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2010 Palisades Nuclear Plant Initial Examination Proposed Exam Files Proposed Administrative JPMs
	ML111460133
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Site:	Palisades
Issue date:	08/16/2010
From:	Palagi B; NRC/RGN-III/DRS/OLB
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ML102070539	List: ML111460125; ML111460133; ML111460149; ML111460158; ML111460166;
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2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION PROPOSED EXAM FILES PROPOSED ADMINISTRATIVE JPMs

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROADMIN l a TITLE: DETERMINE QUADRANT POWER TILT PER PO-3 CANDIDATE:

EXAM1NER:

JPM RO ADMIN l a JOB PERFORMANCE MEASURE Task: Determine Quadrant Power Tilt per PO-3 Alternate Path: NIA Facility JPM #: PL-OPS-ENG-014J WA: G2.1.7 Importance: RO: 4.4 SRO: 4.7 WA Statement: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Task Standard: Four Quadrant Power Tilts added together total equals zero & 0.01 per PO-3 Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform X - Simulate

References:

PO-3, Alternate lncore and Excore Applications Validation Time: 12 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 AUGUST 2010

Tools/EquipmenVProcedures Needed:

PO-3, Alternate lncore and Excore Applications, Attachment 2 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITlAL CONDITIONS:

Plant was at full power.

lncores #9 and #35 are inoperable.

CRD #I 1 has dropped into the core.

INITIATING CUES:

During performance of PO-3, Alternate lncore and Excore Applications, the Control Room Supervisor directs you to calculate Excore Quadrant Power Tilt utilizing Power Range NI Channels on Panel C-06.

I PALISADES NUCLEAR PLANT Page 3 of 9 AUGUST 2010

JPM RO ADMIN l a Proc.

TASK ELEMENT 1 STANDARD Grade Step PO-3, Attachment 2, Excore Quadrant nla Correct Procedure located Power Tilt, located.

su Comment:

Evaluator cue: Provide candidate with a Working Copy of PO-3, attachment 2.

Proc.

Step TASK ELEMENT 2 STANDARD Grade Lower and upper excore readings from the Obtain lower and upper excore Upper and Lower NI Detector meters on 5.2'1 as required* '6L* 'CL, EC-06 are entered on PO-3, Attachment 2, su SOLand SAU,SBU,SCU,SOU). within +I % of the answer key.

Comment:

Proc.

Step TASK ELEMENT 3 STANDARD Grade 5.2.1 I

I Calculate the sum from the Lower +

Upper excore readings (SA,SB,SC,SD)

I Lower + Upper excore readings (SA,SB,SC, SO)summed and entered on PO-3, Attachment #2, within + %Iof the answer I

Comment:

PALISADESNUCLEAR PLANT Page 4 of 9 AUGUST 2010

JPM RO ADMIN l a Proc.

Step TASK ELEMENT 4 STANDARD Grade

Calculatethe sum Of all readings divided by 4:

Sum of all excores reading divided by 4 calculated and entered on PO-3, 5.2.1 (S = C all detectod4).

Attachment 2, within f 1% (0.01) of the su answer key.

Comment:

Proc.

Step TASK ELEMENT 5 STANDARD Grade Using the formula T E=~[(Sx- S)/S],

calculate the tilt for each Quadrant, within 5.2.1 Calculate the Quadrant Tilt. *I% (0.01) of the answer key. su Comment:

EVALUATOR NOTE: Acceptance criteria is all four Quadrant Tilts should add up to approximately zero (0) +, 0.01.

Have calculations verified.

I I I I I Comment:

EVALUATOR CUE:State that someone else will veriflv the calculation.

PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010

JPM RO ADMIN l a Proc. TASK ELEMENT 7 STANDARD Grade Step Operator notifies CRS of completion of Notify the CRS that Excore Quadrant PO-3, Attachment 2, Excore Quadrant n/a Power Tilt has been completed per Power Tilt su PO-3, Attachment 2.

END OF TASK PALISADESNUCLEAR PLANT Page 6 of 9 AUGUST 2010

JPM RO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS SIMULATOR SET UP:

Simulator Setup Instructions:

0 Full power IC 0 Drop CRD #I 1 fully into the core with RD-11 (Final Value = 2) on PIDRD02 0 When plant has stabilized, freeze the Simulator and SNAP 0 Use PO-3, Attachment 2 and recordkalculate from the Upper and Lower NI Detector meters on EC-06 and use as answer key.

PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010

JPM RO ADMIN l a I

Upper Reading(%)

SAUt SBU, SCU, SDU Lower + Upper S A , SB, SC, SD I S = (E All Detectors)/4

= (SA + Se + sc + SD)/4 Excore Quadrant Tilt TEA,TEB,TEC,TED 5(CHA) SAL= SAU = SA= SAL+ SAU QUAD 1 51 50 101 SBU = 96 40

~ ~~

scu = sc = S C L + scu QUAD 4 50 101 8(CH D) SDL= SDU = SD= SDL+ SDU 52 49 101 NOTE: The four QPTs should sum to approximately zero.

Comments:

Performed By: -Pat Person Date: Today Time: Now Calculations Verified By: Date:

After calculations are verified, forward to Reactor Engineering Supervisor or designee for final review.

Reactor Engineering Supervisor or designee: Date:

ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010

JPM RO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

0 Plant was at full power.

0 lncores #9 and #35 are inoperable.

CRD #I 1 has dropped into the core INITIATING CUES:

During performance of PO-3, Alternate ncore and Excore Applications, the Control Room- Supervisor directs you to calculate Excore Quadrant Power Tilt utilizing Power Range NI Channels on Panel C-06.

PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN l b TITLE: RESET UFM CORRECTION FACTORS CANDIDATE:

EXAM1NER:

JPM RO ADMlN I b JOBPERFORMANCEMEASURE DATA PAGE Task: Reset UFM Correction Factors Alternate Path: NIA Facility JPM #: PL-OPS-PPC-001J WA: 2.1.19 Importance: SRO: 3.0 RO: 3.0 WA Statement: Ability to use plant computer to obtain and evaluate parametric information on system or component status.

Task Standard: UFM correction factors set to 1.OOO and UFM is not enabled on PPC Page 521.

Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform J - Simulate

References:

DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 Validation Time: -1 0- minutes Time Critical: NO Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADESNUCLEAR PLANT Page 2 of 11 AUGUST 2010

JPM RO ADMIN I b Tools/Equipment/Procedures Needed:

DWO-1, "Operator's DailyANeekly Items MODES 1, 2, 3, and 4" GOP-8, "Power Reduction and Plant Shutdown to MODE 2 or MODE 3 2 525°F" Tech Data Book 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 86% power.

INITIATING CUES:

Following a power reduction from full power per GOP-8, the Control Room Supervisor directs you to reset the UFM Correction Factors to 1.OOO in accordance with DWO-1, steps 5.2.3.a through 5.2.3.f.

1 PALISADES NUCLEAR PLANT Page 3 of 11 AUGUST 2010

JPM RO ADMIN 1b Proe.Step TASK ELEMENT 1 I STANDARD Grade 1 DWO-1 I Locates correct procedure.

I Operator locates DWO-1 and refers to step 5.2.3.a I Comment:

Evaluator Cue: Provide candidate with a working copy of DWO-I section 5.2.3.

ProcStep TASK ELEMENT 2 OBTAIN PPC Page 521 UFM PLANT I STANDARD Grade 523a CALORIMETRIC Page 521 of PPC is displayed su I Comment:

I Proc.Step TASK ELEMENT 3 STANDARD Grade I

if UFM CAL ENABLED On 5.2.3.b PPC Page 521 UFM CAL ENABLED noted to PPC Page 521 is correct. Refer to Technical Data Book Figure 14.1. be YES.

Proc.Step TASK ELEMENT 4 IF UFM CAL ENABLED will be changed I STANDARD Grade 5.2.3.c from NOT ENABLED to ENABLED, THEN Determines step is N/A. su PERFORM the following:

PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 2010

JPM RO ADMIN l b Pr0c.Step TASK ELEMENT 5 STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN Updates Tech Data Book Figure 14.1 for UFM 5.2.3.d.1 PERFORM the following:

status to Not Enabled.

1. UPDATE Technical Data Book Figure 14.1 indicating UFM CAL ENABLED status.

I Comment:

I

- TASK ELEMENT 6 I STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN PERFORM the following:

I Refers to Attachment 12 and determines 5.2.3.d.2 2. ENSURE HB-PWR-STEADY is lowered power is < 2530 MWt.

su to the 100% thermal power limit allowed by Attachment 12, "100% Thermal Power Limit."

Comment:

Evaluator Cue: Provide candidate with a working copy of DWO-I Attachment 12.

I Proc.Step TASK ELEMENT 7 I IF UFM CAL ENABLED will be changed II STANDARD Grade from ENABLED to NOT ENABLED, THEN PERFORM the following: I UFM CAL ENABLED field is selected. su I I 3. SELECT UFM CAL ENABLED. I ~~

Comment:

PALISADES NUCLEAR PLANT Page 5 of 11 AUGUST 2010

JPM RO ADMIN I b Proc.Step TASK ELEMENT8 STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN 5.2.3 .d.4 PERFORM the following: N is entered. su

4. ENTER N for no.

Proc.Step TASK ELEMENT 9 IF UFM CAL ENABLED will be changed I STANDARD Grade from ENABLED to NOT ENABLED, THEN 5.23-d.5 PERFORM the following: UPDATE hardkey is pressed. su

5. PRESS UPDATE hardkey.

Proc.Step TASK ELEMENT I O STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN 5.2.3.d.5 PERFORM the following: Operator goes to 5.2.3.f. su

6. ENSURE UFM Correction Factors set to 1.OOOO.Refer to Step 5.2.3f.

PALISADES NUCLEAR PLANT Page 6 of 11 AUGUST 2010

JPM RO ADMIN I b Proc.Step TASK ELEMENT I 1 ENSURE Technical Data Book Figure 14.1 I STANDARD Grade 5.2.3.f.1 is updated. Enters 1 .OOOOfor UFM correction factors in

. Tech Data Book Figure 14.1.

Proc.Step TASK ELEMENT 12 I STANDARD Grade I Comment: I ProcStep TASK ELEMENT 13 I STANDARD On PPC page 521, data is selected for first Grade 5.2.3.f.3 Select data.

UFM Correction Factor.

su 1 Comment: I ProcStep TASK ELEMENT 14 I STANDARD Grade 4

Enter new value. 1 .OOOO is entered. su Comment:

PALISADES NUCLEAR PLANT Page 7 of 11 AUGUST 2010

JPM RO ADMIN 1b Proc.Step TASK ELEMENT 15 STANDARD. Grade Press UPDATE hardkey. UPDATE hardkey is pressed.

Comment:

L ProcStep TASK ELEMENT 16 STANDARD Grade On PPC page 521, data is selected for second 5.2.3.f.3 Select data.

UFM Correction Factor.

I Comment: I ProcStep TASK ELEMENT 17 STANDARD Grade 1.OOOO is entered.

Comment:

Press UPDATE hardkey. UPDATE hardkey is pressed. su Comment:

Proc.Step TASK ELEMENT 19 STANDARD Grade 5.2.3.d.7 Wait approximately 30 minutes for Heat Operator waits approximately 30 minutes for Balance power to adjust to the change in Heat Balance power to adjust to the change in S U 5.2-3-f-6 the UFM Correction Factors. the UFM Correction Factors.

PALISADESNUCLEAR PLANT Page 8 of 11 AUGUST 2010

JPM RO ADMIN 1b ProcStep TASK ELEMENT 20 5.2-3.d.8 Perform a heat balance as soon as plant I STANDARD Grade Informs CRS that a heat balance is to be 5.2.3.f.7 conditions allow. performed as soon as plant conditions allow.

su Proc.Step TASK ELEMENT 21 I STANDARD Operator informs the CRS that the UFM Grade

--- Inform CRS that the UFM Correction Correction Factors are reset to 1.OOOO per su Factors are reset to 1.OOOO per DWO-1.

DWO-I.

END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 AUGUST 2010

JPM RO ADMIN 1 b SIMULATOR OPERATOR INSTRUCTIONS IC-16,86%power.

Ensure UFM Correction Factors are 0.9890 and 0.9690 on PPC page 521 and Tech Data Book figure 14.1is updated.

PALISADES NUCLEAR PLANT Page 10 of 11 AUGUST 2010

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

I INITIAL CONDITIONS:

The Plant is at 86% power.

INITIATING CUES:

Following a power reduction from full power per GOP-8, the Control Room Supervisor directs you to reset the UFM Correction Factor to 1.OOO in accordance with DWO-1, steps 5.2.3.a through 5.2.3.f.

PALISADES NUCLEAR PLANT Page 11 of 11 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 2 TITLE: PERFORM DWO4 ACOUSTIC MONITOR 7=DAYCHECK CANDlDATE:

EXAMINER:

JPM RO ADMIN 2 JOBPERFORMANCEMEASURE DATA PAGE Task: Perform Operators Daily/Weekly/Bi-Weekly items in all MODES Alternate Path: N/A Facility JPM #: NEW WA: 2.2.12 Importance: RO: 3.7 SRO: 4.1 K/A Statement: Knowledge of surveillance procedures Task Standard: Identification of one out-of-spec reading during the performance of DWO-1 for Acoustic Monitors.

Preferred Evaluation Location: Simulator X - In Plant Preferred Evaluation Method: Perform -X- Simulate

References:

DWO-1, Operators DailyNeekly Items Modes I, 2, 3, and 4 Validation Time: 15 minutes Time Critical: NO Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADES NUCLEAR PLANT Page 2 of 7 AUGUST 2010

Tools/Equipment/Procedures Needed:

0 DWO-1, Operators DailyNVeekly Items Modes 1, 2, 3, and 4, Section 6.1 and Attachment 1, DailyNVeekly Surveillance Data Sheet Redinkpen Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All c trol 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:

0 The Plant is at full power.

0 It is Wednesday, 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months .

INITIATING CUES:

You have been directed to take the readings of DWO-1, Item 6.1. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 3 of 7 AUGUST 2010

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade nla ILocates correct procedure LOCATES copy of partially completed DWO-1 su Comment:

EVALUATOR CUE: Provide candidate with a partially completed copy of DWO-I.

TASK ELEMENT 2 STANDARD

. Pushes "read preamp bias" button for one of the five (5) monitors

. CHECKS reading between 52.5 and 67.5 PUSH "read preamp bias" button (should

. RECORDS reading in "Wednesday Reading" column for applicable monitor read between 52.5 and 67.5) AND ENTER su 6.1.1 Repeats above three steps for each monitor reading on Attachment 1, "DailyAVeekly 9 Surveillance Data Sheet."

.52.5 DETERMINES FI-l043B reading is less than 9 CIRCLES in RED FI-10438 reading*

. NOTIFY CRS of the out of spec reading

Comment:

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

NOTE: Not part of the critical step Proc. Step TASK ELEMENT 3 I STANDARD Grade

. Pushes "high alarm test" pushbutton for one of the five (5) monitors PUSH "high alarm test" pushbutton - high 6'1'2 alarm on C-13 should annunciate. CHECKS that high alarm on C-I 3 annunciates su

- Repeats above two steps for each monitor Comment:

PALISADESNUCLEAR PLANT Page 4 of 7 AUGUST 2010

JPM RO ADMIN 2 Proc. Step TASK ELEMENT 4 STANDARD Grade I

TURN Channel 1 gain switch to highest Turns Channel 1 gain switch clockwise Until 6.1.3 point - some noise should be present after noise is heard.

switch is at highest point. su Comment:

NOTE: Channel 1 gain switch is switch on LEFT side of panel.

Proc. Step TASK ELEMENT 5 I STANDARD Grade I 6.1.4 I RETURN switch to zero.

I 9 Turns Channel 1 gain switch counterclockwise to zero position I Comment:

Proc. Step TASK ELEMENT 6 I 9 STANDARD INITIALS RECRD BY in Wednesday column Grade IF the pre-amp bias for any of the acoustic for 6.,

monitors is found out of tolerance, THEN INITIATE a work request. The instrument RECORDS a note at bottom of page that 6'1m5 is operable provided the other two checks preamp bias for FI-l043B indicated zero su (alarm operates, audible noise) passed 9 Informs CRS that Work Request initiation is satisfactorily.

reauired for Preamr, bias issue on FI-01438.

EVALUATOR CUE: If notified as the CRS of the out of spec reading and need for a Work Request: Acknowledge.

Proc. Step TASK ELEMENT 7 I STANDARD Grade Return completed DWO-1 to CRS = Completed DWO-1 RETURNED to the CRS nla . Inform CRS of out of spec readings (if not already done) 9 CRS INFORMED of the out of spec readings (if not already done)

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 2010

JPM RO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0 Reset to any full power IC.

Insert the following or use CAE file o Override for FI-I043B Controller Output to 0.01 1597 0 Ensure copies of DWO-1, Section 6.1 and Attachment 1, page 3 of 4 are available 0 Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision Ensure Channel #I is selected on Audio Channels Switch (Panel C-I 1A rear, top right-hand corner of Acoustic Panel.)

PALISADESNUCLEAR PLANT Page 6 of 7 AUGUST 2010

JPM RO ADMlN 2

~

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Plant is at full power.

It is Wednesday, 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months .

INIT1AT1NG CUES:

You have been directed to take the readings of DWO-1, Item 6.1. All remaining readings have already been taken by another NCO.

PALISADESNUCLEAR PLANT Page 7 of 7 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO ADMIN 3 TITLE: DETERMINE EXPECTED DOSE FOR EQUIPMENT INSPECTION CANDIDATE:

EXAMINER:

JPM RO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Expected Dose for Equipment Inspection Alternate Path: NIA Facility JPM #: PL-OPS-ADM-002J KIA: 2.3.4 Importance: SRO: 3.7 RO: 3.2 K/A Statement: Knowledge of radiation exposure limits under normal or emergency conditions.

Task Standard: Expected dose is calculated to be 4.5 mR (allow 4 to 5 mR).

Preferred Evaluation Location: ANY -x-Preferred Evaluation Method: Perform -X- Simulate

References:

Health Physics Procedure 2.14, "Radiological Surveys" Validation Time: minutes Time Critical: NO Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADESNUCLEAR PLANT Page 2 of 8 AUGUST 2010

JPM RO ADMIN 3 Tools/Equipment/Procedures Needed:

Current "Radiological Area Status Sheet" for East Safeguards 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 in a refueling outage. Work is in progress on P-67A Low Pressure Safety Injection Pump. A report has been received in the Control Room that scaffold erecting activities may have damaged the seal cooler and seal injection lines for P-67A.

INITIATING CUES:

You have been assigned the task of inspecting P-67A seal cooler and seal injection lines for damage. This will require close inspection (within 2 feet of pump skid area next to the seal cooler), but you are NOT to cross any contamination boundary. The inspection is expected to require 15 minutes to complete.

Determine the maximum expected radiation dose you will receive for this task.

PALISADESNUCLEAR PLANT Page 3 of 8 AUGUST 2010

JPM RO ADMIN 3 Proc.Step TASK ELEMENT I I STANDARD Grade

--- Obtains correct survey map for P-67A.

Obtains "Radiological Area Status Sheet" for East Engineering Safeguards.

Comment:

EVALUATOR CUE:Provide candidate with attached Radiological Area Status Sheet and picture of P-67A skid.

ProcStep TASK ELEMENT 2 I STANDARD

--- I Determine dose rate near the component. I Dose rate determined to be 18 mRem/hr.

Grade su Comment:

EVALUATOR NOTE: Candidate should select 78 mWhr dose rate reading from Status Sheet since this is the general area where seal cooler is located.

ProcStep TASK ELEMENT 3 STANDARD Grade

--- I Calculates expected dose. Expected dose calculated to be 4.5 mRem. su Comment:

EVALUATOR NOTE: 18 mRem/hr X 0.25 hr = 4.5 mR (allow 4-5 mR)

END OF TASK PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010

JPM RO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS Simulator NOT required for this JPM.

PALISADESNUCLEAR PLANT Page 5 of 8 AUGUST 2010

JPM RO ADMIN 3 Radiological Survey Sheet Room ID RWP# Item Description DatelTime 4 2010 010 I Aux Bldg 570' East Engineered Safeguards 8/16/10 2330 3 Smear Gamma status Shee"RWP Updated Meter TypdSerial No. Meter TypelSerial No. Meter TypelSerial No.

Yes XYZ1/1234~A NIA NIA 7 0 Beta Sup,eyed/&corde. by Reviewed by Date 1Frisk 0 Neutron J Technician J Supervisor 8/16/10 Note: All Dose Rates in mRemlhr unless otherwise noted I Smears dpmllOOcn?

Comments:

5 1P-66A 3 I Masslinn Wipe dpmlMasslinn Alpha Smear PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010

JPM RO ADMIN 3 PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010

JPM RO ADMIN 3 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Plant is in a refueling outage. Work is in progress on P-67A Low Pressure Safety Injection Pump. A report has been received in the Control Room that scaffold erecting activities may have damaged the seal cooler and seal injection lines for P-67A.

INITIATING CUES:

You have been assigned the task of inspecting P-67A seal cooler and seal injection lines for damage. This will require close inspection (within 2 feet of pump skid area next to the seal cooler), but you are NOT to cross any contamination boundary. The inspection is expected to require 15 minutes to complete.

Determine the maximum expected radiation dose you will receive for this task.

PALISADESNUCLEAR PLANT Page 8 of 8 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SROADMIN l a TITLE: DETERMINE COMPENSATION FOR A WITHDRAWN, INOPERABLE CONTROL ROD CANDIDATE:

EXAMI NER:

JPM SRO ADMIN l a JOBPERFORMANCEMEASURE Task: Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path: NIA Facility JPM #: PL-OPS-ENG-01IJ WA: 2.1.25 Importance: RO: 3.9 SRO: 4.2 WA Statement: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Task Standard: EM-04-08, Attachment Iproperly completed per key.

Preferred Evaluation Location: ANY -X-Preferred Evaluation Method: Perform -X- Simulate

References:

EM-04-08, Shutdown Margin Requirements Validation Time: 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 16 AUGUST 2010

JPM SRO ADMIN l a 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.

INIT1AL CONDIT1ON S :

0 Rod #6 is inoperable and fully withdrawn.

0 It is believed that the rod is untrippable.

0 Burnup is 7,000 MWD/MTU.

0 Rx power is loo%, PCS Boron is 865 ppm. All rods out, equilibrium Xenon.

INITIATING CUES:

The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.

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

PALISADES NUCLEAR PLANT Page 3 of 16 AUGUST 2010

JPM SRO ADMlN l a proc, Step TASK ELEMENT I STANDARD Grade EM-04-08 and Tech Data Book located.

Locate correct procedure. Determine EM-04-08, Attachment #1 is the SU correct attachment.

PrOC.

Step TASK ELEMENT 2 STANDARD Grade Record inoperable control rod identification.

I A, 6 and untrippable recorded.

Comment:

EVALUATOR CUE: Reactor Engineering is not available.

Proc.

Step TASK ELEMENT 4 STANDARD Grade r ~ ~

Record source of inoperable control 3 rod worth data. Tech Data Book entered. su Comment:

PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010

JPM SRO ADMIN l a Roc.

TASK ELEMENT 5 STANDARD Grade SMP Record current cycle burnup. Record current cycle burnup = 7000. su Comment:

PCOC.

Step TASK ELEMENT 6 STANDARD Grade k 4 Record current power level. '100' entered. su

.I Comment:

Proc.

Step TASK ELEMENT 7 STANDARD Grade Control rod worth inserted into core. '0'and 'Gp 4 @ 131/132"entered.

Comment:

Roc.

Step TASK ELEMENT 8 STANDARD Grade Record PCS Boron concentration. '865' entered. su Comment:

PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010

JPM SRO ADMlN l a

'7.05(7.04to 7.06)'entered.

Comment:

Proc.

Step TASK ELEMENT 10 STANDARD Grade I 'S F I Determine and record max worth of stuck rod at current power. I to 8),entered.

Proc.

step TASK ELEMENT 11 STANDARD Grade 14 Determine and record PCS boron 5.G concentration at 100% at '865(860to 870)'entered.

7000 MWDIMTU.

Comment:

Proc.

TASK ELEMENT 12 STANDARD Grade Step 5.H I Determine and record power defect for 100% power. I .53 .51 to .55)9entered.

Isu PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010

JPM SRO ADMlN l a t

PrOC.

Step TASK ELEMENT 13 STANDARD Grade I

Determine and record power defect at .53 to .55),entered.

5 current power level. su Proc.

Step TASK ELEMENT 14 STANDARD Grade 5.5 Determine and record required SDM. 2.0 already entered. su r

Comment:

Proc.

Step TASK ELEMENT 15 STANDARD Grade Calculate Net amount of shutdown I 1.82(1.80 to 1.84) entered.

Comment:

Proc, Step TASK ELEMENT 16 STANDARD Grade Enter worth of untrippable rod. 1.17 (1.16 to 1.18)entered. su Comment:

PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010

JPM SRO ADMIN l a Proc.

step TASK ELEMENT 17 STANDARD Grade s

Determine excess shutdown margin 0.65 (0.645 to 0.655) entered. Determines 6M with the inoperable rod. Step 7 substeps are N/A.

TASK ELEMENT 18 STANDARD Grade IF Shutdown margin is negative, 7N-Q THEN ...

Determines Step 7 substeps are NIA. su Proc.

step TASK ELEMENT 19 STANDARD Grade Determine and record PPC PDlL for 8.R current power level.

at lol,, to entered. su Comment:

Proc.

Step TASK ELEMENT 20 STANDARD Grade Determine and record control rod 8.S position corresponding to excess Group 4 at 20 (18 to 22) entered. su shutdown margin.

Comment:

PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010

JPM SRO ADMIN l a Proc.

TASK ELEMENT 21 STANDARD Grade step I 8-T Comment:

I Determine and record PDlL for inoperable control rod condition. I Group 4 at 101 (100 to 105) entered.

Isul Pro%

step TASK ELEMENT 22 STANDARD Grade Comment:

ProC.

Step TASK ELEMENT 23 STANDARD Grade Sign and date Step 9. Operator signs and dates. su Comment:

Proc.

Step TASK ELEMENT 24 STANDARD Grade Report results to Control Room NA Supervisor.

CRS notified. su I EVALUATOR CUE: End JPM Note: Attach completed EM-04-08, Attachment 1 to this JPM.

PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010

~ ~~

JPM SRO ADMIN l a END OF TASK PALISADES NUCLEAR PLANT . Page 10 of 16 AUGUST 2010

JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 2010

_ _ ~ ~

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 1.17 %&

CONTROL ROD (TDB Figure 1.Ior Reactor Engineering)

3. SOURCE OF UNTRIPPABLE OR DROPPED CONTROL ROD WORTH DATA:

4. REFERENCE DATA A. CURRENT CYCLE BURNUP 7000 MWd/MTU (TDB Fig 1.10)

6. CURRENT REACTOR POWER LEVEL I00 %

(Percent of Rated Power)

C. CONTROL ROD WORTH INSERTED INTO CORE 0 %Ap (TDB Fig 1.3)

GROUP 4 INCHES 132 (or 131}

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

D. PCS BORON CONCENTRATION 865 PPm (Chemistry Log or Reactor Logbook)

PALISADES NUCLEAR PLANT Page 12 of 16 AUGUST 2010

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 7.05 %Ap (TDB Fig 1. I )

F. MAXIMUM WORTH OF STUCK CONTROL 1. I 7 %Ap ROD AT A (TDB Fig 1,I)

G. PCS BORON AT 100% POWER AT A 865 PPm (TDB Fig 6.1, Reactor Log)

H. POWER DEFECT AT 100% POWER 1.53 %Ap (TDB Fig 3.2 and G )

I. POWER DEFECT AT POWER B H x B - (1.53) x (100) 1.53 %Ap 100 100 J. REQUIRED SHUTDOWN MARGIN 2.0 %Ap (4 PCPs Operating)

6. CALCULATION K. NET AMOUNT OF SHUTDOWN MARGIN (E - C - F) - I - J 1.I 1.82 %Ap

- [(7.05) - (0) - 1.171 - (1.53) - (2.0) =

1.1 PALISADES NUCLEAR PLANT Page 13 of 16 AUGUST 2010

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 1.17 %Ap DROPPED CONTROL ROD Step 2 M. EXCESS SHUTDOWN MARGIN WITH ONE UNTRIPPABLE OR DROPPED CONTROL ROD K - L = (1.82) - (1.17) = 0.65 %Ap

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 %Ap

0. MAXIMUM REDUCED POWER LEVEL P. Caution Tag the Control Rod joy-stick on panel C-02 that the new PDlL 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.

PALISADES NUCLEAR PLANT Page 14 of 16 AUGUST 2010

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 PDlL FOR CURRENT POWER LEVEL Group 4 (TDB Fig 1.9)

Inches 101 S. CONTROL ROD POSITION CORRESPONDING Group 4 TO EXCESS SHUTDOWN MARGIN IN M (TDB Fig 1.3 or 5.1 and M) Inches 20 T. PDlL FOR UNTRIPPABLE OR DROPPED Group 4 CONTROL ROD CONDITION (R or S, whichever is farthest withdrawn) Inches 101 U. the Control Rod position in S is farther withdrawn than the Control Rod position in R, THEN Caution Tag the Control Rod NIA joy-stick on panel C-02, identifying that the new PPC PDlL as the Control Rod position in S.

9. REVIEWS (Operators Name) I (Today)

Performed By Date I

Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor I

Reactor Engineering Supervisor Date PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 2010

JPM SRO ADMIN l a (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Rod #6 is inoperable and fully withdrawn.

It is believed that the rod is untrippable.

0 Burnup is 7,000 MWD/MTU.

0 Rx power is loo%, PCS Boron is 865 ppm. All rods out, equilibrium Xenon.

INITIATING CUES:

The Control Room Supervisor directs you to determine the compensation for shutdown margin required for control rod #6 utilizing EM-04-08.

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

PALISADES NUCLEAR PLANT Page 16 of 16 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN l b TITLE: CALCULATE BLEND RATIO FOR MAKEUP TO SIRWT CANDIDATE:

EXAMINER:

JPM SRO ADMIN I b JOB PERFORMANCE MEASURE DATA PAGE Task: Perform Safety Injection Refueling Water Tank Operations Alternate Path: NIA Facility JPM #: PL-OPS-ENG-O19J KIA: 2.1.34 Importance: RO: 2.3 SRO: 2.9 K/A Statement: Ability to maintain primary and secondary plant chemistry within allowable limits.

Task Standard: Correct volume of Boric Acid and Primary Makeup Water Calculated for addition to SIRWT Preferred Evaluation Location: Any -x_

Preferred Evaluation Method: Perform -X- Simulate

References:

SOP-2A, Chemical and Volume Control System Technical Data Book, figure 8.2 Validation Time: minutes Time Critical: NO Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADESNUCLEAR PLANT Page 2 of 8 AUGUST 2010

JPM SRO ADMIN I b Tools/Equipment/Procedures Needed:

SOP-2A, "Chemical and Volume Control System" Calculator Pencil and paper READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performec. 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:

Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%

Boric Acid Storage Tank T-53A boron concentration = 12,524ppm INITIATING CUES:

The Control Room Supervisor directs you to perform SOP-2A section 7.6.1 .a to calculate the volumes of Boric Acid and Primary Makeup water needed to raise SIRWT level by 3000 gallons while maintaining current SlRWT boron concentration.

PALISADESNUCLEAR PLANT Page 3 of 8 AUGUST 2010

JPM SRO ADMIN I b Proc. Step TASK ELEMENT 1 STANDARD Grade Operator locates correct procedure SOP-2A section 7.6.1 located su Comment:

EVALUATOR CUE: Provide candidate a working copy of SOP-2A Section 7.6.7 TASK ELEMENT 2 STANDARD During makeup operations to the SIRWT:

1. Makeup to the volume control tank is not available.

2. Opening CV-2155, Boric Acid Blender Outlet Control Valve, will inject the blended 7.6.1.a Caution batch intended for the SIRWT into the Operator reviews caution su PCS.

3. Additions that exceed 2500 ppm may result in exceeding boron concentration limits of Technical Specifications LCO 3.5.4. SITS may also be affected during fill and drain operations Comment:

Proc. step TASK ELEMENT 3 STANDARD To determine the amount of boric acid and primary makeup water to be transferred to SlRW tank, REFER TO the following formulas:

Operator calculates the following:

7.6.1.a.l SlRW Tank Volume = (% meter reading x Amount of volume to add = 3000 gallons (give in 2797) + 18,646 initial conditions)

Where:

SlRW Tank Volume = SlRW total gallons

% meter reading = LIA-0332A or LIA-0331.

Comment:

PALISADESNUCLEAR PLANT Page 4 of 8 AUGUST 2010

JPM SRO ADMIN I b STANDARD Blend Ratio = (BAST ppm/SIRW ppm)

-1 Where: Operator calculates the following:

7.6.1.a.2 Blend Ratio = gallons of PMW per 1 (12,524/2149) - 1 = 4.83 (allow 4.80 -

gallon of concentrated Boric Acid 4.85)

BAST ppm = 12,524 SIRWT ppm = 2149 Comment:

EVALUATOR NOTE: Allow 4.80 to 4.86 TASK ELEMENT 5 STANDARD Gallons of concentrated boric acid to add = Total Volume Makeup to SIRW/(Blend Ratio + 1)

Where:

Total Volume Makeup to SlRWT = Operator calculates the following:

7.6.1.a.3 Desired SIRWT level in gallons minus su 3000/(4.83 + 1) = 514.6 gal of boric acid current level in gallons Blend Ratio = gallons of PMW per 1 gallon of concentrated Boric Acid Comment:

EVALUATOR NOTE: Allow 511.9 - 517.2 PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010

JPM SRO ADMIN 1b TASK ELEMENT 6 STANDARD Gallons of PMW to add = Total volume makeup to SIRWT - Gallons of Boric Acid to add Where:

Operator calculates the following:

7.6.1.a.4 Total Volume Makeup to SIRWT = su 3000 - 514.6 = 2485.4 gal of PMW Desired SIRWT level in gallons minus current level in gallons Gallons of Boric Acid to Add = Item 3.

Comment:

above EVALUATOR NOTE: Allow 2483 - 2488 Proc.

step TASK ELEMENT 7 STANDARD Grade r

CRS informed of the following volumes:

Operator informs Control Room nla Supervisor of the volume of boric acid Primary Makeup Water: 2485.4 gal su and primary makeup water to add.

Concentrated Boric Acid: 514.6 nal Comment:

EVALUATOR NOTE: Allow 2483 - 2488 gal for Primary Makeup Water and 511.9 -

517.2 gal for Boric Acid EVALUA TOR CUE: Role play as CRS END OF TASK PALISADESNUCLEAR PLANT Page 6 of 8 AUGUST 2010

JPM SRO ADMIN Ib SIMULATOR OPERATOR INSTRUCTIONS PALISADESNUCLEAR PLANT Page 7 of 8 AUGUST 2010

JPM SRO ADMIN I b (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Safety Injection Refueling Water Storage Tank boron concentration = 2149ppm Safety Injection Refueling Water Storage Tank level = 96%

Boric Acid Storage Tank T-53A boron concentration = 12,524ppm INITIATING CUES:

The Control Room Supervisor directs you to perform SOP-2A section 7.6.1 .a to calculate the volumes of Boric Acid and Primary Makeup water needed to raise SlRWT level by 3000 gallons while maintaining current SIRWT boron concentration.

PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM SRO ADMlN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Approve a heavy load movement Alternate Path: N/A Facility JPM #: PL-OPS-ADM-001J K/A: 2.2.14 Importance: SRO: 4.3 WA Statement: Knowledge of the process for controlling equipment configuration or status Task Standard: Approve a heavy load movement, ensuring all prerequisites and operational requirements are met.

Preferred Evaluation Location: ANY x -

Preferred Evaluation Method: Perform -X- Simulate

References:

FHS-M-23, Movement Of Heavy Loads In The Spent Fuel Pool Area Administrative Procedure AP 4.02, Control Of Equipment 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 16 AUGUST 2010

JPM SRO ADMlN 2 ToolslEquipmentlProcedures Needed:

FHS-M-23, Movement Of Heavy Loads In The Spent Fuel Pool Area, Attachment I,Rev. 29, Heavy Load Data Sheet, with applicable sections completed by Heavy Load Person In Charge (HL PIC)

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

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

e The Plant is in Mode 1 e A refueling outage was completed 95 days ago, with all spent fuel from the core stored in the south end of the Spent Fuel Pool e You are an on-shift SRO e It is Tuesday, Night shift, 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months e V-IO, Radwaste Area Supply Fan; V-14A and V-146 Radwaste Area Exhaust Fan are in service e Both Control Room HVAC trains for filtration and cooling are operable, with the left train in service, normal operation e VF-66, Fuel Pool Area Refueling Charcoal Filter, is bypassed (not in service) e V-7, Fuel Handling Area Supply Fan; V-8A and V-8B, Radwaste Area Exhaust Fans are in service e Mechanical Maintenance has requested to move the MSB Shielding Lid from the Cask Washdown Pit onto the loaded fuel cask, in the Spent Fuel Pool e This evolution is expected to begin immediately after authorization and to be completed by 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months e No other load movements are planned or in progress e No fuel movement in the SFP is planned or in progress e All spent fuel in the north tilt pit and has decayed for greater than one year INITIATING CUES:

The Shift Manager directs you to approve the requested load movement, ensuring all Operational prerequisites and requirements are met prior to the approval.

PALISADESNUCLEAR PLANT Page 3 of 16 AUGUST 2010

JPM SRO ADMIN 2 Proc. Step I

TASK ELEMENT 1 FHS-M-23, Att. 1, Heavy Load Data Sheet I STANDARD Grade located, with applicable sections n'a completed by HL PIC Operator obtains FHS-M-23, Att. 1 su Comment:

EVALUATOR CUE Provide candidate the HL PIC completed FHS-M-23, Aft. I Working COPY.

Proc. Step TASK ELEMENT 2 I STANDARD Grade SRO determines:

YES, Object is a heavy load su (MSB Shield Lid weighs 6457 Ibs from Att. 2)

I Comment: I EVALUATOR CUE:Provide candidate with a working copy of FHS-M-23.

r t

Proc. Step I

TASK ELEMENT 3 I STANDARD Grade Is the load movement within Load Path 3 -

NO Att. 6 only? Heavy Load path #4 determined for movement s u of DFS components between cask wash-down pit and cask loading floor area, Att.3 PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010

JPM SRO ADMIN 2 TASK ELEMENT 4 I STANDARD Grade Att. 6 I Will loads be moved over Load Path I?

I Isu Comment:

EVALUATOR CUE:lf asked by SRO what load move will be taking place, Reply: the MSB Shielding Lid is being moved from the Cask Wash-down area to the loaded fuel cask in the Spent Fuel Pool.

Proc. step TASK ELEMENT 5 I STANDARD Grade Will loads be moved over Load Path 4 Aft. 6 (Main Fuel Pool)? YES su Comment:

Proc. Step TASK ELEMENT 6 I STANDARD Grade Has fuel decayed 2 30 days?

Att. 6 -

YES (given in the initial conditions) su PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 7 STANDARD Grade Proc. step TASK ELEMENT 8 STANDARD Grade I

Both CRHVAC filtration operable (refer to Att. 6 TS 3.7.10 if one train inoperable) Both CRHVAC filtration trains verified operable S U Comment:

EVALUATOR CUE: If asked by SRO if both CRHVAC Filtration trains are operable, RESPOND: they are not on the LCO or LCO Annex sheet for being inoperable or degraded.

Proc. Step I

TASK ELEMENT 9 I STANDARD I

Grade Both CRHVAC cooling operable (refer to Att. 6 TS 3.7.1 1 if one train inoperable) Both CRHVAC cooling trains verified operable S U Comment:

EVALUATOR CUE: If asked by SRO if both CRHVAC cooling trains are operable, RESPOND: they are not on the LCO or LCO Annex sheet, for being inoperable or degraded.

I Proc. Step TASK ELEMENT 10 I STANDARD Grade Has fuel decayed 190 days?

Att. 6 -

YES (given in the initial conditions) su PALISADESNUCLEAR PLANT Page 6 of 16 AUGUST 2010

JPM SRO ADMlN 2 J

Proc. Step TASK ELEMENT I 1 I STANDARD Grade VF-66 maybe bypassed OR out of service Att. 6 One V-8 fan verified inservice su At least one V-8 shall be inservice Comment:

Proc. step TASK ELEMENT 12 I STANDARD Grade Will loads be moved over Load Path 2?

Att. 6 -NO su Comment:

Evaluator Note: Candidate may answer YES and review Section 4.2.7 Proc. Step TASK ELEMENT 13 I STANDARD Grade Will loads be moved over Load Path 3?

Att. 6 -NO su Comment:

Proc. Step TASK ELEMENT 14 Will non-heavy loads be moved under this I STANDARD Grade Att. 6 procedure? NO (given in initial conditions)

_ I su PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 15 Will load be moved in an alternate path?

I STANDARD Grade Att. 6 NO (Path 4 is the only path for this evolution)

_. su Proc. Step TASK ELEMENT 16 I STANDARD Grade On-Shift, Duty SRO m: SRO references Section 1.O through 4.0, and Review and understand Sections 1.O ensures:

5.11a through 4.0 of procedure.

su No fuel movements in SFP Area (given in initial conditions)

I Comment:

Prw. Step TASK ELEMENT 17 On-Shift, Duty SRO m:

I STANDARD Grade SRO verifies plant systems and conditions are 5.1.lb ENSURE plant systems and conditions are met. met (has effectively completed this step by su ensuring Att. 6 complete)

~

Comment:

Proc. Step TASK ELEMENT 18 I STANDARD Grade On-Shift, Duty SRO shall: SRO enters on FHS-M-23, Att. 1:

Complete Attachment 1 to document Sinns. Dates and Times, in box (8) permission to commence heavy load 5*1*1c movement for approved Load Paths during TOdav1930 for Start in box (9) su specified time period. Todav/2300 OR 0700 tomorrow/ Sinned for Stop in box(9)

I Comment:

Evaluator Note: one-week duration limit found in Section 3.1.3d PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010

JPM SRO ADMIN 2 f

Proc. Step TASK ELEMENT I 9 I STANDARD Grade On-Shift, Duty SRO m:

DOCUMENT authorization of heavy loads SRO makes entry.

5'1m1'd movements in the Operations log.

su Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010

JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0 N/A PALISADESNUCLEAR PLANT Page 10 of 16 AUGUST 2010

(1) Date: TODAY (2) Work Order No: 5199999 (3) Authorization Period:

x Shift c] Daily 0 Week (4) Procedure used in conjunction (5) Special precautions t o be taken:

w/FHS-M-23: NONE Measure uirder temperature for sinule failure power lift (6) General Description of HL(s) Allowed (7) HL Path(s) (8) Approved By: On-Shift, Duty (9) HL Duration Approved To Be Moved Authorized For SRO Start: (Date / Time) Stop: (Date /Time)

(Can attach schedule to satisfy) Use (Name / Date /Time)

MSB Shielding Lid 4 J Onerator/ TODAY I NOW START: TODAY -

1930 TODAY (OR 2300 (OR STOP: Tomorrow) 0700)

{ I O ) CALIBRATED EQUIPMENT (If Required)

FLUKE Model 8660 0-2OO0F/f .02"F CMS234567 06/01/20 10 06/01/2011 (11) HL PIC (12) Crane (13) Crane Operator (14) Signal Person (15) On-Shift, Duty SRO Name / Date / Time Inspection Name / Date / Time Name / Date / Time Contacted -- Name (Print) Complete (4) (Print) (Print) (Print)

J JOHNSON/ TODAY/ NOW X

~ ~~~~~

PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 2010

Proc No FHS-M-23 Attachment 1 HEAVY LOAD DATA SHEET Revision 29 Page 1 of 4 Instructions for completion of Attachment 1:

1. ENTER today's date.

2. ENTER Work Order number that controls movement of heavy loads.

NOTE: Heavy Load Person-in-Chargewill contact the Work Control Center or Control Room each shift to ensure that plant conditions have not changed.

3. CHECK time period where authorization from an On-Shift Duty SRO will be required (Shift, Daily, or Week).

4. ENTER any procedure used in conjunction with FHS-M-23.

5. ENTER any special precautions or temperature measurements for bridge girder (See Step 3.4.1 h).

6. ATTACH schedule information to Attachment 1 or list general description of heavy loads to be moved.

7. LIST heavy load paths authorized for use.

NOTE: This information is only required to approve the beginning of heavy load movements for an extended load move campaign. All subsequent authorizations can be handled over the phone (See Section 3.1).

8. On-Shift, Duty SRO PRINT name, date, and time (SRO authorization required before starting heavy load movements. SRO authorization confirms plantkystedcomponent conditions are met. SRO signature not required for Load Path No 3 or non-heavy loads covered under this procedure).

9. LIST START date and time. LIST STOP date and time (this can not exceed time period authorized in Step No 3).

I O . Enter calibrated equipment information.

NOTE: Multiple Page 3 of this attachment may be used for an extended moving campaign.

11. Heavy Load Person-in-Charge (HL PIC) PRINT name, date, and time (HL PIC signoff confirms proper load path, weight, 8, rigging requirements are understood and will be met. Each time HL PIC changes, new information shall be entered).

12. Crane Inspection requires Crane Operator to ENSURE daily crane inspection is completed. PLACE a check (0) in the box next to the Crane Operator that performed the inspection.

13. Crane Operator PRINT name, date, and time (Crane Operator signoff confirms understanding of heavy load requirements AND that all heavy load prerequisites, precautions & limitation, and equipmentlplant safety or limits are met. Each time Crane Operator changes, new information shall be entered).

14. Signal Person PRINT name, date, and time (Signal Person signoff confirms understanding of heavy load requirements AND that all heavy load prerequisites, precautions & limitation, and equipment/plant safety or limits are met. Each time Signal Person changes, new information shall be entered).

15. Heavy Load Person-in-Chargewill DOCUMENT On-Shift, Duty SRO that was contacted by printing name.

16. Page 3 duplicates the information recorded in Items 11 through 15.

17. DESCRIBE Alternate Load Path (assistance may be required from Engineering to best determine how to best fulfill Step 5.1.4i). CIRCLE YES or NO for Attachment.

18. IF alternate load path is required, THEN OBTAIN Reactor Engineer approval. [CMT891009645, CMT9220014771

19. IF alternate load path is required, THEN OBTAIN On-Shift Duty SRO approval. [CMT891009645]

20. PROVIDE a sketch in the space provided (when adequate space is not available, an Attachment can be attached -- See Item 17).

PALISADES NUCLEAR PLANT Page 12 of 16 AUGUST 2010

Proc No FHS-M-23 Attachment 1 HEAVY LOAD DATA SHEET Revision 29 (1) Date: TODAY (2) Work Order No: 5199999 (3) Authorization Period:

x Shift 0 Daily 0Week (4) Procedure used in conjunction (5) Special precautions to be taken:

wIFHS-M-23: NONE Measure airder temperature for sinale failure power lift (6) General Description of HL(s) Allowed (7) HL Path@) (8) Approved By: On-Shift, Duty (9) HL Duration Approved To Be Moved Authorized For SRO Start: (Date I Time) Stop: (Date I Time)

(Can attach schedule to satisfy) Use (Name / Date / Time)

MSB Shielding Lid 4 I I START: /

I I I I I I STOP: I

/lo) CALIBRATED EQUIPMENT (If Required)

FLUKE Model 8660 0-20O"Fl f .02"F CMS234567 06/0112010 06/01/20 11 (11) HL PIC (12) Crane (13) Crane Operator (14) Signal Person (15) On-Shift, Duty SRO Name / Date / Time Inspection Name I Date I Time Name I Date I Time Contacted -- Name (Print) Complete (4) (Print) (Print) (Print)

J JOHNSON/ TODAY/ NOW X

Proc No FHS-M-23 Attachment 1 HEAVY LOAD DATA SHEET Revision 29 PALISADESNUCLEAR PLANT Page 14 of 16 AUGUST 2010

Proc No FHS-M-23 Attachment 1 HEAVY LOAD DATA SHEET Revision 29 Page 4 of 4 (17) Alternate Load Path (if used),

Description:

(19) Approved By:

(18) Approved By: I I Reactor Engineer Date On-Shift, Duty SRO Date PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 2010

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

INITIAL CONDITIONS:

The Plant is in Mode I A refueling outage was completed 95 days ago, with all spent fuel from the core stored in the south end of the Spent Fuel Pool You are an on-shift SRO It is Tuesday, 'Night' shift, 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months V-IO, Radwaste Area Supply Fan; V-14A and V-146 Radwaste Area Exhaust Fan are in service Both Control Room HVAC trains for filtration and cooling are operable, with the left train in service, normal operation VF-66, Fuel Pool Area Refueling Charcoal Filter, is bypassed (not in service)

V-7, Fuel Handling Area Supply Fan; V-8A and V-86, Radwaste Area Exhaust Fans are in service Mechanical Maintenance has requested to move the MSB Shielding Lid from the Cask Washdown Pit onto the loaded fuel cask, in the Spent Fuel Pool This evolution is expected to begin immediately after authorization and to be completed by 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months No other load movements are planned or in progress No fuel movement in the SFP is planned or in progress All spent fuel in the north tilt pit and has decayed for greater than one year INITIATING CUES:

The Shift Manager directs you to approve the requested load movement, ensuring all Operational prerequisites and requirements are met prior to the approval PALISADESNUCLEAR PLANT Page 16 of 16 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 3 TITLE: DETERMINE INCREASED MONITORING ACTIONS PER ONP-23.2, STEAM GENERATOR TUBE LEAK PROCEDURE CANDIDATE:

EXAMI NER:

JPM SRO ADMIN 3 JOBPERFORMANCEMEASURE DATA PAGE Task: Respond to Steam Generator Tube leakage in accordance with ONP-23.2 Alternate Path: NIA Facility JPM #: NEW WA: 2.3.11 Importance: RO:3.8 SRO: 4.3 WA Statement: Ability to control radiation releases.

Task Standard: Determines RIA-0631 count rate of 8.5E+03 cpm (allow 8.3E+03 to 8.7E+03 cpm)

Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform -X- Simulate

References:

ONP-23.2, Steam Generator Tube Leak Validation Time: minutes Time Critical: NO Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADESNUCLEAR PLANT Page 2 of 8 AUGUST 2010

JPM SRO ADMIN 3 Tools/Equipment/Procedures Needed:

ONP-23.2, Steam Generator Tube Leak 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.

INIT1AL CONDIT10NS:

The Plant is at full power.

A Steam Generator Tube Leak is in progress on the A Steam Generator.

ONP-23.2, Steam Generator Tube Leak Procedure has been entered.

Current estimated primary to secondary leakage is 0.01 gpm and stable.

PCS Gas Total Isotope = 0.5 pCi/cc Offgas flowrate = 4 cfm (taken within last 30 minutes).

INITIATING CUES:

During implementation of ONP-23.2, the Control Room Supervisor directs you to determine the new setpoint for RIA-0631, Condenser Offgas Monitor, per ONP-23.2, Step 3a.

PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 201 0

JPM SRO ADMlN 3 Proc.Step TASK ELEMENT 1 I STANDARD Grade I ONP-23.2 I Locates correct Drocedure. ~ ~~~

I Locates ONP-23.2 and refers to Attachment 2. I S U I Comment EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.

TASK ELEMENT 2 ESTIMATE the count rate indication on RIA-0631, Condenser Off Gas Monitor, Att 2 which would result in a 0.02 gpm primary to step 3.a secondary leakrate. Refer to Attachment 1, Refer to ONP-23.2 Attachment 1 page 2 of 3. su Estimation of Primary to Secondary Leakrate.

Comment:

Proc.Step TASK ELEMENT 3 STANDARD Grade OBTAIN Condenser Off Gas flow rate Determines Off Gas flow rate = 4 cfm from Pg 2 (preferred) OR USE last known reading if initiating cue su taken within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Step 1 PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010

JPM SRO ADMlN 3 ProcStep TASK ELEMENT 4 I STANDARD Grade pg OBTAIN "PCS Gas Total Isotope" from Determines PCS Gas Total Isotope =

Chemistry using last known analysis. 0.5 pCi/cc from initiating cue.

su Step 2 I

ProcStep TASK ELEMENT 5 I STANDARD Grade I IStep pg23 Comment:

DETERMINE maximum Primary to Secondary Leakrate based on current Action Level. I Determines 0.02 gpm (from Attachment 2 Step 3a.)

Proc.Step TASK ELEMENT 6 I STANDARD Grade CALCULATE uncorrected leakrate using the following equation:

Calculates uncorrected leakrate using formula:

pg Uncorrected Leakrate (pCi-gal/min-kg) =

0.02 gpm X 0.5 pCilcc X 1000 = su Step 4 Primary to Secondary Leakrate ( g a h i n ) X PCS Gas Total Isotope (pCi/cc) X 10.0 pCi-gal/min-kg 1000 (cclkg)

PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010

JPM SRO ADMlN 3 Proc.Step TASK ELEMENT 7 I STANDARD Grade

. Determines 8.5E+03cpm using Attachment 1 pg 3 graph with 4 sfm Off Gas flowrate line and 2.OE+00 Uncorrected Leak Rate line.

Pgs 2&3 Step 5 ESTIMATE RIA-0631 count rate using the UncorrectedLeakrate Graph on page 3. . SIGNS Completed By on Attachment 1 su PS 2.*

. Informs CRS of results and that Comment:

Reviewed By signature is still required.*

EVALUATOR NOTE: allow 8.3+03to 8.7+03 cpm EVALUATOR CUE: If notified as the CRS of reading and need for Review signature:

Acknowledge. If asked if Attachment 2 steps should be completed:

RESPOND that another operator will complete Attachment 2 steps.

NOTE: Not part of the critical step END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010

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

It is preferred that this JPM be done separately from the simulator. If, by chance, candidate IS in the simulator while doing this JPM, THEN ensure the IC is an at-power IC.

PALISADESNUCLEAR PLANT Page 7 of 8 AUGUST 2010

JPM SRO ADMlN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

0 The Plant is at full power.

0 A Steam Generator Tube Leak is in progress on the A Steam Generator.

0 ONP-23.2, Steam Generator Tube Leak Procedure has been entered.

0 Current estimated primary to secondary leakage is 0.01 gpm and stable.

PCS Gas Total Isotope = 0.5 pCi/cc 0 Offgas flowrate = 4 cfm (taken within last 30 minutes).

INIT1AT1NG CUES:

During implementation of ONP-23.2, the Control Room Supervisor directs you to determine the new setpoint for RIA-0631, Condenser Offgas Monitor, per ONP-23.2, Step 3a.

PALISADESNUCLEAR PLANT Page 8 of 8 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 4 TITLE: CLASSIFY EVENT AND DETERMINE PAR CANDI DATE:

EXAMINER:

JPM SRO ADMlN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Classify an Event and Determine PARS- Protective Action Recommendations Alternate Path: NIA Facility JPM #: NEW KIA: 2.4.41, 2.4.44 Importance: RO:4.1,4.0 SRO: 4.1 4.4 WA Statement: (2.4.41) Knowledge of the emergency action level threshholds and classifications.

(2.4.44) Knowledge of emergency plan protective action recommendations.

Task Standard: Event classified as a General Emergency within 15 minutes and PAR is evacuation of Areas 1 and 3, within 15 minutes from declaration of GE.

Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform -X- Simulate

References:

El-1, Emergency Classifications and Actions El-3, Communications and Notifications El-6.13, Protective Action Recommendations for Offsite Populations Validation Time: minutes Time Critical: YES - see task standard Candidate:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature PALISADES NUCLEAR PLANT Page 2 of 10 AUGUST 2010

JPM SRO ADMIN 4 Tools/Equipment/Procedures Needed:

ELI, Emergency Classifications and Actions, Attachment 1 El-3, Communications and Notifications El-6.13, Protective Action Recommendations for Offsite Populations, Attachment 1 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 Reactor tripped 10 minutes ago.

A Steam Generator Tube Rupture Event is in progress on the A Steam Generator.

Pressurizer level is off-scale LOW.

PCS pressure is 1000 psia.

CETs indicate 5OOOF.

SlRW tank level is 92% and lowering slowly.

A release IS occurring through a stuck open code safety valve on the A Steam Generator.

Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights Failed fuel analysis is in progress with no results to report yet.

The weather is clear with no precipitation.

INITIATING CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Emergency Plant Manager). You are to classify the event given the above information and complete the Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADESNUCLEAR PLANT Page 3 of 10 AUGUST 2010

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 1 I STANDARD Grade Locates El-1 and refers to Attachment 1, Hot El-I Locates correct procedure.

Conditions (PCS > 200 degrees F).

EVALUATOR: Candidate may use placard of site emergency plan classifications or use paper copy from 1 4 , attachment 1.

Proc.Stt?p TASK ELEMENT 2 I STANDARD Grade r

Refers to lower right-hand corner of El-I, El-1 Refers to Fission Product Barriers section Attachment , Conditions Att 1 (lower right-hand corner) su (PCS > 200 degrees F).

c Comment:

TASK ELEMENT 3 STANDARD

- Refers to Table F1

- Determines a POTENTIAL LOSS of Fuel Cladding (based on RVLMS 614 ft elevation readings (item 4)

El-1 Determines status of fission product - Determines a LOSS of PCS Barrier (based su Att 1 barriers.

on S/G leak rate causing SI actuation)

(item 3).

- Determines a LOSS of Containment Barrier (based on affected S/G faulted outside Containment) (item 4).

Comment:

PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 4 I STANDARD Grade I El-1 Att 1 Declares Emergency Classification.

Declares a GENERAL EMERGENCY per FGl based on status of fission product barriers (loss of TWO and potential loss of THIRD).

S U II Comment:

CRITICAL STEP musP be performedwithin 15 minubs of start of JPM.

Proc.Step El-1 TASK ELEMENT 5 I STANDARD Grade Prepares Emergency Actions/Notifications Obtains El-, , Attachment and fills out. su Att2 form*

Comment:

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

Filling out this form is NOT required for this JPM.

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

Obtains El-3, Attachment 1 and fills out per Prepares Event Notification Form.

attached KEY.

Comment:

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

EVALUATOR NOTE: KEY is attached to this JPM.

EVALUATOR NOTE: 1-3, Attachment 2, "Palisades Event Technical Data Sheet" is NOT required during this JPM.

EVALUATOR NOTE: If JPM is conducted in the Simulator, then Candidate may use computer on Control Room island area to prepare this form.

PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010

JPM SRO ADMlN 4 Proc.Step TASK ELEMNT 7 I STANDARD Obtains 1-6.1 3 and corresponding Attachment 1 and determines:

Determines Protective Action

~ t1t Recommendations (PARS).

- Evacuate Areas 1 and 3 (minimum GE recommendation on bottom of Pg 1 of Attachment 1)

Comment:

EVALUATOR NOTE: Provide candidate with a working copy of 1-6.13.

Proc.Step TASK ELEMENT 8 I STANDARD Grade Candidate refers to El-I 1: determines there is Candidate may determine status of Core E'-1 Damage per El-I 1.

not enough info provided in initiating cue to su determine amount of core damage.

EVALUATOR NOTE: If candidate attempts to perform this step, provide them with a working copy of 1-1 7, attachment 2. I Proc.Step TASK ELEMENT 9 STANDARD Grade Palisades Event Notification Form completely Completes filling out Palisades Event filled per attached KEY AND form is approved Att 1 Notification Form. (Candidate initials, date, and time entered at bottom of form)

Comment:

EVALUATOR NOTE: If JPM is conducfed in the Simulator, then Candidate may use compufer on back-bar of Control Room island area to complete and print this form.

The following are the critical parts of this step:

General Emergency is checked in "current classification" section Date and time filled in "current classification" section 0 FGI filled in "reason for classification" section AND Fission Product Barrier Degradation checked in "reason for classification" section "Yes" checked in Radiological Release in Progress Areas 1 and 3 checked for Evacuation of Areas END OF TASK PALISADESNUCLEAR PLANT Page 6 of 10 AUGUST 2010

~-

ANSWER KEY JPM SRO ADMIN 4 Proc No 1-3 Attachment 1 PALISADES EVENT NOTIFICATION FORM Revision 28 Page 1 of 1

~ ~~~ ~ ~~

0 Actual Event Drill Plant Contact Information Nuclear Power Plant:

Plant Communicator: Time of Communication: V.B.

S.O.M.

NRC Plant Message Number Calling From: c]Control Room c]TSC UEOF Other Call Back Telephone Number:

Current Classification Unusual Event 0 Alert Site Area Emergency General Emergency Is]Termination This Classification was declared as of: Date: Todav Time: Within 15 minutes from start of JPM

~~~ ~~~~~~ ~~~~ ~~~~~~

Reason for Classification 0 Abnormal Rad Levels / Radiological Effluent 0System Malfunctions Hazards and Other Conditions Affecting Cold Shutdown / Refueling System Malfunction Plant Safety Independent Spent Fuel Storage Installation Events Fission Product Barrier Degradation IC Number: FGf Radiological Release in Progress Due to Event (XI Yes No Protective Action Recommendations

[7 None Evacuation of Areas(s): MI n 2 lxl3 04 05 In-Place Shelter of Area(s) 01 2 [7 3 [7 4 [7 5 PAR based on: 0 Dose Calculation (Palisades Event Technical Data Sheet required) Plant Status Security Event (7 Other Meteorological Data Wind Direction (degrees): From 305 To 125 Wind Speed (MPH): 1 Stability Class: G Precipitation: c]Yes No Emergency Director Approval: Date: Time:

ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010

JPM SRO ADMIN 4 SIMULATOR OPERATOR INSTRUCTIONS 0 No Simulator setup required.

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

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

PALISADESNUCLEARPLANT Page 8 of 10 AUGUST 2010

Proc No El-6.7 Attachment 1 Revision 8 Page 1 of 1 PLANT SITE METEOROLOGICAL SYSTEM WORKSHEET

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

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

Multiply by 0.77 (X) 10 meters

( ) 60 meters (see Step 5.1.3 or 5.2.6)

(see Step 5.1.4 or 5.2.7)

3. Stability Class = G Date: TODAY Time: NOW Completed By: JOE OPERATOR PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 2010

JPM SRO ADMlN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Reactor tripped 10 minutes ago.

A Steam Generator Tube Rupture Event is in progress on the A Steam Generator.

Pressurizer level is off-scale LOW.

PCS pressure is 1000 psia.

CETs indicate 5OOOF.

SlRW tank level is 92% and lowering slowly.

A release IS occurring through a stuck open code safety valve on the A Steam Generator.

0 Reactor Vessel Level Monitoring System (RVLMS) indicates ALL red lights Failed fuel analysis is in progress with no results to report yet.

The weather is clear with no precipitation.

INIT1AT1NG CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Emergency Plant Manager). You are to classify the event given the above information and complete the Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 2010

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