ML22166A469

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2017 Pal Ile RO and SRO Admin JPMs
ML22166A469
Person / Time
Site: Palisades Entergy icon.png
Issue date: 02/22/2017
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Entergy Nuclear Operations
Baker R
Shared Package
ML17037C872 List:
References
Download: ML22166A469 (72)
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Text

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 1 of 10 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

RO ADMIN 1 TITLE:

DETERMINE AVERAGE QUALIFIED CET TEMPERATURE AND SUBCOOLING VALUE CANDIDATE:

EXAMINER:

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 2 of 10 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine average qualified CET temperature and subcooling value.

Alternate Path: No Facility JPM #: 2007 NRC Exam (modified)

K/A:

G2.1.23 Importance:

RO:

4.3 SRO:

4.4 K/A Statement: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Task Standard: Average CET Temperature correctly calculated and subcooling value determined.

Preferred Evaluation Location: Simulator

_X_

In Plant Preferred Evaluation Method:

Perform

_X_

Simulate

References:

SOP-34, Palisades Plant Computer (PCC) System EOP Supplement 1, Pressure and Temperature Limit Curves Validation Time: 17 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 3 of 10 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • SOP-34, Palisades Plant Computer (PCC) System
  • EOP Supplement 1, Pressure and Temperature Limit Curves Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • The Plant is at 100% power.

INITIATING CUES:

The CRS has directed you to determine average qualified CET temperature and PCS sub-cooling value in accordance with SOP-34, Attachment 5, using all 16 CET readings.

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 4 of 10 FEBRUARY 2017 Time Start: ______

Proc.

Step TASK ELEMENT 1 STANDARD Grade 1.a Obtain at least 2 Qualified CET readings per core quadrant from the CET recorders.

Operator records qualified CET temperatures as read from the CET recorders (TR-0101A1.

TR-0101A2, TR-0101B1, TR-0101B2) on Panel C-11A and the time.

At least two (2) qualified CET readings per quadrant required. The readings are recorded in section 2.

S U Comment:

Evaluator Note: Verify data taken by Operator, the initiating cue, all 16 readings will be taken.

CRITICAL STEP Proc.

Step TASK ELEMENT 2 STANDARD Grade 1.b CALCULATE the average of the temperature readings used.

Operator sums the CET readings (recorded in section 2), then divides the sum by the number of CETs used (8 minimum) to obtain the average CET temperature (recorded in section 2).

S U Comment:

Evaluator Note: Verify calculation by Operator with attached answer key.

Proc.

Step TASK ELEMENT 3 STANDARD Grade 1.c If any individual temperature readings is greater than 15°F higher or lower from the average, then:

Do not utilize that individual temperature reading.

Return to Step 1a.

CET #25 (3rd quadrant) will be approximately 17°F lower than the average.

The candidate will recalculate excluding this reading.

S U Comment:

CRITICAL STEP

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 5 of 10 FEBRUARY 2017 Proc.

Step TASK ELEMENT 4 STANDARD Grade 1.d REFER TO EOP Supplement 1, Pressure Temperature Limit Curves, to determine sub-cooling value utilizing the average temperature calculated in step 1.b.

Operator performs the following:

Obtains PCS Pressure reading from initial conditions Plots pressure reading versus Average CET reading obtained in step 1.b on EOP Supplement 1, page 1 to determine subcooling value S U Comment:

Evaluator Note: Subcooling value is obtained from EOP Supplement 1 page 1 by finding saturation temperature for 2060 psia (640°F) and subtracting average CET calculated (590.8 to 591°F) to obtain 49°F.

CRITICAL STEP: Determine subcooling value within +/- 5oF.

Proc.

Step TASK ELEMENT 5 STANDARD Grade n/a Operator informs CRS of Average Qualified CET Temperature and sub-cooling value.

CRS informed that subcooling value is approximately 49°F.

S U Comment:

Time Stop: _____

END OF TASK

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 6 of 10 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • Reset to IC-150.
  • Change CET #25 to read 572oF.

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 7 of 10 FEBRUARY 2017 Answer Key All answers are +/- 2°F QUADRANT QUALIFIED CET #

TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago TIME 45 min ago TIME 30 min ago TIME 15 min ago TIME now TIME now 1

2 577 577 9

591 591 10 591 591 19 588 588 2

5 598 598 11 590 590 16 601 601 21 603 603 3

23 586 586 25 572 31 584 584 35 590 590 4

27 593 593 30 591 591 33 589 589 36 590 590 TOTAL 9435 8862 AVERAGE 589.7 590.8

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 8 of 10 FEBRUARY 2017 Proc No SOP-34 Revision 22 QUALIFIED CET CALCULATION FORM Page 1 of 1

1.

INSTRUCTIONS

a.

OBTAIN at least two (2) qualified CET readings per core quadrant from the CET recorders.

b.

CALCULATE the average of the temperature readings used.

c.

IF any individual temperature reading is greater than 15°F higher or lower than the average temperature, THEN:

1.

Do not utilize that individual temperature reading.

2.

Return to Step 1a.

d.

REFER TO EOP Supplement 1, Pressure Temperature Limit Curves, to determine subcooling value utilizing the average temperature calculated in Step 1b.

2.

DATA RECORDING/CALCULATIONS QUADRANT QUALIFIED CET #

TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago TIME 45 min ago TIME 30 min ago TIME 15 min ago TIME TIME 1

2 9

10 19 2

5 11 16 21 3

23 25 31 35 4

27 30 33 36 TOTAL AVERAGE

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 9 of 10 FEBRUARY 2017

JPM RO ADMIN 1 PALISADES NUCLEAR PLANT Page 10 of 10 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The Plant is at 100%.

INITIATING CUES:

The CRS has directed you to determine average qualified CET temperature and PCS sub-cooling value in accordance with SOP-34, Attachment 5, using all 16 CET readings.

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 1 of 8 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

RO ADMIN 2 TITLE:

REVIEW AN EQUIPMENT TAGOUT FOR P-7A SERVICE WATER PUMP CANDIDATE:

EXAMINER:

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 2 of 8 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Review a prepared equipment tagout for taking the P-7A Service Water pump out of service for discharge basket strainer cleaning.

Alternate Path: No Facility JPM #: N/A (new)

K/A:

2.2.13 Importance:

RO:

4.1 SRO:

4.3 K/A Statement: Knowledge of tagging and clearance procedures Task Standard: Review a prepared equipment tagout for taking the P-7A Service Water pump out of service for discharge basket strainer cleaning.

Preferred Evaluation Location: Classroom _X_

In Plant ___

Preferred Evaluation Method:

Perform

_X_

In Plant ___

References:

EN-OP-102, Protective and Caution Tagging SOP-15, Service Water System Palisades P&ID drawings Palisades Electrical drawings Validation Time: 7 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

_______ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 3 of 8 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • Palisades P&ID drawings
  • Palisades Electrical drawings Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • An NCO prepared a paper-based tagging order for taking the P-7A Service Water Pump out of service to support discharge strainer basket cleaning.
  • The NCO who prepared the tagout had to leave due to being ill.

INITIATING CUES:

The Shift Manager has directed you to review a prepared tagging order for the P-7A Service Water Pump discharge strainer basket cleaning.

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 4 of 8 FEBRUARY 2017 Time Start: ________

Evaluator Note: EN-OP-102 is to be provided to applicant at the start of the JPM, along with the prepared copy of the tagging order. Do not provide SOP-15 unless the applicant requests it.

Proc.Step TASK ELEMENT 1 STANDARD Grade EN-OP-102 5.6 Reviews the prepared tagout per Section 5.3 (Tagout Preparation).

Obtains EN-OP-102 and uses Section 5.3 to review the prepared tagout.

S U Comment:

Proc.Step TASK ELEMENT 2 STANDARD Grade N/A Refer to procedures (EN-OP-102 and/or SOP-15) to determine the proper equipment tagout sequence.

Applicant may use either of the following procedures to determine the tagout sequence:

EN-OP-102 Att. 9.2 combined with station electrical and mechanical drawings.

SOP-15 Section 8.1.1 to remove Service Water Pumps from service S U Comment:

Evaluator Cue: Provide the applicant with SOP-15 if requested. Guidance to remove pump P-7A from service is detailed in Section 8.1.1.

Proc.Step TASK ELEMENT 3 STANDARD Grade SOP-15 8.1.1.a

& b

  • Stop Service Water Pump P-7A per SOP-15 and ensure pump is not in standby.
  • Place local control switch at Screenhouse Entrance in OFF and NO Tag control switch
  • Verifies tagging order Step 1 is correct.
  • 1-CSW-Pump-P-7A local control switch NO Tag S U Comment:

Proc.Step TASK ELEMENT 4 STANDARD Grade SOP-15 8.1.1.b Place control room control switch to TRIP and CAUTION Tag

  • Verifies tagging order Step 2 is correct.
  • 1-CSW-CKTBRK-15-204CS control room control switch CAUTION Tag S U

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 5 of 8 FEBRUARY 2017 Comment:

Proc.Step TASK ELEMENT 5 STANDARD Grade SOP-15 8.1.1.c Identifies incorrect Service Water Pump (P-7C) breaker is racked to disconnect with DANGER Tag

  • Verifies tagging order Step 3 is incorrect.
  • Verifies incorrect breaker is tagged out of service and breaker racked is for P-7C, not P-7A.
  • Recognizes that breaker 152-204 should be tagged out.

S U Comment:

Evaluator Cue: Acknowledge report of error.

CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade SOP-15 8.1.1.d Identifies that Service Water Pump P-7A discharge valve MV-SW102 is incorrectly positioned.

  • Verifies tagging order Step 4 is incorrect.
  • Identifies MV-SW102 is incorrectly tagged in the OPEN position.
  • Determines correct action and position is to unlock and Close P-7A Discharge Valve MV-SW102 and place Danger Tag S U Comment:

Evaluator Cue: Acknowledge report of error.

CRITICAL STEP Proc.Step TASK ELEMENT 7 STANDARD Grade SOP-15 8.1.1.e Identifies position and tag errors on P-7A Recirculation Valve MV-SW342

  • Verifies tagging order Step 5 is incorrect.
  • Identifies MV-SW342 is incorrectly tagged locked closed and not closed.
  • Identifies MV-SW342 is incorrectly NOT tagged and should be DANGER Tagged.

S U Comment:

Evaluator Cue: Acknowledge report of error.

CRITICAL STEP

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 6 of 8 FEBRUARY 2017 Time Finish: ________

END OF TASK

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 7 of 8 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • None required.

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 8 of 8 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

CANDIDATE CUE SHEET INITIAL CONDITIONS:

  • An NCO prepared a paper-based tagging order for taking the P-7A Service Water Pump out of service to support discharge strainer basket cleaning.
  • The NCO who prepared the tagout had to leave due to being ill.

INITIATING CUES:

The Shift Manager has directed you to review a prepared tagging order for the P-7A Service Water Pump discharge strainer basket cleaning.

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 1 of 7 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

RO ADMIN 3 TITLE: DETERMINATION OF WHETHER RWP DOSE LIMITS WILL BE EXCEEDED CANDIDATE:

EXAMINER:

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 2 of 7 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determination of whether RWP Dose Limits Will Be Exceeded Alternate Path: NO Facility JPM #: N/A (new)

K/A: G.2.3.7 Importance:

RO: 3.5 SRO: 3.6 K/A Statement: Ability to comply with Radiation Work Permit requirements during normal and abnormal conditions.

Task Standard: Determine that the RWP dose limits will be violated by performing the given task.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

Radiological Survey Sheet, 570 WESG RWP 20170002 Validation Time: 10 minutes Time Critical:

NO Candidate: ______________________________________________________

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 3 of 7 FEBRUARY 2017 Tools/Equipment/Procedures Needed:

  • Radiological Survey Sheet, 570 WESG
  • Calculator EXAMINER COPY ONLY READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • P-67B LPSI Pump was started and a moderate leak was identified from the drain valve MV-ES515.
  • The CRS desires to dispatch an NPO to investigate and repair the drain valve.
  • The NPO currently has 7 mR accumulated dose under RWP 20170002 Task 01 on this shift.
  • It is estimated that the NPO will spend time the following time in the WESG room in the general area of the P-67B pump skid:

o 12 minutes in communication with the Control room via the radio

  • It is estimated that the NPO will spend 21 minutes inside the P-67B pump skid contaminated area as follows:

o 3 minutes investigating the drain valve leak o 6 minutes attempting to tighten the drain valve o 12 minutes to complete venting the pump after pump restart o Note: Drain valve MV-ES515 is approximately 30 cm from HS-11 o Note: Casing vent valve MV-ES535 is approximately 30 cm from HS-10

  • It is estimated that the NPO will pick up 2 mR in transit during this task.

INITIATING CUE:

Your task is to, based on the radiological information provided, determine if the NPO could perform the task while currently signed in on RWP 20170002 Task 01.

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 4 of 7 FEBRUARY 2017 Time Start: ________

Proc.Step TASK ELEMENT 1 STANDARD Grade Calculate dose received in general area around pump skid.

Identify dose field is 5mr/hr and calculate dose received to be 1mR S U Comment:

(5mR/hr)*(1hr/60min)*12min = 1 mR Evaluator Cue: If applicant asks, direct applicant to general area around pump skid to be 5 mR/hr.

Proc.Step TASK ELEMENT 2 STANDARD Grade Calculate dose received investigating drain valve leak Identify dose field is 300/20 mR/hr and calculate dose received during drain valve leak investigation to be 1 mR (use 20 mR/hr based on cue sheet)

S U Comment:

(20mR/hr)*(1hr/60min)*3min = 1 mR CRITICAL STEP: Applicant must determine that 20 mR/hr is correct based on the cue provided.

Applicant should not use the on-contact dose value of 300 mR/hr (this will violate the RWP).

Proc.Step TASK ELEMENT 3 STANDARD Grade Calculate dose received repairing the drain valve leak Identify dose field is 300/20 mR/hr and calculate dose received during drain valve leak repair to be 2 mR (use 20 mR/hr based on cue sheet)

S U Comment:

(20mR/hr)*(1hr/60min)*6min = 2 mR CRITICAL STEP: Applicant must determine that 20 mR/hr is correct based on the cue provided.

Applicant should not use the on-contact dose value of 300 mR/hr (this will violate the RWP).

Proc.Step TASK ELEMENT 4 STANDARD Grade Calculate dose received venting the pump Identify dose field is 430/50 mR/hr and calculate dose received during pump venting to be 10 mR (use 50 mR/hr based on cue sheet)

S U Comment:

(50mR/hr)*(1hr/60min)*12min = 10 mR CRITICAL STEP: Applicant must determine that 50 mR/hr is correct based on the cue provided.

Applicant should not use the on-contact dose value of 430 mR/hr (this will violate the RWP).

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 5 of 7 FEBRUARY 2017 Proc.Step TASK ELEMENT 5 STANDARD Grade Determine total accumulated dose for the NPO Determines total accumulated dose for the NPO:

Prior/existing dose on this shift = 7 mR Transit dose = 2 mR General area dose = 1 mR Leak investigation = 1 mR Leak repair = 2 mR Pump venting = 10 mR Total dose accumulated for NPO = 23 mR S U Comment:

Proc.Step TASK ELEMENT 6 STANDARD Grade Determines that NPO cannot perform the task with the provided time estimates without exceeding the RWP dose allotments.

Determines NPO will exceed RWP allowed dose accumulation of 20 mR.

S U Comment:

CRITICAL STEP Time Stop: ________

END OF TASK

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 6 of 7 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • None required

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 7 of 7 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

CANDIDATE CUE SHEET INITIAL CONDITIONS:

  • P-67B LPSI Pump was started and a moderate leak was identified from the drain valve MV-ES515.
  • The CRS desires to dispatch an NPO to investigate and repair the drain valve.
  • The NPO currently has 7 mR accumulated dose under RWP 20170002 Task 01 on this shift.
  • It is estimated that the NPO will spend time the following time in the WESG room in the general area of the P-67B pump skid:

o 12 minutes in communication with the Control room via the radio

  • It is estimated that the NPO will spend 21 minutes inside the P-67B pump skid contaminated area as follows:

o 3 minutes investigating the drain valve leak o 6 minutes attempting to tighten the drain valve o 12 minutes to complete venting the pump after pump restart o Note: Drain valve MV-ES515 is approximately 30 cm from HS-11 o Note: Casing vent valve MV-ES535 is approximately 30 cm from HS-10

  • It is estimated that the NPO will pick up 2 mR in transit during this task.

INITIATING CUE:

Your task is to, based on the radiological information provided, determine if the NPO could perform the task while currently signed in on RWP 20170002 Task 01.

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 1 of 7 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

RO ADMIN 4 TITLE:

PERFORM EMERGENCY NOTIFICATIONS CANDIDATE:

EXAMINER:

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 2 of 7 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Make emergency notifications as required by the Site Emergency Plan Alternate Path: No Facility JPM #: 1999 NRC Exam K/A:

G2.4.43 Importance:

RO:

3.2 SRO:

3.8 K/A Statement: Knowledge of emergency communications systems and techniques Task Standard: Demonstrate the ability to make emergency notifications using the emergency plan.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

EI-1, Emergency Classification and Actions Procedure EI-3, Communications and Notification Procedure Validation Time: 9 minutes Time Critical:

YES Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 3 of 7 FEBRUARY 2017 Tools/Equipment/Procedures Needed:

  • EI-1, Emergency Classification and Actions Procedure
  • Partially completed EI-1 Att 1 for ALERT (steps 1-3 complete)
  • EI-3, Communications and Notification Procedure
  • Completed EI-3 Att 1 EXAMINER COPY ONLY READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Shift Manager, who is acting as the Emergency Plant Manager, has declared an ALERT.

INITIATING CUES:

The Shift Manager has directed you make all initial emergency notifications required by the Site Emergency Plan.

This JPM is Time Critical.

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 4 of 7 FEBRUARY 2017 Time Start: ________

Evaluator Cue: Provide applicant with a working copy of EI-1 Att 1 for an ALERT, with steps 1-3 completed and provide completed EI-3 Att 1 (Notification 1) for an ALERT.

Proc.Step TASK ELEMENT 1 STANDARD Grade 5.3.1.f Per EI-3, verify Emergency Notification Form is approved (initialed) by the Emergency Director Form checked for Emergency Director initials.

S U Comment:

Proc.Step TASK ELEMENT 2 STANDARD Grade 5.3.1.b Notify Van Buren County Van Buren County Sheriff contacted, within 15 min. of emergency declaration.

S U Comment:

Proc.Step TASK ELEMENT 3 STANDARD Grade N/A Relay information on Emergency Notification Form to Van Buren County

  • Correct information relayed
  • Name of person contacted entered on Emergency Notification Form (not time critical)
  • Documents time of Van Buren County notified in VB block.

S U Comment:

Time Critical Stop: _______

CRITICAL STEP: Time critical (with 15 minutes from the start of the JPM) to transmit this information to Van Buren County.

Proc.Step TASK ELEMENT 4 STANDARD Grade 5.3.1.b Notify the State of Michigan State of Michigan contacted, within 15 min. of emergency declaration.

S U Comment:

Proc.Step TASK ELEMENT 5 STANDARD Grade

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 5 of 7 FEBRUARY 2017 N/A Relay information on Emergency Notification Form to the State of Michigan

  • Correct information relayed
  • Name of person contacted entered on Emergency Notification Form. (not time critical)
  • Documents time of the State of Michigan notified in SOM block.

S U Comment:

Time Critical Stop: _______

CRITICAL STEP: Time critical (with 15 minutes from the start of the JPM) to transmit this information to the State of Michigan.

Proc.Step TASK ELEMENT 6 STANDARD Grade 5.3.1.b Notify the NRC NRC contacted using the direct line to NRC Operations Center.

S U Comment:

Proc.Step TASK ELEMENT 7 STANDARD Grade N/A Relay information on Emergency Notification Form to the NRC.

Correct information relayed Name of person contacted entered on Emergency Notification Form. (not time critical)

Documents time of NRC notified in NRC block S U Comment:

Evaluator Cue: Inform the candidate that the NRC does not desire continuous contact at this time.

Evaluator Cue: Inform applicant that another operator will take care of faxing the forms.

CRITICAL STEP: transmit this information to the NRC Proc.Step TASK ELEMENT 8 STANDARD Grade N/A Notify the Emergency Director that notifications are complete.

Emergency Director notified of initial notification completion.

S U Comment:

Time Stop: ________

END OF TASK

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 6 of 7 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • None required.

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 7 of 7 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Shift Manager, who is acting as the Emergency Plant Manager, has declared an ALERT.

INITIATING CUES:

The Shift Manager has directed you make all initial emergency notifications required by the Site Emergency Plan.

This JPM is Time Critical.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 1 of 10 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

SRO ADMIN 1 TITLE:

REVIEW COMPLETED PROCEDURE TO DETERMINE AVERAGE QUALIFIED CET TEMPERATURE AND SUBCOOLING VALUE CANDIDATE:

EXAMINER:

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 2 of 10 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Review a completed procedure to determine the average qualified CET temperatures and subcooling value.

Alternate Path: NO Facility JPM #: N/A K/A:

G2.1.23 Importance:

RO:

4.3 SRO:

4.4 K/A Statement: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Task Standard: Determine errors in the completed procedure to calculate average qualified CET Temperatures and sub-cooling value determined.

Preferred Evaluation Location: Simulator

_X_

In Plant Preferred Evaluation Method:

Perform

_X_

Simulate

References:

SOP-34, Palisades Plant Computer (PPC) System EOP Supplement 1, Pressure and Temperature Limit Curves Validation Time:

20 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 3 of 10 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • SOP-34, Palisades Plant Computer (PPC) System
  • EOP Supplement 1, Pressure and Temperature Limit Curves Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • A loss of off-site power has resulted in a Reactor trip from 100% power.
  • Buses 1C and 1D are energized from their D/Gs.
  • PCS Pressure is 1750 psia
  • An NCO was directed to determine PCS sub-cooling value in accordance with SOP-34,, using all available CET readings.

INITIATING CUES:

The CRS has directed you to review the completed SOP-34, Attachment 5, to determine PCS sub-cooling value and has turned it in for review. Review all time periods of the completed procedure, verify the current PCS sub-cooling value, and determine any required actions.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 4 of 10 FEBRUARY 2017 Time Start: ______

Proc.

Step TASKELEMENT 1 STANDARD Grade 1.a Verify at least 2 Qualified CET readings per core quadrant from the CET recorders.

Determines that:

At least 2 QCET readings were obtained from all Quadrants.

S U Comment:

Evaluator Note: Verify calculation by Operator with attached answer key.

Evaluator Cue: After applicant identifies that only 2 CET readings were obtained from Quadrants 1 and 3, inform applicant that the missing readings were unavailable.

Proc.

Step TASK ELEMENT 2 STANDARD Grade 1.b CALCULATE the average of the temperature readings used.

Operator sums the CET readings (recorded in section 2), then divides the sum by the number of CETs used (8 minimum) to obtain the average CET temperature (recorded in section 2).

Determines average for 15 minutes ago is incorrect (correct value is 542oF).

May determine average values for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago and just now are incorrect due to using invalid CET values (see task element 3).

S U Comment:

Evaluator Note: Verify calculation by Operator with attached answer key.

CRITICAL STEP: Determine incorrect average value for 15 mins ago and recalculates correct average of the temperature readings.

Proc.

Step TASK ELEMENT 3 STANDARD Grade 1.c If any individual temperature readings is greater than 15°F higher or lower from the average, then:

Do not utilize that individual temperature reading.

Return to Step 1a.

Determines that CET #9 taken 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago was

> 15oF from the average and should not have been used. Recalculates correct average temp.

Determines that CET #23 taken just now was >

15oF from the average and should not have been used. Recalculates correct average temp.

S U Comment:

CRITICAL STEP: Determines CET values recorded for #9 from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago and #23 from time now are erroneous and should not have been used. Applicant determines that the average of the temperature for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago and time now are incorrect and recalculates correct average of the temperatures.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 5 of 10 FEBRUARY 2017 Proc.

Step TASK ELEMENT 4 STANDARD Grade 1.d REFER TO EOP Supplement 1, Pressure Temperature Limit Curves, to determine sub-cooling value utilizing the average temperature calculated in step 1.b.

Operator performs the following:

Obtains PCS Pressure reading from initial conditions.

Plots pressure reading versus Average CET reading obtained in step 1.b on EOP Supplement 1, page 1 to determine subcooling value (~540oF).

Determines subcooling value of ~77oF Determines NCO was incorrect and used curve for minimum pressure for PCP operation.

S U Comment:

Evaluator Note: Subcooling value is obtained from EOP Supplement 1 page 5 by finding saturation temperature for 1750 psia (617°F) and subtracting average CET calculated (540°F) to obtain 77°F.

CRITICAL STEP: Determine subcooling value (~59oF) incorrect and determine correct subcooling value

(~77oF) within +/- 2.5oF. Applicant corrects the sub-cooling value on SOP-34, Attachment 5. (May be verbal to inform CRS.)

Proc.

Step TASK ELEMENT 5 STANDARD Grade n/a Consults Tech Specs when applicant determines the CETs not recorded are inoperable.

Reviews LCO 3.3.7 and determine that 4 CETs are required to be operable in each quadrant and enters the following:

LCO 3.3.7 Cond A for Quadrant 1 and 3 (30 day restoration).

LCO 3.3.7 Cond C for Quadrant 3 (7 day restoration)

S U Comment:

Evaluator Cue: If applicant asks if the CETs not recorded are operable, inform the applicant that per the initial conditions, all available CET reading were recorded..

CRITICAL STEP: Applicant determines correct LCO required actions.

Time Stop: _____

END OF TASK

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 6 of 10 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • None required.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 7 of 10 FEBRUARY 2017 Answer Key Average values should be +/- 2oF QUADRANT QUALIFIED CET #

TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago TIME 45 min ago TIME 30 min ago TIME 15 min ago TIME now TIME now 1

2 537 536 538 536 537 9

557 552 556 548 548 10 19 537 536 538 536 537 2

5 540 541 540 541 540 11 536 536 537 536 536 16 535 534 535 534 535 21 534 535 533 535 535 3

23 545 548 551 554 559 25 31 539 547 545 544 541 35 4

27 538 537 538 537 538 30 547 546 547 546 547 33 541 542 540 542 541 36 550 552 551 552 550 TOTAL 7036 /

6479 7042 7049 7041 7044 /

6485 AVERAGE 541 / 540 542 542 544 / 542 542 / 540 Out of bounds QCET values for #9 and #23 must be rejected and not used.

Average value from 15 min ago is incorrect.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 8 of 10 FEBRUARY 2017

~ 77°F

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 9 of 10 FEBRUARY 2017 Proc No SOP-34 Revision 22 QUALIFIED CET CALCULATION FORM Page 1 of 1

1.

INSTRUCTIONS

a.

OBTAIN at least two (2) qualified CET readings per core quadrant from the CET recorders.

b.

CALCULATE the average of the temperature readings used.

c.

IF any individual temperature reading is greater than 15°F higher or lower than the average temperature, THEN:

1.

Do not utilize that individual temperature reading.

2.

Return to Step 1a.

d.

REFER TO EOP Supplement 1, Pressure Temperature Limit Curves, to determine subcooling value utilizing the average temperature calculated in Step 1b.

2.

DATA RECORDING/CALCULATIONS QUADRANT QUALIFIED CET #

TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago TIME 45 min ago TIME 30 min ago TIME 15 min ago TIME

_NOW_

TIME 1

2 537 536 538 536 537 9

557 552 556 548 548 10 19 537 536 538 536 537 2

5 540 541 540 541 540 11 536 536 537 536 536 16 535 534 535 534 535 21 534 535 533 535 535 3

23 545 548 551 554 559 25 31 539 547 545 544 541 35 4

27 538 537 538 537 538 30 547 546 547 546 547 33 541 542 540 542 541 36 550 552 551 552 550 TOTAL 7036 7042 7049 7041 7044 AVERAGE 541 542 542 544 542 Subcooling determined to be ~ 59oF.

JPM SRO ADMIN 1 PALISADES NUCLEAR PLANT Page 10 of 10 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • A loss of off-site power has resulted in a Reactor trip from 100% power.
  • Buses 1C and 1D are energized from their D/Gs.
  • PCS Pressure is 1750 psia
  • An NCO was directed to determine PCS sub-cooling value in accordance with SOP-34, Attachment 5, using all available CET readings.

INITIATING CUES:

The CRS has directed you to review the completed SOP-34, Attachment 5, to determine PCS sub-cooling value and has turned it in for review. Review all time periods of the completed procedure, verify the current PCS sub-cooling value, and determine any required actions.

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 1 of 6 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

SRO Admin 2 TITLE:

Determine Shift Staffing Requirements CANDIDATE:

EXAMINER:

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 2 of 6 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine the Shift Staffing Requirements following an illness Alternate Path: No Facility JPM #:

K/A: G2.1.5 Importance:

RO:

2.9 SRO:

3.9 K/A Statement: Ability to use procedures related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Task Standard: Based on given conditions, determine that the applicable Plant Staffing Levels are not met.

Preferred Evaluation Location: Classroom _X_

In Plant Preferred Evaluation Method:

Perform

_X_

Simulate

References:

Administrative Procedure 4.00, Operations Organization, Responsibilities, and Conduct EN-OP-115, Conduct of Operations, Attachment 9.6 Palisades Specific 10 CFR Part 50.54 Technical Specifications 5.2 Validation Time:

10 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 3 of 6 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • Normal Control Room references.

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • 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:
  • (1) Shift Manager
  • (1) Control Room Supervisor
  • (1) Shift Engineer/Shift Technical Advisor (SE/STA)
  • (3) Nuclear Control Operators
  • (6) Nuclear Plant Operators
  • (1) Chemistry Technician
  • (1) Radiation Safety Technician (EMT)
  • Required number of Security personnel
  • At 0300 the SE/STA is taken to the hospital by the Radiation Safety Technician (EMT) due to an allergic reaction to something he has eaten.

INITIATING CUES:

You are the Shift Manager. Determine if staffing requirements are met and explain your decision and required actions, if any.

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 4 of 6 FEBRUARY 2017 Time Start: ______

Proc.Step TASK ELEMENT 1 STANDARD Grade N/A Identifies Shift Staffing requirements IAW EN-OP-115 Att 9.6 Section 1.

Verifies SE/STA position is not satisfied.

Determine that in Modes 1-4, the following crew composition is required:

3 SRO (1 must be SE/STA qualified) (not satisfied due to 0 SE/STA) 3 NCO 6 NPO S U Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 2 STANDARD Grade N/A Identifies Plant Staffing requirements IAW TS 5.2 Verifies Rad Safety Tech position is not satisfied.

Determines that a Radiation Safety Tech is required and none are on site.

S U Comment:

CRITICAL STEP Time Stop: _____

END OF TASK

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 5 of 6 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • None required.

JPM SRO Admin 2 PALISADES NUCLEAR PLANT Page 6 of 6 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

CANDIDATE CUE SHEET INITIAL CONDITIONS:

  • 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:
  • (1) Shift Manager
  • (1) Control Room Supervisor
  • (1) Shift Engineer/Shift Technical Advisor (SE/STA)
  • (3) Nuclear Control Operators
  • (6) Nuclear Plant Operators
  • (1) Chemistry Technician
  • (1) Radiation Safety Technician (EMT)
  • Required number of Security personnel
  • At 0300 the SE/STA is taken to the hospital by the Radiation Safety Technician (EMT) due to an allergic reaction to something he has eaten.

INITIATING CUES:

You are the Shift Manager. Determine if staffing requirements are met and explain your decision and required actions, if any.

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 1 of 7 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

SRO ADMIN 3 TITLE:

DETERMINE AND PERFORM THE APPLICABLE TECHNICAL SPECIFICATION ACTIONS CANDIDATE:

EXAMINER:

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 2 of 7 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine any applicable Tech Specs and perform Admin Proc 4.11 actions to determine whether a loss of safety function exists.

Alternate Path: No Facility JPM #: N/A (new)

K/A: G2.2.22 Importance:

RO: 4.0 SRO: 4.7 K/A Statement: Knowledge of limiting conditions for operations and safety limits.

Task Standard: Determine any applicable Tech Specs and perform Admin Proc 4.11 actions to determine whether a loss of safety function exists.

Preferred Evaluation Location: Simulator

__X__

In Plant Preferred Evaluation Method:

Perform

__X__

Simulate

References:

Tech Spec LCO 3.0.6 Tech Spec LCO 3.7.5 Tech Spec LCO 3.7.6 Admin Proc 4.11 Validation Time: 15 minutes Time Critical:

NO Candidate: _______________________________

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 3 of 7 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • Technical Specifications
  • Admin Proc 4.11 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • The Plant is at 100% power.
  • A Forklift has struck the side of Condensate Storage Tank (CST).
  • CST level has dropped to ~37% and is now stable.
  • T-81 (Primary Makeup Storage Tank) is out-of-service/unavailable.

INITIATING CUES:

You are to review the initial conditions for operability and determine any applicable Technical Specifications and, if applicable, perform the actions of Admin Proc 4.11.

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 4 of 7 FEBRUARY 2017 Time Start: ______

Evaluator Cue: If applicant asks, inform the applicant that no AFW System alarms are in.

Proc.

Step TASK ELEMENT 1 STANDARD Grade 5.1.1 Determine LCO 3.7.6 is applicable due to inadequate CST level Review LCO 3.7.6 and determine LCO 3.7.6 Cond A is applicable for insufficient CST inventory.

S U Comment:

Evaluator Cue: If/when applicant attempts to verify backup water sources available to satisfy LCO 3.7.6.A.1, question applicant what the backup sources are. When applicant correctly states backup sources of Service Water and Fire Protection, inform the applicant that these sources are operable.

Proc.

Step TASK ELEMENT 2 STANDARD Grade 2.a Review and perform Admin Proc 4.11 and perform Attachment 1 Technical Specifications Job-Aid Determine LCO 3.7.6 Cond A is applicable.

S U Comment:

Evaluator Cue: Inform applicant that Admin Proc 4.11 Att 1 Steps 2.b-e are not to be performed.

Proc.

Step TASK ELEMENT 3 STANDARD Grade 5.1.2 &

5.1.3 Enter LCO 3.7.6 Cond A and apply the following required actions:

  • A.1 - Verify operability of backup water supplies w/in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after.
  • A.2 - Restore CST volume to within limit w/in 7 days Enter LCO 3.7.6 Cond A and apply the following required actions:
  • A.1 - Verify operability of backup water supplies w/in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after.
  • A.2 - Restore CST volume to within limit w/in 7 days S U Comment:

Evaluator Cue: If/when applicant attempts to verify backup water sources available to satisfy LCO 3.7.6.A.1, question applicant what the backup sources are. When applicant correctly states backup sources of Service Water and Fire Protection, inform the applicant that these sources are operable.

CRITICAL STEP: Enter and perform actions of LCO 3.7.6 Cond A.

Proc.

Step TASK ELEMENT 4 STANDARD Grade 5.2.1.a

& b Identify that the LCO 3.7.6 directs no direct entry into any supported system LCOs Identify that the LCO 3.7.6 directs no direct entry into any supported system LCOs S U Comment:

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 5 of 7 FEBRUARY 2017 Proc.

Step TASK ELEMENT 5 STANDARD Grade 5.1.4 Identify that the AFW system is a supported system of the CST using Admin Proc 4.11 Att 2 (page 6 of 11)

Determine that the AFW System is inoperable as a supported system, using Admin Proc 4.11 Att 2.

S U Comment:

Proc.

Step TASK ELEMENT 6 STANDARD Grade 5.2.1 Identify that the supported pumping system (AFW) is inoperable solely due to the supported system inoperability (insufficient CST level) and invoke LCO 3.0.6.

Applicant can use Admin Proc 4.11 Att 4 flowchart to invoke LCO 3.0.6 to LCO 3.7.5.

Determine that the AFW System is inoperable solely due to insufficient CST level and do NOT perform LCO 3.7.5 Cond A actions.

S U Comment:

CRITICAL STEP: Determine AFW System is inoperable and invoke LCO 3.0.6 such that the required actions of LCO 3.7.5 are not required to be performed.

Proc.

Step TASK ELEMENT 7 STANDARD Grade 5.3.1 Using Admin Proc 4.11 Att 3, determine neither safety function is lost.

  • Provide sufficient water & NPSH for AFW Pump Operability
  • Provide sufficient water inventory for plant cooldown Determine neither safety function is lost per Admin Proc 4.11 Att 3.

Applicant may refer to SOP-12 or EOP Supplement 19 to determine CST level must be > 10% to determine the AFW Pump low suction pressure trip seal-in feature is not enabled and sufficient NPSH remains available (System does not require venting).

S U Comment:

CRITICAL STEP: Determine neither safety function is lost.

Time Stop: _____

END OF TASK

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 6 of 7 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS None required.

JPM: SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 7 of 7 May 2009 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The Plant is at 100% power.
  • A Forklift has struck the side of Condensate Storage Tank (CST).
  • CST level has dropped to ~18% and is now stable.
  • T-81 (Primary Makeup Storage Tank) is out-of-service/unavailable.

INITIATING CUES:

You are to review the initial conditions for operability and determine any applicable Technical Specifications and, if applicable, perform the actions of Admin Proc 4.11.

JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 1 of 7 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

SRO ADMIN 4 TITLE:

RESPOND TO STACK EFFLUENT RADIATION ALARMS CANDIDATE:

EXAMINER:

JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 2 of 7 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Respond to Stack Effluent Radiation Alarms Alternate Path: N/A Facility JPM #: 2009 Audit K/A: G2.3.13 Importance:

RO: 3.4 SRO: 3.8 K/A Statement: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Task Standard: RANGE selector switch on Remote Control Panel JIC-2301B on C-11A placed in HIGH RANGE position and ODCM Appendix A Table A-1 Action 3 entered.

Preferred Evaluation Location: Simulator

__X__

In Plant Preferred Evaluation Method:

Perform

__X__

Simulate

References:

ARP-33, Auxiliary Systems Scheme EK-02 (C-11A)

SOP-38, Gaseous Process Monitoring System Validation Time: 11 minutes Time Critical:

NO Candidate: _______________________________

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 3 of 7 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • ARP-33, Auxiliary Systems Scheme EK-02 (C-11A)
  • SOP-38, Gaseous Process Monitoring System Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • The Plant is at 100% power.
  • Alarm EK-0231, STACK EFF RAD C-169/C-172 FAIL/TROUBLE has just annunciated.

INITIATING CUES:

The CRS has directed you to respond to the alarms on Panel C-11A.

JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 4 of 7 FEBRUARY 2017 Time Start: ______

Proc.

Step TASK ELEMENT 1 STANDARD Grade ARP-33 located for EK-0231 ARP-33 in hand S U Comment:

Proc.

Step TASK ELEMENT 2 STANDARD Grade ARP-33 window 31 CHECK RIAs for failed channel.

CHECK the following on RGEM Control Panel on back of C-11A:

VERIFY C-169 power switch is ON VERIFY sample pump operating VERIFY Low Flow alarm clear RGEM Panel checked.

RIA-2326 determined to be failed low.

S U Comment:

CRITICAL STEP: Determine correct rad monitor.

Proc.

Step TASK ELEMENT 7 STANDARD Grade ARP-33 window 31 REFER TO Palisades Offsite Dose Calculation Manual, Table 1-1.

ODCM Table 1-1 located S U Comment:

Evaluator Cue: When applicant informs CRS, then direct candidate to consult ODCM for applicable actions.

JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 5 of 7 FEBRUARY 2017 Proc.

Step TASK ELEMENT 8 STANDARD Grade ODCM Determine applicable actions from ODCM Table 1-1.

Candidate recognizes that ODCM Table 1-1 Action 3 determined to be applicable:

With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Applicant may inform Chemistry of need to perform grab samples.

S U Comment:

Evaluator Cue: Act as CRS and acknowledge the report.

Evaluator Cue: As Chemistry, acknowledge report to take grab samples.

CRITICAL STEP: Determine ODCM Table 1-1 Action 3 is applicable.

Time Stop: ______

END OF TASK

JPM: SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 6 of 7 May 2009 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-150 Insert malfunction RM08V (RIA-2326 Low Radiation) on PID RM06 Acknowledge alarms on Panel C-11A.

JPM: SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 7 of 7 May 2009 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The Plant is at 100% power.
  • Alarm EK-0231, STACK EFF RAD C-169/C-172 FAIL/TROUBLE has just annunciated.

INITIATING CUES:

The CRS has directed you to respond to the alarms on Panel C-11A.

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 1 of 10 FEBRUARY 2017 PALISADES 2017 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:

SRO ADMIN 5 TITLE:

DETERMINE PROTECTIVE ACTION RECOMMENDATIONS (PARS) FOR AN EVENT CANDIDATE:

EXAMINER:

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 2 of 10 FEBRUARY 2017 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine the applicable PARs for an event Alternate Path: No Facility JPM #: N/A (new)

K/A:

G2.4.44 Importance:

RO:

2.4 SRO:

4.4 K/A Statement: Knowledge of emergency plan protective action recommendations Task Standard: Given a change in plant and meteorological conditions, determine PARs; evacuation of Areas 1, 2, 3 and lake area 6 within 15 minutes.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

SEP Supp 1, Site Emergency Plan Supplement 1 - EAL Wall Charts EI-3, Communications and Notifications EI-6.7, Plant Site Meteorological System EI-6.13, Protective Action Recommendations for Offsite Populations Validation Time: 6 minutes Time Critical:

YES Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 3 of 10 FEBRUARY 2017 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SEP SUP 1, Site Emergency Plan Supplement 1 - EAL Wall Charts EI-3, Communications and Notifications EI-6.7, Plant Site Meteorological System, Attachment 1 EI-6.13, Protective Action Recommendations for Offsite Population EI-3, Attachment 1 completed for notification #1 Completed Dose Assessment form Also see Simulator Operator Instructions (later page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

  • An event occurred which resulted in the declaration of General Emergency FG1.1.
  • A Loss of the Primary Coolant System (PCS)
  • A Loss of Containment (CNMT)
  • A Potential Loss of the Fuel Clad Barrier (FC)
  • Initial PARs resulted in an Initial Evacuation of Area 1 and lake area 6.

INITIATING CUES:

You are the Shift Manager (acting as the Emergency Plant Manager). You are to determine PARs and complete the Palisades Event Notification Form for the change in rapidly deteriorating plant / meteorological conditions, as follows:

  • Field Monitoring Teams report a dose of 1.3 R/hr at the site boundary.
  • Initial dose assessment reviews support the Field Monitoring Teams survey.
  • Meteorological data as given on EI-6.7 Att 1, Plant Site Meteorological System Worksheet.

This JPM is Time Critical.

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 4 of 10 FEBRUARY 2017 Time Start: _____

Proc.Step TASK ELEMENT 1 STANDARD Grade EI-6.13 Refers to EI-6.13, Protective Action Recommendations for Offsite Populations Obtain EI-6.13 and determine that Att 2 must be used for FOLLOW UP PARs to determine if a change is warranted.

S U Comment:

Start Time for Determination of PARs:_________

Evaluator Cue: Candidate may use EI-6.13 Att 1 / 2 Wall-Chart placard or provide working copy of EI-6.13 in its entirety.

Proc.Step TASK ELEMENT 2 STANDARD Grade EI-6.13 Att 2 Determines additional FOLLOW UP PARs (0 to 5 miles)

Determines Initial PAR has been made.

Determines conditions requiring classification of a GE are met.

Determines Rapidly Progressing Severe Accident was NOT declared during the Initial PAR evaluation (initial conditions stated Initial Evacuation of Area 1 and lake area 6 only).

Determines HG4.1 or HG4.2 not declared.

Determines Containment HRRMs not <

20,000 R/hr.

Determines FOLLOW UP PARS are to be applied per Column 3, FOLLOW UP.

  • Evacuates Areas 1,2,3 and lake area 6 S U Comment:

Evaluator Note: Applicant may incorrectly diagnose that a Rapidly Progressing Severe Accident was progressing based on given conditions (1.3 R/hr at the site boundary) in the initiating cue, which would result in evacuating unnecessary areas. These conditions were not present at the time of the INITIAL PAR evaluation and should not be considered for FOLLOW UP PARs.

CRITICAL STEP

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 5 of 10 FEBRUARY 2017 Proc.Step TASK ELEMENT 3 STANDARD Grade EI-6.13 Att 2 Determines additional DOSE PARs (0 to 5 miles)

Using plant/meteorological conditions from the initiating cue, determine that PARs must be expanded based on dose assessment to areas in the 10 mile EPZ that exceed PAGs Uses 0-5 miles as the initiating cue stated the site boundary.

Determines DOSE PARs are to be applied per Column 3, DOSE.

  • Evacuates Areas 1,2,3 and lake area 6.

S U Comment:

End Time for PAR:_________

Evaluator Note: End Time for PARs should be when applicant correctly determines Evacuation of Areas 1, 2, 3 and lake area 6 per EI-6.13 Att 2, Column 3 based on FOLLOW UP and DOSE sections.

Evaluator Note: Applicant may incorrectly chose to use the DOSE column 4 (5 to 10 miles), which would result in evacuating unnecessary areas.

CRITICAL STEP - must be performed within 15 minutes of the start of the JPM

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 6 of 10 FEBRUARY 2017 Proc.Step TASK ELEMENT 4 STANDARD Grade EI-3 Att 1 Completes filling out Palisades Event Notification Form.

Palisades Event Notification Form completely filled per attached KEY AND form is approved (Candidate signature/initials, date, and time entered at bottom of form)

  • S U Comment:

Evaluator Note: EI-3, Attachment 2, "Palisades Event Technical Data Sheet" is NOT required during this JPM.

Evaluator Note: If JPM is conducted in the Simulator, then Candidate may use computer on back-bar of Control Room island area to complete and print this form.

Evaluator Note: KEY is attached to this JPM.

  • The following are the critical parts of this step:

General Emergency is checked in "current classification" section Date and time filled in "current classification" section FG1.1 filled in "reason for classification" section OR Fission Product Barrier Degradation checked in "reason for classification" section YES checked in Radiological Release in Progress Areas 1, 2, 3 and lake area 6 checked for Evacuation of Areas YES checked on PARs based on dose projections CRITICAL STEP Time Stop: _____

END OF TASK

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 7 of 10 FEBRUARY 2017 ANSWER KEY PALISADES EVENT NOTIFICATION FORM Actual Event Drill Plant Contact Information Nuclear Power Plant: __Palisades_______________________________________

Plant Communicator: __________________ Time of Communication: V.B. ______

S.O.M. ______

NRC ______ Plant Message Number Calling From:

Control Room TSC EOF Other______

Call Back Telephone Number: _____________________________________________

Current Classification Unusual Event Alert Site Area Emergency General Emergency Termination This Classification was declared as of: Date: Today Time: Within 15 minutes from start of JPM Reason for Classification Abnormal Rad Levels / Radiological Effluent System Malfunctions Hazards and Other Conditions Affecting Cold Shutdown / Refueling System Malfunction Plant Safety Independent Spent Fuel Storage Installation Events Fission Product Barrier Degradation IC Number: FG1.1 Radiological Release in Progress Due to Event Yes No Protective Action Recommendations None Recommend the following protective actions; implement the State of Michigan KI plan and all other areas monitor and prepare.

Evacuation of Areas(s):

1 2

3 4

5 In-Place Shelter of Area(s):

1 2

3 4

5 Clear Lake Area(s):

6 (L) 7 (L)

PAR based on Dose Calculations (complete and provide EMD 32b)

YES NO PARs beyond 10 Miles (complete and provide EMD 32b)

YES NO Meteorological Data Wind Direction (degrees): From 260 To 80 Wind Speed (MPH): 19 Stability Class: B Precipitation:

Yes No 2

Proc No EI-3 Attachment 1

Revision 32 Page 1 of 1

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 8 of 10 FEBRUARY 2017 Emergency Director Approval: ________________________________ Date: _________ Time: ________

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 9 of 10 FEBRUARY 2017 SIMULATOR OPERATOR INSTRUCTIONS

  • No Simulator setup required.
  • Prepare EI-3, Attachment 1 completed for notification #1
  • Prepare Dose Assessment form
  • Prepare EI-6.7 Attachment 1 with the following data and then sign and date form:

o Wind Speed is 19 mph o Wind Direction is from 260 degrees o Stablity Class = B

  • It is preferred that this JPM be done separately from the simulator. If, by chance, candidate IS in the simulator while doing this JPM, THEN ensure the IC does NOT have a release in progress.

ENSURE ALL DATA IS CLEARED FROM EP NOTIFICATION COMPUTER ON BACK-BAR OF CRS ISLAND PRIOR TO NEXT USE OF THIS JPM.

JPM SRO ADMIN 5 PALISADES NUCLEAR PLANT Page 10 of 10 FEBRUARY 2017 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • An event occurred which resulted in the declaration of General Emergency FG1.1.
  • A Loss of the Primary Coolant System (PCS)
  • A Loss of Containment (CNMT)
  • A Potential Loss of the Fuel Clad Barrier (FC)
  • Initial PARs resulted in an Initial Evacuation of Area 1 and lake area 6.

INITIATING CUES:

You are the Shift Manager (acting as the Emergency Plant Manager). You are to determine PARs and complete the Palisades Event Notification Form for the change in rapidly deteriorating plant / meteorological conditions, as follows:

  • Field Monitoring Teams report a dose of 1.3 R/hr at the site boundary.
  • Initial dose assessment reviews support the Field Monitoring Teams survey.
  • Meteorological data as given on EI-6.7 Att 1, Plant Site Meteorological System Worksheet.

This JPM is Time Critical.

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