ML13070A428

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Proposed RO & SRO Admin JPMs
ML13070A428
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/11/2013
From: Walton R
NRC/RGN-III/DRS/OLB
To:
References
Download: ML13070A428 (74)
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NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 1a TITLE: DETERMINE FINAL PCS BORON CONCENTRATION FROM S/G BACKFLOW DILUTION CANDIDATE:

EXAMINER:

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine Final PCS Boron Concentration per EOP Supplement 38 Alternate Path: N/A Facility JPM #: NEW 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: Final PCS Boron of 450 to 455 ppm and raising PCS boron by 45 to 50 ppm determined.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

EOP Supplement 38, Determination of Final PCS Boron from S/G Backflow Dilution Validation Time:

15 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • EOP Supplement 38, Determination of Final PCS Boron from S/G Backflow Dilution
  • Calculator 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:

  • Plant was at full power when a S/G Tube Rupture occurred in the B S/G.
  • Reactor was tripped and EOP-1.0 was completed.
  • EOP-5.0, S/G Tube Rupture Recovery, has been implemented.
  • B S/G has been isolated per EOP Supplement 13.
  • Current S/G Levels are:

o A S/G = 35%

o B S/G = 85%

  • Chemistry reports current PCS boron = 625 ppm.
  • Cold Shutdown Boron concentration for current core burnup = 500 ppm.

INITIATING CUES:

  • The CRS directs you to perform EOP-5.0 Step 54.a to determine the diluted PCS boron concentration that will exist if the B S/G level is lowered to 30% (backflow the isolated S/G to the PCS).

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of EOP-5.0 Step 54.

Proc.Step TASK ELEMENT 1 STANDARD Grade 54.a DETERMINE the diluted PCS boron concentration assuming 0.5% decrease in boron concentration for every 1% decrease in S/G level. Refer to EOP Supplement 38.

Locates EOP Supplement 38 S U Comment:

EVALUATOR NOTE: Provide candidate with a working copy of EOP Supplement 38.

Proc.Step TASK ELEMENT 2 STANDARD Grade Supp 38 Determines S/G level delta for backflow 55% level delta determined.

S U Comment:

EVALUATOR NOTE: 85% (current level) - 30% (desired level) = 55%

CRITICAL STEP Proc.Step TASK ELEMENT 3 STANDARD Grade Supp 38 Determine final PCS boron after backflow Final PCS boron of 450 to 455 ppm determined.

S U Comment:

EVALUATOR NOTE: Final PCS {B} = [625 ppm]-[(55)(0.005)(625)] = 453.1 ppm (allow 450 to 455 ppm)

CRITICAL STEP

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012 Proc.Step TASK ELEMENT 4 STANDARD Grade Inform CRS of results CRS informed S U Comment:

EVALUATOR CUE: Acknowledge results and cue Operator to perform EOP-5.0 Step 54.b and report any actions that are required prior to backflowing the isolated S/G.

Proc.Step TASK ELEMENT 5 STANDARD Grade 54.b If predicted PCS boron concentration is less than cold shutdown boron concentration, THEN RAISE PCS boron in preparation of backflow of the isolated S/G.

47 ppm determined (allow 45 to 50 ppm)

S U Comment:

EVALUATOR NOTE: Cold Shutdown Boron - Final PCS {B} = [500 ppm]-[453 ppm] = 47 ppm CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade Inform CRS that PCS boron must be raised by 47 (45-50) ppm prior to backflow of isolated S/G CRS informed S U Comment:

END OF TASK

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS None required.

JPM RO ADMIN 1a PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • Plant was at full power when a S/G Tube Rupture occurred in the B S/G.
  • Reactor was tripped and EOP-1.0 was completed.
  • EOP-5.0, S/G Tube Rupture Recovery, has been implemented.
  • B S/G had been isolated per EOP Supplement 13.
  • Current S/G Levels are:

o A S/G = 35%

o B S/G = 85%

  • Chemistry reports current PCS boron = 625 ppm.
  • Cold Shutdown Boron concentration for current core burnup = 500 ppm.

INITIATING CUES:

  • The CRS directs you to perform EOP-5.0 Step 54.a to determine the diluted PCS boron concentration that will exist if the B S/G level is lowered to 30% (backflow the isolated S/G to the PCS).

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 1b TITLE: PERFORM A HEAT BALANCE CALCULATION USING THE PPC CANDIDATE:

EXAMINER:

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Perform a Heat Balance Calculation Using the PPC.

Alternate Path: N/A Facility JPM #: BANK 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: UFM CAL ENABLED NO selected; both UFM Correction Factors changed to 1.0000; and an accurate Heat Balance power is determined for given plant parameters.

Preferred Evaluation Location: Simulator

__X___

In Plant Preferred Evaluation Method:

Perform

__X___

Simulate

References:

DWO-1, Operators Daily/Weekly Items MODES 1, 2, 3, and 4, section 5.2.3 Validation Time:

20 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT

______ UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

DWO-1, Operators Daily/Weekly Items MODES 1, 2, 3, and 4, section 5.2.3 Also see Simulator Operator Instructions (later page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

  • The plant was initially at full power steady state for 11 days
  • A power reduction to 93% has just been completed in accordance with GOP-8, Power Reduction and Plant Shutdown to Mode 2 or Mode 3 525°F, to support troubleshooting high main generator end iron temperatures.
  • S/G Blowdown flow actual values are 19,000 lbm/hr each.

INITIATING CUES:

The CRS directs you to:

  • Change the UFM CAL to NOT ENABLED
  • Set the UFM Correction Factors to 1.0000, and
  • Perform a heat balance per DWO-1 Step 5.2.3.

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of DWO-1, 5.2.3.

Proc. Step TASK ELEMENT 1 STANDARD Grade 5.2.3.a Obtain PPC Page 521.

1. SELECT the current display number in upper left corner of display.
2. TYPE in desired display number (521).
3. DEPRESS UPDATE key. Observe Parametering Done next to entered typing.
4. DEPRESS the right mouse button.

Display will change to desired.

PPC Page 521 is showing on the PPC screen.

S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade 5.2.3.c IF UFM CAL ENABLED will be changed from NOT ENABLED to ENABLED....

Candidate determines this step is N/A.

S U Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.2.3.d.1 If UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN perform the following:

1. UPDATE TDB Figure 14.1 indicating UFM CAL ENABLED status.

TDB Figure 14.1 new line entry made:

Todays date entered in Date column NO entered in Calibration Enabled column.

S U Comment:

CRITICAL STEP

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.2.3.d.2 ENSURE HB_PWR_STEADY is lowered to the 100% thermal power limit allowed by 2, 100% Thermal Power Limit. 2 referenced: first row on page 1 (right hand column-top).

Candidate verifies that 93% power conforms to REDUCE Reactor Power by Total UFM Correction Factor Worth in the TDB Figure 12.1 plus an additional 0.65%.

S U Comment:

100 % - [1.18% (Total UFM Correction Factor Worth)+ 0.65%] = 98.17%

EVALUATOR CUE: Provide candidate with a working copy of DWO-1 Attachment 12.

Proc. Step TASK ELEMENT 5 STANDARD Grade 5.2.3.d

3. SELECT UFM CAL ENABLED
4. ENTER N for no
5. PRESS UPDATE hardkey UFM CAL ENABLED selected N entered [may use 0]

UPDATE hardkey depressed S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade 5.2.3.d.6 ENSURE UFM Correction Factors set to 1.0000 per Step 5.2.3.f Candidate goes to step 5.2.3.f S U Comment:

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 7 STANDARD Grade 5.2.3f If a change to UFM Correction Factors is required, THEN perform the following:

1. ENSURE TDB Figure 14.1 is updated
2. ENSURE HB_PWR_STEADY is acceptable for the new Total UFM Correction Factor Worth in Technical Data Book Figure 14.1.
3. SELECT data
4. ENTER new value
5. PRESS UPDATE hardkey
1. TDB Figure 14.1 new line entry is updated to by adding a 1.0000 to UFM Correction Factor A and UFM Correction Factor B columns
2. This was completed in step 5.2.3.d.2 3, 4. Enters 1.0000 for E-50A (B) UFM Correction factor.
5. Depresses UPDATE hardkey Repeats 3, 4, and 5 for E-50B (A) UFM Correction factor.

S U Comment:

EVALUATOR NOTE: It is assumed that candidate performs the wait 30 minutes steps at same time. If not, then provide individual cue at this point.

CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade 5.2.3.g DETERMINE if Steam Generator Blowdown Flows on PPC Page 521 are correct.

Candidate determines S/G B/D flows are NOT correct.

S U Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade 5.2.3.h.1 If a change to S/G B/D flows is required, THEN perform the following:

1. SELECT data
2. ENTER new value
3. PRESS UPDATE hardkey PPC Page 521 S/G B/D flows:

Enters 19000 lbm/hr for A S/G Blowdown flow and depresses UPDATE hardkey Enters 19000 lbm/hr for B S/G Blowdown flow and depresses UPDATE hardkey S U Comment:

CRITICAL STEP

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 10 STANDARD Grade 5.2.3.d.7 5.2.3.f.6 5.2.3.h.4 WAIT approximately 30 minutes Candidate determines that 30 minute wait is required.

S U Comment:

EVALUATOR NOTE: It is assumed that candidate performs the wait 30 minutes steps at same time. If not, then provide individual cues at these points.

EVALUATOR CUE: 30 minutes have elapsed.

CRITICAL STEP Proc. Step TASK ELEMENT 11 STANDARD Grade 5.2.3.i PRINT out the Heat Balance by depressing the PRINTER hardkey PRINTER hardkey depressed.

Printout of Heat Balance from printer obtained S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade 5.2.3.j SIGN the printout Printout signed anywhere on the printout form S U Comment:

Proc. Step TASK ELEMENT 13 STANDARD Grade 5.2.3.k REQUEST and On-Shift SRO to review AND sign the printout PRINTER hardkey depressed.

Printout of Heat Balance form printer obtained S U Comment:

EVALUATOR CUE: When requested, inform candidate that SRO has reviewed and signed heat balance.

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 14 STANDARD Grade 5.2.3.l GO TO section 5.2.5 Operator attempts to transition to section 5.2.5.

S U Comment:

EVALUATOR CUE: Inform candidate that another operator will perform section 5.2.5.

END OF TASK

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC-19, ramp power down to 93% and stabilize. Then snap to a saved IC.
2. Reset to saved snapshot IC
3. Ensure TDB Figure 14.1 is correct. JPM assumes Simulator laminated Figure 14.1 is used with one line entry at top as follows:

[date]

0.9926 0.9956 1.18%

YES

[initials}

NOTE: Step 4.a requirements can be accomplished by resetting the simulator to saved snapshot IC each time.

4. After each candidate has completed this JPM and prior to the next candidate starting:
a. Ensure that S/G Blowdowns (as indicated on PPC page 521) are as follows:
  • E-50A BLOW FLOW 20000 lbm / hr
  • E-50B BLOW FLOW 20000 lbm / hr
b. Ensure Tech Data Book 14.1 reflects initial UFM correction factors.

JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • The plant was initially at full power steady state for 11 days
  • A power reduction to 93% power has just been completed in accordance with GOP-8, Power Reduction and Plant Shutdown to Mode 2 or Mode 3 525°F, to support troubleshooting high main generator end iron temperatures
  • S/G Blowdown flow actual values are 19,000 lbm/hr each INITIATING CUES:

The CRS directs you to:

  • Change the UFM CAL to NOT ENABLED
  • Set the UFM Correction Factors to 1.0000, and
  • Perform a heat balance per DWO-1 Step 5.2.3

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

EXAMINER:

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Complete the SHO-1 Surveillance Alternate Path: N/A Facility JPM #: 2009 NRC EXAM 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

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • SHO-1, Attachment 1, Shift Surveillance Data Sheet
  • Marked-up PPC Pages 512 and 513 for Incores
  • Red ink pen Also see Simulator Operator Instructions (later page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

  • 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 Shift A readings of SHO-1, Items 5.1.28 through and including 5.1.39. ALL remaining readings have already been taken by another NCO.

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a partially completed copy of SHO-1.

Proc. Step TASK ELEMENT 1 STANDARD Grade 5.1.28 PIP/SPI Rod Position:

OBTAIN control rod position data from Palisades Plant Computer (PPC) Pages 411 and 412.

CHECK each control rod position output data between the Primary and Secondary Systems for agreement within 3 (Admin limit) and 8 (Tech Spec limit).

CHECK each rod is within eight (8) inches of associated group rod positions.

OBTAINS control rod data from PPC pages 411 and 412 CHECKS PIP and SPI readings agree within 3 and 8" CHECKS each rod is within 8 of all other rods in its associated group.

RECORDS a in Shift A Readings column INITIALS "RECRD BY" S U Comment:

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.29 5.1.29 PDIL Rod Position:

CHECK PPC Page 412, "Regulating Rods Information," indicates control rods above the PDIL limit.

CHECKS all rods above PDIL RECORDS a in Shift A Readings column INITIALS "RECRD BY" S U Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.30 Shutdown and Part-Length Rod Position:

CHECK "Control Rod Monitoring" PPC Pages 411 and 412 indicate each Shutdown Control Rod Group and Part-Length Control Rod Group is withdrawn to greater than or equal to 128 inches.

CHECKS all shutdown and part length rods 128" RECORDS a in Shift A Readings column INITIALS "RECRD BY" S U Comment:

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.31 Linear Heat Rate:

CHECK Incore flux below alarm limits as indicated on PPC screens 512 and 513.

CHECKS Incore flux below alarm limits RECORDS a in Shift A Readings column INITIALS RECRD BY S U Comment:

EVALUATOR CUE: When requested, provide candidate copies of marked-up PPC Pages 512 and 513 (these would normally be found in Technical Data Book).

Proc. Step TASK ELEMENT 5 STANDARD Grade 5.1.32 Main Feed Temperature:

CHECK unfiltered Main Feed temperatures on PPC Page 521 are within 10°F of associated readings on REC-C11-03.

RECORDS Main Feed Temperatures from REC-C11-03 in Shift A Readings column RECORDS Main Feed Temperatures from PPC Page 521 in Shift A Readings column CHECKS Main Feed temperatures on PPC Page 521 are within 10°F of associated readings on REC-C11-03 S U Comment:

EVALUATOR NOTE: Data for 'B' S/G Feedwater Temperature indication on PPC is > 10°F less than 'B' S/G Feedwater Temperature on REC-C11-03.

Proc. Step TASK ELEMENT 6 STANDARD Grade 5.1.32 Main Feed Temperature:

CHECK unfiltered Main Feed temperatures on PPC Page 521 are within 10°F of associated readings on REC-C11-03.

DETERMINES 'B' S/G Feedwater Temperature indication on PPC is > 10°F less than 'B' S/G Feedwater Temperature on REC-C11-03 CIRCLES in RED one or both 'B' S/G Feedwater Temperatures

  • INITIALS RECRD BY
  • NOTIFY CRS of the out of spec reading
  • S U 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.

  • EVALUATOR NOTE: Not part of the critical step.

CRITICAL STEP

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 7 STANDARD Grade 5.1.33 Main Feed Flow CHECK unfiltered Main Feed flow on PPC page 521 is within 0.5 E6 PPH of readings on FI-0701 and FI-0703.

RECORDS Main Feed Flow from FLIR-0701/0702 in Shift A Readings column RECORDS Main Feed Flow from PPC Page 521 in Shift A Readings column CHECKS within 0.5 E6 PPH INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 8 STANDARD Grade 5.1.34 Auxiliary Feed Flow CHECK each redundant Auxiliary Feed flow instrument reading is within 30 gpm of its counterpart (45 gpm with no flow to the steam generator).

RECORDS AFW flow to both S/Gs in Shift A Readings column VERIFIES all channels agree within 45 gpm INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade 5.1.35 Pressurizer Level CHECK Pressurizer level is less than 62.8% using the PPC Page 325 for Item LPRZC.

RECORDS PZR level in Shift A Readings column CHECKS PZR level < 62.8%

INITIALS RECRD BY S U Comment:

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 10 STANDARD Grade 5.1.36 PCS Cooling Loops In Modes 1 and 2, CHECK all four Primary Coolant Pumps in operation circulating coolant.

In Mode 3, CHECK both PCS Loops OPERABLE with at least one PCP in one PCS Loop operating.

CHECKS all PCPs operating RECORDS a in Shift A Readings column INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 11 STANDARD Grade 5.1.37 PORV Block Valve Position Indication CHECK each PORV Block Valve position indication is as expected.

CHECKS both PORV block valves indicate closed RECORDS a in Shift A Readings column INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 12 STANDARD Grade 5.1.38 SIT Isolation Valve Position CHECK each Safety Injection Tank Isolation Valve is fully open using Control Room indication.

CHECKS SIT Isolation Valve, MO-3041, MO-3045, MO-3049, MO-3052, position VERIFIES all valves indicate full open S U Comment:

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

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 13 STANDARD Grade 5.1.38 SIT Isolation Valve Position CHECK each Safety Injection Tank Isolation Valve is fully open using Control Room indication.

DETERMINES MO-3045 is out of spec due to being in the mid-position RECORDS a in Shift A Readings column for each valve except MO-3045 *. Candidate may either leave the MO-3045 space blank or place a in the blank and circle in red INITIALS RECRD BY

  • NOTIFY CRS of the out of spec reading
  • S U 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.

  • EVALUATOR NOTE: Not part of the critical step CRITICAL STEP Proc. Step TASK ELEMENT 14 STANDARD Grade 5.1.39 SIRWT Recirc Valve Position CHECK SIRWT Recirc Valves, CV-3027 and CV-3056, and the associated handswitches are in the OPEN position using Control Room indication.

CHECKS SIRWT Recirc Valves, CV-3027 and CV-3056, valves and handswitches indicate open RECORDS a in Shift A Readings column INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 15 STANDARD Grade n/a Return completed SHO-1 to CRS and inform CRS of out of spec readings (if not already done)

Completed SHO-1 RETURNED to the CRS CRS INFORMED of the out of spec readings (if not already done)

S U Comment:

END OF TASK

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS

  • Reset to any full power IC.
  • Insert the following or use CAE file o Override for REC-C11-03-3, E-6A Outlet Temp, 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
  • Printout copy of PPC Pages 512 and 513 and anotate as Reactor Engineer that those incores with a V in Flux Column are not in service.

JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012 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 <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> INITIATING CUES:

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

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 4 TITLE: ACTIVATE EMERGENCY RESPONSE DATA SYSTEM (ERDS) DATALINK TO THE NRC CANDIDATE:

EXAMINER:

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Activate Emergency Response Data System Datalink to NRC Alternate Path: N/A Facility JPM #: BANK K/A:

2.4.43 Importance:

RO:

3.2 SRO:

3.8 K/A Statement: Knowledge of emergency communications systems and techniques Task Standard: ERDS Datalink to the NRC has been activated Preferred Evaluation Location: Simulator

__X__

In Plant Preferred Evaluation Method:

Perform

__X__

Simulate

References:

SOP-34, Palisades Plant Computer (PPC) System Validation Time:

10 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-34, Palisades Plant Computer (PPC) System Also see Simulator Operator Instructions (later page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

An emergency event requires the Emergency Response Data System (ERDS) datalink to the NRC to be established.

The Local Area Network (LAN) is out of service.

INITIATING CUES:

You have been directed to activate the ERDS datalink to the NRC in accordance with the backup method in SOP-34, Palisades Plant Computer (PPC) System, section 7.5.2.

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of SOP-34, section 7.5.2.

Proc. Step TASK ELEMENT 1 STANDARD Grade 7.5.2a SELECT/ENTER the EMERGENCY, OFFNORM, POST TRIP menu from the Main Menu ENTERS EMERGENCY menu from the Main Menu S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade 7.5.2b SELECT/ENTER ERDS ACTIVATION &

STATUS ERDS ACTIVATION & STATUS SELECTED from EMERGENCY menu S U Comment:

CRITICAL STEP EVALUATOR NOTE: Candidate can perform either step 7.5.2.c.1 OR 7.5.2.c.2a-c to successfully start ERDS.

Proc. Step TASK ELEMENT 3 STANDARD Grade 7.5.2c.1 DEPRESS the START DATALINK OR STOP DATALINK Softkey.

START DATALINK Softkey DEPRESSED.

S U Comment:

EVALUATOR NOTE: If Candidate performed this step correctly, then go to Task Element #7.

CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade 7.5.2c.2(a)

SELECT DATALINK (ON/OFF) square DATALINK (ON/OFF) square SELECTED S U Comment:

CRITICAL STEP

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012 Proc. Step TASK ELEMENT 5 STANDARD Grade 7.5.2c.2(b)

TYPE 1 to turn ERDS on OR TYPE 0 to turn ERDS off TYPES "1" to turn ERDS DATALINK on S U Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade 7.5.2c.2(c)

DEPRESS the UPDATE Hardkey, THEN DEPRESS the RETURN key UPDATE Hardkey DEPRESSED, then RETURN key DEPRESSED S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade n/a Notify the CRS that ERDS Datalink to the NRC has been activated CRS notified S U Comment:

EVALUATOR CUE: If notified as CRS of ERDS activation, Acknowledge.

END OF TASK

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS None

JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

An emergency event requires the Emergency Response Data System (ERDS) datalink to the NRC to be established.

The Local Area Network (LAN) is out of service.

INITIATING CUES:

You have been directed to activate the ERDS datalink to the NRC in accordance with the backup method in SOP-34, Palisades Plant Computer (PPC) System, step 7.5.2.

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 1b TITLE: REVIEW AND APPROVE PCS LEAK RATE CANDIDATE:

EXAMINER:

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Review A Primary Coolant System Leak Rate Alternate Path: N/A Facility JPM #: BANK K/A:

2.1.25 Importance:

SRO:

4.2 K/A Statement: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Task Standard: Recognize incorrect data and resultant erroneous leak rate. Recognize revised leak rate exceeding action level.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

DWO-1, Operators Daily/Weekly Items MODES 1, 2, 3, and 4 Validation Time:

30 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Printouts sets (2) from PPC of Pages 550 and 551

  • First set created using initial (incorrect) data, = Cue Sheets #2A and 2B
  • Second set created using correct data, = Cue Sheets #3A and 3B DWO-1, Section 5.1 place-keep steps 5.1.9.a through bb DWO-1, Section 3.3.1 and 4.4 Also see Simulator Operator Instructions (later page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

A PCS leakrate calculation using the PPC has been completed per DWO-1, step 5.1.9 based on the following initial and final parameters:

  • PZR level maintained within 0.3% of level span
  • TAVE maintained within 0.2°F
  • Rx Power maintained within 0.2% of rated power
  • No manual VCT adjustments were made to VCT Pressure
  • No diversions have been made
  • No PMW additions have been made to the PCS
  • T-90 Primary Makeup Water Tank temperature is 72.0 °F
  • No PCS sampling was conducted
  • Controlled Bleed-Off is aligned to the VCT
  • Zinc addition is 2.36 liters/day (from OPS log)
  • Charging Pump Seal leakage (total) is 105 ml/min
  • CRDM Seal leakage is 10 ml/min
  • A S/G has 434 tubes plugged and B S/G has 393 tubes plugged
  • No known leakage sources outside the PCS Pressure Boundary (PCPB)
  • No known leakage sources inside the PCPB INITIATING CUES:

The NCO-R has just completed a PCS Leak Rate, DWO-1, per step 5.1.9 and requests that you review and approve it per steps 5.1.9.cc through gg.

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012 EVALUATOR CUE: Provide candidate with PPC Page 550 and 551 (Cue Sheets 2A and 2B) and a working copy of DWO-1 Section 5.1 (steps 5.1.9.a through bb already marked as completed).

If candidate wishes to review plant conditions and precautions and limitations, provide these as well (they are located in the JPM package).

Proc. Step TASK ELEMENT 1 STANDARD Grade 5.1.9.cc REQUEST an on-shift SRO to review AND VALIDATE the PCS leakrate data by verifying the initial and final parameters are within the allowable deviation. Any warning conditions received will need to be evaluated by an On-Shift SRO for impact on the leakrate calculation.

Candidate reviews table and determines all parameters were maintained within required deviation.

S U Comment:

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.9.dd IF PCS leakrate is valid, THEN the on-shift SRO will SIGN the validation signature block on PPC page 551, PCS SNAPSHOT LR DETAILS printout.

Candidate signs validation block.

S U Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.9.ee IF PCS leakrate is NOT valid, THEN PERFORM the following:

1. DOCUMENT reason for invalid result on PPC printouts
2. REPEAT or defer the PCS leakrate until the Plant is in a more stable condition.

Candidate determines step is N/A.

S U Comment:

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.9.ff REQUEST an on-shift SRO to review AND SIGN the PCS leakage calculation on PPC page 550, PCS LEAKRATE SNAPSHOT printout.

Candidate determines incorrect CRDM leakoff value used.

S U Comment:

EVALUATOR CUE: When candidate determines that another PCS leakrate is needed, report that a second leakrate has been completed and hand candidate Cue Sheets #3A and 3B.

CRITICAL STEP EVALUATOR NOTE: Since this is a new leakrate calculation, candidate should start over at step 5.1.9.cc.

Proc. Step TASK ELEMENT 5 STANDARD Grade 5.1.9.cc REQUEST an on-shift SRO to review AND VALIDATE the PCS leakrate data by verifying the initial and final parameters are within the allowable deviation. Any warning conditions received will need to be evaluated by an On-Shift SRO for impact on the leakrate calculation.

Candidate reviews table and determines all parameters were maintained within required deviation.

S U Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade 5.1.9.dd IF PCS leakrate is valid, THEN the on-shift SRO will SIGN the validation signature block on PPC page 551, PCS SNAPSHOT LR DETAILS printout.

Candidate signs validation block.

S U Comment:

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 7 STANDARD Grade 5.1.9.ee IF PCS leakrate is NOT valid, THEN PERFORM the following:

1. DOCUMENT reason for invalid result on PPC printouts
2. REPEAT or defer the PCS leakrate until the Plant is in a more stable condition.

Candidate determines step is N/A.

S U Comment:

Proc. Step TASK ELEMENT 8 STANDARD Grade 5.1.9.ff REQUEST an on-shift SRO to review AND SIGN the PCS leakage calculation on PPC page 550, PCS LEAKRATE SNAPSHOT printout.

Candidate determines that PCS leakrate calculation is correct and signs Page 550.

S U Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade 5.1.9.gg GO TO Section 5.1.10, PCS Leakage Calculation Completion.

Candidate refers to step 5.10.

S U Comment:

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 10 STANDARD Grade 5.1.10.a RECORD PCS leakage data in PCS Leak Rate Monitoring Program data base AND ANALYZE in accordance with ADMIN 4.19, PCS Leak Rate Monitoring Program.

Candidate attempts to perform this step.

S U Comment:

EVALUATOR CUE: Inform candidate that another SRO will complete step 5.1.10.a.

Proc. Step TASK ELEMENT 11 STANDARD Grade 5.1.10.b IF PCS Unidentified Leakage is greater than or equal to 0.10 gpm, THEN PERFORM the following:

1. NOTIFY Chemistry to determine the current steam generator primary to secondary leakage in accordance with Chemistry Procedure CH 3.31, "Primary to Secondary Leak Rate Determination,"

(based on Xe-133) AND RECORD to the nearest 0.001 gpm as known leakage sources inside the PCPB on Attachment 8, Step 3.b, or PPC page 550 as applicable.

Candidate determines leakrate has exceeded threshold for requiring Chemistry to perform a primary to secondary leakrate calculation.

S U Comment:

EVALUATOR CUE: When SRO attempts to notify Chemistry, then end this JPM.

CRITICAL STEP END OF TASK

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 8 of 9 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS

  • NONE, however, simulator needs to be used prior to administering this JPM to create PPC Pages 550 and 551 as follows:

o Reset to IC-17 o Insert a 0.12 PCS leak and go to RUN.

o Perform a PPC Leak Rate per DWO-1 with the variables listed on the candidate cue sheet except:

Use 160 ml/min for CRDM leakoff rate (instead of 10 ml/min) o Printout PPC Pages 550 and 551 per DWO-1 and mark as Cue Sheets

  1. 2A and 2B o Sign and date PPC Page 550 as Reactor Operator o Reset to IC-17 o Insert a 0.12 PCS leak and go to RUN.

o Perform a PPC Leak Rate per DWO-1 with the variables listed on the candidate cue sheet o Printout PPC Pages 550 and 551 per DWO-1 and mark as Cue Sheets

  1. 3A and 3B o Sign and date PPC Page 550 as Reactor Operator

JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A PCS leakrate calculation using the PPC has been completed per DWO-1, step 5.1.9 based on the following initial and final parameters:

  • PZR level maintained within 0.3% of level span
  • TAVE maintained within 0.2°F
  • Rx Power maintained within 0.2% of rated power
  • No manual VCT adjustments were made to VCT Pressure
  • No diversions have been made
  • No PMW additions have been made to the PCS
  • T-90 Primary Makeup Water Tank temperature is 72.0 °F
  • No PCS sampling was conducted
  • Controlled Bleed-Off is aligned to the VCT
  • Zinc addition is 2.36 liters/day (from OPS log)
  • Charging Pump Seal leakage (total) is 105 ml/min
  • CRDM Seal leakage is 10 ml/min
  • A S/G has 434 tubes plugged and B S/G has 393 tubes plugged
  • No known leakage sources outside the PCS Pressure Boundary (PCPB)
  • No known leakage sources inside the PCPB INITIATING CUES:

The NCO-R has just completed a PCS Leak Rate, DWO-1, per step 5.1.9 and requests that you review and approve it per steps 5.1.9.cc through gg.

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 1a TITLE: DETERMINE COMPENSATION FOR A WITHDRAWN, INOPERABLE CONTROL ROD CANDIDATE:

EXAMINER:

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 2 of 15 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path: N/A Facility JPM #: 2010 NRC EXAM K/A:

2.1.37 Importance:

SRO:

4.6 K/A Statement: Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Task Standard: Designated critical steps of EM-04-08, Attachment 1 completed within tolerances per key.

Preferred Evaluation Location: ANY

__X___

Preferred Evaluation Method:

Perform __X___ Simulate

References:

EM-04-08, Shutdown Margin Requirements Tech Data Book Validation Time:

30 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT

______ UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 3 of 15 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EM-04-08, Shutdown Margin Requirements Technical Data Book Calculator 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:

  • Core Burnup is 7,000 MWd/MTU.
  • The Reactor has been at full power for several weeks.

INITIATING CUES:

The Control Room Supervisor directs you to perform a Shutdown Margin calculation for Control Rod #6 being untrippable in accordance with EM-04-08, attachment 1.

[Provide a calculator to the examinee for this JPM.]

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 4 of 15 OCTOBER 2012 EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 1.

EVALUATOR NOTE: Answers on key marked in Bold with

  • are critical steps.

Proc.

Step TASK ELEMENT 1 STANDARD Grade 1

Record inoperable control rod identification.

A, 6' and untrippable recorded.

S U Comment:

Proc.

Step TASK ELEMENT 2 STANDARD Grade 2

Record worth of inoperable control rod.

1.29 (1.28 to 1.30) entered.

S U Comment:

EVALUATOR CUE: If asked, Reactor Engineering is not available.

Proc.

Step TASK ELEMENT 3 STANDARD Grade 3

Record source of inoperable control rod worth data.

'Tech Data Book' entered.

S U Comment:

Proc.

Step TASK ELEMENT 4 STANDARD Grade 4.A Record current cycle burnup.

7000 entered.

S U Comment:

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 5 of 15 OCTOBER 2012 Proc.

Step TASK ELEMENT 5 STANDARD Grade 4.B Record current power level.

'100' entered.

S U Comment:

Proc.

Step TASK ELEMENT 6 STANDARD Grade 4.C Control rod worth inserted into core.

0' and Gp 4 @ 132 entered.

S U Comment:

EVALUATOR NOTE: The only critical part of this step is to enter 0.

CRITICAL STEP Proc.

Step TASK ELEMENT 7 STANDARD Grade 4.D Record PCS Boron concentration.

'860' entered (given in stem).

S U Comment:

Proc.

Step TASK ELEMENT 8 STANDARD Grade 5.E Determine and record worth of control rods at current power level.

'7.09 (7.07 to 7.11)' entered.

S U Comment:

EVALUATOR NOTE: This will need to be obtained by interpolation.

CRITICAL STEP

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 6 of 15 OCTOBER 2012 Proc.

Step TASK ELEMENT 9 STANDARD Grade 5.F Determine and record max worth of stuck rod at current power.

1.29 (1.28 to 1.30) entered.

S U Comment:

EVALUATOR NOTE: This is the same value as step #2.

Proc.

Step TASK ELEMENT 10 STANDARD Grade 5.G Determine and record PCS boron concentration at 100% at 7000 MWD/MTU.

860 entered (given in stem).

S U Comment:

EVALUATOR NOTE: Since power is 100%, this is given.

Proc.

Step TASK ELEMENT 11 STANDARD Grade 5.H Determine and record power defect for 100% power.

1.55 (1.53 to 1.57) entered.

S U Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 12 STANDARD Grade 5.I Determine and record power defect at current power level.

1.55 (1.53 to 1.57) entered.

S U Comment:

EVALUATOR NOTE: Since power is 100%, this number will be the same as 5.H.

CRITICAL STEP

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 7 of 15 OCTOBER 2012 Proc.

Step TASK ELEMENT 13 STANDARD Grade 5.J Determine and record required SDM.

'2.0' already entered.

S U Comment:

Proc.

Step TASK ELEMENT 14 STANDARD Grade 6.K Calculate Net amount of shutdown margin.

1.72 (1.67 to 1.77) entered.

S U Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 15 STANDARD Grade 6.L Enter worth of untrippable rod.

1.29 (1.28 to 1.30) entered.

S U Comment:

EVALUATOR NOTE: This will be the same value as step #2.

CRITICAL STEP Proc.

Step TASK ELEMENT 16 STANDARD Grade 6.M Determine excess shutdown margin with the inoperable rod.

0.43 (0.37 to 0.49) entered.

S U Comment:

CRITICAL STEP

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 8 of 15 OCTOBER 2012 Proc.

Step TASK ELEMENT 17 STANDARD Grade 7.N-Q IF Shutdown margin is negative, THEN Determines Step 7 substeps are N/A.

S U Comment:

Proc.

Step TASK ELEMENT 18 STANDARD Grade 8.R Determine and record PPC PDIL for current power level.

Group 4 at 101 (100 to 105) entered.

S U Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 19 STANDARD Grade 8.S Determine and record control rod position corresponding to excess shutdown margin.

Group 4 at 34 (28 to 40) entered.

S U Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 20 STANDARD Grade 8.T Determine and record PDIL for inoperable control rod condition.

Group 4 at 101 (100 to 105) entered.

S U Comment:

CRITICAL STEP

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 9 of 15 OCTOBER 2012 Proc.

Step TASK ELEMENT 21 STANDARD Grade 8.U Determine if Caution Tagging Control Room joy-stick on Panel C-02 is NOT required.

Determines Caution Tagging Control Room joy-stick on Panel C-02 is NOT required.

S U Comment:

Proc.

Step TASK ELEMENT 22 STANDARD Grade 9

Sign and date Step 9.

Operator signs and dates.

S U Comment:

Proc.

Step TASK ELEMENT 23 STANDARD Grade N/A Report results to Control Room Supervisor.

CRS notified.

S U Comment:

EVALUATOR CUE: End JPM EVALUATOR NOTE: Attach completed EM-04-08, Attachment 1 to this JPM.

END OF TASK

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 10 of 15 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS NONE

Proc No EM-04-08 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 1 of 4 PALISADES NUCLEAR PLANT Page 11 of 15 OCTOBER 2012

1.

UNTRIPPABLE OR DROPPED CONTROL ROD IDENTIFICATION:

GROUP A NUMBER ___6_____

CONDITION untrippable (Untrippable or Dropped)

2.

WORTH OF UNTRIPPABLE OR DROPPED

_1.29 __ %

CONTROL ROD 1.28-1.30 (TDB Figure 1.1 or Reactor Engineering)

3.

SOURCE OF UNTRIPPABLE OR DROPPED CONTROL ROD WORTH DATA:

Tech Data Book

4.

REFERENCE DATA A.

CURRENT CYCLE BURNUP (TDB Fig 1.10)

__7000__

MWd/MTU B.

CURRENT REACTOR POWER LEVEL (Percent of Rated Power)

___100___

C.

CONTROL ROD WORTH INSERTED INTO CORE (TDB Fig 1.3)

GROUP 4 INCHES __132 __

This Control Rod worth does not include the worth of a dropped Control Rod.

____0*___

D.

PCS BORON CONCENTRATION (Chemistry Log or Reactor Logbook)

___860__

ppm ANSWER KEY

Proc No EM-04-08 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 2 of 4 PALISADES NUCLEAR PLANT Page 12 of 15 OCTOBER 2012

5.

GENERAL DATA E.

WORTH OF ALL CONTROL RODS AT A (TDB Fig 1.1)

__7.09*_

7.07-7.11 F.

MAXIMUM WORTH OF STUCK CONTROL ROD AT A (TDB Fig 1.1)

__1.29__

1.28-1.30 G.

PCS BORON AT 100% POWER AT A (TDB Fig 6.1, Reactor Log)

__860__

ppm H.

POWER DEFECT AT 100% POWER (TDB Fig 3.2 and G)

__1.55*_

1.53-1.57 I.

POWER DEFECT AT POWER B

=

100 (100) x (1.55)

=

100 B

x H

__1.55*_

1.53-1.57 J.

REQUIRED SHUTDOWN MARGIN (4 PCPs Operating) 2.0

6.

CALCULATION K.

NET AMOUNT OF SHUTDOWN MARGIN J

- I 1.1

)

F C

E

(

=

(2.0)

(1.55) 1.1 1.29]

(0)

(7.09)

[

=

__1.72*__

1.67-1.77 ANSWER KEY

Proc No EM-04-08 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 3 of 4 PALISADES NUCLEAR PLANT Page 13 of 15 OCTOBER 2012 L.

WORTH OF UNTRIPPABLE OR DROPPED CONTROL ROD 2

Step

__1.29*_

1.28-1.30 M.

EXCESS SHUTDOWN MARGIN WITH ONE UNTRIPPABLE OR DROPPED CONTROL ROD

=

(1.29)

(1.72)

=

L K

__0.43*_

0.37-0.49

7.

IF excess Shutdown Margin (M) is NEGATIVE, THEN borate the PCS to reduce reactor power until M is POSITIVE performing Steps N through Q to calculate the maximum reduced reactor power level.

N.

POWER DEFECT AT REDUCED POWER

=

)

(

+

)

(

=

M

+

I

___N/A___

O.

MAXIMUM REDUCED POWER LEVEL

=

)

(

)

(

x

)

(

=

I B

x N

___N/A___

P.

Caution Tag the Control Rod joy-stick on panel C-02 that the new PDIL is Control Rod position at C.

N/A Q.

IF power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin requirements are satisfied.

N/A ANSWER KEY

Proc No EM-04-08 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 4 of 4 PALISADES NUCLEAR PLANT Page 14 of 15 OCTOBER 2012

8.

IF M is POSITIVE, THEN sufficient Shutdown Margin is available and no power reduction is necessary to ensure required Shutdown Margin. Perform Steps R though U to determine maximum allowable Control Rod insertion limit corresponding to excess Shutdown Margin available (M).

R.

PPC PDIL FOR CURRENT POWER LEVEL (TDB Fig 1.9)

Group Inches

___4*___

__101*__

100-105 S.

CONTROL ROD POSITION CORRESPONDING TO EXCESS SHUTDOWN MARGIN IN M (TDB Fig 1.3 or 5.1 and M)

Group Inches

___4*__

__34*__

28-40 T.

PDIL FOR UNTRIPPABLE OR DROPPED CONTROL ROD CONDITION (R or S, whichever is farthest withdrawn)

Group Inches

___4*___

__101*__

100-105 U.

IF the Control Rod position in S is farther withdrawn than the Control Rod position in R, THEN Caution Tag the Control Rod joy-stick on panel C-02, identifying that the new PPC PDIL as the Control Rod position in S.

N/A

9.

REVIEWS (Operators Name) /

(Today)

Performed By Date

/

Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor

/

Reactor Engineering Supervisor Date ANSWER KEY

JPM SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 15 of 15 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • Core Burnup is 7,000 MWd/MTU.
  • The Reactor has been at full power for several weeks.

INITIATING CUES:

The Control Room Supervisor directs you to perform a Shutdown Margin calculation for Control Rod #6 being untrippable in accordance with EM-04-08, attachment 1.

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 2 TITLE: REVIEW AND APPROVE A COMPLETED TECHNICAL SPECIFICATION SURVEILLANCE TEST CANDIDATE:

EXAMINER:

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Conduct Surveillance Testing Alternate Path: N/A Facility JPM #: BANK K/A:

2.2.12 Importance:

SRO:

4.1 K/A Statement: Knowledge of Surveillance Procedures Task Standard: Supervisory Review of MO-29 completed in accordance with MO-29, step 5.3 AND LCO 3.6.6.A entered due to left train Containment Spray inoperable.

Preferred Evaluation Location: ANY

_X_

Preferred Evaluation Method:

Perform

_X_

Simulate

References:

ADMIN 9.20, Technical Specification Surveillance and Special Test Program MO-29, Engineered Safety System Alignment Validation Time:

30 minutes Time Critical:

NO Candidate:

Time Start: ________

Time Finish:

Performance Time:

________ minutes Performance Rating:

SAT______

UNSAT ______

Comments:

Examiner: _______________________________

Date:

Signature

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

  • Completed MO-29, Engineered Safety System Alignment, with one data point for Containment Spray Header pressure (PI-3001) below the acceptance range.

Also include a missed signature date.

  • ADMIN 9.20, Technical Specification Surveillance and Special Test Program
  • Technical Specifications
  • Technical Specifications Bases 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:

  • Its Friday night shift, 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.
  • You are an on-shift SRO.
  • MO-29, Engineered Safety System Alignment, 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 MO-29, Engineered Safety System Alignment, in accordance with step 5.3 of MO-29.

Evaluator Note: Provide candidate with completed MO-29 with the data point for Containment Spray Header 'B' pressure (PI-3001) below the acceptance range at 61.8 psig. Do not circle the reading in red. Also, include a missed signature date for step 3.1 Authorization.

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012 EVALUATOR CUE: Hand candidate a complete MO-29 Surveillance Test with one spray header pressure (PI-3001) indication below the acceptance criteria.

Proc. Step TASK ELEMENT 1 STANDARD Grade 5.3.1.a REVIEW MO-29 to ensure all applicable components have been inspected.

All pages present with all blanks filled in or N/A except for the date field of step 3.1 Authorization.

S U Comment:

EVALUATOR NOTE: The missed signature date is not a critical task Proc. Step TASK ELEMENT 2 STANDARD Grade 5.3.1.b ENSURE entries on MO-29 are circled in red for any components found in an incorrect position OR acceptance criteria not met.

Operator reviews section 6.0 of MO-29 and verifies the following:

___ Containment Air Cooler 'A' Fans operated for greater than or equal to 15 minutes.

___ Containment Spray Header pressure gauges (PI-3001 and PI-3001) greater than or equal to 62.0 psig.

___ "As Found" position of applicable fans, valves, breakers, and controls agrees with "Required Position" listed in MO-29 Checklist (Attachment 1).

___ All out of tolerance data shall be circled in red.

S U Comment:

EVALUATOR NOTE: The containment spray header pressure reading for PI-3001 is below the acceptance range. The candidate must recognize this.

CRITICAL STEP

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 3 STANDARD Grade 5.3.1.c INITIATE a Condition Report in accordance with EN-LI-102, Corrective Action Process, for acceptance criteria not met unless at least one of the following conditions exist:

1. Out of tolerance item is controlled by a previously identified LCO.
2. Component is in position resulting from prior Operations review and approval. To allow alternate position of any component, adequate redundancy shall exist to ensure operability of Engineering Safety System Equipment.

Operator determines that this step is applicable and recognizes that a CR should be initiated.

S U Comment:

EVALUATOR CUE: Inform candidate that CR has been initiated Proc. Step TASK ELEMENT 4 STANDARD Grade 5.3.1.d IF spray header pressures are less than 62.8 psig, THEN NOTIFY System Engineer to determine if Containment Spray Header Fill can wait until the next scheduled performance of MO-29 based on MO-29 trend data analysis.

1.

System Engineer: NOTIFY Planning/Scheduling and Operations when to schedule ESSO-1, Containment Spray Header Fill.

Operator notifies System Engineer.

S U Comment:

EVALUATOR CUE: If asked as System Engineer: report that the containment spray header fill can not wait until the next scheduled performance of MO-29 and they will notify Planning/Scheduling.

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 5 STANDARD Grade 5.3.1.e COMPLETE Acceptance Criteria and Operability Sheet.

Operator performs the following for the acceptable criteria and operability sheet:

___

  • Answers #1 NO and signs and provides explanation on page 2 (i.e., Spray Header pressure PI-3001 is below acceptance range) (signature is not part of the critical step)

___

  • Answers #2 NO and signs (signature is not part of the critical step)

___ Completes CAP and WR numbers for #3

___ Notifies SM/CRS/SE and signs for #4 (signature is not part of the critical step)

___

  • Operator reviews LCO 3.6.6A.1 and determines that left train of Containment Cooling system is inoperable and LCO Action A.1 of LCO 3.6.6 has been entered.

The Yes or NO box will be checked for #5 and justification filled out on page 2. This justification should explain that the plant has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore left train of containment cooling system back to operable status or place the plant in a MODE where the LCO is not applicable.

S U Comment:

EVALUATOR CUE: If asked, supply candidate with the following:

  • WR#: 02004567 (not required since this is an Operations activity, per ESSO-1, and is not controlled by Work Order process.)

EVALUATOR CUE: Inform candidate that SM/CRS/SE have been notified.

EVALUATOR CUE: If asked, candidate also performs Step 5. System Engineer will perform Step 6, Tech. Rev.

  • CRITICAL STEP

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012 Proc. Step TASK ELEMENT 6 STANDARD Grade 5.3.2 On Shift SRO Reviewed Completed by:

Operator signs and dates for SRO Review S U Comment:

END OF TASK

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 8 of 9 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS N/A

JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

  • Its Friday night shift, 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.
  • You are an on-shift SRO.
  • MO-29, Engineered Safety System Alignment, 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 MO-29, Engineered Safety System Alignment, in accordance with step 5.3 of MO-29.

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 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012 JOB PERFORMANCE MEASURE DATA PAGE Task:

Determine maximum permissible stay time Alternate Path: N/A Facility JPM #: NEW K/A:

2.3.4 Importance

SRO:

3.7 K/A Statement: Knowledge of radiation exposure limits under normal or emergency conditions.

Task Standard: Maximum time to perform Task #2 is calculated to be 16.59 to 16.86 minutes.

Preferred Evaluation Location: ANY

__X__

Preferred Evaluation Method:

Perform

__X__

Simulate

References:

EI-2.1, Emergency Plant Manager 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

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-2.1, Emergency Plant Manager 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 Loss of Coolant Accident outside Containment occurred. A General Emergency was declared due to the plant conditions (fuel failure is evident) and a radioactive release is in progress. Electrical power for all buses is from offsite power. D/G 1-1 was inadvertently started during EOP-1.0, Standard Post Trip Actions, and has lost Service Water cooling.

Worker #1 year-to-date dose = 1.85 R TEDE. Worker #1 has performed the following task for this event:

TASK DOSE RECEIVED 1

Search of Auxiliary Building for missing person during accountability 3.2 R The following additional outside the Control Room task is now required for equipment protection:

TASK DOSE RATE 2

Trip D/G 1-1 (D/G is operating but is not loaded) 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 Task 2. Your task is to determine the maximum time Worker #1 can take to perform Task 2 without exceeding any established emergency dose limits. Report your results to the Shift Manager.

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012 Proc.Step TASK ELEMENT 1 STANDARD Grade Determine total dose received by Worker #1.

Calculates dose received to be 5.05R (Allow 5.0 - 5.1).

S U Comment:

(3.2R) + (1.85R) = 5.05 R EVALUATOR NOTE: Candidate may combine task elements 1 and 2.

CRITICAL STEP Proc.Step TASK ELEMENT 2 STANDARD Grade Determine dose remaining from emergency dose limits.

Dose remaining determined to be 4.95 R (Allow 4.9 - 5.0).

Candidate may use EI-2.1, Site Emergency Director to determine 10R emergency dose limit.

S U Comment:

(10R) - (5.05) = 4.95 R EVALUATOR CUE: If candidate asks which emergency dose limit is being considered for Task #2, inform them to determine this from plant conditions.

EVALUATOR CUE: If asked, inform candidate that the worker does not desire to volunteer dose limit above 25R.

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade Determine time available for Worker #1 to complete Task #2 without exceeding emergency dose level.

Time available calculated to be 16.73 min (allow 16 - 17).

S U Comment:

(Available Dose)/(Dose Rate) = (4.95 R)/(17.75 R/hr) = 0.2788 hr x (60 min/hr) = 16.73 minutes (accept 16 to 17 minutes)

CRITICAL STEP

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade n/a Inform the Shift Manager of calculation results.

Inform the Shift Manager that the maximum time Worker #1 can take to perform Task 2 without exceeding any established emergency dose limits is 16.73 minutes (allow 16 - 17).

S U Comment:

END OF TASK

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS

  • No Simulator setup required.

JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant was at 100% power when a Loss of Coolant Accident outside Containment occurred. A General Emergency was declared due to the plant conditions (fuel failure is evident) and a radioactive release is in progress. Electrical power for all buses is from offsite power. D/G 1-1 was inadvertently started during EOP-1.0, Standard Post Trip Actions, and has lost Service Water cooling.

Worker #1 year-to-date dose = 1.85 R TEDE. Worker #1 has performed the following task for this event:

TASK DOSE RECEIVED 1

Search of Auxiliary Building for missing person during accountability 3.2 R The following additional outside the Control Room task is now required for equipment protection:

TASK DOSE RATE 2

Trip D/G 1-1 (D/G is operating but is not loaded) 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 Task 2. Your task is to determine the maximum time Worker #1 can take to perform Task 2 without exceeding any established emergency dose limits. Report your results to the Shift Manager.

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