Text

2009 Palisades Initial License Examination Administered Admin JPMs
	ML100690473
Person / Time
Site:	Palisades
Issue date:	05/25/2009
From:	Valos N; Operations Branch III
To:	; Entergy Nuclear Operations
References
	Download: ML100690473 (68)
	v • d • e

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 3.7 to 4.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

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 JUNE 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

It is 15 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 JUNE 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 (92,000 to 96,000 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 JUNE 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 (92,000 to 96,000 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 JUNE 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) (49,000 to 55,000 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months RECORDED 5.4 S U Graph line for elapsed time after (Interpolation may be used) shutdown (3.7 to 4.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months allowed)

Amount of inventory available to remove decay heat (graph)

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months S U available interval and that additional (3.7 to 4.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 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 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 JUNE 2009

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

JPM RO/SRO ADMIN 1a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

It is 15 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 JUNE 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 #: Modified from RO-A.1b 2008AUDIT K/A: 2.1.23 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: Allowable Shutdown Cooling outage time calculated to be 57 minutes (54 minutes to 60 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 JUNE 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:

Seven days after a plant shutdown, PCS temperature is 116ºF

The Reactor cavity is flooded to a level of 640'

The Pressurizer manway is removed

Shutdown Cooling is in operation, but must be shutdown for the maximum time allowed 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 JUNE 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 640 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 116°F (given in initial 17, S U of the following: conditions)

Att.1) 2.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 8 JUNE 2009

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 5 STANDARD Grade Page #10 of Attachment 1 REFERRED TO:

Uses Refueling Cavity Flooded to 640' to determine time to 200ºF (ONP17, REFER TO appropriate page in this USES "7 Days" (time after reactor shutdown) S U Att.1) 5. attachment for PCS conditions and 116ºF point (initial PCS temperature) and DETERMINES time to 200ºF is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Comment:

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

Heatup rate CALCULATED to be 21ºF / hour 7.3.7b (200°F - TINITIAL)_______________ S U (allow 20 - 22ºF / hour).

Approximate Time to 200°F (Hours)

Comment:

NOTE: Heatup rate is calculated by dividing 84ºF (200ºF - 116ºF) by 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 57 minutes (54 - 60 minutes).

20°F/Hr)

Comment:

NOTE: Allowable outage time calculated by dividing 20ºF (maximum allowed heatup) by 21ºF / hour (previously calculated heatup rate) and converting to minutes.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 JUNE 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 secured for approximately 57 minutes (54 - 60 S U approximately 57 minutes. allowed).

Comment:

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

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

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

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

INITIAL CONDITIONS:

Seven days after a plant shutdown, PCS temperature is 116ºF

The Reactor cavity is flooded to a level of 640'

The Pressurizer manway is removed

Shutdown Cooling is in operation, but must be shutdown for the maximum time allowed 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 JUNE 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: PPC setup to monitor the PCS heatup rate and candidate determines that LCO action statement 3.4.3.A needs to be entered due to heatup rate being above the limit.

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 8 June 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

Shutdown Cooling is NOT in service

PCS temperature is approximately 190°F

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 monitor and record PCS parameters during the heatup using the PPC per PO-2, step 5.1.

PALISADES NUCLEAR PLANT Page 3 of 8 June 2009

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 1 STANDARD Grade Locate PO-2, PCS Heatup/Cooldown n/a Step 5.1 of PO-2 LOCATED S U Operations, step 5.1 Comment:

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

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 5.1.1.d.1 follows: F7 key HCR Reports DEPRESSED S U DEPRESS F7 key HCR Reports Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 June 2009

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

5.1.1.d.2 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 5.1.1.d.3 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: When candidate has completed this step, hand them a printout of PPC pages 391, 392, and 393 for one hour later. Ensure the candidate understands that one hour has elapsed.

CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade Candidate determines that step 5.2 is N/A.

DETERMINE PCS parameters are within allowable limits at least once every 15 Candidate refers to step 5.3 and compares heatup minutes during the heatup/cooldown AND limits in step 6.0 to the heatup rates determined 5.1.1.d.4 S U INITIAL the PPC Data Sheet. Refer to on the PPC printout.

Step 5.2 and Step 5.3. Candidate determines that the heatup rate limit of 40°F hour has been exceeded Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 June 2009

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 8 STANDARD Grade IF any PCS parameter exceeds its limit or Candidate determines that LCO 3.4.3 condition A the heatup/cooldown rate exceeds the 5.3.1 needs to be entered because the heatup rate limit S U maximum allowable rate, THEN PERFORM has been exceeded.

the following ...

Comment:

EVALUATOR: When candidate determines that LCO 3.4.3 condition A needs to be entered, end the JPM.

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 June 2009

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

Remove SDC from service.

Ensure PCS temperature is approximately 190°F.

PALISADES NUCLEAR PLANT Page 7 of 8 June 2009

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

INITIAL CONDITIONS:

A Plant refueling has just been completed

Shutdown Cooling is NOT in service

PCS temperature is approximately 190°F

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 monitor and record PCS parameters during the heatup using the PPC per PO-2, step 5.1.

PALISADES NUCLEAR PLANT Page 8 of 8 June 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 #: Modified from 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 MO-3045, T-82B Outlet Isolation, and 'B' S/G Feedwater Temperature.

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 10 JUNE 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 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.28 through and including 5.1.39 for A Shift. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 3 of 10 JUNE 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 PIP/SPI Rod Position: CHECKS all readings agree within 8" Check PIP/SPI within 8 inches and each 5.1.28 RECORDS a in Shift A Readings column S U rod within 8 inches of other group rods on PPC pages 411 and 412 INITIALS "RECRD BY" Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.29 PDIL Rod Position: CHECKS all rods above PDIL 5.1.29 Check rod position above PDIL on PPC RECORDS a in Shift A Readings column S U Page 412 INITIALS "RECRD BY" Comment:

Proc. Step TASK ELEMENT 4 STANDARD Grade Shutdown and Part-Length CHECKS all rods 128" Rod Position:

5.1.30 RECORDS a in Shift A Readings column S U Check rods 128" on PPC Pages 411 &

412 INITIALS "RECRD BY" Comment:

PALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 5 STANDARD Grade Linear Heat Rate: CHECKS Incore flux below alarm limits 5.1.31 Check Incore flux below alarm limits on RECORDS a in Shift A Readings column S U PPC Pages 512 & 513 INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade RECORDS Main Feed Temperatures from TR-0706 in Shift A Readings column Main Feed Temperature: RECORDS Main Feed Temperatures from 5.1.32 Record data and check channels agree PPC Page 521 in Shift A Readings column S U within 10°F on PPC Page 521 CHECKS Main Feed temperatures on PPC Page 521 are within 10°F of associated readings on TR-0706 Comment:

NOTE: Data for 'B' S/G Feedwater Temperature indication on PPC is > 10°F less than

'B' S/G Feedwater Temperature on TR-0706 Proc. Step TASK ELEMENT 7 STANDARD Grade DETERMINES 'B' S/G Feedwater Temperature indication on PPC is > 10°F less than 'B' S/G Feedwater Temperature on TR-Main Feed Temperature: 0706 5.1.32 Record data and check channels agree CIRCLES in RED one or both 'B' S/G S U within 10°F on PPC Page 521 Feedwater Temperatures

INITIALS RECRD BY

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: Not part of the critical step CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 8 STANDARD Grade Main Feed Flow RECORDS Main Feed Flow to both S/Gs 5.1.33 Record data and check channels agree CHECKS within 0.5 E6 PPH S U within 0.5 E6 PPH on PPC Page 521 INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade Auxiliary Feed Flow RECORDS AFW flow to both S/Gs Record flow and check channels agree 5.1.34 VERIFIES all channels agree within 45 gpm S U within 30 GPM (45 GPM with no flow to the steam generator) INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 10 STANDARD Grade RECORDS PZR level in Shift A Readings Pressurizer Level column 5.1.35 Record data and check Pressurizer level S U CHECKS PZR level < 62.8%

< 62.8% on PPC Page 325 INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 11 STANDARD Grade PCS Cooling Loops CHECKS all PCPs operating Check at least minimum pumps operating:

5.1.36 RECORDS a in Shift A Readings column S U Modes 1, 2 - 4 Pumps Mode 3 - 1 Pump INITIALS RECRD BY Comment:

PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 12 STANDARD Grade CHECKS both PORV block valves indicate PORV Block Valve Position Indication closed 5.1.37 Check indication is as expected S U RECORDS a in Shift A Readings column INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 13 STANDARD Grade CHECKS SIT Isolation Valve, MO-3041, SIT Isolation Valve Position MO-3045, MO-3049, MO-3052, position 5.1.38 S U Check each SIT Isolation Valve fully open VERIFIES all valves indicate full open Comment:

Evaluator Note: MO-3045, T-82B Isolation, will indicate in the mid-position, (red and green lights energized)

Proc. Step TASK ELEMENT 14 STANDARD Grade DETERMINES MO-3045 is out of spec due to being in the mid-position RECORDS a in Shift A Readings column SIT Isolation Valve Position for each valve except MO-3045 *. Candidate 5.1.38 may either leave the MO-3045 space blank or S U Check each SIT Isolation Valve fully open place a in the blank and circle in red INITIALS RECRD BY

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: Not part of the critical step CRITICAL STEP PALISADES NUCLEAR PLANT Page 7 of 10 JUNE 2009

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 15 STANDARD Grade CHECKS SIRWT Recirc Valves, CV-3027 and SIRWT Recirc Valve Position CV-3056, valves and handswitches indicate open 5.1.39 Check SIRWT Recirc Valves and S U Handswitches in the OPEN position RECORDS a in Shift A Readings column INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 16 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 8 of 10 JUNE 2009

JPM RO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS

Reset to any full power IC.

Insert the following or use CAE file o Override for 'B' S/G Feedwater Temperature TR-0706-R to 0.915 o Override MO-3045-G to ON

Adjust all PWR Range NI to 99.9 -100.1% power as necessary.

Ensure copies of SHO-1, Attachment 1, pages 10-13 are available

Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision PALISADES NUCLEAR PLANT Page 9 of 10 JUNE 2009

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

INITIAL CONDITIONS:

The plant is at 100% power

It is Monday, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.28 through and including 5.1.39 for A Shift. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 10 of 10 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 2 TITLE: DETERMINE A TECHNICAL SPECIFICATION COMPLETION TIME EXTENSION CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADM 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Given a technical specification entry condition and references, determine a completion time extension.

Alternate Path: N/A Facility JPM #: NEW K/A: 2.2.23 Importance: RO:3.1 SRO: 4.6 K/A Statement: Ability to track Technical Specification limiting conditions for operation.

Task Standard: LCO 3.5.2.D and LCO 3.0.3 entered and completion time of action statement 3.5.2.B extended to June 5th, 2009 at 0900.

Preferred Evaluation Location: ANY _X_

Preferred Evaluation Method: Perform _X_ Simulate _____

References:

LCO 3.5.2, "ECCS - Operating" LCO 1.3, "Completion Times" 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 JUNE 2009

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

Also see Simulator Operator Instructions (last page of this document).

EXAMINER NOTE: There are two initiating cue sheets for this JPM. Ensure the cue sheet on page 8 is handed out FIRST.

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 full power

Today's date is June 3rd, 2009. The time is 0900

On June 1st, 2009 at 0900, P-66A, HPSI Pump, was declared INOPERABLE

LCO Action Statement 3.5.2.B, "One or more ECCS trains INOPERABLE for reasons other than Condition A," was entered at that time

P-66B, HPSI Pump, was just declared INOPERABLE today at 0855 FIRST INITIATING CUE:

The Shift Manager has directed you to determine the Technical Specification Action Statement(s), if any, that need to be entered as a result of the INOPERABILITY of P-66B.

SECOND INITIATING CUE:

The time is now 1300 on June 3rd, 2009

P-66A was just declared OPERABLE following completion of corrective maintenance, return to service and satisfactory surveillance testing.

The Shift Manager directs you to determine the latest date and time that P-66B must be repaired without having to enter action statement LCO 3.5.2.C, "Required Action and associated Completion Time of Condition A or B not met."

PALISADES NUCLEAR PLANT Page 3 of 8 JUNE 2009

JPM SRO ADM 2 Proc. Step TASK ELEMENT 1 STANDARD Grade

-- Candidate locates LCO 3.5.2 LCO 3.5.2 is located S U Comment:

Proc. Step TASK ELEMENT 2 STANDARD Grade Candidate determines that LCO 3.5.2.D "Less LCO Evaluate additional TS LCO action than 100% of the required ECCS flow available" S U 3.5.2 statements that need to be entered. is applicable and that LCO 3.0.3 needs to be entered immediately.

Comment:

Evaluator Note: Candidate may refer to TS Bases 3.5.2 for this answer.

Evaluator Cue: Hand the candidate the SECOND Initiating Cue sheet.

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade Candidate reviews action statement Candidate determines that the criteria of LCO 1.3 completion time extension criteria of LCO 1.3 are met to allow an extension of the S U LCO 1.3. completion time of LCO 3.5.2.B.

Comment:

Proc. Step TASK ELEMENT 4 STANDARD Grade Candidate evaluates the amount of time Candidate determines that the actions of LCO 1.3 that action of LCO 3.5.2.B may be LCO 3.5.2.B may be extended until June 5th, S U extended. 2009 at 0900.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 JUNE 2009

JPM SRO ADM 2 Proc. Step TASK ELEMENT 5 STANDARD Grade Candidate notifies the Shift Manager that LCO 3.5.2.B may be extended to June 5th,

--- Shift Manager notified. S U 2009 at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months prior to entering LCO 3.5.2.C.

Comment:

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

JPM SRO ADM 2 SIMULATOR OPERATOR INSTRUCTIONS N/A PALISADES NUCLEAR PLANT Page 6 of 8 JUNE 2009

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

INITIAL CONDITIONS:

The time is now 1300 on June 3rd, 2009.

P-66A was just declared OPERABLE following completion of corrective maintenance, return to service and satisfactory surveillance testing.

INITIATING CUES:

The Shift Manager directs you to determine the latest date and time that P-66B must be repaired without having to enter action statement LCO 3.5.2.C, "Required Action and associated Completion Time of Condition A or B not met."

PALISADES NUCLEAR PLANT Page 7 of 8 JUNE 2009

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

INITIAL CONDITIONS:

The Plant is at full power

Today's date is June 3rd, 2009. The time is 0900

On June 1st, 2009 at 0900, P-66A, HPSI Pump, was declared INOPERABLE

LCO Action Statement 3.5.2.B, "One or more ECCS trains INOPERABLE for reasons other than Condition A," was entered at that time

P-66B, HPSI Pump, was just declared INOPERABLE today at 0855 INITIATING CUES:

The Shift Manager has directed you to determine the Technical Specification Action Statement(s), if any, that need to be entered as a result of the INOPERABILITY of P-66B.

PALISADES NUCLEAR PLANT Page 8 of 8 JUNE 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 51.0 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 JUNE 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). Due to plant conditions, a radioactive release is in progress. 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

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

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 (in minutes) 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 JUNE 2009

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

--- Calculates dose received at 1.18 - 1.20R. 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 0.88 - 0.90R. 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 0.88 - 0.90R. S U performing Task #4.

Comment:

(17.75 R/hr) (1hr/60 min) (3 min) = 0.8875 R CRITICAL STEP Proc.Step TASK ELEMENT 4 STANDARD Grade Dose remaining determined to be 22.042 R.

Determine dose remaining from emergency (allow 22.00 - 22.06R). Candidate may use

--- S U dose limits. EI-2.1, Site Emergency 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 to determine this from plant conditions. Also if asked, inform candidate that the worker does not desire to volunteer dose limit above 25R.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 JUNE 2009

JPM SRO ADMIN 3 Proc. Step TASK ELEMENT 5 STANDARD Grade Determine time available for Worker #1 to Time available calculated to be 51.9 min (allow

--- complete Task #3 without exceeding S U 51.0 - 51.9).

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 51.0 to 51.9 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. takes more than 51.9 minutes (allow 51.0 - S U 51.9).

Comment:

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

JPM SRO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS

No Simulator setup required.

PALISADES NUCLEAR PLANT Page 6 of 7 JUNE 2009

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

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). Due to plant conditions, a radioactive release is in progress. 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

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

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 (in minutes) 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 JUNE 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 within 12 minutes per attached key 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: YES - 12 Minutes Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 JUNE 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.

This data is required to complete EI-3, attachment 1, Palisades Event Notification Form.

THIS JPM IS TIME CRITICAL.

PALISADES NUCLEAR PLANT Page 3 of 8 JUNE 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, WS, Wind Speed = 6.93 mph (6.9-7.0 page 351 acceptable) 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 JUNE 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:

Date: Todays date EI-6.7, Attachment 1 completed:

n/a *Time: Current time -within 12 minutes from S U Date:, Time:, Completed By:

start of JPM Completed By: Operators name Comment:

CRITICAL STEP

Time is only portion of critical step 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 JUNE 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 JUNE 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 (6.9 - 7.0 acceptable)

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 JUNE 2009

JPM RO ADMIN 4 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER 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 of EI-6.7, utilizing Meteorological Data display in the Control Room.

This data is required to complete EI-3, attachment 1, Palisades Event Notification Form.

THIS JPM IS TIME CRITICAL PALISADES NUCLEAR PLANT Page 8 of 8 JUNE 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 within 15 minutes and PAR is evacuation of Areas 1 and 2, within 12 minutes from declaration of GE.

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 - see task standard Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 10 JUNE 2009

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

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

1. The Reactor tripped 12 minutes ago.

2. A LOCA is in progress.

3. Pressurizer level is off-scale 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. The 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 complete the Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 3 of 10 JUNE 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 EI-1 Determines status of fission product (based on leak rate and PCS subcooling)(item 2) OR based on S U Att 1 barriers.

Containment Gamma Monitor readings (item 4).

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

Comment:

PALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009

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

Comment:

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

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

Comment:

EVALUATOR NOTE: This Task Element may be performed at any time during the JPM.

Filling out this form is NOT required for this JPM.

EVALUATOR 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:

EVALUATOR NOTE: When candidate asks for Meteorological Data, hand them attachment 1 of EI-6.7, "Plant Site Meteorological System Worksheet," which has been previously completed (attached)

EVALUATOR NOTE: KEY is attached to this JPM.

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

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

PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 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 Areas 1 and 2 (minimum GE S U Att 1 Recommendations (PARs).

recommendation on bottom of Pg 1 of Attachment 1)

Comment:

EVALUATOR NOTE: Provide candidate with a working copy of EI-6.13.

CRITICAL STEP - must be performed within 12 minutes of declaration of General Emergency.

Proc.Step TASK ELEMENT 8 STANDARD Grade Candidate may determine status of Core Candidate refers to graph on attachment 2 and EI-11 S U Damage per EI-11. determines that < 20% of the core is damaged.

Comment:

EVALUATOR NOTE: If candidate attempts to perform this step, provide them with a working copy of EI-11, attachment 2.

Proc.Step TASK ELEMENT 9 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 will use computer on back-bar of Control Room island area to complete and print this form.

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 filled in "reason for classification" section OR Fission Product Barrier Degradation checked in "reason for classification" section

Areas 1 and 2 checked for Evacuation of Areas CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009

ANSWER KEY JPM SRO ADMIN 4 Proc No EI-3 Attachment 1 PALISADES EVENT NOTIFICATION FORM Revision 27 Page 1 of 1 Actual Event Drill Plant Contact Information Nuclear Power Plant: _________________________________________

Plant Communicator: __________________ Time of Communication: V.B. ______ 1 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 Radiological Release in Progress Due to Event Yes No Protective Action Recommendations None Evacuation of Areas(s): 1 2 3 4 5 In-Place Shelter of Area(s) 1 2 3 4 5 PAR based on: Dose Calculation (Palisades Event Technical Data Sheet required) Plant Status Security Event Other ___________________________________________________________________________________________________

Meteorological Data Wind Direction (degrees): From 235 To 55 Wind Speed (MPH): 1 Stability Class: G Precipitation: Yes No Emergency Director Approval: ________________________________ Date: _________ Time: ________

ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 10 JUNE 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 10 JUNE 2009

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

1. WS, Wind Speed = 1.0 mph (X) 10 meters

( ) 60 meters, *corrected (see Step 5.1.3 or 5.2.6)

Multiply by 0.77

2. WD, Wind Direction = 235 ° from (X) 10 meters

( ) 60 meters (see Step 5.1.3 or 5.2.6)

(see Step 5.1.4 or 5.2.7)

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

PALISADES NUCLEAR PLANT Page 9 of 10 JUNE 2009

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

INITIAL CONDITIONS:

1. The Reactor tripped 12 minutes ago.

2. A LOCA is in progress.

3. Pressurizer level is off-scale 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. The 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 complete the Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 10 of 10 JUNE 2009

ML100690473

Contents

Text

References:

References:

References:

References:

References:

References:

References:

References:

Navigation menu

ML100690473

Text

References:

References:

References:

References:

References:

References:

References:

References:

Navigation menu

Search