Text

2010 Palisades Nuclear Plant Initial Examination As-Administered Exam Files Administrative JPMs
	ML111460555
Person / Time
Site:	Palisades
Issue date:	08/16/2010
From:	Palagi B; NRC/RGN-III/DRS/OLB
To:	;
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ML102070508	List: ML111460555; ML111460567; ML111460575;
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2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION AS -ADMINISTERED EXAM FILES 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:

JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Quadrant Power Tilt per PO-3 Alternate Path: N/A 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 NI Power readings recorded within f 1% of key and Quadrant Power Tilt calculated correctly 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 8 AUGUST 2010

JPM RO ADMIN l a Tools/Equipment/Procedures 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.

INITIAL CONDITIONS:

0 Plant was at full power.

0 lncores #9 and #35 are inoperable.

0 Control Rod #I 1 has dropped into the core.

I NIT1AT1NG 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.

PALISADESNUCLEAR PLANT Page 3 of 8 AUGUST 2010

JPM RO ADMIN l a EVALUATOR CUE: Provide candidate with a working copy of PO-3, Attachment 2.

TASK ELEMENT 1 STANDARD Grade Lower and upper excore readings from the Obtain lower and upper excore Upper and Lower NI Detector meters on su I 5.2.1 Comment:

readings as required. (SAL,SBL, ScL, SDLand SAU,s B U 3 SCU,SDU).

EGO6 are entered on PO-3, Attachment 2, within + %Iof the answer key.

Calculate the sum from the Lower +

Proc. TASK ELEMENT 3 STANDARD Grade Step

1. Calculate the sum of all excore Sum of all excores reading divided by 4 readings divided by 4: calculated and entered on PO-3, 5.2.1 Attachment 2. su (S= C all detectord4).

Comment:

PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010

JPM RO ADMIN l a Proc.

Step TASK ELEMENT 4 STANDARD Grade Using the formula TEX= [(SX- S)/S],

5.2.1 Calculate the Quadrant Tilt. calculate the tilt for each Quadrant. su Proc.

Step TASK ELEMENT 5 STANDARD Grade Have another qualified individual verify the Have calculations verified.

5.2.1 calculations. su Comment:

EVALUATOR CUE: State that another Operator will verify the calculation.

Proe.

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

END OF TASK PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010

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

Simulator Setup Instructions:

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

PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010

JPM RO ADMIN l a Excore Lower Reading (%) Upper Reading (%) Lower + Upper S = 4 All DetectorsY4 Excore Quadrant Tilt SAL,SBL,SCL,SDL SAU, SBUv SCU, SOU S A , SB, SC, SD = (SA + Se + s c + SD)/4 TEA,TEE,TEC,TED 5 (CH A) SAL= SAU = SA= SAL+ SAU T u = [(SA-S)/S]X 100% QUAD I

[NI-005 Lower (A)] [NI-005 Upper (B)]

k 51 50 101 5.2 6 (CH B) SBL = SBU = SB = SBL + SBU TEB = [(Ss-S)/S] x 100% QUAD 3 96

[NI-0065 Lower (A)] [NI-006 Upper (B)]

41 40 -15.6 7 (CH C) SCL = scu = sc = SCL + scu TEC= [(Sc-S)/S] x 100% QUAD 4

[NI-007 Lower (A)] [NI-007 Upper (B)]

51 50 5.2 8 (CH D) SDL= SOU = SD= SDL+ SOU TED= [(S&)/s] X 100% QUAD 2

[NI-008 Lower (A)] [NI-008 Upper (B)]

52 49 101 5.2 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 NSSS and 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 7 of 8 AUGUST 2010

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

! INITIAL CONDITIONS:

Plant was at full power.

lncores #9 and #35 are inoperable.

Control Rod #I 1 has dropped into the core.

INIT1AT1NG 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.

PALISADES NUCLEAR PLANT Page 8 of 8 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 ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Reset UFM Correction Factors Alternate Path: N/A 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 Eva1uation Method: Perform-X- Simulate

References:

DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 Validation Time:-I 0- 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 AUGUST 2010

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

DWO-1, Operators DailyNVeekly Items MODES 1, 2, 3, and 4 DWO-1 Attachment 12 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 following a power reduction from full power.

INITIATING CUES:

The Control Room Supervisor directs you to ensure UFM CAL ENABLED on PPC Page 521 is NOT ENABLED per DWO-1, Section 5.2.3.

PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010

JPM RO ADMIN l b Evaluator Cue: Provide candidate with a working copy of DWO-I section 5.2.3.

Page 521 of PPC is displayed Proc.Step TASK ELEMENT 2 STANDARD Grade if UFM cAL ENABLED On PPC Page 521 UFM CAL ENABLED noted to 5.2.3.b PPC Page 521 is correct. Refer to be YES.

Technical Data Book Figure 14.1.

ProcStep TASK ELEMENT 3 STANDARD Grade IF UFM CAL ENABLED will be changed 5.2.3.c from NOT ENABLED to ENABLED, THEN Determines step is N/A. su PERFORM the following:

Comment:

ProcStep TASK ELEMENT 4 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.

PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010

w JPM RO ADMIN 1b ProcStep TASK ELEMENT 5 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 c 2530 MWt.

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

I Comment:

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

I Proc.Step TASK ELEMENT 6 STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN 5.2.3.d-3 PERFORM the following:

Comment:

3. SELECT UFM CAL ENABLED.

UFM CAL ENABLED field is selected.

lsul Proc.Stgp TASK ELEMENT 7 IF UFM CAL ENABLED will be changed I STANDARD Grade .

from ENABLED to NOT ENABLED, THEN 5-2-3-d.4 PERFORM the following: N is entered. su

4. ENTER N for no. I I Comment:

I Proc.Step TASK ELEMENT 8 STANDARD Grade IF UFM CAL ENABLED will be changed from ENABLED to NOT ENABLED, THEN 5.2-3-d5 PERFORM the following: UPDATE hardkey is pressed. su 5 . PRESS UPDATE hardkey.

~

I ~~~

Comment:

PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010

JPM RO ADMIN 1b Proc.Step TASK ELEMENT 9 STANDARD 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.

Comment:

TASK ELEMENT 10 ENSURE Technical Data Book Figure 14.1 I STANDARD Grade 5.2.3.f.1 is updated. Enters 1 .OOOO for UFM correction factors in Tech Data Book Figure 14.1.

I Comment:

I ProcStep TASK ELEMENT 11 I STANDARD Operator verifies HB-PWR-STEADY is Grade ENSURE HB-PWR-STEADY is acceptable for the new Total UFM Correction Factor lowered to a value less than the Maximum 5-2-3.f-2 Worth in Technical Data Book Figure 14.1. UFM Corrected Power for Resetting Correction su Factors to 1 .Ofound in Tech Data Book Figure 14.1.

I Comment:

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

UFM Correction Factor.

su I Comment: I ProcStep TASK ELEMENT 13 STANDARD Grade Enter new value. 1.OOOO is entered.

Comment:

I I PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010

JPM RO ADMIN I b Proc.Step TASK ELEMENT 14 STANDARD Grade Press UPDATE hardkey. UPDATE hardkey is pressed. Isu Comment:

I I Proc.Step TASK ELEMENT 15 I STANDARD Grade I I 5.2.3.f.3 Select data.

I I

I On PPC page 521, data is selected for second UFM Correction Factor. lsul I

Comment:

II Proc.Step TASK ELEMENT 16 I STANDARD Grads Ptoc.Step TASK ELEMENT 17 I STANDARD Grade I 5.2.3.f.5 I Press UPDATE hardkey. I UPDATE hardkey is pressed. Isu I I Comment:

Proc.Step TASK ELEMENT 18 I STANDARD Operator waits approximately 30 minutes for Grade 5.2.3.d.7 Wait approximately 30 minutes for Heat 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.

Comment:

EVALUATOR CUE: Another person will perform the Heat Balance.

PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010

JPM RO ADMlN I b PrOcStep TASK ELEMENT I 9 5.2.3-d-8 Perform a heat balance as soon as plant I STANDARD informs CRS that a heat balance is to be Grade performed as soon as plant conditions allow.

su 5.2.3.f.7 conditions allow.

Operator informs the CRS that the UFM inform CRS that the UFM Correction Correction Factors are reset to 1 .OOOO per Factors are reset to 1.OOOO per DWO-1.

I Comment:

EVALUATOR CUE: Repeat back notification.

END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010

JPM RO ADMIN I b SIMULATOR OPERATOR INSTRUCTIONS 0 lC-16,86% power.

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

0 Ensure UFM CAL ENABLED (= YES)

PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 2010

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

INITIAL CONDITIONS:

The Plant is at 86% power following a power reduction from full power.

INITIATING CUES:

The Control Room Supervisor directs you to ensure UFM CAL ENABLED on PPC Page 521 is NOT ENABLED per DWO-1, Section 5.2.3.

PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROADMIN 2 TITLE: PERFORM DWO-I ACOUSTIC MONITOR 7-DAY CHECK CANDIDATE:

EXAM1NER:

JPM RO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Perform Operators DailyNVeeklylBi-Weekly items in all MODES Alternate Path: N/A Facility JPM #: NEW WA: 2.2.12 Importance: RO: 3.7 SRO: 4.1 WA 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-I, Operators DailyNVeekly 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 PALISADESNUCLEAR PLANT Page 2 of 7 AUGUST 2010

JPM RO ADMIN 2 Tools/Equipment/Procedures Needed:

DWO-1, Operators DailyANeekly Items Modes 1, 2, 3, and 4, Section 6.1 and Attachment 1, Daily/Weekly Surveillance Data Sheet Red ink pen Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

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

INITIAL CONDITIONS:

0 The Plant is at full power.

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.

PALISADESNUCLEAR PLANT Page 3 of 7 AUGUST 2010

JPM RO ADMIN 2 EVALUATOR CUE: Provide candidate with page 3 of D WO-7, attachment 7 and section 6,7, 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 6m1'1 reading on Attachment 1, "DailyNVeekly . Repeats above three steps for each monitor su Surveillance Data Sheet."

. DETERMINES FI-l043B reading is less than 52.5

. CIRCLES in RED FI-l043B 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 2 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-I 3 should annunciate. . CHECKS that high alarm on C-13 annunciates su I I. Repeats above two steps for each monitor I I Comment:

PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010

JPM RO ADMIN 2 Proc. step TASK ELEMENT 3 I STANDARD Grade k

L 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. su switch is at highest point.

Comment:

NOTE: Channel 7 gain switch is switch on LEFT side of panel.

Proc. Step TASK ELEMENT 4 I 9 STANDARD Turns Channel 1 gain switch counterclockwise Grade 6.1.4 RETURN switch to zero.

to zero position TASK ELEMENT 5 STANDARD c

INITIALS RECRD BY in Wednesday column IF the pre-amp bias for any of the acoustic for Item 6.1 monitors is found out of tolerance, THEN INITIATE a work request. The instrument RECORDS a note at bottom of page that 6.1.5 is operable provided the other two checks 9

preamp bias for FI-I0438 indicated zero su (alarm operates, audible noise) passed Informs CRS that Work Request initiation is satisfactorily.

required for preamp bias issue on FI-0143B.

Comment:

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

I F

Proc. Step TASK ELEMENT 6 STANDARD Grade I

- Return completed DWO-1 to CRS I - Completed DWO-1 RETURNED to the CRS I I 9 Inform CRS of out of spec readings (if not already done)

- 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.

0 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 0 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 ADMIN 2 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITlAL 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.

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 WA: 2.3.4 Importance: SRO: 3.7 RO: 3.2 WA 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 PALISADES NUCLEAR 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 1-2 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. Do not include dose received during transit time.

PALISADESNUCLEAR PLANT Page 3 of 8 AUGUST 2010

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

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

I Obtains "Radiological Area Status Sheet" for East Engineering Safeguards. I Comment:

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

Proc.Step TASK ELEMENT 2 I STANDARD

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

Grade I S "

Comment:

EVALUATOR NOTE: Candidate should select 18 mWhr dose rate reading from Status Sheet since this is the general area where seal cooler is located and they were instructed not to cross any contamination areas.

Proc.Step TASK ELEMENT 3 I STANDARD Grade I --- I Calculates expected dose. I Expected dose calculated to be 4.5 mRem. I S U 1

I Comment:

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

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

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

PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010

JPM RO ADMIN 3 Radiological Survey Sheet 0m k 10 Neutron I J Technician I J Supervisor 8116110 Smears dpdI00 cn?

Note: All Dose Rates in rnRernlhr unless otherwise noted Comments:

PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010

JPM RO ADMIN 3 PALISADESNUCLEAR 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 1-2 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. Do not include dose received during transit time.

PALISADES NUCLEAR 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:

EXAM1NER:

JPM SRO ADMIN l a JOBPERFORMANCEMEASURE DATA PAGE Task: Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path: N/A Facility JPM #: PL-OPS-ENG-011J 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 1 properly completed per key.

Preferred Evaluation Location: ANY X -

Preferred Evaluation Method: PerformX- 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 PALISADESNUCLEAR PLANT Page 2 of 15 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.

INITIAL CONDITIONS:

Rod #6 is inoperable and fully withdrawn.

It is believed that the rod is untrippable.

Burnup is 7,000 MWD/MTU.

Rx power is 100%.

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.]

PALISADESNUCLEAR PLANT Page 3 of 15 AUGUST 2010

JPM SRO ADMIN l a EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.

Proc.

SWP TASK ELEMENT I STANDARD Grade Record inoperable control rod identification.

I A, 6 and untrippable recorded.

Isu I Comment:

I I I EVALUATOR CUE: Reactor Engineering is not available.

Proc.

Step TASK ELEMENT 3 STANDARD Grade Record source of inoperable control 3 rod worth data. Tech Data Book entered. su Comment:

Proc.

TASK ELEMENT 4 STANDARD Grade StsP Record current cycle burnup. Record current cycle burnup = 7000. su Comment:

PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 2010

JPM SRO ADMlN l a Proc.

Step TASK ELEMENT 5 STANDARD Grade Record current power level. '100' entered. su Comment:

A Proc.

TASK ELEMENT 6 STANDARD Grade step I 4.C I Control rod worth inserted into core. I '0' and 'Gp 4 @ 131/132" entered.

~ ~~~

Isu I Comment:

Ptoc.

Step TASK ELEMENT 7 STANDARD Grade Record PCS Boron concentration. '865' entered.

Comment:

Proc.

Step TASK ELEMENT 8 STANDARD Grade I 5.E Comment:

I Determine and record worth of control rods at current power level. I 17.05(7.04 to 7.06. entered.

lsul EVALUATOR NOTE: This will need to be obtained by interpolation of the graph.

PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 2010

JPM SRO ADMIN l a Roc.

Step TASK ELEMENT 9 STANDARD Grade I 5F 1 Determine and record max worth of stuck rod at current power. I ,, . to 8), entered.

ROC.

TASK ELEMENT 10 STANDARD Grade StgP Determine and record PCS boron 5.G concentration at 100% at 865 (860 to 870)entered. su 7000 MWD/MTU.

PW.

TASK ELEMENT 11 STANDARD Grade Step Determine and record power defect for .53 to ,-5), entered.

5.H 100% power.

su I Comment:

I Proc.

Step TASK ELEMENT 12 STANDARD Grade I 5. I Determine and record power defect at current power level. I 1 5 3 (1.51 to 1.55) entered Comment:

PALISADESNUCLEAR PLANT Page 6 of 15 AUGUST 2010

JPM SRO ADMIN l a Proc.

step TASK ELEMENT 13 STANDARD Grade Determine and record required SDM. 2.0 already entered.

Proc.

TASK ELEMENT 14 STANDARD Grade Calculate Net amount of shutdown I 1.82 (1.80 to 1.84) entered.

Isu Comment:

Proc.

Step TASK ELEMENT 15 STANDARD Grade Enter worth of untrippable rod. 1.17 (1.16 to 1.18)entered. su Comment:

Proc.

Step TASK ELEMENT 16 STANDARD Grade I 6.M I Determine excess shutdown margin with the inoperable rod. I 0.65 (0.645 to 0.655) entered. Determines Step 7 substew are N/A. I Comment:

PALISADESNUCLEAR PLANT Page 7 of 15 AUGUST 2010

JPM SRO ADMIN l a Roc.

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

Comment:

Proc.

Step TASK ELEMENT 18 STANDARD Grade 8.R Determine and record PPC PDlL for Group at lol,, to 105)1entered.

su current power level.

I Comment:

Proc.

Step TASK ELEMENT 19 STANDARD Grade Determine and record control rod 8.S position corresponding to excess Group 4 at 2 0 (18 to 22) entered. su shutdown margin.

Proc.

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

Group 4 at 101 (100 to 105) entered. su PALISADES NUCLEAR PLANT Page 8 of 15 AUGUST 2010

JPM SRO ADMIN l a prOC.

step TASK ELEMENT 21 STANDARD Grade

_ _ _ ~

Comment:

Proc.

§tep TASK ELEMENT 22 STANDARD Grade Sign and date Step 9. Operator signs and dates.

Comment:

Proc.

Step TASK ELEMENT 23 STANDARD Grade I NA I Report results to Control Room Supervisor.

I CRS notified.

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

END OF TASK PALISADESNUCLEAR PLANT Page 9 of 15 AUGUST 2010

JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADESNUCLEAR PLANT Page 10 of 15 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 %Ap CONTROL ROD (TDB Figure 1.Ior Reactor Engineering)

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

4. REFERENCEDATA 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 %Ap (TDB Fig 1.3)

GROUP 4 INCHES 132(or131)

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 11 of 15 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.l)

F. MAXIMUM WORTH OF STUCK CONTROL 1.17 %Ap ROD AT A (TDB Fig 1.1)

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 PALISADESNUCLEAR PLANT Page 12 of 15 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 = ( ) + ( ) = NIA %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. NlA Q. power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin NIA requirements are satisfied.

PALISADESNUCLEAR PLANT Page 13 of 15 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 I.3or 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. If.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 14 of 15 AUGUST 2010

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

INITIAL CONDITIONS:

0 Rod #6 is inoperable and fully withdrawn.

0 It is believed that the rod is untrippable.

Burnup is 7,000 MWD/MTU.

Rx power is 100%.

PCS Boron is 865 ppm.

0 All rods out, equilibrium Xenon.

I NITI AT I NG CUES:

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

PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010

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

EXAMINER:

JPM SRO ADMlN l a JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Compensation for a Withdrawn, Inoperable Control Rod Alternate Path: NIA Facility JPM #: PL-OPS-ENG-011J KIA: 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 1 properly 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 15 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 CONDIT1ONS:

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 100%.

0 PCS Boron is 865 ppm.

0 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.]

PALISADESNUCLEAR PLANT Page 3 of 15 AUGUST 2010

JPM SRO ADMIN l a EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.

Proc.

Step TASK ELEMENT 1 STANDARD Grade I Record inoperable control rod identification.

I A, 6 and untrippable recorded.

Comment:

Proc.

Step TASK ELEMENT 2 STANDARD Grade Record worth of inoperable control rod.

I (1.16 to l.,8), entered. Isu I Comment:

EVALUATOR CUE: Reactor Engineering is not available.

Proc.

Step TASK ELEMENT 3 STANDARD Grade Record source of inoperable control 3 rod worth data. Tech Data Book entered. su I I

. Proc.

step TASK ELEMENT 4 STANDARD Grade Record current cycle burnup. Record current cycle burnup = 7000. su Comment:

I I PALISADESNUCLEAR PLANT Page 4 of 15 AUGUST 2010

JPM SRO ADMIN l a Roc.

Step TASK ELEMENT 5 STANDARD Grade Record current power level. '100' entered.

Comment:

t Proc.

SbP TASK ELEMENT 6 STANDARD Grade 4.C I Control rod worth inserted into core. I '0'and 'Gp 4 @ 131/132"entered.

Comment:

Proc.

Step TASK ELEMENT 7 STANDARD Grade Record PCS Boron concentration. '865' entered. su Comment:

Proc.

step TASK ELEMENT 8 STANDARD Grade Determine and record worth of control rods at current power level. 17,05(7.04 to 7.06)l entered, su Comment:

EVALUA TOR NOTE: This will need to be obtained by interpolation of the graph.

PALISADESNUCLEAR PLANT Page 5 of 15 AUGUST 2010

JPM SRO ADMIN l a Proc. TASK ELEMENT 9 STANDARD Step Grade Determine and record max worth of 5'F stuck rod at current power.

.16 to l.18)9 entered. su PrOC.

TASK ELEMENT I O STANDARD Grade Step Determine and record PCS boron 5.G concentration at 100% at '865 (860 to 870)' entered. su 7000 MWD/MTU.

Comment:

Proc.

TASK ELEMENT I 1 STANDARD Grade I 5-H I Determine and record power defect for 100% power. I .53 to .55), entered, Proc.

step TASK ELEMENT 12 STANDARD Grade Determine and record power defect at current power level. .53 (, .51 to .55), entered. su PALISADESNUCLEAR PLANT Page 6 of 15 AUGUST 2010

JPM SRO ADMlN l a I

Proc.

Step TASK ELEMENT 13 STANDARD Grade 5.5 I Determine and record required SDM. I2.0 already entered. l s u l Proc.

Step TASK ELEMENT 14 STANDARD Grade Calculate Net amount of shutdown I

I 1.82 (1.80 to 1.84) entered.

lsul Comment:

Proc.

Step TASK ELEMENT 15 STANDARD Grade Enter worth of untrippable rod. 1.17 (1.16 to 1.18)entered. su Comment:

Proc.

Step TASK ELEMENT 16 STANDARD Grade 6M Determine excess shutdown margin 0.65(0.645 to 0.655) entered. Determines with the inoperable rod. Step 7 substeps are NIA.

I I PALISADESNUCLEAR PLANT Page 7 of 15 AUGUST 2010

JPM SRO ADMIN l a Roc.

Step TASK ELEMENT 17 STANDARD Grade IF Shutdown margin is negative, 7.N-Q THEN...

Determines Step 7 substeps are NIA. su Group 4 at 101 (100 to 105) entered.

Comment:

Proc.

step TASK ELEMENT 19 STANDARD Grade Determine and record control rod 8.S position corresponding to excess Group 4 at 2 0 (18 to 22) entered. su shutdown margin.

I Proc.

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

Group 4 at 101 (100 to 105) entered. su Comment:

PALISADESNUCLEAR PLANT Page 8 of 15 AUGUST 2010

JPM SRO ADMIN l a Proc.

Step TASK ELEMENT 21 STANDARD Grade Comment:

Proc.

Step TASK ELEMENT 22 STANDARD Grade Sign and date Step 9. Operator signs and dates.

Comment:

Proc.

Step TASK ELEMENT 23 STANDARD Grade Report results to Control Room Supervisor. I CRS notified.

Comment:

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

END OF TASK PALISADES NUCLEAR PLANT Page 9 of 15 AUGUST 2010

JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 10 of 15 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 untriwable (Untrippable or Dropped)

2. WORTH OF UNTRIPPABLE OR DROPPED 1.17 %bp 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. I O )

B. CURRENT REACTOR POWER LEVEL 100 %

(Percent of Rated Power)

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

GROUP 4 INCHES 132(or131)

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 11 of 15 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 1.1)

F. MAXIMUM WORTH OF STUCK CONTROL 1.17 %Ap ROD AT A (TDB Fig 1.1)

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 12 of 15 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 UNTRIPPABLEOR 1. I 7 %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 performingSteps N through Q to calculate the maximum reduced reactor power level.

N. POWER DEFECT AT REDUCED POWER I + M = ( ) + ( ) = NIA %Ap

0. MAXIMUM REDUCED POWER LEVEL NIA %

P. Caution Tag the Control Rod joy-stick on panel C-02 that the new PDlL is Control Rod position at C. NIA Q. power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin NIA requirements are satisfied.

PALISADES NUCLEAR PLANT Page 13 of 15 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 UNTRIPPABLEOR 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) / (Today)

Performed By Date Reviewed By Date Forward Completed Form to Reactor Engineering Supervisor I

Reactor Engineering Supervisor Date PALISADES NUCLEAR PLANT Page 14 of 15 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.

Burnup is 7,000 MWD/MTU.

Rx power is 100%.

PCS Boron is 865 ppm.

All rods out, equilibrium Xenon.

ir TlNG CUES:

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

PALISADES NUCLEAR PLANT Page 15 of 15 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:

EXAMINER:

Alternate Path: N/A I

Facility JPM #: PL-OPS-ENG-011J

~

K/A: 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 1 properly 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 15 AUGUST 2010

JPM SRO ADMIN l a Tools/EquipmentlProcedures 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.

INITlAL CONDITIONS:

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 100%.

0 PCS Boron is 865 ppm.

0 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 15 AUGUST 2010

JPM SRO ADMIN l a EVALUATOR CUE: Provide candidate a working copy of EM-04-08 Attachment 7.

Proc.

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

A,6 and untrippable recorded. su I Comment:

Comment:

EVALUATOR CUE: Reactor Engineering is not available.

rod worth data. Tech Data Book entered.

Proc.

Step TASK ELEMENT 4 STANDARD Grade Record current cycle burnup. Record current cycle burnup = 7000.

Comment:

I CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 2010

JPM SRO ADMIN l a Proc.

Step TASK ELEMENT 5 STANDARD Grade Record current power level. '100' entered. su Comment:

Proc. TASK ELEMENT 6 STANDARD Grade step r

Control rod worth inserted into core. '0'and 'Gp 4 @ 131/132" entered. Isu Comment:

Proc.

Step TASK ELEMENT 7 STANDARD Grade Record PCS Boron concentration. '865' entered.

Comment:

Proc, Step TASK ELEMENT 8 STANDARD Grade I Comment:

I Determine and record worth of control rods at current power level. I ,7.05 (7.04 to 7.06), entered I su EVALUATOR NOTE: This will need to be obtained by interpolation of the graph.

PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 2010

JPM SRO ADMIN l a Determine and record max worth of 5'F stuck rod at current power.

'1.17 (1.16 to 1.18)'entered. su Comment:

Proc.

TASK ELEMENT 10 STANDARD Grade Step Determine and record PCS boron 5.G concentration at 100% at '865 (860 to 870)' entered. su 7000 MWD/MTU.

Proc.

TASK ELEMENT 11 STANDARD Grade Step I 5-H I Determine and record power defect for 100% power. I .53 to .55), entered.

lsul Proc.

Step TASK ELEMENT 12 STANDARD Grade Determine and record power defect at 5.'

current power level.

3-, .51 to .55), entered. su PALISADES NUCLEAR PLANT Page 6 of 15 AUGUST 2010

JPM SRO ADMlN l a Proc.

TASK ELEMENT 13 STANDARD Grade SW 5.5 Determine and record required SDM. 2.0 already entered. su Proc.

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

1.82 (1.80 to 1.84) entered. su Proc.

Step TASK ELEMENT 15 STANDARD Grade Enter worth of untrippable rod. 1.17 (1.16 to 1.18)entered.

Comment:

Proc.

step TASK ELEMENT 16 STANDARD Grade Determine excess shutdown margin 0.65 (0.645 to 0.655) entered. Determines 6mM with the inoperable rod. Step 7 substeps are N/A.

PALISADESNUCLEAR PLANT Page 7 of 15 AUGUST 2010

JPM SRO ADMIN l a Prac.

Step TASK ELEMENT 17 STANDARD Grade I 7.N-Q I IF Shutdown margin is negative, THEN ...

I Determines Step 7 substeps are N/A.

Isu Comment:

Proc.

Step TASK ELEMENT 18 STANDARD Grade I 8.R I I

Determine and record PPC PDlL for current power level. I I

at ,ol,, oo to 105)Bentered.

lsuI I

Comment:

Proc.

Step TASK ELEMENT 19 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:

Proc.

step TASK ELEMENT 20 STANDARD Grade I 8.T Comment:

I Determine and record PDlL for inoperable control rod condition.

I Group 4 at 101 (100 to 105) entered.

IsuI PALISADES NUCLEAR PLANT Page 8 of 15 AUGUST 2010

JPM SRO ADMlN l a Roc.

Step TASK ELEMENT 21 STANDARD Grade Proc.

Step TASK ELEMENT 22 STANDARD Grade Sign and date Step 9. Operator signs and dates. su Comment:

Prw.

Step TASK ELEMENT 23 STANDARD Grade Report results to Control Room NA Supervisor. CRS notified. su PALISADES NUCLEAR PLANT Page 9 of 15 AUGUST 2010

JPM SRO ADMIN l a SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 10 of 15 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 untriopable (Untrippable or Dropped)

2. WORTH OF UNTRIPPABLE OR DROPPED 1.17 %Ap 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 MW d/MTU (TDB Fig 1.10)

B. CURRENT REACTOR POWER LEVEL 100 %

(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 11 of 15 AUGUST 2010

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

5. GENERAL DATA E. WORTH OF ALL CONTROL RODS AT A 7.05 %Ap (TDB Fig 1.1)

F. MAXIMUM WORTH OF STUCK CONTROL 1.17 %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) I.53 %Ap 100 100 J. REQUIRED SHUTDOWN MARGIN 2.0 %Ap (4 PCPs Operating)

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

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

1.1 PALISADES NUCLEAR PLANT Page 12 of 15 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 UNTRIPPABLEOR 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 performingSteps N through Q to calculate the maximum reduced reactor power level.

N. POWER DEFECT AT REDUCED POWER I + M = ( ) + ( ) = NIA %Ap

0. MAXIMUM REDUCED POWER LEVEL NIA %

P. Caution Tag the Control Rod joy-stick on panel C-02 that the new PDlL is Control Rod position at C. NIA Q. power reduction is required, THEN after power reduction re-perform Attachment 1 to verify Shutdown Margin NIA requirements are satisfied.

PALISADES NUCLEAR PLANT Page 13 of 15 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 Re ctor Engin ering Supervisor I

Reactor Engineering Supervisor Date PALISADES NUCLEAR PLANT Page 14 of 15 AUGUST 2010

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

INITlAL CONDITIONS:

0 Rod #6 is inoperable and fully withdrawn.

0 It is believed that the rod is untrippable.

Burnup is 7,000 MWD/MTU.

0 Rx power is 100%.

PCS Boron is 865 ppm.

0 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.

PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010

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

EXAMINER:

JPM SRO ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Perform Safety Injection Refueling Water Tank Operations Alternate Path: NIA Facility JPM #: PL-OPS-ENG-O19J K/A: 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-2AI 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 PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010

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

0 SOP-2A, "Chemical and Volume Control System" Calculator 0 Pencil and paper 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:

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

0 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 SIRWT boron concentration.

PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010

JPM SRO ADMIN l b EVALUATOR CUE: Provide candidate a working copy of SOP-2A Section 7.6.1 TASK ELEMENT 1 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 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. SITSmay also be affected during fiII and drain operations -

TASK ELEMENT 2 STANOARO 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:

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

Where:

SlRW Tank Volume = SlRW total gallons

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

PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010

JPM SRO ADMlN I b I Where: I Operator calculates the following: I 7.6-1.a.2 Blend Ratio = gallons of PMW per 1 (12,524/2149) - 1 = 4.83 (allow 4.80 - su gallon of concentrated Boric Acid 4.85)

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

EVALUATOR NOTE: Allow 4.80 fo 4.86 TASK ELEMENT 4 STANDARD Grade Gallons of concentrated boric acid to add = Total Volume Makeup to SIRW/(Blend Ratio + 1)

Where:

Total Volume Makeup to SIRWT = 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 5 STANDARD Gallons of PMW to add = Total volume makeup to SIRWT - Gallons of Boric Acid to add Where:

Operator calculates the following:

Total Volume Makeup to SIRWT =

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.

above EVALUATOR NOTE: Allow 2483 - 2488 I

Proc.

Step TASK ELEMENT 6 STANDARD 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.

I Comment:

Concentrated Boric Acid: 514.6 gal EVALUATOR NOTE: Allow 2483 - 2488 gal for Primary Makeup Water and 511.9 -

517.2 gal for Boric Acid EVALUATOR CUE: Role play as CRS END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010

JPM SRO ADMIN I b SIMULATOR OPERATOR INSTRUCTIONS 0 NONE PALISADESNUCLEAR PLANT Page 7 of 8 AUGUST 2010

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

INITlAL CONDITIONS:

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

0 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 SIRWT boron concentration.

PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010

NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: SRO ADMIN 2 TITLE: APPROVE A HEAVY LOAD MOVEMENT CANDIDATE:

EXAM1NER:

JPM SRO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Approve a heavy load movement Alternate Path: N/A Facility JPM #: PL-OPS-ADM-001J WA: 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 3-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 ADMIN 2 Tools/Equipment/ProceduresNeeded:

FHS-M-23, Movement of Heavy Loads in The Spent Fuel Pool Area, Attachment 1, 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:

The Plant is in Mode 1 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-14B 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-8B, 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.

PALISADES NUCLEAR PLANT Page 3 of 16 AUGUST 2010

JPM SRO ADMIN 2 EVALUATOR CUE Provide candidate the completed FHS-M-23, Aft. 7 Working Copy.

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

Att. 6 Is the load a heavy load (>I300 Ibs)? -

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

Comment:

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

Proc. Step TASK ELEMENT 2 I STANDARD Grade Is the load movement within Load Path 3 -

NO Att. 6 only? Heavy Load path #4 determined for movement su of DFS components between cask wash-down pit and cask loading floor area, Att.3 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.

Evaluator Note: Candidate determines FHS-M-23 Attachment 7 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).

Proc. Step I

TASK ELEMENT 3 I STANDARD Grade Att. 6 Will loads be moved over Load Path I? -

NO su 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.

PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010

JPM SRO ADMlN 2 proc. step TASK ELEMENT 4 STANDARD Grade Will loads be moved over Load Path 4 Aft. 6 (Main Fuel Pool)? -

YES su Comment:

Evaluator Note: Candidate determines FHS-M-23 Attachment 1 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).

Proc. W p TASK ELEMENT 5 I STANDARD Grade Has fuel decayed 2 30 days?

Att. 6 -

YES (given in the initial conditions) su Proc. Step TASK ELEMENT 6 STANDARD Grade

\

su I Comment:

PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010

JPM SRO ADMlN 2 Proc. Step TASK ELEMENT 7 I STANDARD Grade 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 TASK ELEMEPIT 8 I STANDARD 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.

r PrOC. step TASK ELEMENT 9 I STANDARD Grade Has fuel decayed 2 90 days?

Att. 6 -

YES (given in the initial conditions) su Comment:

Rtoc. step TASK ELEMENT 10 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 I

PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010

JPM SRO ADMIN 2 Proc. step TASK ELEMENT I 1 I STANDARD Grade I Att. 6 I Will loads be moved over Load Path 2?

I su Comment:

Evaluator Note: Candidate determines FHS-M-23 Attachment 7 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).

Proc. Step TASK ELEMENT 12 I STANDARD Orade Will loads be moved over Load Path 3?

Att. 6 -

NO su Proc. Step TASK ELEMENT 13 I STANDARD Grade I

Will non-heavy loads be moved under this Att. 6 procedure? -

NO (given in initial conditions) su Proc. Step TASK ELEMENT 14 I STANDARD Grade I Att. 6 I Will load be moved in an alternate path?

I-NO (Path 4 is the only path for this evolution) lsul Comment:

PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010

JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 15 I . STANDARD Grade On-Shift, Duty SRO m: SRO references Section 1.O through 4.0, and Review and understand Sections 1.O ensures:

'.'.la through 4.0 of procedure.

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

I Comment: I TASK ELEMENT 16 STANDARD Grade I On-Shift, Duty SRO &aJ: SRO verifies plant systems and conditions are ENSURE plant systems and conditions are 5.1 .Ib met.

met (has effectively completed this step by su ensuring Att. 6 complete)

Comment:

Proc. Step TASK ELEMENT 17 I STANDARD Grade I On-Shift, Duty SRO shall: I SRO enters on FHS-M-23, Att. 1:

I I

Complete Attachment 1 to document Signs, Dates and Times, in box ( 8 )

permission to commence heavy load 5'1'1c movement for approved Load Paths during Todav/l930 for Start in box (9) su specified time period. Todav/2300 OR 0700 tomorrow/ Sinned for Stop in box(9)

Comment:

Evaluator Note: Candidate determines FHS-M-23 Attachment 1 working copy Block 7 "HL Path(s) Authorized For Use" is wrong and changes to reflect Load Path 4 (may be done at anytime prior to end of JPM).

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

JPM SRO ADMlN 2 Roc. Step TASK ELEMENT 18 STANDARD On-Shift, Duty SRO DOCUMENT authorization of heavy loads 5'1'1md movements in the Operations log.

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

JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS 0 NIA PALISADES NUCLEAR PLANT Page 10 of 16 AUGUST 2010

JPM SRO ADMIN 2

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

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

w/FHS-M-23: NONE Measure airder temperature for sinale failure Dower lift (6) General Description of HL(s) Allowed To Be Moved (Can attach schedule to satisfv)

MSB Shieldincl Lid 1

I (7) HL Path@)

Authorized For Use 4

(8) Approved By: On-Shift, Duty SRO (Name / Date / Time)

(9) HL Duration Approved Start: (Date / Time) Stop: (Date / Time)

I IJ Operator/ TODAY I NOW START: TODAY -

1930 I I

/IO) CALIBRATED EQUIPMENT Ilf Rewired)

STOP:

TODAY (OR Tomorrow) 2300 (OR 0700)

Equipment Description Range / Accuracy Serial Number Calibration Date Calibration Due Date

________~ _______~ __

FLUKE M o d e l 6 6 0 I 0-200"FI & .02"F I CMS234567 06/01/2010 1- 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 I I I I ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY PALISADESNUCLEAR PLANT Page 11 of 16 AUGUST 2010

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

8. On-Shift, Duty SRO PRINT name, date, and time (SRO authorization required before starting heavy load movements. SRO authorization confirms plantlsystedcornponent 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.

i 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, & rigging requirementsare understoodand 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 understandingof heavy load requirements AND that all heavy load prerequisites, precautions & limitation, and equipmentlplantsafety 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 understandingof heavy load requirementsAND that all heavy load prerequisites, precautions & limitation, and equipmentlplantsafety 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 Engineeringto 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 l(l) Date: TODAY (2) Work Order No: 5199999 1

Page 2 of 4 (3) Authorization Period:

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

wlFHS-M-23: NONE Measure airder temDerature for sinule failure Dower 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 / Time) Stop: (Date / Time)

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

~ ~ ~ ~~~

MSB Shielding Lid 2

/ I START: /

STOP: /

/ I O ) CALIBRATED EQUIPMENT (If Rewired)

FLUKE Model 8660 0-200°F/f .02"F CMS234567 06101/2010 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

oioz i s n m v I N W d tlV313flN S 3 a V S l l V d

~ ~

I I I I

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

Description:

Attachment (YES I NO)

I (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:

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-14B 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 PALISADES NUCLEAR 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:

EXAM1NER:

JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task: Respond to Steam Generator Tube leakage in accordance with ONP-23.2 Alternate Path: N/A Facility JPM #: NEW K/A: 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.OE+03 to 9.OE+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 PALISADES NUCLEAR PLANT Page 2 of 7 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.

INITIAL CONDITIONS:

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.

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

PCS Gas Total Isotope = 0.5 VCi/cc 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.

PALISADES NUCLEAR PLANT Page 3 of 7 AUGUST 2010

JPM SRO ADMIN 3 EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.

TASK ELEMENT 1 STANDARD 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.

t1-Proc.Step TASK ELEMENT 2 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 I Comment:

Proc.Step TASK ELEMENT 3 I STANDARD Grade I p g 22 Step Comment:

OBTAIN PCS Gas Total Isotope from Chemistry using last known analysis.

I Determines PCS Gas Total Isotope =

0.5 pCi/cc from initiating cue. lsul PALISADESNUCLEAR PLANT Page 4 of 7 AUGUST 2010

JPM SRO ADMIN 3 Proe.$tep TASK ELEMENT 4 STANDARD Grade pg 2 DETERMINE maximum Primary to Determines 0.02 gpm (from Attachment 2 su Secondary Leakrate based on current Step 3a.)

Step 3 Action Level.

Comment:

Proc.Step TASK ELEMENT 5 I STANDARD Grade CALCULATE uncorrected leakrate using the following equation: Calculates uncorrected leakrate using formula:

Uncorrected Leakrate (pCi-gal/min-kg) = 0.02 gpm X 0.5 pCi/cc X 1000 = su Step 4 Primary to Secondary Leakrate (gallmin) X PCS Gas Total Isotope (pCi/cc) X 10.0 pCi-gal/min-kg 1000 (cc/kd Comme TASK ELEMENT 6 STANDARD

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

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

Informs CRS of results and that Reviewed By signature is still required.*

Comment:

EVALUATOR NOTE: allow 8.OE+03 to 9.OE+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 5 of 7 AUGUST 2010

JPM SRO ADMIN 3 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 is an at-power IC.

PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010

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

I NIT1AL CONDIT1ONS:

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 7 of 7 AUGUST 2010

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

EXAMINER:

JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE 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.OE+03 to 9.OE+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 PALISADES NUCLEAR PLANT Page 2 of 7 AUGUST 2010

JPM SRO ADMlN 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.

INITIAL CONDITIONS:

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.

0 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 7 AUGUST 2010

JPM SRO ADMIN 3 EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.

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

step 3.a secondary leakrate. Refer to Attachment 1, Estimation of Primary to Secondary Leakrate.

Comment:

Proc.Step TASK ELEMENT 2 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 I Comment:

Proc.Step TASK ELEMENT 3 I STANDARD Grade pg OBTAIN PCS Gas Total Isotope from Determines PCS Gas Total Isotope =

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

su step 2 Comment:

PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010

JPM SRO ADMIN 3 Proc.Step TASK ELEMENT 4 I STANDARD Grade pg 2 DETERMINE maximum Primary to Determines 0.02 gpm (from Attachment 2 Secondary Leakrate based on current Step 3a.)

su step 3 Action Level.

Proc.Step TASK ELEMENT 5 I STANDARD Grade CALCULATE uncorrected leakrate using the following equation: Calculates uncorrected leakrate using formula:

pg 2 Uncorrected Leakrate (pCi-gal/min-kg) = 0.02 gpm X 0.5 pCi/cc X 1000 = su Step 4 Primary to Secondary Leakrate (gal/min) X PCS Gas Total Isotope (pCi/cc) X 10.0 pCi-gal/min-kg 1000 (cc/kg) -

Comment:

TASK ELEMENT 6 STANDARD

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

ESTIMATE RIA-0631 count rate using the su Uncorrected Leakrate Graph on page 3.

SIGNS Completed By on Attachment 1 Step 5

- Pg 2.*

Informs CRS of results and that Reviewed By signature is still required.*

Comment:

EVALUATOR NOTE: allow 8.OE+03 to 9.0+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 5 of 7 AUGUST 2010

JPM SRO ADMIN 3 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 is an at-power IC.

PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010

JPM SRO ADMIN 3 (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 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 7 of 7 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:

EXAM1NER:

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

Task Standard: Determines RIA-0631 count rate of 8.5E+03 cpm (allow 8.OE+03 to 9.OE+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 PALISADES NUCLEAR PLANT Page 2 of 7 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.

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 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 7 AUGUST 2010

JPM SRO ADMlN 3 EVALUATOR CUE:Provide candidate a working copy of ONP-23.2.

Proc.Step TASK ELEMENT 1 ESTIMATE the count rate indication on I ""

STANDARD Grade RIA-0631, Condenser Off Gas Monitor, Att which wouldresultin 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."

Proc.Step TASK ELEMENT 2 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 Proc,Step TASK ELEMENT 3 I STANDARD 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 Comment:

PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010

JPM SRO ADMIN 3 ProcSteR TASK ELEMENT 4 I STANDARD Grade pg 2 DETERMINE maximum Primary to Determines 0.02 gpm (from Attachment 2 Secondary Leakrate based on current Step 3a.)

su Step 3 Action Level.

Comment:

TASK ELEMENT 5 STANDARD CALCULATE uncorrected leakrate using the following equation:

Calculates uncorrected leakrate using formula:

pg 2 Uncorrected Leakrate (VCi-gal/min-kg) =

0.02 gpm X 0.5 VCi/cc X 1000 = su Step 4 Primary to Secondary Leakrate (gal/min) X PCS Gas Total Isotope (VCikc) X 10.0 VCi-gal/min-kg 1000 (cc/kg)

Comment:

TASK ELEMENT 6 STANDARD Determines 8.5E+03 cpm using Attachment 1 pg 3 graph with 4 scfm Off Gas flowrate line and 2.OE+00 Pgs 2&3 Uncorrected Leak Rate line.

Step 5 ESTIMATE RIA-0631 count rate using the Uncorrected Leakrate Graph on page 3. . SIGNS Completed By on Attachment 1 su Pg 2.*

. Informs CRS of results and that Comment:

Reviewed By signature is still required.*

EVALUATOR NOTE: allow 8.0+03 to 9.0+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.

art of the critical step END OF TASK PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 2010

JPM SRO ADMIN 3 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 is an at-power IC.

PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010

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

INIT1AL CONDITIONS:

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 7 of 7 AUGUST 2010

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

EXAMINER:

JPM SRO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Classify an Event and Determine PARS- Protective Action Recommendations Alternate Path: NIA Facility JPM #: NEW WA: 2.4.41, 2.4.44 Importance: RO:4.1, 4.0 SRO: 4.1,4.4 WA Statement: (2.4.41) Knowtedge 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: Any 2-Preferred Evaluation Method: Perform X - Simulate

References:

El-I Emergency Classifications and Actions I

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 ADMlN 4 Tools/EquipmenVProcedures Needed:

El-I , Emergency Classifications and Actions, Attachment 1 EI -3, Communicat ions and Notificat ions El-6.13, Protective Action Recommendationsfor 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.

SIRWT 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.

PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010

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

Proc.Step TASK ELEMENT 1 I STANDARD Refers to lower right-hand corner of El-I ,

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

Comment:

TASK ELEMENT 2 STANDARD Refers to Table F1

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

Determines status of fission product - Determines a LOSS of PCS Barrier (based 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).

Proc.Step TASK ELEMENT 3 I STANDARD Grade I 1 El-I Att 1 Declares Emergency Classification.

Declares a GENERAL EMERGENCY per FG1 based on status of fission product barriers (loss of TWO and potential loss of THIRD). su I I Comment:

CRITtCAI; @T'EP-- muat b pMormed wM%a15 minutes of start of JPM.

I PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 4 I STANDARD Grade El-1 Prepares Emergency Actions/Notifications Obtains El-I, Attachment 2 and fills out. su

~ t t 2 form.

Comment:

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

Filling out this form is NOT required for this JPM.

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

Proc.Step TASK ELEMENT 5 STANDARD Grade EI-3 Obtains EI-3, Attachment 1 and fills out per Prepares Event Notification Form.

attached KEY.

su Att 1

~~~ ~~~

Comment:

EVALUATOR CUE: 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 CUE: If JPM is not conducted in the Simulator, hand them a blank Event Notification form to fill out (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.

Proc.Step TASK ELEMENT 6 STANDARD Grade Obtains EI-6.13 and corresponding Attachment 1 and determines:

1-6.13 Determines Protective Action Recommendations (PARS). - Evacuate Areas 1 and 3 (minimum GE su

, Att 1 recommendation on bottom of Pg 1 of Attachment 1)

Comment:

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

PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010

JPM SRO ADMlN 4 ProcStep TASK ELEMENT 7 I STANDARD Grade Candidate refers to El-I 1: determines there is Candidate may determine status of Core su E'-1 not enough info provided in initiating cue to Damage per El-I 1.

determine amount of core damage.

Comment:

EVALUATOR NOTE: If candidate attempts to pertbrm this step, provide them with a working copy of 1-11, attachment 2.

Prgc.SCp TASK ELEMENT 8 I STANDARD Grade Palisades Event Notification Form completely Et-3 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)

I CRITICAL STEP - must be performed wlthfn 13 minutes of deQlaration of General Qnergency. I END OF TASK PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010

ANSWER KEY JPM SRO ADMIN 4 Proc No El-3 Attachment 1 PALISADES EVENT NOTIFICATION FORM Revision 29 Page 1 of 1 0 ActualEvent Drill Plant Contact Information Nuclear Power Plant:

Plant Communicator: Time of Communication: V.B.

S.O.M.

NRC Plant Message Number Calling From: 0 Control Room 0TSC OEOF 0 Other Call Back Telephone Number:

Current Classification 0Unusual Event 0Alert Site Area Emergency General Emergency 0 Termination This Classificationwas declared as of: Date: Today Time: Within 15 minutes from start of JPM Reason for Classification 0Abnormal Rad Levels / Radiological Effluent 0 System Malfunctions 0 Hazards and Other Conditions Affecting Cold Shutdown / Refueling System Malfunction Plant Safety 0Independent Spent Fuel Storage Installation Events Fission Product Barrier Degradation IC Number: FGl Radiological Release in Progress Due to Event IXI Yes 0 No Protective Action Recommendations 0None Evacuation of Areas(s): 1 2 3 4 5 In-Place ShelterofArea(s) 01 02 3 c]4 5 PAR based on: [7 Dose Calculation (Palisades Event Technical Data Sheet required) Plant Status 0 Security Event Other Meteorological Data Wind Direction (degrees): From 305 To 125 Wind Speed (MPH): 1 Stability Class: G Precipitation: 0Yes 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.

PALISADES NUCLEAR PLANT 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 .0 mph (X) 10 meters

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

Multiply by 0.77

2. WD, Wind Direction = 305 from O (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 ADMIN 4 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

e The Reactor tripped 10 minutes ago.

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

e Pressurizer level is off-scale LOW.

e PCS pressure is 1000 psia.

e CETs indicate 5OOOF.

e SIRWT level is 92% and lowering slowly.

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

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

e 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.

PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 2010

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