ML052270331

From kanterella
Jump to navigation Jump to search
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)
v • d • e


Text

PROPOSE NRC DEVELOPED JPMs

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:

Administrative Job Performance Measure Conduct of Operations Ability to Apply Technical Specifications and Determine Reportability Requirements for an Event

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:

  • 2) Determine that the automatic Aux. Feedwater pump start is from a valid signal and that this is reportable per 50.72(b)(3)(iv)(A) or 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.

Determine that Tech Spec 3.7.5 Cond A applies for the failure of P-8A, Aux.

Feedwater Pump Determine that the automatic Aux. Feedwater pump start is from a valid signal and that this is reportable per 50.72(b)(3)(iv)(A) or 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.

S / U S / U

Terminate JPM when applicant indicates that he has completed the task

  • 3) Determine that the Reactor tripped on low S/G level and that this is reportable per 50.72(b)(2)(iv)(B) and is an 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 Trip and Aux. Feedwater Actuation is reportable in a LER within 60 days per 50.73(a)(2)(iv)(A) or 50.73(a)(2)(iv)(B)(1) & (6)

Determine that the Reactor tripped on low S/G level and that this is reportable per 50.72(b)(2)(iv)(B) and is an 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report.

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

S / U S / U STOP TIME:

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.

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:

Administrative Job Performance Measure Conduct of Operations Ability to Locate and Use Procedures and Directives Related to Shift Staffing and Activities

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.

Terminate JPM when applicant indicates that he has completed the task 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 Tech Spec and Admin staffing is NOT met
  • 2) Explain the minimum manning required Determine that Tech Spec manning is NOT met Required to have one STA qualified individual on 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 />.

S / U S / U STOP TIME:

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.

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:

Administrative Job Performance Measure Equipment Control Knowledge of Tagging and Clearance Procedures

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

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:

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

Determine that the pump Suction Vlv should be closed after the Discharge Vlv Determine that the pump casing vent MV-ES3287 needs to be opened.

S / U S / U

Terminate JPM when applicant indicates that he has completed the task

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

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.

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:

Administrative Job Performance Measure Radiation Control Knowledge of 10CFR 20 and Related Facility Radiation Control Requirements

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 received passing through Regen Hx radiation field.

(9000mR/hr)(1hr/3600s)(20s/trip)(2trips)=100 mR

2) Calculate dose received near P-50D PCP (2600 mR/hr)(5 m)(1hr/60m) = 217 mR
3) Calculate dose received for transit inside containment

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

4) Calculate total dose received by each worker during inspection 100mR + 217mR +

0.5mR = 317.5 mR

5) Calculate total dose each worker has accumulated.

Worker 1 317.5mR + 1700mR =

2017.5mR Worker 2 317.5mR + 1680mR =

1997.5mR Calculate dose received to be 50 mR for each time the Regen Hx is passed for a total of 100 mR per worker (once going to the PCP and once coming back from PCP after inspection).

Calculate dose received to be 217 mR per worker at PCP for the inspection.

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

Calculate total dose received by each worker during inspection of 317.5mR Calculates accumulated dose received after inspection to be 2017.5mR and 1997.5mR S / U S / U S / U S / U S / U

Cue: Is there any way possible for worker 1 to complete this task?

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

  • 6) Determine that the annual admin dose limit will be exceeded by Worker 1 but not be Worker 2
7) Informs the Shift Manager that the admin dose limit would be exceeded by one of the workers but not by the other STOP TIME:

Determines Worker 1 will exceed annual dose limit if allowed to perform inspection 2017.5mR > 2000mR Informs the Shift Manager that the admin dose limit would be exceeded by one of the workers but not by the other. A dose extension will have to be obtained to allow Worker 1 to perform this task. No extension necessary for Worker 2.

S / U S / U

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)

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:

Control Room Systems Job Performance Measure Reactivity Control

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, Chemical and Volume Control System procedure Attatchment 14 Emergency Manual Boration.
2) Step 1.0 Ensure charging flow is > 33 gpm.

When applicant indicates where to find current copy of procedure provide a copy of SOP-2A, Chemical and Volume Control System procedure Attatchment 14 Emergency Manual Boration.

Ensure charging flow is > 33 gpm S / U S / U

3) Step 2.a Determine that Bus 1D is not available and that Boric Acid Pumps are unavailable
4) Step 2.b Determine that Bus 1C is Energized and that Gravity Feed can be established
  • 5) Step 2.b.1 Open the following Boric Acid Tank Gravity Feed Isol Valves MO-2169 MO-2170
  • 6) Step 2.b.2 Close the Boric Acid Blender Outlet Control Valve CV-2155
  • 7) Step 2.b.3 Close the VCT Outlet Isol Valve MO-2087
8) Step 2.b.4 Verify Closed SIRW Tank to Charging Pump Isol Valve MO-2160
9) Step 2.b.5 is not applicable because Y01 is energized
10) Step 2.b.6 Verify Charging Flow is > 33 gpm as indicated by FIA-0212, Charging Line Flow Indicator Alarm Determine that Bus 1D is not available and that Boric Acid Pumps are unavailable Determine that Bus 1C is Energized and that Gravity Feed can be established Open the following Boric Acid Tank Gravity Feed Isol Valves MO-2169 MO-2170 Close the Boric Acid Blender Outlet Control Valve CV-2155 Close the VCT Outlet Isol Valve MO-2087 Verify Closed SIRW Tank to Charging Pump Isol Valve MO-2160 Step 2.b.5 is not applicable because Y01 is energized Verify Charging Flow is > 33 gpm as indicated by FIA-0212, Charging Line Flow Indicator Alarm S / U S / U S / U S / U S / U S / U S / U S / U

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

& MO-2170 Closed Charging Pumps Suction from SIRWT MO-2160 Operate each Charging Pump for at least five minutes start a non-running charging pump per SOP-2A, Chemical and Volume Control System procedure.

S / U S / U S / U S / U S / U 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.

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:

Control Room Systems Job Performance Measure Primary Coolant System Inventory Control

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

S / U S / U

  • 3) Step 1a Ensure Both LPSI Pumps trip
4) Step 1b Check Open Both Containment Sump Isolation Valves CV-3030 CV-3029
  • 5) Step 1.b.1)a) Stop the following pumps:

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

6) Step 1.b.1)b) Check Closed Containment Spray Valve CV-3001
7) Step 1c Ensure Both SIRWT Isolation Valves Close:

CV-3031 CV-3057

8) Step 1d Ensure Both SI pump Minimum Flow Stop Valves are Closed CV-3027 CV-3056
9) Step 1e Ensure Both CCW Hx SW outlet valves Open:

CV-0826 CV-0823 LPSI P-67B must be manually tripped. P-67A trips automatically CV-3030 does not auto OPEN but CV-3029 is Open Stop the following pumps:

P-66B HPSI Pp P-54B CS Pp P-54C CS Pp CV-3001 closed automatically Both SIRWT Isolation Valves Close automatically CV-3031 CV-3057 Both SI pump Minimum Flow Stop Valves are Closed CV-3027 CV-3056 CV-0826 is Open CV-0823 is Open S / U S / U S / U S / U S / U S / U S / U

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

CV-0822 CV-0821

11) Step 1g.1 Ensure at least 1 CS pump operating for each operating HPSI
12) Step 1g.2 Open HPSI Subcooling Valve for operating HPSI Pp
13) Step 1.h If any HPSI pump is operating with HPSI subcooling valve closed, then stop pump
14) Step 1i.1 If only 1 CS Pp is operating Ensure only 1 HPSI Pp is operating
  • 15) Step 1i.2 Place HS-3001C to Bypass (key 397)
16) Ensure CV-3001 Closed
17) Inform CRS that CV-3030 is closed and ask if he would like it Opened Cue: Attempt to Open CV-3030
  • 18) Step 1j.1a Perform the following to Open CV-3030. Place HS-3001C in Bypass (key 397).

Both CCW Hx TCVs Closed:

CV-0822 CV-0821 Check that CS Pp P-54A and HPSI Pp P-66A are operating Verify Open CV-3071 HPSI Subcooling Valve for P-66A No action required Check that CS Pp P-54A and HPSI Pp P-66A are operating Place HS-3001C to Bypass (key 397)

Ensure CV-3001 Closed Inform CRS that CV-3030 is closed To Open CV-3030.

Place HS-3001C in Bypass (key 397).

S / U S / U S / U S / U S / U S / U S / U S / U S / U

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.

19) Step 1j.1b Ensure HS-3001A in Closed position
  • 20) Step 1j.1c Place HS-3030A to Open position (key 147)
21) Inform CRS that CV-3030 is Open and ask if he wants additional CS or HPSI pumps running?

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

Ensure HS-3001A in Closed position.

Place HS-3030A to Open position (key 147) Valve CV-3030 opens Inform CRS that CV-3030 is Open and ask if he wants additional CS or HPSI pumps running?

S / U S / U S / U 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.

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:

Control Room Systems Job Performance Measure Rx Pressure Control

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 SOP-1A, Primary Coolant System procedure
  • 2) Determine that Section 7.2.2.3 of SOP-1A should be use to alternate Pzr Press Controllers When applicant indicates where to find current copy of procedure provide a copy of SOP-1A, Primary Coolant System Review Section 7.2.2 Pzr Press Control and determine section 7.2.2.3 needs to be performed S / U S / U
3) Step 3a Verify PIC-0101A is in MANUAL
4) Step 3b Adjust output signal on PIC-0101A to match output signal on PIC-0101B
  • 5) Step 3c Place selector switch 1/PRC-0101 to PIC-0101A CUE: If asked, state that AUTO CONTROL IS DESIRED
6) Step 3.d.1 Ensure Pzr Htr Control Channel Selector Switch in CHAN A & B
  • 7) Step 3.d.2 Ensure PIC-0101A setpoint set at desired PCS pressure
  • 8) Step 3.d.3 Adjust PIC-0101A output to match indicated Pzr Press (red pointer) with setpoint press. (Blue pointer)
  • 9) Step 3.d.4 Depress the A pushbutton on PIC-0101A to place it in AUTO Verify PIC-0101A is in MANUAL Adjust output signal on PIC-0101A to match output signal on PIC-0101B for bumpless transfer Place selector switch 1/PRC-0101 to PIC-0101A Ensure Pzr Htr Control Channel Selector Switch in CHAN A & B Ensure PIC-0101A setpoint set at desired PCS pressure Adjust PIC-0101A output to match indicated Pzr Press (red pointer) with setpoint press. (Blue pointer)

Depress the A pushbutton on PIC-0101A to place it in AUTO S / U S / U S / U S / U S / U S / U S / U

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).

Cue: Control Room Supervisor directs the Reactor Operator to restore PIC-0101B to Automatic control

10) Step 3e Place PIC-0101B in MANUAL with 50%

output signal

  • 11) Applicant should recognize the failure by observing the output of PIC-0101A failing high. Pzr Press.

Off Normal Hi-Lo alarm will also alert Applicant of the problem

12) Inform CRS of the problem with PIC-0101A and recommend switching back to PIC-0101B
13) Step 3a Verify PIC-0101B is in MANUAL
  • 14) Step 3b Adjust output signal on PIC-0101B to desired output
  • 15) Step 3c Place selector switch 1/PRC-0101 to PIC-0101B CUE: IF ASKED STATE THAT AUTO CONTROL IS DESIRED Place PIC-0101B in MANUAL with 50% output signal Place PIC-0101A back to MANUAL and reduce controller output to restore Pzr Press to 2060 psig Inform CRS of the problem with PIC-0101A and recommend switching back to PIC-0101B Verify PIC-0101B is in MANUAL Adjust output signal on PIC-0101B to desired output Place selector switch 1/PRC-0101 to PIC-0101B S / U S / U S / U S / U S / U S / U

Terminate JPM when applicant indicates that he has informed the Control Room Supervisor of the problem with PIC-0101A.

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

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

(Blue pointer)

  • 19) Step 3.d.4 Depress the A pushbutton on PIC-0101B to place it in AUTO Ensure Pzr Htr Control Channel Selector Switch in CHAN B Ensure PIC-0101B setpoint set at desired PCS pressure Adjust PIC-0101B output to match indicated Pzr Press (red pointer) with setpoint press. (Blue pointer)

Depress the A pushbutton on PIC-0101B to place it in AUTO S / U S / U S / U S / U 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.

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:

Control Room Systems Job Performance Measure Heat Removal From Rx Core

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

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

  • 3) 7.3.2.ii SLOWLY OPEN the remaining LPSI injection valves to establish the following:
1) Total LPSI flow of 3600-4000gpm
2) Balanced flow between all four injection legs approx. 950 gpm
  • 5) 7.3.2.kk SLOWLY OPEN CV-3025, SDC Hx outlet to pressurize the SDC Hxs while observing the following:
1) PZR level
2) SDC Hx inlet pressure

& LPSI pump discharge pressure

  • 6) 7.3.2.ll CLOSE CV-3025 when PZR level stabilizes
  • 7) 7.3.2.mm OPEN CV-3055, SDC Hx Inlet (key 102)

OPEN the remaining LPSI injection valves to establish the following:

1) Total LPSI flow of 3600-4000gpm
2) Balanced flow between all four injection legs approx. 950 gpm PLACE HS-3025A shutdown cooling flow control in MANUAL (key 97)

OPEN CV-3025, SDC Hx outlet to pressurize the SDC Hxs CLOSE CV-3025 when PZR level stabilizes by setting HIC-3025A to Manual at 0%

OPEN CV-3055, SDC Hx Inlet (key 102)

S / U S / U S / U S / U S / U

  • 8) 7.3.2.nn OPERATE CV-3006, SDC Hx Bypass Valve as follows:
1. CHECK FIC-0306 in MANUAL with 0%

output signal (full open)

2. PLACE CV-3006 keyswitch to AUTO (key 94)
3. ADJUST FIC-0306 to establish a flow rate of 3400-3600 gpm.
9) 7.3.2.oo REQUEST Chemistry to sample the PCS for Boron CUE: Chemistry will sample the PCS for boron concentration.
  • 10) 7.3.2.pp CLOSE CV-3031 (key 149) and CV-3057 (key 150) SI Pump Suction SIRWT Valves and PLACE Caution Tags on keyswitches
  • 11) 7.3.2.qq PLACE LPSI pump trip on Low Level in SIRWT handswitches to DEFEAT P-67A key 154 P-67B key 155 CUE: This completes this JPM OPERATE CV-3006 as follows:
1. CHECK FIC-0306 in MANUAL with 0%

output signal (full open)

2. PLACE CV-3006 keyswitch to AUTO (key 94)
3. ADJUST FIC-0306 to establish a flow rate of 3400-3600 gpm.

REQUEST Chemistry to sample the PCS for Boron CLOSE CV-3031 (key 149) and CV-3057 (key 150) SI Pump Suction SIRWT Valves and PLACE Caution Tags on keyswitches PLACE LPSI pump trip on Low Level in SIRWT handswitches to DEFEAT P-67A key 154 P-67B key 155 S / U S / U S / U S / U

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 />.

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:

Control Room Systems Job Performance Measure Containment Integrity

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 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, Contaiment Air Cooling and Hydrogen Recombiner System procedure section 7.1.1.
2) For VHX-4 Verify Open High Capacity Inlet Valve CV-0869 When applicant indicates where to find current copy of procedure provide a copy of SOP-5, Contaiment Air Cooling and Hydrogen Recombiner System section 7.1.1 Verify Open High Capacity Inlet Valve CV-0869 S / U S / U

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

  • 3) For VHX-4 Open High Capacity Outlet Valve CV-0867
4) For VHX-1 Verify Open High Capacity Inlet Valve CV-0862
  • 5) For VHX-1 Open High Capacity Outlet Valve CV-0861
7) Obtain SOP-15 Service Water Pump procedure
8) Notify Chemistry to recalculate mixing basin 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-7C discharge valve MV-SW104 and Check P-7C motor oil levels.

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

Open High Capacity Outlet Valve CV-0867 Verify Open High Capacity Outlet Valve CV-0862 Open High Capacity Outlet Valve CV-0861 Determine that the Standby Service Water Pump P-7C needs to be started because system pressure decreased to

< 55 psig Obtain SOP-15 Service Water Pump procedure Notify Chemistry to recalculate mixing basin discharge flow volume.

Dispatch AO to OPEN P-7C discharge valve MV-SW104 and Check P-7C motor oil levels.

S / U S / U S / U S / U S / U S / U S / U

10) REMOVE P-7C from standby by placing Control Switch to TRIP

CUE: AO states that Local discharge pressure is 73 psig and packing leakoff is not excessive.

12) Verify Service Water Header Pressure increases to >

55psig

  • 13) For VHX-1 Start fan V-1A
  • 14) For VHX-1 Start fan V-1B
  • 15) For VHX-4 Start V-4A
  • 16) For VHX-4 Start V-4B REMOVE P-7C from standby by placing Control Switch to TRIP START P-7C to increase Service Water Header Pressure Verify Service Water Header Pressure increases to > 55psig Start fan V-1A Start fan V-1B Start fan V-4A Start fan V-4B S / U S / U S / U S / U S / U S / U 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.

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:

Control Room Systems Job Performance Measure Electrical

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-30, Station Power procedure
2) Check Safeguards/Station Power supply Bkrs 152-401 & 152-402 aligned per Section 7.2.3 or 7.2.4 When applicant indicates where to find current copy of procedure provide a copy of SOP-30, Station Power Review Sections 7.2.3 &

7.2.4 and check Bkr alignments S / U S / U CUE: Breaker 152-401 is Closed &

Breaker 152-402 is Open

3) Check bus 1C, 1D, & 1E control power lamps LIT
4) Check Startup XFMR UV aux. relays 127X-5 and 127X-6 reset.
5) Check Station Power XFMR 1-2 trouble lamp functional.

Check bus 1C, 1D, & 1E control power lamps LIT Check Startup XFMR UV aux. relays 127X-5 and 127X-6 reset.

Check Station Power XFMR 1-2 trouble lamp functional S / U S / U S / U

6) Check voltage on Safeguards Bus approximately 2400 V
7) Direct AO to Check all relays cut in and targets reset on bus and feeder breakers for:

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

  • 8) Scope and Close Safeguards/Station Power Incoming Brk for Bus 1C 152-105
9) Verify Startup Power Incoming BKR Opens on Bus 1C 152-106
10) Verify White Springs Charged lamp lit for 152-105
  • 11) Scope and Close Safeguards/Station Power Incoming Brk for Bus 1D 152-203
12) Verify Startup Power Incoming BKR Opens on Bus 1D 152-202
13) Verify White Springs Charged lamp lit for 152-203
  • 14) Scope and Close Safeguards/Station Power Incoming Brk for Bus 1E 152-302 Check voltage on Safeguards Bus approximately 2400 V Direct AO to Check all relays cut in and targets reset on bus and feeder breakers for:

Bus 1C Bus 1D Bus 1E Scope and Close Safeguards/Station Power Incoming Brk for Bus 1C 152-105 Verify Startup Power Incoming BKR Opens on Bus 1C 152-106 White Springs Charged lamp lit for 152-105 Scope and Close Safeguards/Station Power Incoming Brk for Bus 1D 152-203 Verify Startup Power Incoming BKR Opens on Bus 1D 152-202 White Springs Charged lamp lit for 152-203 Scope and Close Safeguards/Station Power Incoming Brk for Bus 1E 152-302 S / U S / U S / U S / U S / U S / U S / U S / U S / U

15) Verify Startup Power Incoming BKR Opens on Bus 1E 152-303
16) Verify White Springs Charged lamp lit for 152-302
17) When the buses have been transferred Place Startup Power Incoming BKR control switches momentarily to Trip to match targets 1C 152-106 1D 152-202 1E 152-302 Startup Power Incoming BKR Opens on Bus 1E 152-303.

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

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:

Control Room Systems Job Performance Measure Plant Service Systems

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.

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-24, Ventilation and Air Conditioning System procedure.
2) Notify the RETS/REMP Supervisor or Duty HP to ensure requirements of HP 6.14, Containment Purge, are met.

Cue: The Duty HP indicates that the requirements of HP 6.14 are met.

When applicant indicates where to find current copy of procedure provide a copy of SOP-24, Venti lation and Air Conditioning System procedure section 7.2.5.

Notify the

Note: Applicant will call AO to verify the following valves are locked closed Cue: AO Reports that MV-VA506, 508, & 505 are locked closed and capped Cue: CRS indicates that these times have been logged.

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

S / U S / U

3) Ensure one Main Exhaust Fan operating
4) Ensure RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.

Ensure Main Exhaust Fan V-6A running RGEM system is in operation per SOP-38, Gaseous Process Monitoring System per initial conditions (from initiating cue)

S / U S / U

5) Ensure the following Test Tap Valves are Locked Closed &Capped MV-VA506 MV-VA508 MV-VA505
  • 6) 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)

7) Record the time the valves were opened in the Control Room Logbook Ensure the following Test Tap Valves are Locked Closed &

Capped MV-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 trips.
10) Per ARP-7, EK-1127 directs starting standby main exhaust fan V-6B
  • 11) Per ARP-7, EK1127 secure any radioactive waste gas batch per SOP-18A &

shutdown any plant ventilation air flow per SOP-24.

12) Stop Air Room Supply Fan V-46
  • 13) Manually CLOSE all OPEN Purge CIVs. The Applicant may use EOP Supplement 6, Cnmt Isolation as a guide CV-1805 (key 272)

CV-1806 (key274)

CV-1807 (key 275)

CV-1808 (key 277)

CV-1813 (key 273)

CV-1814 (key 276)

Start Air Room Purge Supply Fan V-46 The Applicant refers to ARP-7, EK-1127, Main Exhaust Fan V-6A or B trip.

V-6B will not auto or manually start.

Secure any radioactive waste gas batch per SOP-18A & shutdown any plant ventilation air flow per SOP-24.

Stop Air Room Supply Fan V-46 Manually CLOSE all OPEN Purge CIVs CV-1805 (key 272)

CV-1806 (key274)

CV-1807 (key 275)

CV-1808 (key 277)

CV-1813 (key 273)

CV-1814 (key 276)

S / U S / U S / U S / U S / U S / U

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.

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:

In-Plant Job Performance Measure Electrical

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-20, Diesel Generator Manual Control procedure.
  • 2) Step 4.3.2.a.1 Trip all breakers on Bus 1C electrically or mechanically.

Cue: (Opened electrically)

The Green & if applicable, White status lights are lit

& red light is not lit.

(Opened mechanically)

Bkr status flag reads OPEN.

Obtain a copy of ONP-20, Diesel Generator Manual Control procedure. (in room between diesel generator rooms)

Applicant describes tripping Bkrs electrically by using handswitch or mechanically using the mechanical trip plunger located bottom center of the bkr inside the cubicle.

S / U S / U

  • 3) Step 4.3.2.a.2 Remove Closing Circuit and Close and Trip Circuit Fuses for all Bkrs on Bus 1C EXCEPT 152-103(P-7B),

152-107(D/G 1-1), & 152-108(Bus 13)

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

  • 4) Step 4.3.2.a.3 Obtain the Remote-Local-Transfer Switch (RLTS) Handles from cubicle 152-102(Dilution Water Pp)
5) Step 4.3.2.a.4 Review Att 2 for effects of placing D/G 1-1 RLTSs in LOCAL position.
  • 6) Step 4.3.2.a.5 Isolate D/G 1-1 control circuits by Placing the RLTSs on D/G Exciter Control Panel (HS-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
  • 7) Step 4.3.2.a.6 Isolate Bkr Control Circuits by Placing the following RLTSs in LOCAL:

HS-152-107RLTS (D/G 1-1)

HS-152-103RLTS (P-7B)

HS-152-108RLTS (Bus 13)

Applicant describes how to Remove Closing Circuit and Close and Trip Circuit Fuses for all Bkrs on Bus 1C EXCEPT 152-103(P-7B), 152-107(D/G 1-1), &

152-108(Bus 13)

Applicant describes where to Obtain the RLTS Handles. From cubicle 152-102(Dilution Water Pp)

Review Att 2 for effects of placing D/G 1-1 RLTS switches in LOCAL position.

Isolate D/G 1-1 control circuits by Placing HS-C22-RLTS and HS-G20-RLTS in LOCAL Isolate Bkr Control Circuits by Placing the following RLTSs in LOCAL:

HS-152-107RLTS (D/G 1-1)

HS-152-103RLTS (P-7B)

HS-152-108RLTS (Bus 13)

Cue: HS-152-107RLTS HS-152-103RLTS &

HS-152-108RLTS are in Local S / U S / U S / U S / U S / U

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

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

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

152-107 D/G 1-1 152-103 P-7B 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 D/G 1-1 by Placing Engine Control Switch on Local 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
  • 11) Step 4.3.2.a.10 Energize Bus 1C by Locally Closing D/G 1-1 Output Bkr 152-107.

Cue: Red and White Bkr status lights are lit and the Green Bkr status light is Out Remove the Close and Trip Circuit fuses for the following Bkrs:

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

152-107 D/G 1-1 152-103 P-7B 152-108 Bus 13 Start D/G 1-1 by Placing Engine Control Switch on Local Gauge Board to START Applicant will describe Closing D/G 1-1 Output Bkr 152-107 Locally.

S / U S / U S / U S / U

  • 12) Step 4.3.2.a.11 Locally Close the Service Water Pumps Bkr 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 Locally Close the Supply Bkr to 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 Service Water Header pressure is > 25 psig on PI-1472 on D/G 1-1 Local Control Panel Cue: PI-1472 is reading 30 psig
15) Notify CRS the 1-1 D/G is running and Service Water Pump P-7B and Bus 13 are energized.

Applicant will describe Closing the Service Water Pump Bkr 152-103 Applicant will describe Closing the Supply Bkr to Bus 13 152-108.

Verify Service Water Header pressure is > 25 psig on PI-1472 on D/G 1-1 Local Control Panel Notify CRS the 1-1 D/G is running and Service Water Pump P-7B and Bus 13 are energized.

S / U S / U S / U S / U 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.

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:

In-Plant Job Performance Measure Plant Service Systems

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 Supplement 31, Supply AFW Pumps from Alternate Sources
  • 2) Step 2.3 Place K-8 Cooling Water 3-Way Valve, MV-FW211 in EMERGENCY position (turn vlv handle fully clockwise)

Cue: Vlv handle is in the fully clockwise position Obtain a copy of EOP Supplement 31, Supply AFW Pumps from Alternate Sources Place K-8 Cooling Water 3-Way Valve, MV-FW211 in EMERGENCY position (turn vlv handle fully clockwise)

S / U S / U

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

P-8B AFW Pps have Fire Protection System water aligned to them S / U 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.

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:

In-Plant Job Performance Measure Containment Integrity

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-5, Containment Air Cooling and Hydrogen Recombining System.
2) Step 7.2.1.a Ensure at least one safety related CAC fan is in service.

Cue: If asked All CACs are in Emergency Mode

  • 3)Step 7.2.1.b CLOSE M-69B Hydrogen Recombiner Bkr 52-176 Cue: 52-176 Indicates ON Locate procedure SOP-5, Containment Air Cooling and Hydrogen Recombining System.

Ensure at least one safety related CAC fan is in service. All are in service per initial conditions.

CLOSE M-69B Hydrogen Recombiner Bkr 52-176 S / U S / U S / U

4) Step 7.2.1.c.1 Verify Power Available lamp lit Cue: Power Available light is lit
5) Step 7.2.1.c.2 Ensure Power Adjust knob is set at 000' Cue: Power Adjust knob is set at 000'
  • 6) Step 7.2.1.c.3 Place Power Out Switch to ON position Cue: Power Out Switch is ON
7) Step 7.2.1.c.4 Verify Power Out Switch Red light lit.

Cue: Power Out Switch red light is lit

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

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

9) Step 7.2.1.d If Recombiner is being started for testing...
10) Step 7.2.1.e.1 Determine the following:

Current Cnmt Pressure Previous Cnmt Temp.

Verify Power Available lamp lit on Hydrogen Recombiner control panel C-123 Ensure Power Adjust knob is set at 000' Place Power Out Switch to ON position Verify Power Out Switch Red light lit.

Place Temp Channel Selector Switch to position 1, 2, or 3.

Applicant determines that Recombiner is Not to be started for testing per initiating cue.

From Initial Conditions:

Cnmt Pressure is 24 psia Previous Cnmt temp 90oF S / U S / U S / U S / U S / U S / U S / U

11) Step 7.2.1.e.2 Determine Recombiner Power setting using Att 1 of SOP-5 and parameters determined above for Cnmt Press & Cnmt Temp.
  • 12) 7.2.1.e.3.a Adjust Power Adjust knob in the clockwise direction until Recombiner power (as read on the kw power out meter) is between 58 to 60 kw Cue: Power Out meter is reading 59 kw
13) 7.2.1.e.3.b Commence monitoring Power Out meter on C-123
14) Step 7.2.1.e.3.c Adjust Power Adjust knob to maintain desired setting between 58 and 60 kw.
15) Step 7.2.1.e.4 Notify CRS that M-69B is in service and that the CR should commence sampling Cnmt hydrogen per SOP-38, Gaseous Process Monitoring System.

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

Applicant should determine power setting between 58 to 60 kw using 9 psig and 90oF Adjust Power Adjust knob in the clockwise direction until Recombiner power (as read on the kw power out meter) is bewteen 58 to 60 kw Commence monitoring Power Out meter on C-123 Adjust Power Adjust knob to maintain desired setting between 58 and 60 kw.

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

S / U S / U S / U S / U S / U 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.

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:

Control Room Systems Job Performance Measure Radioactivity Release

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-18A, Radioactive Waste System - Gaseous procedure from the NCO.
2) Step 7.5.l Ensure Closed CV-1113, Waste Gas Surge Tank Discharge (At C-40 panel using HS-1113 and position indicator lights).

Cue: CV-1113 is closed

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

Cue: HS-1123 is in Open Obtain a copy of SOP-18A, Radioactive Waste System -

Gaseous procedure from the NCO.

Ensure Closed CV-1113, Waste Gas Surge Tank Discharge Place in OPEN HS-1123, WGDT Discharge S / U S / U S / U

4) Step 7.5.n Reset CV-1123 WGDT Discharge, high-radiation trip on Panel C-40.

Cue: CV-1123 is Reset

5) Step 7.5.o Ensure RE-1113 is valved in correctly by checking the following valves in their Locked position:

MV-WG117 Open MV-WG119 Open MV-WG118 Closed MV-WG114 Open Cue: MV-WG117 Open MV-WG119 Open MV-WG118 Closed MV-WG114 Open

  • 6) Step 7.5.p.1 Open MV-WG726, Drain Trap DT-1123 equalizing valve Cue: MV-WG726 is Open
  • 7) Step 7.5.p.2 Close MV-WG721, DT-1123 Bypass Valve Cue: MV-WG721 is Closed
  • 8) Step 7.5.p.3 Close MV-WG735, N2 Purge Isolation Cue: MV-WG735 is Closed
  • 9) Step 7.5.q Open WGDT outlet valve for the tank to be released T-101A.

Open MV-CA367, T-101A Outlet CV1160 A/S Cue: MV-CA367 is Open Reset CV-1123 WGDT Discharge, high-radiation trip on Panel C-40. (Vlv indication will not change until it is opened in step 7.5.r)

Ensure RE-1113 is valved in correctly by checking the following valves in their Locked position:

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

Open MV-WG726, Drain Trap DT-1123 equalizing valve Close MV-WG721, DT-1123 Bypass Valve (C-50 Comp Rm)

Close MV-WG735, N2 Purge Isolation (C-50 Comp Rm)

Open MV-CA367, T-101A Outlet CV1160 A/S S / U S / U S / U S / U S / U S / U

  • 10) Step 7.5.r Open CV-1123, SGDT Discharge, using HIC-1123, Waste Gas Discharge To Stack Cue: CV-1123 is Open
11) Step 7.5.s.1 Record the following on HP 6.6-3 Tank Pressure Wind Speed Wind Direction Stability Class Start Time Start Date
12) Step 7.5.s.2 Determine initial DP on dPI-1817, F-58 Decay Tank Discharge Filter DP indicator Cue: dPI-1817 is reading 0.5" H2O
  • 13) Step 7.5.t Slowly Open Discharge Hdr Vlvs for the T-101A tank:

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

14) Step 7.5.v Check dPI-1817, F-58 Decay Tank Discharge Filter DP indicator, < 2.5" H2O Cue: dPI-1817 is reading 1.5" H2O Open CV-1123, SGDT Discharge, using HIC-1123, Waste Gas Discharge To Stack Record the following on HP 6.6-3 Tank Pressure Wind Speed Wind Direction Stability Class Start Time Start Date Determine initial DP on dPI-1817, F-58 Decay Tank Discharge Filter DP indicator Slowly Open Discharge Hdr Vlvs for the T-101A tank MV-WG718 T-101A outlet vlv MV-WG718A T-101A outlet vlv Check dPI-1817, F-58 Decay Tank Discharge Filter DP indicator, < 2.5" H2O S / U S / U S / U S / U S / U

Terminate JPM when MV-WG718A is Closed

15) Step 7.5.w Record RIA-1113 reading on Form HP 6.6-3
16) Step 7.5.x Tank pressure indicates less than 3 psig Cue: 30 Mins have elapsed and tank pressure is 2 psig
17) Step 7.5.y Record final tank pressure on Form HP 6.6.3
  • 18) Step 7.5.z Close the following valve MV-WG718A for T-101A Cue: MV-WG718A is closed Record RIA-1113 reading on Form HP 6.6-3 Record final tank pressure on Form HP 6.6.3 Close the following valve MV-WG718A for T-101A S / U S / U S / U S / U 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.

asee02.jpm 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

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm asee02.jpm Page 89 of 4 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.

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm asee02.jpm Page 90 of 4 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 and PPC displays checked.

S/U 6.

Compare indicated positions from Primary and Secondary.

STANDARD:

Compare indicated positions using rod positions from Primary and Secondary. Verify Primary and Secondary agree.

S/U

  • 7.

Identify cause of out of sequence condition.

STANDARD:

Operator identifies failure of PIP node sequencers as the cause of the problem.

S/U

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm asee02.jpm Page 91 of 4

[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:

Rev. 2 JPM - ASEE-02.JPM Respond to a Control Rods Out of Sequence Alarm asee02.jpm Page 92 of 4 2.1 OPERATOR PERFORMANCE

~ Satisfactory

~ Unsatisfactory JPM was performed in minutes.

COMMENTS 3.0 GENERAL REFERENCES SOP 6, rev 23 ARP 5 rev 66

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.

Retrieved from "https://kanterella.com/w/index.php?title=ML052270331&oldid=5378312"