ML13070A428

Proposed RO & SRO Admin JPMs

ML13070A428
Person / Time
Site:	Palisades
Issue date:	03/11/2013
From:	Walton R NRC/RGN-III/DRS/OLB
To:
References
Download: ML13070A428 (74)

Text

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 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 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012

JPM RO ADMIN 1a 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).

PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012

JPM RO ADMIN 1a EVALUATOR CUE: Provide candidate with a working copy of EOP-5.0 Step 54.

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

Comment:

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

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

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

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

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

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012

JPM RO ADMIN 1a 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 If predicted PCS boron concentration is less than cold shutdown boron concentration, THEN 54.b RAISE PCS boron in preparation of backflow of 47 ppm determined (allow 45 to 50 ppm) S U the isolated S/G.

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 PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012

JPM RO ADMIN 1a SIMULATOR OPERATOR INSTRUCTIONS None required.

PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012

JPM RO ADMIN 1a 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).

PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012

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 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 PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012

JPM RO ADMIN 1b 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.

PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012

JPM RO ADMIN 1b EVALUATOR CUE: Provide candidate with a working copy of DWO-1, 5.2.3.

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

1. SELECT the current display number in upper left corner of display.

2. TYPE in desired display number (521).

5.2.3.a 3. DEPRESS UPDATE key. Observe PPC Page 521 is showing on the PPC screen. S U Parametering Done next to entered typing.

4. DEPRESS the right mouse button.

Display will change to desired.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade IF UFM CAL ENABLED will be changed 5.2.3.c Candidate determines this step is N/A. S U from NOT ENABLED to ENABLED....

Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade If UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN TDB Figure 14.1 new line entry made:

perform the following:

5.2.3.d.1 Todays date entered in Date column S U

1. UPDATE TDB Figure 14.1 indicating UFM CAL ENABLED status. NO entered in Calibration Enabled column.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 4 STANDARD Grade Attachment 12 referenced: first row on page 1 ENSURE HB_PWR_STEADY is lowered (right hand column-top).

to the 100% thermal power limit allowed by Candidate verifies that 93% power conforms to 5.2.3.d.2 S U Attachment 12, 100% Thermal Power REDUCE Reactor Power by Total UFM Limit. Correction Factor Worth in the TDB Figure 12.1 plus an additional 0.65%.

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 UFM CAL ENABLED selected

3. SELECT UFM CAL ENABLED 5.2.3.d 4. ENTER N for no N entered [may use 0] S U

5. PRESS UPDATE hardkey UPDATE hardkey depressed Comment:

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

PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 7 STANDARD Grade If a change to UFM Correction Factors is 1. TDB Figure 14.1 new line entry is updated to required, THEN perform the following: by adding a 1.0000 to UFM Correction Factor

1. ENSURE TDB Figure 14.1 is updated A and UFM Correction Factor B columns

2. ENSURE HB_PWR_STEADY is

2. This was completed in step 5.2.3.d.2 acceptable for the new Total UFM 5.2.3f Correction Factor Worth in Technical Data 3, 4. Enters 1.0000 for E-50A (B) UFM S U Book Figure 14.1. Correction factor.

3. SELECT data

5. Depresses UPDATE hardkey

4. ENTER new value

5. PRESS UPDATE hardkey Repeats 3, 4, and 5 for E-50B (A) UFM Correction factor.

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 DETERMINE if Steam Generator Candidate determines S/G B/D flows are NOT 5.2.3.g Blowdown Flows on PPC Page 521 are S U correct.

correct.

Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade If a change to S/G B/D flows is required, PPC Page 521 S/G B/D flows:

THEN perform the following:

Enters 19000 lbm/hr for A S/G Blowdown flow

1. SELECT data 5.2.3.h.1 and depresses UPDATE hardkey S U

2. ENTER new value

3. PRESS UPDATE hardkey Enters 19000 lbm/hr for B S/G Blowdown flow and depresses UPDATE hardkey Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012

JPM RO ADMIN 1b Proc. Step TASK ELEMENT 10 STANDARD Grade 5.2.3.d.7 Candidate determines that 30 minute wait is 5.2.3.f.6 WAIT approximately 30 minutes S U required.

5.2.3.h.4 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 PRINT out the Heat Balance by PRINTER hardkey depressed.

5.2.3.i S U depressing the PRINTER hardkey Printout of Heat Balance from printer obtained 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 REQUEST and On-Shift SRO to review PRINTER hardkey depressed.

5.2.3.k S U AND sign the printout Printout of Heat Balance form printer obtained Comment:

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

PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012

JPM RO ADMIN 1b 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 PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012

JPM RO ADMIN 1b 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.

PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012

JPM RO ADMIN 1b 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 PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012

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 #: 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 PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012

JPM RO ADMIN 2 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.

PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012

JPM RO ADMIN 2 EVALUATOR CUE: Provide candidate with a partially completed copy of SHO-1.

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

OBTAINS control rod data from PPC pages 411 OBTAIN control rod position data from and 412 Palisades Plant Computer (PPC) Pages 411 and 412. CHECKS PIP and SPI readings agree within 3 and 8" CHECK each control rod position output 5.1.28 S U data between the Primary and Secondary CHECKS each rod is within 8 of all other rods Systems for agreement within 3 (Admin in its associated group.

limit) and 8 (Tech Spec limit).

RECORDS a in Shift A Readings column CHECK each rod is within eight (8) inches INITIALS "RECRD BY" of associated group rod positions.

Comment:

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.29 PDIL Rod Position: CHECKS all rods above PDIL CHECK PPC Page 412, "Regulating Rods 5.1.29 RECORDS a in Shift A Readings column S U Information," indicates control rods above the PDIL limit. INITIALS "RECRD BY" Comment:

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

CHECKS all shutdown and part length CHECK "Control Rod Monitoring" PPC rods 128" Pages 411 and 412 indicate each 5.1.30 S U Shutdown Control Rod Group and RECORDS a in Shift A Readings column Part-Length Control Rod Group is INITIALS "RECRD BY" withdrawn to greater than or equal to 128 inches.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 4 STANDARD Grade Linear Heat Rate: CHECKS Incore flux below alarm limits 5.1.31 CHECK Incore flux below alarm limits as RECORDS a in Shift A Readings column S U indicated on PPC screens 512 and 513.

INITIALS RECRD BY 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 RECORDS Main Feed Temperatures from REC-C11-03 in Shift A Readings column Main Feed Temperature:

CHECK unfiltered Main Feed RECORDS Main Feed Temperatures from PPC 5.1.32 temperatures on PPC Page 521 are within Page 521 in Shift A Readings column S U 10°F of associated readings on CHECKS Main Feed temperatures on PPC REC-C11-03.

Page 521 are within 10°F of associated readings on REC-C11-03 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 DETERMINES 'B' S/G Feedwater Temperature indication on PPC is > 10°F less than 'B' S/G Main Feed Temperature:

Feedwater Temperature on REC-C11-03 CHECK unfiltered Main Feed 5.1.32 temperatures on PPC Page 521 are within CIRCLES in RED one or both 'B' S/G Feedwater S U 10°F of associated readings on Temperatures

• REC-C11-03. 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.

• EVALUATOR NOTE: Not part of the critical step.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 7 STANDARD Grade RECORDS Main Feed Flow from FLIR-0701/0702 in Shift A Readings column Main Feed Flow CHECK unfiltered Main Feed flow on PPC RECORDS Main Feed Flow from PPC Page 5.1.33 521 in Shift A Readings column S U page 521 is within 0.5 E6 PPH of readings on FI-0701 and FI-0703. CHECKS within 0.5 E6 PPH INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 8 STANDARD Grade Auxiliary Feed Flow RECORDS AFW flow to both S/Gs in Shift A CHECK each redundant Auxiliary Feed Readings column 5.1.34 flow instrument reading is within 30 gpm of S U VERIFIES all channels agree within 45 gpm its counterpart (45 gpm with no flow to the steam generator). INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade RECORDS PZR level in Shift A Readings Pressurizer Level column CHECK Pressurizer level is less than 5.1.35 S U 62.8% using the PPC Page 325 for Item CHECKS PZR level < 62.8%

LPRZC.

INITIALS RECRD BY Comment:

PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 10 STANDARD Grade PCS Cooling Loops In Modes 1 and 2, CHECK all four Primary Coolant Pumps in operation circulating CHECKS all PCPs operating 5.1.36 coolant. RECORDS a in Shift A Readings column S U In Mode 3, CHECK both PCS Loops INITIALS RECRD BY OPERABLE with at least one PCP in one PCS Loop operating.

Comment:

Proc. Step TASK ELEMENT 11 STANDARD Grade CHECKS both PORV block valves indicate PORV Block Valve Position Indication closed 5.1.37 CHECK each PORV Block Valve position S U RECORDS a in Shift A Readings column indication is as expected.

INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 12 STANDARD Grade SIT Isolation Valve Position CHECKS SIT Isolation Valve, MO-3041, 5.1.38 CHECK each Safety Injection Tank MO-3045, MO-3049, MO-3052, position S U Isolation Valve is fully open using Control Room indication. 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)

PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 13 STANDARD Grade DETERMINES MO-3045 is out of spec due to being in the mid-position SIT Isolation Valve Position RECORDS a in Shift A Readings column for CHECK each Safety Injection Tank each valve except MO-3045 *. Candidate may 5.1.38 either leave the MO-3045 space blank or place S U Isolation Valve is fully open using Control Room indication. 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.

• EVALUATOR NOTE: Not part of the critical step CRITICAL STEP Proc. Step TASK ELEMENT 14 STANDARD Grade SIRWT Recirc Valve Position CHECKS SIRWT Recirc Valves, CV-3027 and CV-3056, valves and handswitches indicate CHECK SIRWT Recirc Valves, CV-3027 open 5.1.39 and CV-3056, and the associated S U handswitches are in the OPEN position RECORDS a in Shift A Readings column using Control Room indication.

INITIALS RECRD BY Comment:

Proc. Step TASK ELEMENT 15 STANDARD Grade Return completed SHO-1 to CRS and 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 (if S U already done) not already done)

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012

JPM RO ADMIN 2 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.

PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012

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 <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.

PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012

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 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 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012

JPM RO ADMIN 4 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.

PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012

JPM RO ADMIN 4 EVALUATOR CUE: Provide candidate with a working copy of SOP-34, section 7.5.2.

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

CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade SELECT/ENTER ERDS ACTIVATION & ERDS ACTIVATION & STATUS SELECTED 7.5.2b S U STATUS from EMERGENCY menu 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 DEPRESS the START DATALINK OR 7.5.2c.1 START DATALINK Softkey DEPRESSED. S U STOP DATALINK Softkey.

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 PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012

JPM RO ADMIN 4 Proc. Step TASK ELEMENT 5 STANDARD Grade TYPE 1 to turn ERDS on OR TYPE 0 to 7.5.2c.2(b) TYPES "1" to turn ERDS DATALINK on S U turn ERDS off Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade DEPRESS the UPDATE Hardkey, THEN UPDATE Hardkey DEPRESSED, then 7.5.2c.2(c) S U DEPRESS the RETURN key RETURN key DEPRESSED Comment:

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

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

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012

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

JPM RO ADMIN 4 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.

PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012

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 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 PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012

JPM SRO ADMIN 1b 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 Boric Acid Additions were made

• 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.

PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012

JPM SRO ADMIN 1b 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 REQUEST an on-shift SRO to review AND VALIDATE the PCS leakrate data by verifying the initial and final parameters are Candidate reviews table and determines all 5.1.9.cc within the allowable deviation. Any warning parameters were maintained within required S U conditions received will need to be deviation.

evaluated by an On-Shift SRO for impact on the leakrate calculation.

Comment:

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

Comment:

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

1. DOCUMENT reason for invalid result on 5.1.9.ee Candidate determines step is N/A. S U PPC printouts

2. REPEAT or defer the PCS leakrate until the Plant is in a more stable condition.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 4 STANDARD Grade REQUEST an on-shift SRO to review AND SIGN the PCS leakage calculation on PPC Candidate determines incorrect CRDM leakoff 5.1.9.ff S U page 550, PCS LEAKRATE SNAPSHOT value used.

printout.

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 REQUEST an on-shift SRO to review AND VALIDATE the PCS leakrate data by verifying the initial and final parameters are Candidate reviews table and determines all 5.1.9.cc within the allowable deviation. Any warning parameters were maintained within required S U conditions received will need to be deviation.

evaluated by an On-Shift SRO for impact on the leakrate calculation.

Comment:

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

Comment:

PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 7 STANDARD Grade IF PCS leakrate is NOT valid, THEN PERFORM the following:

1. DOCUMENT reason for invalid result on 5.1.9.ee Candidate determines step is N/A. S U PPC printouts

2. REPEAT or defer the PCS leakrate until the Plant is in a more stable condition.

Comment:

Proc. Step TASK ELEMENT 8 STANDARD Grade REQUEST an on-shift SRO to review AND SIGN the PCS leakage calculation on PPC Candidate determines that PCS leakrate 5.1.9.ff S U page 550, PCS LEAKRATE SNAPSHOT calculation is correct and signs Page 550.

printout.

Comment:

Proc. Step TASK ELEMENT 9 STANDARD Grade GO TO Section 5.1.10, PCS Leakage 5.1.9.gg Candidate refers to step 5.10. S U Calculation Completion.

Comment:

PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012

JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 10 STANDARD Grade RECORD PCS leakage data in PCS Leak Rate Monitoring Program data base AND 5.1.10.a Candidate attempts to perform this step. S U ANALYZE in accordance with ADMIN 4.19, PCS Leak Rate Monitoring Program.

Comment:

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

Proc. Step TASK ELEMENT 11 STANDARD Grade 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 Candidate determines leakrate has exceeded 5.1.10.b secondary leakage in accordance with threshold for requiring Chemistry to perform a S U Chemistry Procedure CH 3.31, "Primary to primary to secondary leakrate calculation.

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.

Comment:

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

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012

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

JPM SRO ADMIN 1b 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 Boric Acid Additions were made

• 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.

PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012

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 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 PALISADES NUCLEAR PLANT Page 2 of 15 OCTOBER 2012

JPM SRO ADMIN 1a 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:

• Control Rod #6 is declared INOPERABLE and untrippable.

• Control Rod #6 is fully withdrawn.

• Core Burnup is 7,000 MWd/MTU.

• The Reactor has been at full power for several weeks.

• PCS Boron is 860 ppm.

• All Control Rods are fully withdrawn.

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.]

PALISADES NUCLEAR PLANT Page 3 of 15 OCTOBER 2012

JPM SRO ADMIN 1a 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 Record inoperable control rod 1 A, 6' and untrippable recorded. S U identification.

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 Record source of inoperable control 3 'Tech Data Book' entered. S U rod worth data.

Comment:

Proc.

Step TASK ELEMENT 4 STANDARD Grade 4.A Record current cycle burnup. 7000 entered. S U Comment:

PALISADES NUCLEAR PLANT Page 4 of 15 OCTOBER 2012

JPM SRO ADMIN 1a 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 Determine and record worth of control 5.E '7.09 (7.07 to 7.11)' entered. S U rods at current power level.

Comment:

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

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 15 OCTOBER 2012

JPM SRO ADMIN 1a Proc.

Step TASK ELEMENT 9 STANDARD Grade Determine and record max worth of 5.F 1.29 (1.28 to 1.30) entered. S U stuck rod at current power.

Comment:

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

Proc.

Step TASK ELEMENT 10 STANDARD Grade Determine and record PCS boron 5.G concentration at 100% at 860 entered (given in stem). S U 7000 MWD/MTU.

Comment:

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

Proc.

Step TASK ELEMENT 11 STANDARD Grade Determine and record power defect for 5.H 1.55 (1.53 to 1.57) entered. S U 100% power.

Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 12 STANDARD Grade Determine and record power defect at 5.I 1.55 (1.53 to 1.57) entered. S U current power level.

Comment:

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

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 15 OCTOBER 2012

JPM SRO ADMIN 1a 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 Calculate Net amount of shutdown 6.K 1.72 (1.67 to 1.77) entered. S U margin.

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 Determine excess shutdown margin 6.M 0.43 (0.37 to 0.49) entered. S U with the inoperable rod.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 7 of 15 OCTOBER 2012

JPM SRO ADMIN 1a Proc.

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

Proc.

Step TASK ELEMENT 18 STANDARD Grade Determine and record PPC PDIL for 8.R Group 4 at 101 (100 to 105) entered. S U current power level.

Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 19 STANDARD Grade Determine and record control rod 8.S position corresponding to excess Group 4 at 34 (28 to 40) entered. S U shutdown margin.

Comment:

CRITICAL STEP Proc.

Step TASK ELEMENT 20 STANDARD Grade Determine and record PDIL for 8.T Group 4 at 101 (100 to 105) entered. S U inoperable control rod condition.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 8 of 15 OCTOBER 2012

JPM SRO ADMIN 1a Proc.

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

required.

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 Report results to Control Room N/A CRS notified. S U Supervisor.

Comment:

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

END OF TASK PALISADES NUCLEAR PLANT Page 9 of 15 OCTOBER 2012

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

Proc No EM-04-08 Attachment 1 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 1 of 4

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 __7000__ MWd/MTU (TDB Fig 1.10)

B. CURRENT REACTOR POWER LEVEL ___100___  %

(Percent of Rated Power)

C. CONTROL ROD WORTH INSERTED INTO CORE ____0*___  %

(TDB Fig 1.3)

GROUP 4 INCHES __132 __

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

D. PCS BORON CONCENTRATION ___860__ ppm (Chemistry Log or Reactor Logbook)

ANSWER KEY PALISADES NUCLEAR PLANT Page 11 of 15 OCTOBER 2012

Proc No EM-04-08 Attachment 1 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 2 of 4

5. GENERAL DATA E. WORTH OF ALL CONTROL RODS AT A __7.09*_  %

(TDB Fig 1.1) 7.07-7.11 F. MAXIMUM WORTH OF STUCK CONTROL __1.29__  %

ROD AT A 1.28-1.30 (TDB Fig 1.1)

G. PCS BORON AT 100% POWER AT A __860__ ppm (TDB Fig 6.1, Reactor Log)

H. POWER DEFECT AT 100% POWER __1.55*_  %

(TDB Fig 3.2 and G) 1.53-1.57 I. POWER DEFECT AT POWER B H x B (1.55) x (100) __1.55*_  %

= = 1.53-1.57 100 100 J. REQUIRED SHUTDOWN MARGIN 2.0  %

(4 PCPs Operating)

6. CALCULATION K. NET AMOUNT OF SHUTDOWN MARGIN (E - C - F)

- I- J 1.1

__1.72*__  %

[(7.09) - (0) - 1.29] 1.67-1.77

- (1.55) - (2.0)

1.1 ANSWER KEY PALISADES NUCLEAR PLANT Page 12 of 15 OCTOBER 2012

Proc No EM-04-08 Attachment 1 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 3 of 4 L. WORTH OF UNTRIPPABLE OR __1.29*_  %

DROPPED CONTROL ROD 1.28-1.30 Step 2 M. EXCESS SHUTDOWN MARGIN WITH ONE UNTRIPPABLE OR DROPPED CONTROL ROD K - L = (1.72) - (1.29) = __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 I + M = ( ) + ( ) = ___N/A___  %

O. MAXIMUM REDUCED POWER LEVEL N x B ( )x( ) ___N/A___  %

I ( )

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 N/A requirements are satisfied.

ANSWER KEY PALISADES NUCLEAR PLANT Page 13 of 15 OCTOBER 2012

Proc No EM-04-08 Attachment 1 UNTRIPPABLE OR DROPPED CONTROL ROD Revision 30 SHUTDOWN MARGIN CALCULATION Page 4 of 4

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 Group ___4*___

(TDB Fig 1.9)

Inches __101*__

100-105 S. CONTROL ROD POSITION CORRESPONDING Group ___4*__

TO EXCESS SHUTDOWN MARGIN IN M (TDB Fig 1.3 or 5.1 and M) Inches __34*__

28-40 T. PDIL FOR UNTRIPPABLE OR DROPPED Group ___4*___

CONTROL ROD CONDITION (R or S, whichever is farthest withdrawn) Inches __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 N/A joy-stick on panel C-02, identifying that the new PPC PDIL as the Control Rod position in S.

9. REVIEWS (Operators Name) / (Today)

Performed By Date

/

Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor

/

Reactor Engineering Supervisor Date ANSWER KEY PALISADES NUCLEAR PLANT Page 14 of 15 OCTOBER 2012

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

INITIAL CONDITIONS:

• Control Rod #6 is declared INOPERABLE and untrippable.

• Control Rod #6 is fully withdrawn.

• Core Burnup is 7,000 MWd/MTU.

• The Reactor has been at full power for several weeks.

• PCS Boron is 860 ppm.

• All Control Rods are fully withdrawn.

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.

PALISADES NUCLEAR PLANT Page 15 of 15 OCTOBER 2012

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 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 PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012

JPM SRO ADMIN 2 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.

PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012

JPM SRO ADMIN 2 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 All pages present with all blanks filled in or N/A REVIEW MO-29 to ensure all applicable 5.3.1.a except for the date field of step 3.1 S U components have been inspected.

Authorization.

Comment:

EVALUATOR NOTE: The missed signature date is not a critical task Proc. Step TASK ELEMENT 2 STANDARD Grade 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 ENSURE entries on MO-29 are circled in gauges (PI-3001 and PI-3001) greater than red for any components found in an 5.3.1.b or equal to 62.0 psig. S U incorrect position OR acceptance criteria not met. ___ "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.

Comment:

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

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 3 STANDARD Grade 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. Operator determines that this step is applicable 5.3.1.c S U

2. Component is in position resulting and recognizes that a CR should be initiated.

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.

Comment:

EVALUATOR CUE: Inform candidate that CR has been initiated Proc. Step TASK ELEMENT 4 STANDARD Grade 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 5.3.1.d on MO-29 trend data analysis. Operator notifies System Engineer. S U

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

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.

PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 5 STANDARD Grade 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 COMPLETE Acceptance Criteria and ___ Notifies SM/CRS/SE and signs for #4 5.3.1.e S U Operability Sheet. (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.

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.)

• CR#: CR-PLP-2012-99999.

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 PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012

JPM SRO ADMIN 2 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 PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012

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

JPM SRO ADMIN 2 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.

PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012

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: 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 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012

JPM SRO ADMIN 3 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:

1. TASK DOSE RECEIVED Search of Auxiliary Building for missing person during 1 3.2 R accountability The following additional outside the Control Room task is now required for equipment protection:

1. 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.

PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012

JPM SRO ADMIN 3 Proc.Step TASK ELEMENT 1 STANDARD Grade Determine total dose received by Calculates dose received to be 5.05R

--- S U Worker #1. (Allow 5.0 - 5.1).

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

Determine dose remaining from emergency

--- Candidate may use EI-2.1, Site Emergency S U dose limits.

Director to determine 10R emergency dose limit.

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 Time available calculated to be 16.73 min

--- complete Task #2 without exceeding S U (allow 16 - 17).

emergency dose level.

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 PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012

JPM SRO ADMIN 3 Proc. Step TASK ELEMENT 4 STANDARD Grade Inform the Shift Manager that the maximum Inform the Shift Manager of calculation time Worker #1 can take to perform Task 2 n/a results. without exceeding any established emergency S U dose limits is 16.73 minutes (allow 16 - 17).

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012

JPM SRO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS

• No Simulator setup required.

PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012

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 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:

1. TASK DOSE RECEIVED Search of Auxiliary Building for missing person during 1 3.2 R accountability The following additional outside the Control Room task is now required for equipment protection:

1. 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.

PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012