ML100690431

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2009 Palisades Proposed Admin JPMs
ML100690431
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/25/2009
From: Valos N
NRC/RGN-III/DRS/OLB
To:
Entergy Nuclear Operations
References
Download: ML100690431 (66)


Text

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO ADMIN 1a TITLE: DETERMINE FEEDWATER RESERVE INVENTORY CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO/SRO ADMIN 1a JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Feedwater Reserve Inventory Alternate Path: N/A Facility JPM #: Modified RO-A.1a 2008 AUDIT K/A: 2.1.25 Importance: RO: 3.9 SRO: 4.2 K/A Statement: Ability to interpret reference materials such as graphs, curves, tables, etc.

Task Standard: Feedwater reserve inventory calculated to last 3.9 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EOP Supplement 2, PCS Cooldown Strategy Validation Time: 10 minutes Time Critical: NO Candidate: ___________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 MAY 2009

JPM RO/SRO ADMIN 1a EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EOP Supplement 2, PCS Cooldown Strategy 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:

With the plant at 100% power, a loss of offsite power occurs. The reactor was manually tripped and the operators transitioned to EOP-8.0. The following plant conditions exist:

  • Offsite power is not expected to be restored for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
  • Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
  • It is 30 minutes after shutdown
  • T-81 gravity feed to T-2 is not aligned
  • T-2 is at 86%, T-81 is at 85%, and T-939 is at 58%
  • Cold leg temperatures are stable at 535°F INITIATING CUES:

The CRS has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

Calculation of minimum cooldown rate (section 5.0 step 6) is NOT required at this time.

PALISADES NUCLEAR PLANT Page 3 of 9 MAY 2009

JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 1 STANDARD Grade Locate EOP Supplement 2, PCS n/a EOP Supplement 2 LOCATED S U Cooldown Strategy Comment:

Evaluator: Provides a working copy of EOP Supplement 2.

Proc. Step TASK ELEMENT 2 STANDARD Grade CONDENSATE STORAGE TANK T-2 T-2 inventory = 94,000 gallons RECORDED 1.1 DETERMINE AND RECORD Condensate S U Storage Tank T-2 level using the T-2 (93,000 to 95,000 allowed) inventory curve Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade DEMINERALIZED WATER TANK T-939 IF any of the following conditions exist:

2.1 DETERMINES T-939 water is NOT available S U THEN Demineralized Water Tank T-939 is available Comment:

NOTE: Loss of Bus 13 combined with loss of Bus 1E (due to loss of offsite power) results in inability to power P-936 to transfer T-936 water to T-2.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 9 MAY 2009

JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 4 STANDARD Grade If any of the following conditions Determines T-81 is NOT available 3.1 exist..THEN Primary System Makeup S U Tank T-81 is available.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade ADD the available tank inventories:

Total Inventory = 94,000 gallons RECORDED 4.1 (Step 1.1 T-2) + (Step 2.2 T-939) = (Total S U (93,000 to 95,000 allowed) inventory)

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade DETERMINE AND RECORD present TC Initial = 535 °F RECORDED (given in initial 5.1 S U highest PCS Loop TC (TC Initial) conditions)

Comment:

Proc. Step TASK ELEMENT 7 STANDARD Grade DETERMINE AND RECORD inventory Required Sensible Heat Removal Inventory =

required to remove sensible heat using TC 42,000 gallons RECORDED 5.2 S U Initial temperature and the Sensible Heat Removal curve. (41,000 to 43,000 allowed)

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 9 MAY 2009

JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 8 STANDARD Grade SUBTRACT Step 5.2 results from Step 4.1 Inventory Available to remove decay heat =

results: 52,000 gallons RECORDED 5.3 S U (Step 4.1 Total FW) - (Step 5.2 Sensible (94,000 - 42,000 = 52,000)

Heat) = (Inventory for decay heat removal) (50,000 to 54,000 allowed)

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 9 STANDARD Grade DETERMINE AND RECORD the time interval available for heat removal using the following:

Applicable Decay Heat Removal curve Time interval available for heat removal for the number of PCPs operating = 4.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RECORDED 5.4 S U Graph line for elapsed time after (Interpolation may be used) shutdown (3.7 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> allowed)

Amount of inventory available to remove decay heat (graph)

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 9 MAY 2009

JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 10 STANDARD Grade If the time interval available for heat removal is less than eight hours, THEN PERFORM the following: Shift Manager Informed that time interval 5.5.a a. Inform the Shift Manager of the available for heat removal = 4.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> S U available interval and that additional (3.7 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> allowed) inventory sources are required.

Comment:

EVALUATOR: Notify candidate that the Shift Manager will have someone else identify potential inventory sources that can be made available in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per step 5.b of section 5.0.

Proc. Step TASK ELEMENT 11 STANDARD Grade Notify the CRS EOP Supplement 2 is complete [reported time interval available CRS NOTIFIED that EOP Supplement 2 task is n/a for heat removal and available inventory complete S U sources]

Comment:

Evaluator: If notified as CRS, Acknowledge.

END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 MAY 2009

JPM RO/SRO ADMIN 1a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 8 of 9 MAY 2009

JPM RO/SRO ADMIN 1a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

With the plant at 100% power, a loss of offsite power occurs. The reactor was manually tripped and the operators transitioned to EOP-8.0. The following plant conditions exist:

  • Offsite power is not expected to be restored for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
  • Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
  • It is 30 minutes after shutdown
  • T-81 gravity feed to T-2 is not aligned
  • T-2 is at 86%, T-81 is at 85%, and T-939 is at 58%
  • Cold leg temperatures are stable at 535°F INITIATING CUES:

The CRS has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

Calculation of minimum cooldown rate (section 5.0 step 6) is NOT required at this time.

PALISADES NUCLEAR PLANT Page 9 of 9 MAY 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 1b TITLE: PERFORM A PCS HEATUP DETERMINATION CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Perform PCS Heatup Determination Alternate Path: N/A Facility JPM #: RO-A.1b 2008AUDIT K/A: 2.1.25 Importance: RO: 3.9 SRO: 4.2 K/A Statement: Ability to interpret reference materials such as graphs, curves, tables etc.

Task Standard: Allowable Shutdown Cooling outage time calculated to be 28 minutes (27 minutes to 29 minutes).

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SOP-3, Safety Injection and Shutdown Cooling System ONP-17, Loss of Shutdown Cooling Validation Time: 15 minutes Time Critical: NO Candidate: ________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 May 2009

JPM RO ADMIN 1b EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-3, Safety Injection and Shutdown Cooling System ONP-17, Loss of Shutdown Cooling 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:

  • Ten days after a plant shutdown, PCS temperature is 114ºF
  • The Reactor cavity is flooded to a level of 629'
  • The Pressurizer manway is removed
  • Shutdown Cooling is in operation, but must be shutdown for the maximum time allowable INITIATING CUES:

The CRS directs you to determine how long (in minutes) Shutdown Cooling may be secured in accordance with SOP-3, Section 7.3.7.

PALISADES NUCLEAR PLANT Page 3 of 8 May 2009

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 1 STANDARD Grade Locates SOP-3, Safety Injection And n/a Shutdown Cooling System, Section 7.3.7, Section 7.3.7 of SOP-3 LOCATED S U PCS Heatup Rate Determination Comment:

Evaluator: Provides a working copy of SOP-3, section 7.3.7.

Proc. Step TASK ELEMENT 2 STANDARD Grade DETERMINE Approximate Time to 200°F time from appropriate curve in ONP-17, Attachment 1, Approximate Time to 200°F 7.3.7a Loss of Shutdown Cooling, for S U Curves, of ONP-17 LOCATED existing/anticipated PCS conditions and convert to hours.

Comment:

Evaluator: Provide a working copy of ONP-17, Attachment 1.

Proc. Step TASK ELEMENT 3 STANDARD Grade (ONP-DETERMINE PCS level using all available 17, PCS level 629 feet (given in initial conditions) S U indications.

Att.1) 1.

Comment:

Proc. Step TASK ELEMENT 4 STANDARD Grade (ONP-DETERMINE PCS temperature using any PCS temperature 114°F (given in initial 17, S U of the following: conditions)

Att.1) 2.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 8 May 2009

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 5 STANDARD Grade Page #8 of Attachment 1 REFERED TO:

Uses Refueling Cavity Flooded to 629' to determine time to 200ºF (ONP17, REFER TO appropriate page in this USES "10 Days" (time after reactor shutdown) S U Att.1) 5. attachment for PCS conditions and 114ºF point (initial PCS temperature) and DETERMINES time to 200ºF is ~2 hours Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade DETERMINE PCS heatup rate as follows:

7.3.7b (200°F - TINITIAL)_______________ Heatup rate CALCULATED to be ~43ºF / hour S U Approximate Time to 200°F (Hours)

Comment:

NOTE: Heatup rate is calculated by dividing 86ºF (200ºF - 114ºF) by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade DETERMINE the allowable Shutdown CALCULATES allowable Shutdown Cooling 7.3.7c. Cooling outage time (heatup rate > S U outage time to be 28 minutes (27 - 29 minutes).

20°F/Hr)

Comment:

NOTE: Allowable outage time calculated by dividing 20ºF (maximum allowed heatup) by 43ºF / hour (previously calculated heatup rate) and converting to minutes.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 May 2009

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 8 STANDARD Grade Notifies the CRS that securing Shutdown CRS NOTIFIED Shutdown Cooling can be n/a Cooling has been calculated at S U secured for approximately 28 minutes.

approximately 28 minutes.

Comment:

Evaluator: If notified by Operator of time for securing Shutdown Cooling, Acknowledge.

END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 May 2009

JPM RO ADMIN 1b SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 7 of 8 May 2009

JPM RO ADMIN 1b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • Ten days after a plant shutdown, PCS temperature is 114ºF
  • The Reactor cavity is flooded to a level of 629'
  • The Pressurizer manway is removed
  • Shutdown Cooling is in operation, but must be shutdown for the maximum time allowable INITIATING CUES:

The CRS directs you to determine how long (in minutes) Shutdown Cooling may be secured in accordance with SOP-3, Section 7.3.7.

PALISADES NUCLEAR PLANT Page 8 of 8 May 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 1b TITLE: MONITOR PCS HEATUP/COOLDOWN WITH THE PPC CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Operate the Palisades Plant Computer System Alternate Path: N/A Facility JPM #: PPC-JPM-02 K/A: 2.1.19 Importance: RO: 3.9 SRO: 3.8 K/A Statement: Ability to use plant computers to evaluate system or component status.

Task Standard: Commence monitoring a PCS heatup/cooldown using Page 372 SDC 15 Minute Rate Trend, of the PPC.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

GOP-2, MODE 5 To MODE 3 525°F PO-2, PCS Heatup/Cooldown Operations Validation Time: 10 minutes Time Critical: NO Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 May 2009

JPM SRO ADMIN 1b EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • PO-2, PCS Heatup/Cooldown Operations 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 Plant refueling has just been completed.
  • GCL-2, Mode 5 to Mode 3 525°F Checklist is in progress.
  • Two PCPs are in service.
  • Technical Specification Surveillance Procedure PO-2, PCS Heatup/Cooldown Operations, has just been authorized by the CRS.
  • No equipment is out of service, all systems are OPERABLE.

INITIATING CUES:

  • The CRS directs you to setup for monitoring a PCS heatup via the PPC, utilizing Page 361 PCS 15 Minute Rate Trend per PO-2, step 5.1.1.

PALISADES NUCLEAR PLANT Page 3 of 7 May 2009

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 1 STANDARD Grade Locate PO-2, PCS Heatup/Cooldown n/a Step 5.1.1 of PO-2 LOCATED S U Operations, step 5.1.1 Comment:

EVALUATOR: Provide Operator a working copy of PO-2, step 5.1.1.

Proc. Step TASK ELEMENT 2 STANDARD Grade Main menu screen SELECTED.

SELECT the Operator Mode Support 5.1.1b Operator Mode Support screen SELECTED S U screen from the main menu from main menu screen.

Comment:

EVALUATOR NOTE: Operator may go straight to PPC page 361 (task element 3).

Proc. Step TASK ELEMENT 3 STANDARD Grade SELECT any of the following, as applicable, to monitor PCS heatup/cooldown rate: Page 361 PCS 15 Minute Trend page 5.1.1c S U SELECTED Page 361 PCS 15 Minute Rate Trend Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade START 15 minute automatic reports as 5.1.1d follows: F7 key HCR Reports DEPRESSED S U DEPRESS F7 key HCR Reports Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 May 2009

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 5 STANDARD Grade START 15 minute automatic reports as follows:

5.1.1d Cyclic Printout Enabled SELECTED S U SELECT the Cyclic Printout Enabled response Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade START 15 minute automatic reports as follows: One (1) or Y is TYPED AND Update Hardkey is 5.1.1d S U TYPE a one (1) AND DEPRESS the DEPRESSED.

UPDATE Hardkey to start the reports.

Comment:

NOTE: The Heatup/Cooldown print out is on a 15 minute timer that is always running.

When the printout is enabled, the next print timeout could be anywhere from 1 second to 15 minutes later.

Evaluator: If Operator checks that the printout is printing and it is not, STATE that the hardcopy printout is not required and to continue.

CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade Notify the CRS that heatup/cooldown CRS notified that heatup/cooldown monitoring by 5.1.1d monitoring of the SDC by PPC, Page 361 is S U PPC in progress in progress Comment:

EVALUATOR: If notified as CRS that PPC monitoring is in progress, Acknowledge.

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 May 2009

JPM SRO ADMIN 1b SIMULATOR OPERATOR INSTRUCTIONS IC-3, Ready to come off S/D Cooling.

PALISADES NUCLEAR PLANT Page 6 of 7 May 2009

JPM SRO ADMIN 1b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • A Plant refueling has just been completed.
  • GCL-2, Mode 5 to Mode 3 525°F Checklist is in progress.
  • Two PCPs are in service.
  • Technical Specification Surveillance Procedure PO-2, PCS Heatup/Cooldown Operations, has just been authorized by the CRS.
  • No equipment is out of service, all systems are OPERABLE.

INITIATING CUES:

The CRS directs you to setup for monitoring a PCS heatup via the PPC, utilizing Page 361 PCS 15 Minute Rate Trend per PO-2, step 5.1.1.

PALISADES NUCLEAR PLANT Page 7 of 7 May 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 2 TITLE: PERFORM SHO-1 SURVEILLANCE CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Complete the SHO-1 Surveillance Alternate Path: N/A Facility JPM #: RO-A.2 2008 AUDIT K/A: 2.2.12 Importance: RO: 3.7 SRO: 4.1 K/A Statement: Knowledge of surveillance procedures Task Standard: Identification of two out-of-spec readings during the performance of SHO-1 for Wide Range Nuclear Instruments and B Steam Generator Pressure Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SHO-1, Operators Shift Items Modes 1, 2, 3, and 4 Validation Time: 20 minutes Time Critical: NO Candidate: __________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 11 May 2009

JPM RO ADMIN 2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • SHO-1, Attachment 1, Shift Surveillance Data Sheet
  • Red ink pen 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.
  • It is Monday, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.1 through and including 5.1.14 on pages 1,2,3,4, and 5 for A Shift. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 3 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Partially completed copy of SHO-1 located LOCATES copy of partially completed SHO-1 S U Comment:

Evaluator: Provides Operator with a partially completed copy of SHO-1.

Proc. Step TASK ELEMENT 2 STANDARD Grade CHECKS all channels agree within 1%

Power Range Nuclear Instrumentation:

RECORDS readings in Shift A Readings 5.1.1 Record data and check all channels agree S U column within 1%

INITIALS "RECRD BY" Comment:

NOTE: Surveillance steps may be performed in any order.

Proc. Step TASK ELEMENT 3 STANDARD Grade CHECKS all channels agree within 1%

Thermal Margin Monitor T Power:

RECORDS readings in Shift A Readings 5.1.2 Record data and check all channels agree S U column within 1%

INITIALS "RECRD BY" Comment:

PALISADES NUCLEAR PLANT Page 4 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 4 STANDARD Grade Thermal Margin Monitor Functions, NI/T Power Deviation Meter (C-27): CHECKS NI/T and TMM Primary Screens updating Check NI/T Comparator varying as 5.1.3 S U expected for changes between NI/T RECORDS a in Shift A Readings column Power INITIALS RECRD BY Check TMM Primary Screens updating Comment:

Proc. Step TASK ELEMENT 5 STANDARD Grade CHECKS TMM System Status Screen Power Axial Shape Index: Density status OK 5.1.4 Check TMM System Status Screen S U RECORDS a in Shift A Readings column Power Density status OK INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade CHECKS TMM System Status Screen TC PCS Cold Leg Temperature: < 543.5°F Check TMM System Status Screen TC Check TMM System Status Screen Trip 5.1.5 <543.5°F Status Box indicates TC: OK S U Check TMM System Status Screen Trip RECORDS a in Shift A Readings column Status Box indicates TC: OK INITIALS RECRD BY Comment:

PALISADES NUCLEAR PLANT Page 5 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 7 STANDARD Grade Wide Range Nuclear Instrumentation (NIs): CHECKS data within 11/2 decades 5.1.6 S U Record data and check NIs agree within RECORDS data in Shift A Readings column 11/2 decades Comment:

NOTE: Data for NI 1/3 is NOT within 11/2 decades Proc. Step TASK ELEMENT 8 STANDARD Grade Wide Range Nuclear Instrumentation DETERMINES NI 1/3 not within 11/2 decades (NIs): CIRCLES in RED NI-1/3A reading 5.1.6 S U Determine out of tolerance data for NI 1/3 INITIALS RECRD BY

  • Identifies out of tolerance reading May NOTIFY CRS of the out of spec reading Comment:

Evaluator Cue: If notified as the CRS of the out of spec reading: Acknowledge. If asked if the surveillance should continue: RESPOND to continue with the surveillance.

  • NOTE: INITIALS RECRD BY is not part of the critical step CRITICAL STEP Proc. Step TASK ELEMENT 9 STANDARD Grade CHECKS no Deviation lights lit for NI 5, 6, 7 Quadrant Power Tilt: and 8 Check NI Channels 5, 6, 7 and 8 VERIFIES no alarms (EK-06C3) 5.1.7 S U Deviation lights not lit RECORDS a in Shift A Readings column No alarms (EK-06C3)

INITIALS RECRD BY Comment:

PALISADES NUCLEAR PLANT Page 6 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 10 STANDARD Grade Steam Generator Pressure: RECORDS S/G pressures in Shift A 5.1.8 Readings column S U Record data and check all channels for each S/G agree within 40 psi CHECKS S/G pressures within 40 psi Comment:

NOTE: Data for PIC-0752C indication for B S/G is > 40 psi out of agreement.

Proc. Step TASK ELEMENT 11 STANDARD Grade DETERMINES PIC-0752C indication for B S/G is >40 psi out of agreement with the other three for B S/G Steam Generator Pressure:

5.1.8 CIRCLES in RED at least PIC-0752C reading S U Record data and check all channels for (may circle all four) each S/G agree within 40 psi

  • INITIALS RECRD BY May NOTIFY CRS of the out of spec reading Comment:

Evaluator Cue: If notified as the CRS of the out of spec reading: Acknowledge. If asked if the surveillance should continue: RESPOND to continue with the surveillance.

  • NOTE: INITIALS RECRD BY is not part of the critical step CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade RECORDS S/G levels in Shift A Readings Steam Generator Level: column 5.1.9 Record data and check all channels for S U CHECKS S/G levels within 4%

each S/G agree within 4%

INITIALS RECRD BY Comment:

PALISADES NUCLEAR PLANT Page 7 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 13 STANDARD Grade RECORDS PCS flow in Shift A Readings Primary Coolant Flow: column 5.1.10 Record data and check all channels agree S U CHECKS PCS flows within 5%

within 5%

INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 14 STANDARD Grade PZR Code Safety Relief Valve Position RECORDS PZR Safety Relief temperatures Indication Temperature: readings ranging from approx. 100° to 120°F in 5.1.11 Shift A Readings column S U Record data and check temperatures are consistent with plant conditions INITIALS RECRD BY Comment:

Note: These reading are ambient and consistent with plant conditions.

Proc. Step TASK ELEMENT 15 STANDARD Grade PORV Position Indication Temperature:

Record data and check temperatures are RECORDS N/A in this block (does not apply 5.1.12 S U consistent with plant conditions and other for plant conditions)

PORV indications Comment:

PALISADES NUCLEAR PLANT Page 8 of 11 May 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 16 STANDARD Grade RECORDS PZR pressures in Shift A Readings column PZR Pressure:

CHECKS pressures within 40 psia 5.1.13 Record data and check all agree within S U 40 psi and Mode 1 pressure 2010 psia Checks PZR pressure between 2010 psia and and 2100 psia 2100 psia INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 17 STANDARD Grade Thermal Margin Low Pressure Trip RECORDS TMM low pressures in Shift A Channels: Readings column Record data and: CHECKS Channels A and C agree within 5.1.14 85 psi S U Check Channels A and C agree within 85 psi CHECKS Channels B and D agree within 85 psi Check Channels B and D agree within 85 psi INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 18 STANDARD Grade Return completed SHO-1 to CRS Completed SHO-1 RETURNED to the CRS n/a Inform CRS of out of spec readings (if not CRS INFORMED of the out of spec readings S U already done) (if not already done)

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 May 2009

JPM RO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS

  • Reset to any full power IC.
  • Insert the following or use CAE file o OVERRIDE NI-1/3A Wide Range Log Meter indication to failed low (NI PWR-1 @ 0.75) o OVERRIDE PIC-0752C to indicate ~860# (Value = 0.71) o OVRD NI-4-PWR-1 @ 1.0.
  • Ensure "A" Channel TMM VHPT setpoint is at normal value.
  • Ensure NI @ 100.1%, i.e., accurate.
  • Ensure copies of SHO-1, Attachment 1, page 1, 2, 3, 4, and 5 are available with Section 5.1.14 grayed out.
  • Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision.

PALISADES NUCLEAR PLANT Page 10 of 11 May 2009

JPM RO ADMIN 2 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The plant is at 100% power
  • It is Monday, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.1 through and including 5.1.14 on pages 1,2,3,4, and 5 for A Shift. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 11 of 11 May 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 2 TITLE: REVIEW SHO-1 SURVEILLANCE CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Conduct Surveillance Testing Alternate Path: N/A Facility JPM #: NEW K/A: 2.2.12 Importance: RO: 3.7 SRO: 4.1 K/A Statement: Knowledge of surveillance procedures Task Standard: Identification of two out-of-spec readings during the performance of SHO-1 for Wide Range Nuclear Instrumentation and B Steam Generator Pressure AND the identification of the appropriate Technical Specification LCO action statement entries due to the out-of-spec readings.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SHO-1, Operators Shift Items Modes 1, 2, 3, and 4 Validation Time: 15 minutes Time Critical: NO Candidate: _________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 MAY 2009

JPM SRO ADMIN 2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Completed SHO-1, Attachment 1, Shift Surveillance Data Sheet for Monday Technical Specifications Technical Specifications Bases 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.
  • It is Monday, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.
  • You are an on-shift SRO.
  • SHO-1, Shift Surveillance Data Sheet, was completed at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.
  • The plant is in Mode 1.

INITIATING CUES:

  • The Shift Manager directs you to complete a supervisory review of completed SHO-1 in accordance with step 5.3 of SHO-1.

Evaluator Note: Provide candidate with completed SHO-1 for Monday with one data point for S/G Pressure and one for NI-1/3A are below the acceptance range. Do NOT circle the readings in red. Bad data should be for 'C' shift only.

PALISADES NUCLEAR PLANT Page 3 of 7 MAY 2009

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Partially completed copy of SHO-1 located LOCATES copy of partially completed SHO-1 S U Comment:

Evaluator: Provides Operator with a copy of SHO-1 completed for Monday (all three shifts).

Proc. Step TASK ELEMENT 2 STANDARD Grade At the end of each day, an On Shift SRO shall review the data sheets applicable to that day for REVIEW SHO-1 Monday entries to ensure completion of applicable items and ensure 5.3.1 all applicable components have been proper disposition of off-normal items. This is S U inspected. documented by sign-off on Attachment 1, "Shift Surveillance Data Sheet."

Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade Wide Range Nuclear Instrumentation DETERMINES NI 1/3 not within 11/2 decades (NIs):

5.1.6 CIRCLES in RED NI-1/3A entry for C-shift S U Determine out of tolerance data for NI 1/3 May NOTIFY CRS of the out of spec reading Identifies out of tolerance entry for A-shift Comment:

Evaluator Cue: If notified as the CRS of the out of spec reading: Acknowledge. If asked if the surveillance review should continue: RESPOND to continue with the surveillance review.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 MAY 2009

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 4 STANDARD Grade DETERMINES PIC-0752C indication for B S/G is >40 psi out of agreement with the other Steam Generator Pressure: three for B S/G for C-shift.

5.1.8 Reviews data and checks all channels for S U CIRCLES in RED PIC-0752C reading (may each S/G agree within 40 psi circle others as well)

May NOTIFY CRS of the out of spec reading Comment:

Evaluator Cue: If notified as the CRS of the out of spec reading: Acknowledge. If asked if the surveillance review should continue: RESPOND to continue with the surveillance review.

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade Attachment 1 5.3 Reviewed: space signed.

The following TS Conditions are identified for the inoperable NI instrumentation:

At the end of each day, an On Shift SRO

  • LCO 3.3.1.B that day for completion of applicable 5.3 items and ensure proper disposition of The following TS Conditions are identified for S U off-normal items. This is documented by the inoperable S/G pressure instrument:

sign-off on Attachment 1, "Shift

  • LCO 3.3.1.A LCO 3.3.9.A MAY be identified for the inoperable NI instrumentation for LCO Annex entry (since it applies in MODES 3, 4 and 5):

Comment:

Evaluator Cue: If asked as the CRS to disposition the out of spec readings:

Acknowledge and inform candidate that they need to determine proper disposition of the off-normal items.

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 MAY 2009

JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS IF Simulator is used for conducting this JPM, then perform the following:

  • Reset to any full power IC.
  • Insert the following or use CAE file o OVERRIDE NI-1/3A Wide Range Log Meter indication to failed low (NI-3 PWR-1 @ 0.75) o OVERRIDE PIC-0752C to indicate ~860# (Value = 0.71) o OVRD NI-4-PWR-1 @ 1.0.
  • Ensure "A" Channel TMM VHPT setpoint is at normal value.
  • Ensure NI @ 100.1%, i.e., accurate.
  • Ensure copies of SHO-1, Attachment 1, page 1, 2, 3, 4, and 5 are available with Section 5.1.14 grayed out.
  • Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision.

PALISADES NUCLEAR PLANT Page 6 of 7 MAY 2009

JPM SRO ADMIN 2 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The plant is at 100% power.
  • It is Monday, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.
  • You are an on-shift SRO.
  • SHO-1, Shift Surveillance Data Sheet, was completed at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.
  • The plant is in Mode 1.

INITIATING CUES:

The Shift Manager directs you to complete a supervisory review of completed SHO-1 in accordance with step 5.3 of SHO-1.

PALISADES NUCLEAR PLANT Page 7 of 7 MAY 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 3 TITLE: CALCULATE MAXIMUM PERMISSIBLE STAY TIME CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task: Determine maximum permissible stay time Alternate Path: N/A Facility JPM #: NEW K/A: 2.3.4 Importance: RO: 3.2 SRO: 3.7 K/A Statement: Knowledge of radiation exposure limits under normal or emergency conditions.

Task Standard: Maximum time to perform Task #3 is calculated to be 51.4 to 51.9 minutes.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EI-2.1, Site Emergency Director EN-RP-201, Dosimetry Administration Validation Time: 20 minutes Time Critical: NO Candidate: _____________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 MAY 2009

JPM SRO ADMIN 3 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-2.1, Site Emergency Director 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 was at 100% power when a Steam Generator Tube Rupture occurred. A General Emergency was declared due to the plant conditions (fuel failure is also evident). Worker #1 has received 1.85 R TEDE this year prior to this event. Worker #1 has performed the following task for this event:

TIME DOSE

  1. TASK REQUIRED RATE 1 Closed A S/G ASDV air supply isolation valves 4 min 17.75 R/hr The Shift Manager then determined that the B S/G should have been isolated instead of A S/G. The following outside the Control Room tasks are now required:

TIME DOSE

  1. TASK REQUIRED RATE 2 Open A S/G ASDV air supply isolation valves 3 min 17.75 R/hr 3 Manually open MO-0510, A S/G MSIV Bypass Valve unknown 25.5 R/hr 4 Close B S/G ASDV air supply isolation valves 3 min 17.75 R/hr NOTE: Assume no dose is received while traveling between tasks.

INITIATING CUES:

Worker #1 is the only worker available to perform Tasks 2, 3 and 4. Your task is to determine the maximum time for Worker #1 to perform Task #3 without exceeding any established emergency dose limits. Report your results to the Shift Manager.

PALISADES NUCLEAR PLANT Page 3 of 7 MAY 2009

JPM SRO ADMIN 3 Proc.Step TASK ELEMENT 1 STANDARD Grade Determine dose received while performing

--- Calculates dose received at 1.18 R. S U Task #1.

Comment:

(17.75 R/hr) (1hr/60 min) (4 min) = 1.183 R CRITICAL STEP Proc.Step TASK ELEMENT 2 STANDARD Grade Determine dose to be received while

--- Calculates dose received at 0.878 R. S U performing Task #2.

Comment:

(17.75 R/hr) (1hr/60 min) (3 min) = 0.8875 R CRITICAL STEP Proc.Step TASK ELEMENT 3 STANDARD Grade Determine dose to be received while

--- Calculates dose received at 0.878 R. S U performing Task #4.

Comment:

(17.75 R/hr) (1hr/60 min) (3 min) = 0.8875 R CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 MAY 2009

JPM SRO ADMIN 3 Proc.Step TASK ELEMENT 4 STANDARD Grade Dose remaining determined to be 22.064 R.

Determine dose remaining from emergency Candidate may use EI-2.1, Site Emergency

--- S U dose limits. Director to determine 25R emergency dose limit.

Comment:

(25R) - (1.183R) - (2) (0.8875R) = 22.042 R EVALUATOR: If candidate asks which emergency dose limit is being considered for Task #3, inform them that this would be for protection of large populations. Also if asked, inform candidate that they do not desire to volunteer dose limit above 25R.

CRITICAL STEP Proc.Step TASK ELEMENT 5 STANDARD Grade Determine time available for Worker #1 to

--- complete Task #3 without exceeding Time available calculated to be 51.9 min. S U emergency dose level.

Comment:

(Available Dose)/(Dose Rate) = (22.042 R)/(25.5 R/hr) = 0.8644 hr (60 min/Hr) = 51.86 minutes (accept 51.9 to 51.4 minutes)

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade Inform the Shift Manager that Worker #1 will Inform the Shift Manager of calculation exceed 25 R emergency dose limit if Task #3 n/a results. S U takes more than 51.9 minutes.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 MAY 2009

JPM SRO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS

  • No Simulator setup required.

PALISADES NUCLEAR PLANT Page 6 of 7 MAY 2009

JPM SRO ADMIN 3 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant was at 100% power when a Steam Generator Tube Rupture occurs. A General Emergency was declared due to the plant conditions (fuel failure is also evident). Worker #1 has received 1.85 R TEDE this year. The following task has been performed by Worker #1:

TIME DOSE

  1. TASK REQUIRED RATE 1 Closed A S/G ASDV air supply isolation valves 4 min 17.75 R/hr The Shift Manager has determined that the wrong S/G has been isolated. The following outside the Control Room tasks are now required:

TIME DOSE

  1. TASK REQUIRED RATE 2 Open A S/G ASDV air supply isolation valves 3 min 17.75 R/hr 3 Manually open MO-0510, A S/G MSIV Bypass Valve unknown 25.5 R/hr 4 Close B S/G ASDV air supply isolation valves 3 min 17.75 R/hr NOTE: Assume no dose is received while traveling between tasks.

INITIATING CUES:

Worker #1 is the only worker available to perform Tasks 2, 3 and 4. Your task is to determine the maximum time for Worker #1 to perform Task #3 without exceeding any established emergency dose limits. Report your results to the Shift Manager.

PALISADES NUCLEAR PLANT Page 7 of 7 MAY 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 4 TITLE: OBTAIN METEOROLOGICAL DATA FOR EMERGENCY NOTIFICATION FORM CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Obtain Meteorological Data for Emergency Notification Form Alternate Path: N/A Facility JPM #: RO-A.4 2008 NRC K/A: 2.4.39 Importance: RO: 3.9 K/A Statement: Knowledge of RO responsibilities in emergency plan implementation Task Standard: EI-6.7, Attachment 1, completed with correct data obtained Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EI-3.0, Communications and Notifications EI-6.0, Offsite Dose Calculation and Recommendations for Protective Actions EI-6.7, Plant Site Meteorological System Validation Time: 10 minutes Time Critical: NO Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 May 2009

JPM RO ADMIN 4 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-6.7, Attachment 1 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 Shift Manager, acting as the Site Emergency Director, has declared an Alert condition. A thunderstorm is in progress.

INITIATING CUES:

The Shift Manager has directed you to obtain Meteorological Data by completing of EI-6.7, utilizing the Meteorological Data display in the Control Room.

PALISADES NUCLEAR PLANT Page 3 of 8 May 2009

JPM RO ADMIN 4 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Correct Procedure located EI-6.7, Attachment 1 located S U Comment:

Evaluator: Provide candidate with a Working Copy.

EVALUATOR NOTE: EI-6.7 Attachment 1 is completed by referencing steps 5.1.3 and 5.1.4. Due to wind speed and wind direction at 10 meters unavailable, 60 meter data is used.

Proc. Step TASK ELEMENT 2 STANDARD Grade On EI-6.7 Att. 1 data recorded as follows:

Obtain meteorological data from the PPC, page 351 WS, Wind Speed = 6.93 mph 5.1.3 S U WS, Wind Speed (WS60) _9_MPH 9 mph X .77 = 6.93 MPH

( X ) 60 meters, *corrected Comment:

NOTE: WS60 must be used. WS60 multiplied by 0.77 to obtain corrected wind speed.

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade Obtain meteorological data from the PPC, On EI-6.7 Att. 1 data recorded as follows:

page 351 5.1.3 WD, Wind Direction = 73° from S U WD, Wind Direction (WD60) ____°

( X ) 60 meters Comment:

NOTE: WD60 must be used.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 May 2009

JPM RO ADMIN 4 Proc. Step TASK ELEMENT 4 STANDARD Grade Obtain meteorological data from the PPC, page 351 On EI-6.7 Att. 1 data recorded as follows:

5.1.4 Stability Class (STAB) ____ S U Stability Class = C Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade On EI-6.7 Att. 1 data recorded as follows:

EI-6.7, Attachment 1 completed: Date: Todays date n/a S U Date:, Time:, Completed By: Time: Current time Completed By: Operators name Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade Notify the CRS that EI-6.7 Attachment 1 Operator notifies CRS of completion of EI-6.7, n/a completed. Attachment 1. S U Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 8 May 2009

JPM RO ADMIN 4 SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC 17
2. Remove the following two PPC points from service by using MFs PC20 and PC 21 on PID PC02. These MFs will cause a V or invalid display from the Met Tower 10 meter height. Candidate will have to use the 60 meter readings and use a conversion factor of 0.77 to obtain appropriate data. (ENSURE these MFs are changed back after JPM is completed)
  • MWD10
  • MWS10
3. Provide a Working Copy of EI-6.7, Att. 1 to evaluator.
4. Use Remote Functions (RF) on PID PC02 to modify the following (after all RFs are changed, then use UPDATE NOW and respond YES):
  • WS60 = 9 (change RF to this value)
  • WD60 = 73 degrees FROM (change RF to this value)
  • Stability = C (no change needed since RF should already say 3)
5. Candidate may use PPC monitor in Simulator Computer Room for this JPM: ensure it is up and running.

PALISADES NUCLEAR PLANT Page 6 of 8 May 2009

Proc No EI-6.7 Attachment 1 Revision 7 Page 1 of 1 PLANT SITE METEOROLOGICAL SYSTEM WORKSHEET ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY

1. WS, Wind Speed = 6.93 mph ( ) 10 meters (X) 60 meters, *corrected (See Step 5.1.3 or 5.2.6)
  • Multiply by 0.77 ( 9 MPH X 0.77 = 6.93 MPH)
2. WD, Wind Direction = 73 ° from ( ) 10 meters (X) 60 meters (See Step 5.1.3 or 5.2.6)

(see Step 5.1.4 or 5.2.7)

3. Stability Class = C Date: __TODAY_____ Time: __NOW___ Completed By: __JOE OPERATOR_______

ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 8 May 2009

JPM RO ADMIN 4 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Shift Manager, acting as the Site Emergency Director, has declared an Alert condition. A thunderstorm is in progress.

INITIATING CUES:

The Shift Manager has directed you to obtain Meteorological Data by completing Attachment 1 of EI-6.7, utilizing Meteorological Data display in the Control Room.

PALISADES NUCLEAR PLANT Page 8 of 8 May 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 4 TITLE: CLASSIFY EVENT AND DETERMINE PAR CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Classify an Event and Determine PARs - Protective Action Recommendations Alternate Path: N/A Facility JPM #: SRO-A.4 2003 NRC K/A: 2.4.41, 2.4.44 Importance: RO:4.1, 4.0 SRO: 4.1, 4.4 K/A Statement: (2.4.41) Knowledge of the emergency action level threshholds and classifications.

(2.4.44) Knowledge of emergency plan protective action recommendations.

Task Standard: Event classified as a General Emergency and PAR is evacuation of 2 mile radius and 5 miles in Areas 1 and 2, within 30 minutes.

Preferred Evaluation Location: Simulator __X__ In Plant ______

Preferred Evaluation Method: Perform __X__ Simulate ______

References:

EI-1, Emergency Classifications and Actions EI-3, Communications and Notifications EI-6.13, Protective Action Recommendations for Offsite Populations Validation Time: __30__ minutes Time Critical: YES Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 May 2009

JPM SRO ADMIN 4 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-1 Attachment 1 EI-3 EI-6.13 Attachment 1 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:

1. The Reactor has tripped.
2. A LOCA is in progress.
3. Pressurizer level is offscale LOW.
4. PCS pressure is 100 psia.
5. CETs indicate 600ºF.
6. Total LPSI/HPSI flow is NOT adequate per EOP Supplement 4.
7. SIRW tank level is 38% and lowering slowly.
8. Containment isolation has occurred as designed and EOP Supplement 6 for Containment Isolation is in progress.
9. A release is NOT occurring through the plant stack or steam dumps.
10. Containment Gamma Monitors (RIA-2321 and 2322) are indicating 5E4R/hr.
11. Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights
12. Failed fuel analysis is in progress with no results to report yet.
13. Obtained Meteorological Data is as follows:

QN = 0.0 QI = 0.0 Wind Speed = 1.1 Stability Class = G Wind Direction = 235 (from)

Weather is clear with no precipitation INITIATING CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Site Emergency Director). You are to classify the event given the above information and determine any required Protective Action Recommendations, and complete an Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 3 of 9 May 2009

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 1 STANDARD Grade Locates procedure to determine Emergency Locates EI-1 and refers to Attachment 1, Hot EI-1 S U Classification. Conditions (PCS > 200 degrees F).

Comment:

EVALUATOR: Candidate may use placard of site emergency plan classifications or use paper copy from EI-1, attachment 1.

Proc.Step TASK ELEMENT 2 STANDARD Grade EI-1 Refers to lower right-hand corner of EI-1, Refers to "Fission Product Barriers" section Attachment 1, Hot Conditions S U Att 1 (lower right-hand corner)

(PCS > 200 degrees F).

Comment:

Proc.Step TASK ELEMENT 3 STANDARD Grade

___ Refers to Table F1

___ Determines a LOSS of Fuel Cladding (based on Containment Gamma monitors readings (item 5)

___ Determines a LOSS of PCS Barrier (based EI-1 Determines status of fission product on leak rate and PCS subcooling)(item 2) S U Att 1 barriers. OR based on Containment Gamma Monitor readings.

___ Determines a POTENTIAL LOSS of Containment Barrier (based on Containment Gamma monitors readings).(item 6)

Comment:

EVALUATOR: If candidate refers to EI-11, inform them "That procedure will be performed by the TSC."

Proc.Step TASK ELEMENT 4 STANDARD Grade PALISADES NUCLEAR PLANT Page 4 of 9 May 2009

JPM SRO ADMIN 4 EI-1 Declares a GENERAL EMERGENCY per FG1 Declares Emergency Classification. based on status of fission product barriers (loss S U Att 1 of TWO and potential loss of THIRD).

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 5 STANDARD Grade EI-1 Prepares Emergency Actions/Notifications Obtains EI-1, Attachment 2 and fills out per S U Att 2 form. attached KEY.

Comment:

NOTE: This Task Element may be performed at any time during the JPM. Filling out this form is NOT required for this JPM; however a key is attached in case candidate fills out the form.

NOTE: It is NOT the intent of this JPM to have candidate actually make the notifications.

Proc.Step TASK ELEMENT 6 STANDARD Grade EI-3 Obtains EI-3, Attachment 1 and fills out per Prepares Event Notification Form. S U Att 1 attached KEY.

Comment:

NOTE: KEY is attached to this JPM.

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

NOTE: Candidate may use computer on Control Room island area to prepare this form.

PALISADES NUCLEAR PLANT Page 5 of 9 May 2009

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 7 STANDARD Grade Obtains EI-6.13 and corresponding Attachment 1 and determines:

EI-6.13 Determines Protective Action

___ Evacuate 5 mile in Areas 1 and 2 S U Att 1 Recommendations (PARs).

(minimum GE recommendation on bottom of Pg 1 of Attachment 1)

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 8 STANDARD Grade Palisades Event Notification Form completely EI-3 Completes filling out Palisades Event filled per attached KEY AND form is approved S U Att 1 Notification Form. (Candidate initials, date, and time entered at bottom of form)

Comment:

NOTE: Candidate may use computer on back-bar of Control Room island area to complete and print this form.

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 6 of 9 May 2009

JPM SRO ADMIN 4 ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 9 May 2009

JPM SRO ADMIN 4 SIMULATOR OPERATOR INSTRUCTIONS No Simulator setup required.

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.

PALISADES NUCLEAR PLANT Page 8 of 9 May 2009

JPM SRO ADMIN 4 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. The Reactor has tripped.
2. A LOCA is in progress.
3. Pressurizer level is offscale LOW.
4. PCS pressure is 100 psia.
5. CETs indicate 600ºF.
6. Total LPSI/HPSI flow is NOT adequate per EOP Supplement 4.
7. SIRW tank level is 38% and lowering slowly.
8. Containment isolation has occurred as designed and EOP Supplement 6 for Containment Isolation is in progress.
9. A release is NOT occurring through the plant stack or steam dumps.
10. Containment Gamma Monitors (RIA-2321 and 2322) are indicating 5E4R/hr.
11. Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights.
12. Failed fuel analysis is in progress with no results to report yet.
13. Obtained Meteorological Data is as follows:

QN = 0.0 QI = 0.0 Wind Speed = 1.1 Stability Class = G Wind Direction = 235 (from)

Weather is clear with no precipitation INITIATING CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Site Emergency Director). You are to classify the event given the above information and determine any required Protective Action Recommendations, and complete an Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 9 of 9 May 2009