initial Conditions:

Current Cnmt Pressure Cnmt Pressure is 24 psia Previous Cnmt Temp. Previous Cnmt temp 90oF

11) Step 7.2.1.e.2 Determine Applicant should determine S/U Recombiner Power setting power setting between 58 to using Att 1 of SOP-5 and 60 kw using 9 psig and 90oF parameters determined above for Cnmt Press & Cnmt Temp.
  • 12) 7.2.1.e.3.a Adjust Adjust Power Adjust knob in S/U Power Adjust knob in the the clockwise direction until clockwise direction until Recombiner power (as read on Recombiner power (as read the kw power out meter) is on the kw power out meter) bewteen 58 to 60 kw is between 58 to 60 kw Cue: Power Out meter is reading 59 kw
13) 7.2.1.e.3.b Commence Commence monitoring Power S/U monitoring Power Out meter Out meter on C-123 on C-123
14) Step 7.2.1.e.3.c Adjust Adjust Power Adjust knob to S/U Power Adjust knob to maintain desired setting maintain desired setting between 58 and 60 kw.

between 58 and 60 kw.

Notify CRS that M-69B is in S/U

15) Step 7.2.1.e.4 Notify service and that the CR should CRS that M-69B is in commence sampling Cnmt service and that the CR hydrogen per SOP-38, should commence sampling Gaseous Process Monitoring Cnmt hydrogen per SOP-38, System.

Gaseous Process Monitoring System.

Cue: Terminate JPM after the Applicant informs the CRS that the M-69B Hydrogen Recombiner is in service.

STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

10. Palisades Emergency Operating Procedure EOP-4, Loss of Coolant Accident Recovery
2. Palisades System Operating Procedure SOP-5, Containment Air Cooling and Hydrogen Recombining System GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The following plant conditions exist:

! A LOCA is in progress

! Containment Pressure is 24 psia

! All Containment Air Coolers and fans are in service in Emergency Mode

! Pre-Accident Containment temperature was 90oF Initiating Cue:

The Control Room Supervisor is performing step 58 of EOP-4.0, Loss of Coolant Accident Recovery Procedure and he directs you to start the M-69B Hydrogen Recombiner per SOP-5, Containment Air Cooling and Hydrogen Recombining System. All initial conditions and Precautions and Limitations of SOP-5, Containment Air Cooling and Hydrogen Recombining System, are met.

Control Room Systems Job Performance Measure Radioactivity Release TITLE: Set up Radwaste Discharge Monitor RIA-1049 High Alarm Stepoint.

Evaluation Location: Simulator X Control Room Plant Classroom Projected Time: 30 Min.

Alternate Path Time Critical Date: Trainee:

Evaluator:

JPM Performance: Satisfactory Unsatisfactory Evaluator Comments:

Initial Conditions The Initiating Cue:

Your task is to complete the release of Waste Gas Decay Tank T-101A.

EVALUATION CHECKLIST Task Standard:

The applicant will complete the release of Waste Gas Decay Tank, T-101A, in accordance with SOP-18A, Radioactive Waste System - Gaseous.

TASKS: STANDARDS: RESULTS:

Start Time:

  • 1) Obtain a copy of SOP- Obtain a copy of SOP-18A, S/U 18A, Radioactive Waste Radioactive Waste System -

System - Gaseous procedure Gaseous procedure from the from the NCO. NCO.

2) Step 7.5.l Ensure Closed Ensure Closed CV-1113, CV-1113, Waste Gas Surge Waste Gas Surge Tank S/U Tank Discharge (At C-40 Discharge panel using HS-1113 and position indicator lights).

Cue: CV-1113 is closed S/U

  • 3) Step 7.5.m Place in Place in OPEN HS-1123, OPEN HS-1123, WGDT WGDT Discharge Discharge.

Cue: HS-1123 is in Open

4) Step 7.5.n Reset CV- Reset CV-1123 WGDT S/U 1123 WGDT Discharge, Discharge, high-radiation high-radiation trip on Panel trip on Panel C-40. (Vlv C-40. indication will not change Cue: CV-1123 is Reset until it is opened in step 7.5.r)
5) Step 7.5.o Ensure RE- Ensure RE-1113 is valved S/U 1113 is valved in correctly in correctly by checking the by checking the following following valves in their valves in their Locked Locked position:

position:

MV-WG117 Open MV-WG117 Open MV-WG119 Open MV-WG119 Open MV-WG118 Closed MV-WG118 Closed MV-WG114 Open MV-WG114 Open (Inside Vent Plenum on Cue: MV-WG117 Open 590') (there should be a MV-WG119 Open locked valve program that MV-WG118 can be used to verify Closed positions)

MV-WG114 Open

  • 6) Step 7.5.p.1 Open MV- Open MV-WG726, Drain S/U WG726, Drain Trap DT- Trap DT-1123 equalizing 1123 equalizing valve valve Cue: MV-WG726 is Open
  • 7) Step 7.5.p.2 Close MV- Close MV-WG721, DT-WG721, DT-1123 Bypass 1123 Bypass Valve (C-50 S/U Valve Comp Rm)

Cue: MV-WG721 is Closed

  • 8) Step 7.5.p.3 Close MV- Close MV-WG735, N2 S/U WG735, N2 Purge Isolation Purge Isolation (C-50 Comp Rm)

Cue: MV-WG735 is Closed

  • 9) Step 7.5.q Open WGDT Open MV-CA367, T-101A S/U outlet valve for the tank to Outlet CV1160 A/S be released T-101A.

Open MV-CA367, T-101A Outlet CV1160 A/S Cue: MV-CA367 is Open

  • 10) Step 7.5.r Open CV- Open CV-1123, SGDT S/U 1123, SGDT Discharge, Discharge, using HIC-1123, using HIC-1123, Waste Gas Waste Gas Discharge To Discharge To Stack Stack Cue: CV-1123 is Open
11) Step 7.5.s.1 Record the Record the following on S/U following on HP 6.6-3 HP 6.6-3 Tank Pressure Tank Pressure Wind Speed Wind Speed Wind Direction Wind Direction Stability Class Stability Class Start Time Start Time Start Date Start Date
12) Step 7.5.s.2 Determine Determine initial DP on S/U initial DP on dPI-1817, F- dPI-1817, F-58 Decay Tank 58 Decay Tank Discharge Discharge Filter DP Filter DP indicator indicator Cue: dPI-1817 is reading 0.5" H 2O
  • 13) Step 7.5.t Slowly Slowly Open Discharge Hdr S/U Open Discharge Hdr Vlvs Vlvs for the T-101A tank for the T-101A tank:

MV-WG718 T-101A MV-WG718 T-101A outlet vlv outlet vlv MV-WG718A T-101A MV-WG718A T-101A outlet vlv outlet vlv Cue: MV-WG718 and MV-WG718A are open

14) Step 7.5.v Check dPI- Check dPI-1817, F-58 S/U 1817, F-58 Decay Tank Decay Tank Discharge Discharge Filter DP Filter DP indicator, < 2.5" indicator, < 2.5" H2O H2O Cue: dPI-1817 is reading 1.5" H 2O
15) Step 7.5.w Record Record RIA-1113 reading on S/U RIA-1113 reading on Form Form HP 6.6-3 HP 6.6-3
16) Step 7.5.x Tank S/U pressure indicates less than 3 psig Cue: 30 Mins have elapsed and tank pressure is 2 psig Record final tank pressure on S/U
17) Step 7.5.y Record final Form HP 6.6.3 tank pressure on Form HP 6.6.3
  • 18) Step 7.5.z Close the Close the following valve S/U following valve MV- MV-WG718A for T-101A WG718A for T-101A Cue: MV-WG718A is closed Terminate JPM when MV-WG718A is Closed STOP TIME:

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk ( * ) before the element number.

GENERAL

REFERENCES:

5. Palisades System Operating Procedure SOP-18A, Ventilation and Air Conditioning System.
2. Palisades Health Physics Procedure HP 6.14, Containment Purge.
3. Palisades Health Physics Form 6.6-3, Batch Releases GENERAL TOOLS AND EQUIPMENT:

COMMENTS:

Initial Conditions The T-101A, Waste Gas Decay Tank is to be released and the following plant conditions exist:

T-101A pressure is 85 psig Wind Speed is 12 mph Wind Direction is from 165o Stability Class B Radiation Monitor RE-1113 is operable Main Exhaust Fan V-6B is operating and no Containment Purge is in progress The NCO has just completed setting the RE-1113 Hi Alarm Setpoint per step 7.5.k of SOP-18A.

Initiating Cue:

Your task is to complete the release of Waste Gas Decay Tank T-101A.

CONSUMERS ENERGY PALISADES NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE Job Performance Measure: ASEE-02.JPM UFI No.: 06*26 Course No.: 601284 Approx. Time: 7.5 minutes Program

Title:

NUCLEAR OPERATOR TRAINING Course: Advanced Systems Module: N/A JPM

Title:

Respond to a Control Rods Out of Sequence Alarm Revision: 2 Prepared by Date Validated by Date Approved - Training Section Supervisor/Lead Individual Date DEVELOPMENT HISTORY Date Originator: RLTucker 2/22/98 Approval: RJFrigo 2/22/98 Revision: 1 Originator: RLTucker 10/13/89 Approval: RJFrigo 11/09/89 Revision: 0 PREVIOUSLY RO-097 asee02.jpm

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm TASK NUMBER: 014 001 01 01 IMPORTANCE RATING:

3.5 001 009 01 01 4.0 001 104 04 01 5.0 APPROX COMPLETION TIME: 7.5 minutes OPERATOR: ~ RO ~ SRO EVALUATOR:

EVALUATION METHOD: ~ Actual ~ Simulated EVALUATION LOCATION: Simulator DATE:

SIMULATOR SETUP: IC-6, insert rods in Manual Sequential until Group 3 is at 87", then insert Group 4 in manual group until Control Rods Out of Sequence alarm (EK-09-16) comes in (should be around 4.5"). Will also get Group 4 PPDIL alarm and PPC audible alarm acknowledged. Put group selector switch back to manual sequential. JPM is now ready to give.

1.0 DIRECTIONS Please read 1.1, 1.2 and 1.3. Repeat back same. If correct, then I will tell you to continue.

1.1 Task Standards Performance Time Limit = NONE 1.2 Task Conditions A. Reactor Startup was in progress using Control Rods in "Manual Sequential".

B. EK-09 Alarm 16 'Control Rods out of Sequence' alarm is in.

C. All rod motion is currently stopped.

1.3 INITIATING CUES A. During performance of a Reactor Startup using Control Rods, the Control Room Supervisor directs you to identify the cause of, and to take actions to clear the 'Control Rods Out of Sequence' alarm.

asee02.jpm Page 89 of 4

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm 2.0 PERFORMANCE CHECKLIST (Critical Elements designated by *)

Start Time:

1. Locate ARP 5 and SOP 6.

STANDARD: ARP 5 and SOP 6, Attachment 1 located. S/U

2. Stop all rod motion.

STANDARD: All rod motion stopped as part of IC. N/A

3. Check Primary Rod position on control board or syncho on PPC to identify cause of alarm.

STANDARD: Check rod positions on PPC page. S/U

  • 4. Check that 78.5" to 81.5" exists between groups being moved.

STANDARD: Identify that > 81.5" exists between Group 3 and 4. S/U

5. Turn Rod Selector Switch for Groups out of sequence through all positions and compare Primary & Secondary Rod position indications on PPC display 412.

STANDARD: Rod Selector Switch for groups out of sequence rotated S/U and PPC displays checked.

6. Compare indicated positions from Primary and Secondary.

STANDARD: Compare indicated positions using rod positions from S/U Primary and Secondary. Verify Primary and Secondary agree.

  • 7. Identify cause of out of sequence condition.

STANDARD: Operator identifies failure of PIP node sequencers as the S/U cause of the problem.

asee02.jpm Page 90 of 4

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm

[CUE: The Control Room Supervisor directs you to continue with SOP-6.]

[CUE: If asked Recommend inserting Group 3 in Manual.]

[Note: Based on ARP-5, candidate may use manual individual to re-align control rods or he/she may use manual group to re-align control rods per SOP-6.]

S3 *8. Return Rod Groups to their proper sequence to clear alarm.

STANDARD: Insert Group 3 in manual group to at least 84". S/U

9. Make necessary log entries.

STANDARD: Loss of sequencing logged. S/U

10. Notify CRS.

STANDARD: CRS notified. S/U Stop Time:

asee02.jpm Page 91 of 4

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm 2.1 OPERATOR PERFORMANCE

~ Satisfactory ~ Unsatisfactory JPM was performed in minutes.

COMMENTS 3.0 GENERAL REFERENCES SOP 6, rev 23 ARP 5 rev 66 asee02.jpm Page 92 of 4

1.0 DIRECTIONS Please read 1.1, 1.2 and 1.3. Repeat back same. If correct, then I will tell you to continue.

1.1 TASK STANDARDS Performance Time Limit = NONE

Task Conditions A. Reactor Startup was in progress using Control Rods in "Manual Sequential".

B. EK-09 Alarm 16 'Control Rods out of Sequence' alarm is in.

C. All rod motion is currently stopped.

INITIATING CUE During performance of a Reactor Startup using Control Rods, the Control Room Supervisor directs you to identify the cause of, and to take actions to clear the 'Control Rods Out of Sequence' alarm.