ML100690431: Difference between revisions

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(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 130: Line 130:
: a. Inform the Shift Manager of the available interval and that additional inventory sources are required.
: a. Inform the Shift Manager of the available interval and that additional inventory sources are required.
Shift Manager Informed that time interval available for heat removal =
Shift Manager Informed that time interval available for heat removal =
4.2 hours (3.7 to 4.5 hours allowed)
 
===4.2 hours===
(3.7 to 4.5 hours allowed)
S  U Comment:
S  U Comment:
EVALUATOR: Notify candidate that the Shift Manager will have someone else identify potential inventory sources that can be made available in the next 4 hours per step 5.b of section 5.0.  
EVALUATOR: Notify candidate that the Shift Manager will have someone else identify potential inventory sources that can be made available in the next 4 hours per step 5.b of section 5.0.  

Revision as of 07:33, 14 October 2018

2009 Palisades Proposed Admin JPMs
ML100690431
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/25/2009
From: Valos N A
NRC/RGN-III/DRS/OLB
To:
Entergy Nuclear Operations
References
Download: ML100690431 (66)


Text

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: RO/SRO ADMIN 1a TITLE: DETERMINE FEEDWATER RESERVE INVENTORY

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO/SRO ADMIN 1a JOB PERFORMANCE MEASURE DATA PAGE Task: Determine Feedwater Reserve Inventory

Alternate Path: N/A

Facility JPM #: Modified RO-A.1a 2008 AUDIT

K/A: 2.1.25 Importance: RO: 3.9 SRO: 4.2

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

Task Standard: Feedwater reserve inventory ca lculated to last 3.9 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EOP Supplement 2, "PCS Cooldown Strategy"

Validation Time: 10 minutes Time Critical: NO

Candidate: ___________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 MAY 2009 JPM RO/SRO ADMIN 1a EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EOP Supplement 2, "PCS Cooldown Strategy"

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

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

With the plant at 100% power, a loss of offsit e power occurs. The reactor was manually tripped and the operators transiti oned to EOP-8.0. The following plant conditions exist:

Offsite power is not expected to be restored for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> It is 30 minutes after shutdown T-81 gravity feed to T-2 is not aligned T-2 is at 86%, T-81 is at 85%, and T-939 is at 58%

Cold leg temperatures are stable at 535 F INITIATING CUES:

The CRS has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

Calculation of minimum cooldown rate (section 5.0 step 6) is NOT required at this time.

PALISADES NUCLEAR PLANT Page 3 of 9 MAY 2009 JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Locate EOP Supplement 2, PCS Cooldown Strategy EOP Supplement 2 LOCATED S U Comment:

Evaluator: Provides a working copy of EOP Supplement 2.

Proc. Step TASK ELEMENT 2 STANDARD Grade 1.1 CONDENSATE STORAGE TANK T-2 DETERMINE AND RECORD Condensate Storage Tank T-2 level using the "T-2 inventory" curve T-2 inventory =

94,000 gallons RECORDED (93,000 to 95,000 allowed)

S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 3 STANDARD Grade 2.1 DEMINERALIZED WATER TANK T-939 IF any of the following conditions exist: -

THEN Demineralized Water Tank T-939 is available DETERMINES T-939 water is NOT available S U Comment: NOTE: Loss of Bus 13 combined with loss of Bus 1E (due to loss of offsite power) results in inability to power P-936 to transfer T-936 water to T-2.

CRITICAL STEP

PALISADES NUCLEAR PLANT Page 4 of 9 MAY 2009 JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 4 STANDARD Grade 3.1 If any of the following conditions exist-..THEN Primary System Makeup

Tank T-81 is available.

Determines T-81 is NOT available S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade 4.1 ADD the available tank inventories: (Step 1.1 T-2) + (Step 2.2 T-939) = (Total inventory)

Total Inventory

= 94,000 gallons RECORDED (93,000 to 95,000 allowed)

S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 6 STANDARD Grade 5.1 DETERMINE AND RECORD present highest PCS Loop T C (T C Initial)

T C Initial =

535 °F RECORDED (given in initial conditions)

S U Comment:

Proc. Step TASK ELEMENT 7 STANDARD Grade 5.2 DETERMINE AND RECORD inventory required to remove sensible heat using "T C Initial" temperature and the "Sensible Heat Removal" curve.

Required Sensible Heat Removal Inventory =

42,000 gallons RECORDED (41,000 to 43,000 allowed)

S U Comment:

CRITICAL STEP

PALISADES NUCLEAR PLANT Page 5 of 9 MAY 2009 JPM RO/SRO ADMIN 1a Proc. Step TASK ELEMENT 8 STANDARD Grade 5.3 SUBTRACT Step 5.2 results from Step 4.1 results: (Step 4.1 Total FW) - (Step 5.2 Sensible Heat) = (Inventory for decay heat removal)

Inventory Available to remove decay heat =

52,000 gallons RECORDED (94,000 - 42,000 = 52,000)

(50,000 to 54,000 allowed)

S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 9 STANDARD Grade 5.4 DETERMINE AND RECORD the time interval available for heat removal using the following: Applicable "Decay Heat Removal" curve for the number of PCPs operating Graph line for elapsed time after shutdown Amount of inventory available to remove decay heat (graph)

Time interval available for heat removal

= 4.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RECORDED (Interpolation may be used)

(3.7 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> allowed)

S U Comment:

CRITICAL STEP

PALISADES NUCLEAR PLANT Page 6 of 9 MAY 2009 JPM RO/SRO ADMIN 1a PALISADES NUCLEAR PLANT Page 7 of 9 MAY 2009 Proc. Step TASK ELEMENT 10 STANDARD Grade 5.5.a If the time interval available for heat removal is less than eight hours, THEN

PERFORM the following:

a. Inform the Shift Manager of the available interval and that additional inventory sources are required.

Shift Manager Informed that time interval available for heat removal =

4.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s

(3.7 to 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> allowed)

S U Comment:

EVALUATOR: Notify candidate that the Shift Manager will have someone else identify potential inventory sources that can be made available in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per step 5.b of section 5.0.

Proc. Step TASK ELEMENT 11 STANDARD Grade n/a Notify the CRS EOP Supplement 2 is complete [reported time interval available

for heat removal and available inventory

sources] CRS NOTIFIED that EOP Supplement 2 task is

complete S U Comment:

Evaluator: If notified as CRS, Acknowledge.

END OF TASK

JPM RO/SRO ADMIN 1a SIMULATOR OPERATOR INSTRUCTIONS NONE

PALISADES NUCLEAR PLANT Page 8 of 9 MAY 2009 JPM RO/SRO ADMIN 1a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

With the plant at 100% power, a loss of offs ite power occurs. The reactor was manually tripped and the operators transiti oned to EOP-8.0. The following plant conditions exist:

Offsite power is not expected to be restored for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Bus 13 is out of service and not expected to be restored for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> It is 30 minutes after shutdown T-81 gravity feed to T-2 is not aligned T-2 is at 86%, T-81 is at 85%, and T-939 is at 58%

Cold leg temperatures are stable at 535 F INITIATING CUES:

The CRS has directed you to complete EOP Supplement 2, PCS Cooldown Strategy.

Calculation of minimum cooldown rate (section 5.0 step 6) is NOT required at this time.

PALISADES NUCLEAR PLANT Page 9 of 9 MAY 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: RO ADMIN 1b TITLE: PERFORM A PCS HEATUP DETERMINATION

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Perform PCS Heatup Determination

Alternate Path: N/A

Facility JPM #: RO-A.1b 2008AUDIT

K/A: 2.1.25 Importance: RO: 3.9 SRO: 4.2

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

Task Standard: Allowable Shutdown Cooling out age time calculated to be 28 minutes (27 minutes to 29 minutes).

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SOP-3, "Safety Injection and Shutdown Cooling System" ONP-17, "Loss of Shutdown Cooling"

Validation Time: 15 minutes Time Critical: NO

Candidate: ________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 May 2009 JPM RO ADMIN 1b EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-3, "Safety Injection and Shutdown Cooling System" ONP-17, "Loss of Shutdown Cooling"

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

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Ten days after a plant shutdown, PCS temperature is 114ºF The Reactor cavity is flooded to a level of 629' The Pressurizer manway is removed Shutdown Cooling is in operation, but must be shutdown for the maximum time allowable

INITIATING CUES:

The CRS directs you to determine how l ong (in minutes) Shutdown Cooling may be secured in accordance with SOP-3, Section 7.3.7.

PALISADES NUCLEAR PLANT Page 3 of 8 May 2009 JPM RO ADMIN 1b Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Locates SOP-3, Safety Injection And Shutdown Cooling System, Section 7.3.7, PCS Heatup Rate Determination Section 7.3.7 of SOP-3 LOCATED S U Comment:

Evaluator: Provides a working c opy of SOP-3, section 7.3.7.

Proc. Step TASK ELEMENT 2 STANDARD Grade 7.3.7a DETERMINE "Approximate Time to 200°F time from appropriate curve in ONP-17, Loss of Shutdown Cooling, for

existing/anticipated PCS conditions and

convert to hours. , Approximate Time to 200°F

Curves, of ONP-17 LOCATED S U Comment:

Evaluator: Provide a working copy of ONP-17, Attachment 1.

Proc. Step TASK ELEMENT 3 STANDARD Grade (ONP-17, Att.1) 1.

DETERMINE PCS level using all available indications.

PCS level 629 feet (given in initial conditions)

S U Comment:

Proc. Step TASK ELEMENT 4 STANDARD Grade (ONP-17, Att.1) 2.

DETERMINE PCS temperature using any of the following:

PCS temperature 114°F (given in initial conditions)

S U Comment:

PALISADES NUCLEAR PLANT Page 4 of 8 May 2009 JPM RO ADMIN 1b Proc. Step TASK ELEMENT 5 STANDARD Grade (ONP17, Att.1) 5.

REFER TO appropriate page in this attachment for PCS conditions Page #8 of Attachment 1 REFERED TO:

Uses Refueling Cavity Flooded to 629' to determine time to 200ºF USES "10 Days" (time after reactor shutdown) and 114ºF point (initial PCS temperature) and

DETERMINES time to 200ºF is ~2 hours S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 6 STANDARD Grade 7.3.7b DETERMINE PCS heatup rate as follows:

(200°F - TINITIAL)_______________

Approximate Time to 200°F (Hours)

Heatup rate CALCULATED to be ~43ºF / hour S U Comment:

NOTE: Heatup rate is calculated by dividing 86ºF (200ºF - 114ºF) by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

CRITICAL STEP

Proc. Step TASK ELEMENT 7 STANDARD Grade 7.3.7c. DETERMINE the allowable Shutdown Cooling outage time (heatup rate >

20°F/Hr) CALCULATES allowable Shutdown Cooling

outage time to be 28 minutes (27 - 29 minutes).

S U Comment: NOTE: Allowable outage time calculated by dividing 20ºF (maximum allowed heatup) by 43ºF / hour (previously calculated heatup rate) and converting to minutes.

CRITICAL STEP

PALISADES NUCLEAR PLANT Page 5 of 8 May 2009 JPM RO ADMIN 1b PALISADES NUCLEAR PLANT Page 6 of 8 May 2009 Proc. Step TASK ELEMENT 8 STANDARD Grade n/a Notifies the CRS that securing Shutdown Cooling has been calculated at

approximately 28 minutes.

CRS NOTIFIED Shutdown Cooling can be

secured for approximately 28 minutes.

S U Comment:

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

END OF TASK

JPM RO ADMIN 1b SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 7 of 8 May 2009 JPM RO ADMIN 1b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Ten days after a plant shutdown, PCS temperature is 114ºF The Reactor cavity is flooded to a level of 629' The Pressurizer manway is removed Shutdown Cooling is in operation, but must be shutdown for the maximum time allowable

INITIATING CUES:

The CRS directs you to determine how l ong (in minutes) Shutdown Cooling may be secured in accordance with SOP-3, Section 7.3.7.

PALISADES NUCLEAR PLANT Page 8 of 8 May 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: SRO ADMIN 1b TITLE: MONITOR PCS HEATUP/COOLDOWN WITH THE PPC

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 1b JOB PERFORMANCE MEASURE DATA PAGE Task: Operate the Palisades Plant Computer System

Alternate Path: N/A

Facility JPM #: PPC-JPM-02

K/A: 2.1.19 Importance: RO: 3.9 SRO: 3.8

K/A Statement: Ability to use plant computer s to evaluate system or component status.

Task Standard: Commence monitoring a PCS heatup/cooldown using Page 372 "SDC 15 Minute Rate Trend," of the PPC.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

GOP-2, "MODE 5 To MODE 3 525°F" PO-2, "PCS Heatup/Cooldown Operations"

Validation Time: 10 minutes Time Critical: NO

Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 May 2009 JPM SRO ADMIN 1b EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

PO-2, PCS Heatup/Cooldown Operations Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A Plant refueling has just been completed. Shutdown Cooling is in service with a PCS temperature of 186°F. GCL-2, Mode 5 to Mode 3 525°F Checklist is in progress. Two PCPs are in service. Technical Specification Surveillanc e Procedure PO-2, PCS Heatup/Cooldown Operations, has just been authorized by the CRS. No equipment is out of serv ice, all systems are OPERABLE.

INITIATING CUES:

The CRS directs you to setup for monitoring a PCS heatup via the PPC, utilizing Page 361 "PCS 15 Minute Rate Tr end" per PO-2, step 5.1.1.

PALISADES NUCLEAR PLANT Page 3 of 7 May 2009 JPM SRO ADMIN 1b Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Locate PO-2, PCS Heatup/Cooldown Operations, step 5.1.1 Step 5.1.1 of PO-2 LOCATED S U Comment:

EVALUATOR: Provide Operator a working copy of PO-2, step 5.1.1.

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.1b SELECT the "Operator Mode Support" screen from the main menu Main menu screen SELECTED. "Operator Mode Support" screen SELECTED from main menu screen

. S U Comment:

EVALUATOR NOTE: Operator may go straight to PPC page 361 (task element 3).

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.1c SELECT any of the following, as applicable, to monitor PCS heatup/cooldown rate: Page 361 "PCS 15 Minute Rate Trend" Page 361 "PCS 15 Minute Trend" page SELECTED S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.1d START 15 minute automatic reports as follows: DEPRESS F7 key "HCR Reports" F7 key "HCR Reports" DEPRESSED S U Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 May 2009 JPM SRO ADMIN 1b PALISADES NUCLEAR PLANT Page 5 of 7 May 2009 Proc. Step TASK ELEMENT 5 STANDARD Grade 5.1.1d START 15 minute automatic reports as follows: SELECT the "Cyclic Printout Enabled" response "Cyclic Printout Enabled" SELECTED S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 6 STANDARD Grade 5.1.1d START 15 minute automatic reports as follows: TYPE a one (1)

AND DEPRESS the "UPDATE" Hardkey to start the reports.

One (1) or Y is TYPED AND "Update" Hardkey is DEPRESSED.

S U Comment:

NOTE: The Heatup/Cooldown print out is on a 15 minute timer that is always running.

When the printout is enabled, the next pr int timeout could be anywhere from 1 second to 15 minutes later. Evaluator: If Operator checks that the printout is printing and it is not, STATE that the hardcopy printout is not required and to continue.

CRITICAL STEP

Proc. Step TASK ELEMENT 7 STANDARD Grade 5.1.1d Notify the CRS that heatup/cooldown monitoring of the SDC by PPC, Page 361 is

in progress CRS notified that heatup/cooldown monitoring by

PPC in progress S U Comment:

EVALUATOR: If notified as CRS that PPC monitoring is in progress, Acknowledge.

END OF TASK

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

PALISADES NUCLEAR PLANT Page 6 of 7 May 2009 JPM SRO ADMIN 1b CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A Plant refueling has just been completed. Shutdown Cooling is in service with a PCS temperature of 186°F. GCL-2, Mode 5 to Mode 3 525°F Checklist is in progress. Two PCPs are in service. Technical Specification Surveillanc e Procedure PO-2, PCS Heatup/Cooldown Operations, has just been authorized by the CRS. No equipment is out of serv ice, all systems are OPERABLE.

INITIATING CUES:

The CRS directs you to setup for monitoring a PCS heatup via the PPC, utilizing Page 361

"PCS 15 Minute Rate Trend" per PO-2, step 5.1.1.

PALISADES NUCLEAR PLANT Page 7 of 7 May 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: RO ADMIN 2 TITLE: PERFORM SHO-1 SURVEILLANCE

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Complete the SHO-1 Surveillance

Alternate Path: N/A

Facility JPM #: RO-A.2 2008 AUDIT

K/A: 2.2.12 Importance: RO: 3.7 SRO: 4.1

K/A Statement: Knowledge of surveillance procedures

Task Standard: Identification of two out-of-spec readings during the performance of SHO-1 for Wide Range Nuclear Inst ruments and 'B' Steam Generator Pressure Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SHO-1, "Operator's Shift Items Modes 1, 2, 3, and 4"

Validation Time: 20 minutes Time Critical: NO

Candidate: __________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 11 May 2009 JPM RO ADMIN 2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SHO-1, Attachment 1, Shift Surveillance Data Sheet Red ink pen Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant is at 100% power. It is Monday, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.1 through and

including 5.1.14 on pages 1,2,3,4, and 5 for

'A' Shift. ALL remaining readings have already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 3 of 11 May 2009 JPM RO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Partially completed copy of SHO-1 located LOCATES copy of partially completed SHO-1 S U Comment:

Evaluator: Provides Operator with a pa rtially completed copy of SHO-1.

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.1 Power Range Nuclear Instrumentation:

Record data and check all channels agree within 1% CHECKS all channels agree within 1% RECORDS readings in "Shift A Readings" column INITIALS "RECRD BY" S U Comment:

NOTE: Surveillance steps may be performed in any order.

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.2 Thermal Margin Monitor T Power: Record data and check all channels agree within 1% CHECKS all channels agree within 1% RECORDS readings in "Shift A Readings" column INITIALS "RECRD BY" S U Comment:

PALISADES NUCLEAR PLANT Page 4 of 11 May 2009 JPM RO ADMIN 2 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.3 Thermal Margin Monitor Functions, NI/T Power Deviation Meter (C-27): Check NI/T Comparator varying as expected for changes between NI/T Power Check TMM Primary Screens updating CHECKS NI/T and TMM Primary Screens updating RECORDS a in "Shift A Readings" column INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 5 STANDARD Grade 5.1.4 Axial Shape Index:

Check TMM "System Status" Screen Power Density status "OK" CHECKS TMM "System Status" Screen Power Density status "OK" RECORDS a in "Shift A Readings" column INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade 5.1.5 PCS Cold Leg Temperature:

Check TMM "System Status" Screen T C <543.5°F Check TMM "System Status" Screen Trip Status Box indicates T C: "OK" CHECKS TMM "System Status" Screen T C < 543.5°F Check TMM "System Status" Screen Trip Status Box indicates T C: "OK" RECORDS a in "Shift A Readings" column INITIALS RECRD BY S U Comment:

PALISADES NUCLEAR PLANT Page 5 of 11 May 2009 JPM RO ADMIN 2 Proc. Step TASK ELEMENT 7 STANDARD Grade 5.1.6 Wide Range Nuclear Instrumentation (NIs): Record data and check NIs agree within 11/2 decades CHECKS data within 11/2 decades RECORDS data in "Shift A Readings" column S U Comment:

NOTE: Data for NI 1/3 is NOT within 11/2 decades

Proc. Step TASK ELEMENT 8 STANDARD Grade 5.1.6 Wide Range Nuclear Instrumentation (NIs): Determine out of tolerance data for NI 1/3 Identifies out of tolerance reading DETERMINES NI 1/3 not within 11/2 decades CIRCLES in RED NI-1/3A reading INITIALS RECRD BY

  • May NOTIFY CRS of the out of spec reading S U Comment:

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

  • NOTE: 'INITIALS RECRD BY" is not part of the critical step CRITICAL STEP

Proc. Step TASK ELEMENT 9 STANDARD Grade 5.1.7 Quadrant Power Tilt:

Check NI Channels 5, 6, 7 and 8 Deviation lights not lit No alarms (EK-06C3) CHECKS no Deviation lights lit for NI 5, 6, 7 and 8 VERIFIES no alarms (EK-06C3) RECORDS a in "Shift A Readings" column INITIALS RECRD BY S U Comment:

PALISADES NUCLEAR PLANT Page 6 of 11 May 2009 JPM RO ADMIN 2 Proc. Step TASK ELEMENT 10 STANDARD Grade 5.1.8 Steam Generator Pressure:

Record data and check all channels for each S/G agree within 40 psi RECORDS S/G pressures in "Shift A Readings" column CHECKS S/G pressures within 40 psi S U Comment:

NOTE: Data for PIC-0752C indication for "B" S/G is > 40 psi out of agreement.

Proc. Step TASK ELEMENT 11 STANDARD Grade 5.1.8 Steam Generator Pressure:

Record data and check all channels for each S/G agree within 40 psi DETERMINES PIC-0752C indication for "B" S/G is >40 psi out of agreement with the other

three for "B" S/G CIRCLES in RED at least PIC-0752C reading (may circle all four) *INITIALS RECRD BY May NOTIFY CRS of the out of spec reading S U Comment:

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

  • NOTE: 'INITIALS RECRD BY" is not part of the critical step CRITICAL STEP

Proc. Step TASK ELEMENT 12 STANDARD Grade 5.1.9 Steam Generator Level:

Record data and check all channels for each S/G agree within 4% RECORDS S/G levels in "Shift A Readings" column CHECKS S/G levels within 4% INITIALS RECRD BY S U Comment:

PALISADES NUCLEAR PLANT Page 7 of 11 May 2009 JPM RO ADMIN 2 Proc. Step TASK ELEMENT 13 STANDARD Grade 5.1.10 Primary Coolant Flow:

Record data and check all channels agree within 5% RECORDS PCS flow in "Shift A Readings" column CHECKS PCS flows within 5% INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 14 STANDARD Grade 5.1.11 PZR Code Safety Relief Valve Position Indication Temperature:

Record data and check temperatures are consistent with plant conditions RECORDS PZR Safety Relief temperatures readings ranging from approx. 100 to 120 F in "Shift A Readings" column INITIALS RECRD BY S U Comment: Note: These reading are ambient and consistent with plant conditions.

Proc. Step TASK ELEMENT 15 STANDARD Grade 5.1.12 PORV Position Indication Temperature:

Record data and check temperatures are consistent with plant conditions and other

PORV indications RECORDS 'N/A' in this block (does not apply for plant conditions)

S U Comment:

PALISADES NUCLEAR PLANT Page 8 of 11 May 2009 JPM RO ADMIN 2 PALISADES NUCLEAR PLANT Page 9 of 11 May 2009 Proc. Step TASK ELEMENT 16 STANDARD Grade 5.1.13 PZR Pressure:

Record data and check all agree within 40 psi and Mode 1 pressure 2010 psia and 2100 psia RECORDS PZR pressures in "Shift A Readings" column CHECKS pressures within 40 psia Checks PZR pressure between 2010 psia and 2100 psia INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 17 STANDARD Grade 5.1.14 Thermal Margin Low Pressure Trip Channels: Record data and: Check Channels A and C agree within 85 psi Check Channels B and D agree within 85 psi RECORDS TMM low pressures in "Shift A Readings" column CHECKS Channels A and C agree within 85 psi CHECKS Channels B and D agree within 85 psi INITIALS RECRD BY S U Comment:

Proc. Step TASK ELEMENT 18 STANDARD Grade n/a Return completed SHO-1 to CRS Inform CRS of out of spec readings (if not already done) Completed SHO-1 RETURNED to the CRS CRS INFORMED of the out of spec readings (if not already done)

S U Comment:

END OF TASK

JPM RO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS Reset to any full power IC. Insert the following or use CAE file o OVERRIDE NI-1/3A Wide Range Log Mete r indication to failed low (NI PWR-1 @ 0.75) o OVERRIDE PIC-0752C to indicate ~860# (Value = 0.71) o OVRD NI-4-PWR-1 @ 1.0. Ensure "A" Channel TMM VHPT setpoint is at normal value. Ensure NI @ 100.1%, i.e., accurate.

Ensure copies of SHO-1, Attachment 1, page 1, 2, 3, 4, and 5 are available with Section 5.1.14 grayed out. Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision.

PALISADES NUCLEAR PLANT Page 10 of 11 May 2009 JPM RO ADMIN 2 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100% power It is Monday, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

INITIATING CUES:

You have been directed to take the readings of SHO-1, Items 5.1.1 through and

including 5.1.14 on pages 1,2,3,4, and 5 for 'A' Shift. ALL remaining readings have

already been taken by another NCO.

PALISADES NUCLEAR PLANT Page 11 of 11 May 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: SRO ADMIN 2 TITLE: REVIEW SHO-1 SURVEILLANCE

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 2 JOB PERFORMANCE MEASURE DATA PAGE Task: Conduct Surveillance Testing

Alternate Path: N/A

Facility JPM #: NEW

K/A: 2.2.12 Importance: RO: 3.7 SRO: 4.1

K/A Statement: Knowledge of surveillance procedures

Task Standard: Identification of two out-of-spec readings during the performance of SHO-1 for Wide Range Nuclear In strumentation and 'B' Steam Generator Pressure AND the identification of t he appropriate Technical Specification LCO action statement entries due to the out-of-spec

readings.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SHO-1, "Operator's Shift Items Modes 1, 2, 3, and 4"

Validation Time: 15 minutes Time Critical: NO

Candidate: _________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 MAY 2009 JPM SRO ADMIN 2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

Completed SHO-1, Attachment 1, Sh ift Surveillance Data Sheet for Monday Technical Specifications Technical Specifications Bases Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant is at 100% power. It is Monday, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.

You are an on-shift SRO.

SHO-1, Shift Surveillance Data Sheet, was completed at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.

The plant is in Mode 1.

INITIATING CUES:

The Shift Manager directs you to comple te a supervisory review of completed SHO-1 in accordance with step 5.3 of SHO-1.

Evaluator Note: Provide candidate with co mpleted SHO-1 for Monday with one data point for S/G Pressure and one for NI-1/3A are below the acceptance range. Do NOT circle the readings in red. Bad data should be for 'C' shift only.

PALISADES NUCLEAR PLANT Page 3 of 7 MAY 2009 JPM SRO ADMIN 2 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Partially completed copy of SHO-1 located LOCATES copy of partially completed SHO-1 S U Comment: Evaluator: Provides Operator with a copy of SHO-1 completed for Monday (all three shifts).

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.3.1 REVIEW SHO-1 Monday entries to ensure all applicable components have been

inspected.

At the end of each day, an On Shift SRO shall

review the data sheets applicable to that day for

completion of applicable items and ensure

proper disposition of off-normal items. This is

documented by sign-off on Attachment 1, "Shift

Surveillance Data Sheet." S U Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.6 Wide Range Nuclear Instrumentation (NIs): Determine out of tolerance data for NI 1/3 Identifies out of tolerance entry for A-shift DETERMINES NI 1/3 not within 11/2 decades CIRCLES in RED NI-1/3A entry for C-shift May NOTIFY CRS of the out of spec reading S U Comment:

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

CRITICAL STEP

PALISADES NUCLEAR PLANT Page 4 of 7 MAY 2009 JPM SRO ADMIN 2 PALISADES NUCLEAR PLANT Page 5 of 7 MAY 2009 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.8 Steam Generator Pressure:

Reviews data and checks all channels for each S/G agree within 40 psi DETERMINES PIC-0752C indication for "B" S/G is >40 psi out of agreement with the other

three for "B" S/G for C-shift. CIRCLES in RED PIC-0752C reading (may circle others as well) May NOTIFY CRS of the out of spec reading S U Comment:

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

CRITICAL STEP

Proc. Step TASK ELEMENT 5 STANDARD Grade 5.3 At the end of each day, an On Shift SRO shall review the data sheets applicable to that day for completion of applicable

items and ensure proper disposition of

off-normal items. This is documented by

sign-off on Attachment 1, "Shift

Surveillance Data Sheet." Attachment 1 "5.3 Reviewed:" space signed. The following TS Conditions are identified for the inoperable NI instrumentation: LCO 3.3.7.A LCO 3.3.1.B The following TS Conditions are identified for the inoperable S/G pressure instrument: LCO 3.3.7.A LCO 3.3.1.A LCO 3.3.9.A MAY be identified for the inoperable NI instrumentation for LCO Annex

entry (since it applies in MODES 3, 4 and 5):

S U Comment:

Evaluator Cue: If asked as the CRS to disposition the out of spec readings:

Acknowledge and inform candidate th at they need to determine proper disposition of the off-normal items.

CRITICAL STEP END OF TASK

JPM SRO ADMIN 2 SIMULATOR OPERATOR INSTRUCTIONS IF Simulator is used for conducting this JPM, then perform the following: Reset to any full power IC. Insert the following or use CAE file o OVERRIDE NI-1/3A Wide Range Log Meter indication to failed low (NI-3 PWR-1 @ 0.75) o OVERRIDE PIC-0752C to indicate ~860# (Value = 0.71) o OVRD NI-4-PWR-1 @ 1.0. Ensure "A" Channel TMM VHPT setpoint is at normal value. Ensure NI @ 100.1%, i.e., accurate.

Ensure copies of SHO-1, Attachment 1, page 1, 2, 3, 4, and 5 are available with Section 5.1.14 grayed out. Ensure Simulator clipboard copy of SHO-1, Attachment 1 is the current revision.

PALISADES NUCLEAR PLANT Page 6 of 7 MAY 2009 JPM SRO ADMIN 2 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100% power. It is Monday, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.

You are an on-shift SRO.

SHO-1, Shift Surveillance Data Sheet, was completed at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.

The plant is in Mode 1.

INITIATING CUES:

The Shift Manager directs you to complete a supervisory review of completed SHO-1 in accordance with step 5.3 of SHO-1.

PALISADES NUCLEAR PLANT Page 7 of 7 MAY 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: SRO ADMIN 3 TITLE: CALCULATE MAXIMUM PERMISSIBLE STAY TIME

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 3 JOB PERFORMANCE MEASURE DATA PAGE Task: Determine maximum permissible stay time

Alternate Path: N/A

Facility JPM #: NEW

K/A: 2.3.4 Importance: RO: 3.2 SRO: 3.7

K/A Statement: Knowledge of radiation ex posure limits under normal or emergency conditions.

Task Standard: Maximum time to perform Task #3 is calculated to be 51.4 to 51.9 minutes.

Preferred Evaluation Location: ANY __X__

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EI-2.1, "Site Emergency Director" EN-RP-201, "Dosimetry Administration"

Validation Time: 20 minutes Time Critical: NO

Candidate: _____________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 7 MAY 2009 JPM SRO ADMIN 3 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-2.1, "Site Emergency Director"

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant was at 100% power when a Steam Generator Tube Rupture occurred. A General Emergency was declared due to the pl ant conditions (fuel failure is also evident). Worker #1 has received 1.85 R TEDE this year prior to this event. Worker #1

has performed the following task for this event:

  1. TASK TIME REQUIRED DOSE RATE 1 Closed 'A' S/G ASDV air supply isolation valves 4 min 17.75 R/hr The Shift Manager then determined that t he 'B' S/G should have been isolated instead of 'A' S/G. The following outside the Control Room tasks are now required:
  1. TASK TIME REQUIRED DOSE RATE 2 Open 'A' S/G ASDV air supply isolation valves 3 min 17.75 R/hr 3 Manually open MO-0510, 'A' S/G MSIV Bypass Valve unknown 25.5 R/hr 4 Close 'B' S/G ASDV air supply isolation valves 3 min 17.75 R/hr NOTE: Assume no dose is received while traveling between tasks.

INITIATING CUES:

Worker #1 is the only worker available to perform Tasks 2, 3 and 4. Your task is to

determine the maximum time for Worker

  1. 1 to perform Task #3 without exceeding any established emergency dose limits. Report your results to the Shift Manager.

PALISADES NUCLEAR PLANT Page 3 of 7 MAY 2009 JPM SRO ADMIN 3 Proc.Step TASK ELEMENT 1 STANDARD Grade--- Determine dose received while performing Task #1. Calculates dose received at 1.18 R.

S U Comment:

(17.75 R/hr) (1hr/60 min) (4 min) = 1.183 R CRITICAL STEP

Proc.Step TASK ELEMENT 2 STANDARD Grade--- Determine dose to be received while performing Task #2.

Calculates dose received at 0.878 R.

S U Comment:

(17.75 R/hr) (1hr/60 min) (3 min) = 0.8875 R CRITICAL STEP

Proc.Step TASK ELEMENT 3 STANDARD Grade--- Determine dose to be received while performing Task #4.

Calculates dose received at 0.878 R.

S U Comment:

(17.75 R/hr) (1hr/60 min) (3 min) = 0.8875 R CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 7 MAY 2009 JPM SRO ADMIN 3 PALISADES NUCLEAR PLANT Page 5 of 7 MAY 2009 Proc.Step TASK ELEMENT 4 STANDARD Grade--- Determine dose remaining from emergency dose limits.

Dose remaining determined to be 22.064 R.

Candidate may use EI-2.1, "Site Emergency

Director" to determine 25R emergency dose

limit. S U Comment:

(25R) - (1.183R) - (2)

(0.8875R) = 22.042 R EVALUATOR: If candidate asks which emergency dose limit is being considered for Task #3, inform them that this would be "for protection of large populations." Also if asked, inform candidate that they do not desire to volunteer dose limit above 25R.

CRITICAL STEP

Proc.Step TASK ELEMENT 5 STANDARD Grade--- Determine time available for Worker #1 to complete Task #3 without exceeding

emergency dose level.

Time available calculated to be 51.9 min.

S U Comment: (Available Dose)/(Dose Rate) = (22.042 R)/(25.5 R/hr) = 0.8644 hr (60 min/Hr) = 51.86 minutes (accept 51.9 to 51.4 minutes)

CRITICAL STEP

Proc. Step TASK ELEMENT 6 STANDARD Grade n/a Inform the Shift Manager of calculation results. Inform the Shift Manager that Worker #1 will

exceed 25 R emergency dose limit if Task #3

takes more than 51.9 minutes.

S U Comment:

END OF TASK

JPM SRO ADMIN 3 SIMULATOR OPERATOR INSTRUCTIONS No Simulator setup required.

PALISADES NUCLEAR PLANT Page 6 of 7 MAY 2009 JPM SRO ADMIN 3 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant was at 100% power when a Steam Generator Tube Rupture occurs. A General Emergency was declared due to the pl ant conditions (fuel failure is also evident). Worker #1 has received 1.85 R TEDE this year. The following task has been

performed by Worker #1:

  1. TASK TIME REQUIRED DOSE RATE 1 Closed 'A' S/G ASDV air supply isolation valves 4 min 17.75 R/hr The Shift Manager has determined that the wrong S/G has been isolated. The following outside the Control Room tasks are now required:
  1. TASK TIME REQUIRED DOSE RATE 2 Open 'A' S/G ASDV air supply isolation valves 3 min 17.75 R/hr 3 Manually open MO-0510, 'A' S/G MSIV Bypass Valve unknown 25.5 R/hr 4 Close 'B' S/G ASDV air supply isolation valves 3 min 17.75 R/hr NOTE: Assume no dose is received while traveling between tasks.

INITIATING CUES:

Worker #1 is the only worker available to perform Tasks 2, 3 and 4. Your task is to

determine the maximum time for Worker

  1. 1 to perform Task #3 without exceeding any established emergency dose limits. Repor t your results to the Shift Manager.

PALISADES NUCLEAR PLANT Page 7 of 7 MAY 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: RO ADMIN 4 TITLE: OBTAIN METEOROLOGICAL DATA FOR EMERGENCY NOTIFICATION FORM

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM RO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Obtain Meteorological Data for Emergency Notification Form

Alternate Path: N/A

Facility JPM #: RO-A.4 2008 NRC

K/A: 2.4.39 Importance: RO: 3.9

K/A Statement: Knowledge of RO responsib ilities in emergency plan implementation

Task Standard: EI-6.7, Attachment 1, completed with correct data obtained

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

EI-3.0, "Communications and Notifications" EI-6.0, "Offsite Dose Calculation and Recommendations for Protective

Actions" EI-6.7, "Plant Site Meteorological System"

Validation Time: 10 minutes Time Critical: NO

Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 8 May 2009 JPM RO ADMIN 4 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-6.7, Attachment 1 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE

DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Shift Manager, acting as the Site Emergency Director, has declared an Alert

condition. A thunderstorm is in progress.

INITIATING CUES:

The Shift Manager has directed you to obtain Meteorological Data by completing of EI-6.7, utilizing the Meteor ological Data display in the Control Room.

PALISADES NUCLEAR PLANT Page 3 of 8 May 2009 JPM RO ADMIN 4 Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Correct Procedure located EI-6.7, Attachment 1 located S U Comment:

Evaluator: Provide candidate with a Working Copy.

EVALUATOR NOTE: EI-6.7 Attachment 1 is completed by referencing steps 5.1.3 and 5.1.4. Due to wind speed and wind direction at 10 meters unavailable, 60 meter data is used.

Proc. Step TASK ELEMENT 2 STANDARD Grade 5.1.3 Obtain meteorological data from the PPC, page 351 WS, Wind Speed (WS60)

_9_MPH On EI-6.7 Att. 1 data recorded as follows:

WS, Wind Speed =

6.93 mph 9 mph X .77 = 6.93 MPH

( X ) 60 meters, *corrected S U Comment:

NOTE: WS60 must be used. WS60 multiplied by 0.77 to obtain corrected wind speed.

CRITICAL STEP

Proc. Step TASK ELEMENT 3 STANDARD Grade 5.1.3 Obtain meteorological data from the PPC, page 351 WD, Wind Direction (WD60)

____° On EI-6.7 Att. 1 data recorded as follows:

WD, Wind Direction =

73° from ( X ) 60 meters S U Comment:

NOTE: WD60 must be used.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 May 2009 JPM RO ADMIN 4 PALISADES NUCLEAR PLANT Page 5 of 8 May 2009 Proc. Step TASK ELEMENT 4 STANDARD Grade 5.1.4 Obtain meteorological data from the PPC, page 351 Stability Class (STAB)

____ On EI-6.7 Att. 1 data recorded as follows: Stability Class =

C S U Comment:

CRITICAL STEP

Proc. Step TASK ELEMENT 5 STANDARD Grade n/a EI-6.7, Attachment 1 completed: Date:, Time:, Completed By:

On EI-6.7 Att. 1 data recorded as follows:

Date: Today's date Time: Current time Completed By:

Operator's name S U Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade n/a Notify the CRS that EI-6.7 Attachment 1 completed.

Operator notifies CRS of completion of EI-6.7, Attachment 1.

S U Comment:

END OF TASK

JPM RO ADMIN 4 SIMULATOR OPERATOR INSTRUCTIONS

1. Reset to IC 17
2. Remove the following two PPC points from service by using MFs PC20 and PC 21 on PID PC02. These MFs will cause a "V" or invalid display from the Met Tower

10 meter height. Candidate will have to use the 60 meter readings and use a conversion factor of 0.77 to obtain appropriate data. (ENSURE these MFs are changed back after JPM is completed)

MWD10 MWS10

3. Provide a Working Copy of EI-6.7, Att. 1 to evaluator.
4. Use Remote Functions (RF) on PID PC02 to modify the following (after all RFs are changed, then use UPDATE NOW and respond 'YES"): WS60 = 9 (change RF to this value) WD60 = 73 degrees FROM (change RF to this value)

Stability = C (no change needed since RF should already say "3")

5. Candidate may use PPC monitor in Simula tor Computer Room for this JPM: ensure it is up and running.

PALISADES NUCLEAR PLANT Page 6 of 8 May 2009 Proc No EI-6.7 Attachment 1 Revision 7 Page 1 of 1 PLANT SITE METEOROLOGICAL SYSTEM WORKSHEET ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY

1. WS, Wind Speed =

6.93 mph ( ) 10 meters (X) 60 meters, *corrected (See Step 5.1.3 or 5.2.6) *Multiply by 0.77 ( 9 MPH X 0.77 = 6.93 MPH)

2. WD, Wind Direction =

73 ° from ( ) 10 meters (X) 60 meters (See Step 5.1.3 or 5.2.6)

(see Step 5.1.4 or 5.2.7)

3. Stability Class

= C

Date: __TODAY_____ Time: __

NOW___ Completed By: __

JOE OPERATOR

_______

ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 8 May 2009 JPM RO ADMIN 4 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The Shift Manager, acting as the Site Emergency Director, has declared an Alert condition. A thunderstorm is in progress.

INITIATING CUES:

The Shift Manager has directed you to obtain Met eorological Data by completing Attachment 1 of EI-6.7, utilizing Meteorological Da ta display in the Control Room.

PALISADES NUCLEAR PLANT Page 8 of 8 May 2009 NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE

JPM: SRO ADMIN 4 TITLE: CLASSIFY EVENT AND DETERMINE PAR

CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM SRO ADMIN 4 JOB PERFORMANCE MEASURE DATA PAGE Task: Classify an Event and Determine PARs - Protective Action Recommendations

Alternate Path: N/A

Facility JPM #: SRO-A.4 2003 NRC

K/A: 2.4.41, 2.4.44 Importance: RO: 4.1, 4.0 SRO: 4.1, 4.4

K/A Statement: (2.4.41) Knowledge of t he emergency action level threshholds and classifications. (2.4.44) Knowledge of emergency plan protective action recommendations.

Task Standard: Event classified as a Gener al Emergency and PAR is evacuation of 2 mile radius and 5 miles in Areas 1 and 2, within 30 minutes.

Preferred Evaluation Location: Simulator __X__ In Plant ______

Preferred Evaluation Method: Perform __X__ Simulate ______

References:

EI-1, Emergency Classifications and Actions EI-3, Communications and Notifications EI-6.13, Protective Action Recommendations for Offsite Populations

Validation Time: __30__ minutes Time Critical: YES

Candidate: __________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes

Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 May 2009 JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 3 of 9 May 2009 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EI-1 Attachment 1 EI-3 EI-6.13 Attachment 1 READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have

completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. The Reactor has tripped.
2. A LOCA is in progress.
3. Pressurizer level is offscale LOW.
4. PCS pressure is 100 psia.
5. CETs indicate 600ºF.
6. Total LPSI/HPSI flow is NOT adequate per EOP Supplement 4. 7. SIRW tank level is 38% and lowering slowly.
8. Containment isolation has occurr ed as designed and EOP Supplement 6 for Containment Isolation is in progress. 9. A release is NOT occurring through the plant stack or steam dumps. 10. Containment Gamma Monitors (RIA

-2321 and 2322) are indicating 5E4R/hr. 11. Reactor Vessel Level Monitoring Syst em (RVLMS) indicates ALL red lights 12. Failed fuel analysis is in progress with no results to report yet.

13. Obtained Meteorological Data is as follows:

QN = 0.0 QI = 0.0 Wind Speed = 1.1 Stability Class = G Wind Direction = 235 (from)

Weather is clear with no precipitation

INITIATING CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Site Emergency Director). You are to classify the event given the above information

and determine any required Protective Action Recommendations, and complete an

Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

JPM SRO ADMIN 4 Proc.Step TASK ELEMENT 1 STANDARD Grade EI-1 Locates procedure to determine Emergency Classification.

Locates EI-1 and refers to Attachment 1, "Hot

Conditions (PCS > 200 degrees F)".

S U Comment: EVALUATOR: Candidate may use placard of site emergency plan classifications or use paper copy from EI-1, attachment 1.

Proc.Step TASK ELEMENT 2 STANDARD Grade EI-1 Att 1 Refers to "Fission Product Barriers" section (lower right-hand corner)

Refers to lower right-hand corner of EI-1, , "Hot Conditions (PCS > 200 degrees F)".

S U Comment:

Proc.Step TASK ELEMENT 3 STANDARD Grade EI-1 Att 1 Determines status of fission product barriers.

___ Refers to Table F1 ___ Determines a LOSS of Fuel Cladding (based on Containment Gamma monitors

readings (item 5) ___ Determines a LOSS of PCS Barrier (based on leak rate and PCS subcooling)(item 2)

OR based on Containment Gamma

Monitor readings. ___ Determines a POTENTIAL LOSS of Containment Barrier (based on

Containment Gamma monitors

readings).(item 6)

S U Comment: EVALUATOR: If candidate refers to EI-11, inform them "That procedure will be performed by the TSC."

Proc.Step TASK ELEMENT 4 STANDARD GradePALISADES NUCLEAR PLANT Page 4 of 9 May 2009 JPM SRO ADMIN 4 EI-1 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).

S U Comment:

CRITICAL STEP

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

attached KEY.

S U Comment: NOTE: This Task Element may be performed at any time during the JPM. Filling out this form is NOT required for this JPM; however a key is attached in case candidate fills out the form.

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

Proc.Step TASK ELEMENT 6 STANDARD Grade EI-3 Att 1 Prepares Event Notification Form.

Obtains EI-3, Attachment 1 and fills out per attached KEY.

S U Comment:

NOTE: KEY is attached to this JPM. NOTE: EI-3, Attachment 2, "Palisades Event Technical Data Sheet" is NOT required during this JPM. NOTE: Candidate may use computer on Cont rol Room island area to prepare this form.

PALISADES NUCLEAR PLANT Page 5 of 9 May 2009 JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 6 of 9 May 2009 Proc.Step TASK ELEMENT 7 STANDARD Grade EI-6.13 Att 1 Determines Protective Action Recommendations (PARs).

Obtains EI-6.13 and corresponding Attachment

1 and determines: ___ Evacuate 5 mile in Areas 1 and 2 (minimum GE recommendation on bottom of Pg 1 of Attachment 1)

S U Comment:

CRITICAL STEP

Proc.Step TASK ELEMENT 8 STANDARD Grade EI-3 Att 1 Completes filling out Palisades Event Notification Form.

Palisades Event Notification Form completely

filled per attached KEY AND form is approved (Candidate initials, date, and time entered at

bottom of form)

S U Comment: NOTE: Candidate may use computer on back-bar of Control Room island area to complete and print this form.

CRITICAL STEP END OF TASK

JPM SRO ADMIN 4 ANSWER KEY PALISADES NUCLEAR PLANT Page 7 of 9 May 2009 JPM SRO ADMIN 4 PALISADES NUCLEAR PLANT Page 8 of 9 May 2009 SIMULATOR OPERATOR INSTRUCTIONS No Simulator setup required.

It is preferred that this JPM be done separat ely from the simulator. If, by chance, candidate IS in the simulator while doing th is 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.

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

INITIAL CONDITIONS:

1. The Reactor has tripped.
2. A LOCA is in progress.
3. Pressurizer level is offscale LOW.
4. PCS pressure is 100 psia.
5. CETs indicate 600ºF.
6. Total LPSI/HPSI flow is NOT adequate per EOP Supplement 4. 7. SIRW tank level is 38% and lowering slowly.
8. Containment isolation has occurr ed as designed and EOP Supplement 6 for Containment Isolation is in progress. 9. A release is NOT occurring through the plant stack or steam dumps. 10. Containment Gamma Monitors (RIA

-2321 and 2322) are indicating 5E4R/hr. 11. Reactor Vessel Level Monitoring Syst em (RVLMS) indicates ALL red lights. 12. Failed fuel analysis is in progress with no results to report yet.

13. Obtained Meteorological Data is as follows:

QN = 0.0 QI = 0.0 Wind Speed = 1.1 Stability Class = G Wind Direction = 235 (from)

Weather is clear with no precipitation

INITIATING CUES:

During activation of the Site Emergency Plan, you are the Shift Manager (acting as the Site Emergency Director). You are to classify the event given the above information

and determine any required Protective Action Recommendations, and complete an

Event Notification Form. No previous event declaration has been made.

This JPM is Time Critical.

PALISADES NUCLEAR PLANT Page 9 of 9 May 2009