ML12297A122

6 North Anna 2012-301 Draft Administrative JPMs

ML12297A122
Person / Time
Site:	North Anna
Issue date:	10/23/2012
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-338/12-301, 50-339/12-301
Download: ML12297A122 (47)

Text

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS

• Current Critical Conditions are as follows:

Unit 1 is at 100% power.

Control Banks C and D are at the All Rods Out (ARO) position.

RCS boron concentration is 1350 ppm from a sample taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.

No dilutions have taken place since RCS boron concentration was determined.

Core age is 4950 MWD/MTU.

• Single Bank of Control Rods inserted out of sequence 18 steps from fully withdrawn position.

• No control rods are stuck or untrippable.

INITIATING CUE The Shift Manager has directed you to determine the Shutdown Margin with Control Rods of a single bank inserted out of sequence 18 steps from the Fully Withdrawn Position in accordance with 1-PT-10.1, Attachment 1.

(Record your calculated Shutdown Margin results in the space provided)

Calculated Shutdown Margin: ___________________ pcm NAPS 2012 NRC EXAM Page: 1 of 8 ADMIN JPM (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine Shutdown Margin (SDM).

TASK STANDARDS Given a copy of 1-PT-10.1, determine the Shutdown Margin with Control Rods of a single bank inserted out of sequence 18 steps from the Fully Withdrawn Position.

K/A

REFERENCE:

001-A4.11, Determination of SDM (3.5/4.1) 005-AK1.05, Calculation of minimum Shutdown Margin (3.3/4.1)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 15 minutes Start Time = ________

Actual Time = ________ minutes Stop Time = ________

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM Page: 2 of 8 ADMIN JPM (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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

• Current Critical Conditions are as follows:

Unit 1 is at 100% power.

Control Banks C and D are at the All Rods Out (ARO) position.

RCS boron concentration is 1350 ppm from a sample taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.

No dilutions have taken place since RCS boron concentration was determined.

Core age is 4950 MWD/MTU.

• Single Bank of Control Rods inserted out of sequence 18 steps from fully withdrawn position.

• No control rods are stuck or untrippable.

INITIATING CUE The Shift Manager has directed you to determine Shutdown Margin with Control Rods of a single bank inserted out of sequence 18 steps from the Fully Withdrawn Position in accordance with 1-PT-10.1, Attachment 1.

NAPS 2012 NRC EXAM Page: 3 of 8 ADMIN JPM (M)

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT Calculator Copy of 1-PT-10.1 Plant Curve Book PERFORMANCE STEPS START TIME __________

1 Operator enters the Current Critical Conditions on 1-PT-10.1 Procedure Step Attachment 1. Att. 1, Items 1 - 7 SAT [ ] UNSAT [ ]

Standards Operator completes Current Critical Conditions on Attachment 1 in accordance with the information provided by the JPM Initial Conditions.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 4 of 8 ADMIN JPM (M)

2 Operator enters the Boron Worth Coefficient on Attachment 1. Procedure Step:

Att. 1, Item 8 SAT [ ] UNSAT [ ]

Standards Operator determines a value of -6.49 from 1-SC-3.4.

Acceptance criteria: -6.46 to -6.52 (based on readability).

Notes/Comments:

3 Operator enters the number and worth of untrippable or dropped Procedure Step:

rods on Attachment 1. Att. 1, Items 9 & 10 SAT [ ] UNSAT [ ]

Standards Operator N/As Items 9 & 10 based on the procedure NOTE preceding Item 9.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 5 of 8 ADMIN JPM (M)

4 Operator enters Rod Worth on Attachment 1. Procedure Step:

Att. 1, Item 11 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines the following values from 1-SC-8.5 & 1-SC-3.5:

Instantaneous Shutdown Conditions Current Critical Conditions

-5820 0 acceptance criteria: -5810 to

-5835 (based on readability)

Notes/Comments: Cycle Burnup Information is provided by the Initial Conditions of the JPM.

5 Operator enters the Untrippable or Dropped Rod Worth on Procedure Step:

Attachment 1. Att. 1, Item 12 SAT [ ] UNSAT [ ]

Standards Operator enters 0 for Item 12 based on the procedure NOTE preceding Item 12.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 6 of 8 ADMIN JPM (M)

6 Operator enters the Worth of a Single Rod Bank inserted up to 18 Procedure Step:

steps from fully withdrawn position on Attachment 1. Att. 1, Item 13 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines a value of -331 from 1-SC-8.1.

Notes/Comments:

7 Operator enters the Reactivity Redistribution Factor on Procedure Step:

Attachment 1. Att. 1, Item 14 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines a value of 160 from 1-SC-8.4.

Acceptance criteria: 150 to 170 (based on readability).

Notes/Comments:

NAPS 2012 NRC EXAM Page: 7 of 8 ADMIN JPM (M)

8 Operator enters the Power Defect on Attachment 1. Procedure Step:

Att. 1, Item 15 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines a value of -1775 from 1-SC-3.8.

Acceptance criteria: -1725 to -1800 (based on readability).

Notes/Comments: Item 16 is provided on the Attachment 1.

9 Operator calculates the Totals (determination of SDM). Procedure Step:

Att. 1, Item 17 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines a value of:

-5560 - -2106 = -3454 Acceptance criteria: -3400 to -3500 (based on variations in Items due to readability of curves).

Notes/Comments: Item 18 is N/A since SDM is > -1770 pcm.

>>>>> END OF EVALUATION <<<<<

STOP TIME __________

NAPS 2012 NRC EXAM Page: 8 of 8 ADMIN JPM (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS SRO notified of the Reactor Coolant System leak rate hand calculation Periodic Test.

Unit is in mode 1 at 100% with the RCS in stable steady state operation during data collection.

Unit 1 PCS is not operable.

1-PT-52.2 Attachment 5, Other Identified Leakage, is 0 gpm.

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 0700 Accumulator Levels: A LI-1920 56.4% LI-1922 56.7%

B LI-1924 60.1% LI-1926 60.1%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 77.0%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Accumulator Levels: A LI-1920 56.2% LI-1922 56.6%

B LI-1924 60.1% LI-1926 60.0%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 78.0%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Pressurizer Level: RC-LI-1459A 52.5%

VCT Level CH-LI-1112-1 46.2%

PDTT Level DG-LI-101 17.5%

RCS TAVE RC-TI-412D 580.8 degrees Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 2300 Pressurizer Level: RC-LI-1459A 53.0%

VCT Level CH-LI-1112-1 38.1%

PDTT Level DG-LI-101 18.0%

RCS TAVE RC-TI-412D 580.7 degrees INITIATING CUE You are requested to perform a Reactor Coolant System leak rate hand calculation in accordance with 1-PT-52.2, and complete the following actions:

• Perform step 6.2 and complete Attachment 4, SI Accumulators and PRT Leakage.

• Perform step 6.12 and complete the Attachment 2, Leak Rate Data Sheet Without Using the Unit 1 PCS Computer.

NAPS 2012 NRC EXAM Page: 1 of 8 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Calculate the Reactor Coolant System leak rate manually (1-PT-52.2).

TASK STANDARDS Given a copy of 1-PT-52.2, Reactor Coolant System Leak Rate (Hand Calculation), calculate the Identified and Unidentified Leakage by completing procedure Attachments 2 & 4 without the Unit 1 PCS computer.

K/A

REFERENCE:

2.1.20 (41.10 / 43.5 / 45.12)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 20 minutes Start Time = ______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM Page: 2 of 8 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 SRO notified of the Reactor Coolant System leak rate hand calculation Periodic Test.

Unit is in mode 1 at 100% with the RCS in stable steady state operation during data collection.

Unit 1 PCS is not operable.

1-PT-52.2 Attachment 5 Other Identified Leakage is 0 gpm.

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 0700 Accumulator Levels: A LI-1920 56.4% LI-1922 56.7%

B LI-1924 60.1% LI-1926 60.1%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 77.0%

NAPS 2012 NRC EXAM Page: 3 of 8 ADMIN JPM - (M)

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Accumulator Levels: A LI-1920 56.2% LI-1922 56.6%

B LI-1924 60.1% LI-1926 60.0%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 78.0%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Pressurizer Level: RC-LI-1459A 52.5%

VCT Level CH-LI-1112-1 46.2%

PDTT Level DG-LI-101 17.5%

RCS TAVE RC-TI-412D 580.8 degrees Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 2300 Pressurizer Level: RC-LI-1459A 53.0%

VCT Level CH-LI-1112-1 38.1%

PDTT Level DG-LI-101 18.0%

RCS TAVE RC-TI-412D 580.7 degrees INITIATING CUE You are requested to perform a Reactor Coolant System leak rate hand calculation in accordance with 1-PT-52.2, and complete the following actions:

• Perform step 6.2 and complete Attachment 4, SI Accumulators and PRT Leakage.

• Perform step 6.12 and complete the Attachment 2, Leak Rate Data Sheet Without Using the Unit 1 PCS Computer.

EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))

Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))

TOOLS AND EQUIPMENT Copy of 1-PT-52.2 Plant Curve Book Calculator NAPS 2012 NRC EXAM Page: 4 of 8 ADMIN JPM - (M)

PERFORMANCE STEPS START TIME __________

1 Review Initial Conditions and Precautions and Limitations. Procedure Step 3.0/4.0 SAT [ ] UNSAT [ ]

Standards Precautions and limitations have been reviewed.

Notes/Comments: Operator may review these sections prior to performing the Attachments.

2 Per Attachment 4, calculate the SI Accumulator Leakage. Procedure Step Attachment 4 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of -.0018 gpm (+/- .0008 gpm)

Notes/Comments 3 Per Attachment 4, calculate the PRT Leakage. Procedure Step Attachment 4 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .1334 gpm (+/- .0005 gpm)

Notes/Comments NAPS 2012 NRC EXAM Page: 5 of 8 ADMIN JPM - (M)

4 Per Attachment 2, calculate the Pressurizer Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of 22.95 gallons (+/- .05 gallons)

Notes/Comments 5 Per Attachment 2, calculate the VCT Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of - 114.21 gallons (+/- .1 gallons)

Notes/Comments 6 Per Attachment 2, calculate the PDTT Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of 3.33 gallons (+/- .1 gallons)

Notes/Comments NAPS 2012 NRC EXAM Page: 6 of 8 ADMIN JPM - (M)

7 Per Attachment 2, calculate the PDTT Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of 3.33 gallons (+/- .1 gallons)

Notes/Comments 8 Per Attachment 2, calculate the RCS TAVE Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of - 7.87 gallons (+/- .05 gallons)

Notes/Comments 9 Per Attachment 2, calculate the Total Leak Rate. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .3473 gpm (+/- .001 gpm)

Notes/Comments NAPS 2012 NRC EXAM Page: 7 of 8 ADMIN JPM - (M)

10 Per Attachment 2, calculate the Identified Leakage. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .1456 gpm (+/- .0008 gpm)

Notes/Comments 11 Per Attachment 2, calculate the Unidentified Leakage. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .2018 gpm (+/- .005 gpm)

Notes/Comments 12 Obtain an Independent Review of the Calculations. Procedure Step 6.12.6 SAT [ ] UNSAT [ ]

Performance Que Assume another Operator will complete the PT.

Notes/Comments:

>>>>> END OF EVALUATION <<<<<

STOP TIME __________

NAPS 2012 NRC EXAM Page: 8 of 8 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM (SRO - ONLY)

INITIAL CONDITIONS Crew notified of the Reactor Coolant System leak rate hand calculation Periodic Test.

Unit is in mode 1 at 100% with the RCS in stable steady state operation during data collection.

Unit 1 PCS is not operable.

Leak rate results from the last 1-PT-46.21 performance:

Identified Leakage = .1115 gpm Unidentified Leakage = .0485 gpm 1-PT-52.2 Attachment 5, Other Identified Leakage is currently 0 gpm.

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 0700 Accumulator Levels: A LI-1920 56.4% LI-1922 56.7%

B LI-1924 60.1% LI-1926 60.1%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 77.0%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Accumulator Levels: A LI-1920 56.2% LI-1922 56.6%

B LI-1924 60.1% LI-1926 60.0%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 78.5%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Pressurizer Level: RC-LI-1459A 52.5%

VCT Level CH-LI-1112-1 46.2%

PDTT Level DG-LI-101 17.5%

RCS TAVE RC-TI-412D 580.8 degrees Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 2300 Pressurizer Level: RC-LI-1459A 53.0%

VCT Level CH-LI-1112-1 38.6%

PDTT Level DG-LI-101 18.0%

RCS TAVE RC-TI-412D 580.7 degrees INITIATING CUE You are requested to perform a Reactor Coolant System leak rate hand calculation in accordance with 1-PT-52.2, and complete the following actions:

• Perform step 6.2 and complete Attachment 4, SI Accumulators and PRT Leakage.

• Perform step 6.12 and complete the Attachment 2, Leak Rate Data Sheet Without Using The Unit 1 PCS Computer.

• Perform Section 7.0 and identify any Follow-On Tasks that must be completed.

Dominion NAPS 2012 NRC EXAM Page: 1 of 12 ADMIN JPM - SRO- (M)

North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM (SRO - ONLY)

TASK Calculate the Reactor Coolant System leak rate manually (1-PT-52.2).

TASK STANDARDS Given a copy of 1-PT-52.2, Reactor Coolant System Leak Rate (Hand Calculation), calculate the Identified and Unidentified Leakage by completing procedure Attachments 2 & 4 without the Unit 1 PCS computer, analyze results against the acceptance criteria, and identify applicable actions as directed by the Follow-On Tasks of the procedure.

K/A

REFERENCE:

2.1.20 (41.10 / 43.5 / 45.12)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = Start Time = ______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM Page: 2 of 12 ADMIN JPM - SRO- (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM (SRO - ONLY)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 SRO notified of the Reactor Coolant System leak rate hand calculation Periodic Test.

Unit is in mode 1 at 100% with the RCS in stable steady state operation during data collection.

Unit 1 PCS is not operable.

Leak rate results from the last 1-PT-46.21 performance:

Identified Leakage = .1115 gpm Unidentified Leakage = .0485 gpm 1-PT-52.2 Attachment 5, Other Identified Leakage, is currently 0 gpm.

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 0700 Accumulator Levels: A LI-1920 56.4% LI-1922 56.7%

B LI-1924 60.1% LI-1926 60.1%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 77.0%

NAPS 2012 NRC EXAM Page: 3 of 12 ADMIN JPM - SRO- (M)

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Accumulator Levels: A LI-1920 56.2% LI-1922 56.6%

B LI-1924 60.1% LI-1926 60.0%

C LI-1928 62.3% LI-1930 62.2%

PRT Level LI-1470 78.5%

Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 1900 Pressurizer Level: RC-LI-1459A 52.5%

VCT Level CH-LI-1112-1 46.2%

PDTT Level DG-LI-101 17.5%

RCS TAVE RC-TI-412D 580.8 degrees Leak Rate data was taken as follows: Date/Time: 9/12/2012 / 2300 Pressurizer Level: RC-LI-1459A 53.0%

VCT Level CH-LI-1112-1 38.6%

PDTT Level DG-LI-101 18.0%

RCS TAVE RC-TI-412D 580.7 degrees INITIATING CUE You are requested to perform a Reactor Coolant System leak rate hand calculation in accordance with 1-PT-52.2, and complete the following actions:

• Perform step 6.2 and complete Attachment 4, SI Accumulators and PRT Leakage.

• Perform step 6.12 and complete the Attachment 2, Leak Rate Data Sheet Without Using The Unit 1 PCS Computer.

• Perform Section 7.0 and identify any Follow-On Tasks that must be completed.

EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))

Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))

TOOLS AND EQUIPMENT Partially signed-off copy of 1-PT-52.2 Plant Curve Book Calculator PERFORMANCE STEPS START TIME __________

NAPS 2012 NRC EXAM Page: 4 of 12 ADMIN JPM - SRO- (M)

1 Review Initial Conditions and Precautions and Limitations. Procedure Step 3.0/4.0 SAT [ ] UNSAT [ ]

Standards Precautions and limitations have been reviewed.

Notes/Comments: Operator may review these sections prior to performing the Attachments.

2 Per Attachment 4, calculate the SI Accumulator Leakage. Procedure Step Attachment 4 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of -.0018 gpm (+/- .0008 gpm)

Notes/Comments 3 Per Attachment 4, calculate the PRT Leakage. Procedure Step Attachment 4 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .1995 gpm (+/- .001 gpm)

Notes/Comments NAPS 2012 NRC EXAM Page: 5 of 12 ADMIN JPM - SRO- (M)

4 Per Attachment 2, calculate the Pressurizer Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of 22.95 gallons (+/- .05 gallons)

Notes/Comments 5 Per Attachment 2, calculate the VCT Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of - 107.16 gallons (+/- .1 gallons)

Notes/Comments 6 Per Attachment 2, calculate the PDTT Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of 3.33 gallons (+/- .1 gallons)

Notes/Comments NAPS 2012 NRC EXAM Page: 6 of 12 ADMIN JPM - SRO- (M)

7 Per Attachment 2, calculate the RCS TAVE Level Difference. Procedure Step Attachment 2 SAT [ ] UNSAT [ ]

Standards Calculation yields a result of - 7.87 gallons (+/- .07 gallons)

Notes/Comments 8 Per Attachment 2, calculate the Total Leak Rate. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .3180 gpm (+/- .005 gpm)

Notes/Comments 9 Per Attachment 2, calculate the Identified Leakage. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .2116 gpm (+/- .005 gpm)

Notes/Comments NAPS 2012 NRC EXAM Page: 7 of 12 ADMIN JPM - SRO- (M)

10 Per Attachment 2, calculate the Unidentified Leakage. Procedure Step Attachment 2 Critical Step SAT [ ] UNSAT [ ]

Standards Calculation yields a result of .1064 gpm (+/- .005 gpm)

Notes/Comments 11 Obtain an Independent Review of the Calculations on Attachment Procedure Step 6.12.6 2.

SAT [ ] UNSAT [ ]

Simulation Cue(s) Assume another CRO has performed an independent review of the calculations and has initialed the procedure.

Notes/Comments:

12 Operator reviews the Acceptance Criteria. Procedure Step 7.1 SAT [ ] UNSAT [ ]

Standards Operator determines that the Leak Rate calculation results meet the Acceptance Criteria for Identified and Unidentified Leakage.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 8 of 12 ADMIN JPM - SRO- (M)

13 If the Unidentified Leak Rate is greater than .2 gpm, THEN do Procedure Step 7.2.1 Substep 7.2.1.a OR Substep 7.2.1.b.

SAT [ ] UNSAT [ ]

Standards Operator determines that the Unidentified Leak Rate calculation results do not exceed .2 gpm.

Notes/Comments:

14 If Unidentified Leak Rate increased by more than .2 gpm since the Procedure Step 7.2.2 last performance of 1-PT-46.21, THEN do the following.

SAT [ ] UNSAT [ ]

Standards Operator determines that the Unidentified Leak Rate did not increase more than .2 gpm.

Notes/Comments 15 If any symptom of RCS leakage exists such as even a slight Procedure Step 7.2.3 change to the leakrate baseline as per 1-PT-46.21 or an adverse trend, THEN do the following.

SAT [ ] UNSAT [ ]

Standards Operator determines that the Leak Rate calculation results may be indicative of a symptom of RCS leakage or adverse trend and contacts the OMAC and System Engineering.

Operator informs crew of the trend and requests that Operators investigate symptoms of increase leakage.

Simulation Cue(s) Assume another Operator has made the notifications.

Notes/Comments: The increase in the total Leak Rate may not be interpreted by the operator as an adverse trend at this point until monitored over a longer period of time.

NAPS 2012 NRC EXAM Page: 9 of 12 ADMIN JPM - SRO- (M)

16 If the Unidentified Leak Rate doubles since the last performance of Procedure Step 7.2.4 1-PT-46.21 AND is greater than .05 gpm, (YES)

THEN do the following:

• Report increased leakage to OMOC and System Engineering.

• Notify OMOC to evaluate implementing the Operational Decision Making Process.

Critical Step SAT [ ] UNSAT [ ]

Standards Operator ensures required notifications are made based on determination that the Unidentified Leak Rate calculation results doubled compared to the last PT-46.21 results (provided in the JPM Initial Conditions), AND is greater than.05 gpm.

Simulation Cue(s) Assume another Operator has made the notifications.

Notes/Comments:

17 If the Identified Leak Rate recorded is greater than 10 gpm, THEN Procedure Step 7.2.5 refer to Action Statement of Tech Spec 3.4.13. (NO)

SAT [ ] UNSAT [ ]

Standards Operator determines that the Identified Leak Rate did not increase to more than 10 gpm.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 10 of 12 ADMIN JPM - SRO- (M)

18 If the Unidentified Leak Rate recorded is greater than 1 gpm, THEN Procedure Step 7.2.6 refer to Action Statement of Tech Spec 3.4.13. (NO)

SAT [ ] UNSAT [ ]

Standards Operator determines that the Identified Leak Rate did not increase to more than 1 gpm.

Notes/Comments:

19 If the Identified Leak Rate recorded is greater than 5 gpm, THEN Procedure Step 7.2.7 submit a Condition Report. (NO)

SAT [ ] UNSAT [ ]

Standards Operator determines that the Identified Leak Rate did not increase to more than 5 gpm.

Notes/Comments:

20 If the Unidentified Leak Rate recorded is greater than 0.5 gpm, Procedure Step 7.2.8 THEN submit a Condition Report. (NO)

SAT [ ] UNSAT [ ]

Standards Operator determines that the Unidentified Leak Rate did not increase to more than 0.5 gpm.

Notes/Comments:

NAPS 2012 NRC EXAM Page: 11 of 12 ADMIN JPM - SRO- (M)

21 If the Unidentified Leak Rate recorded is more negative than -0.1 Procedure Step 7.2.9 gpm, THEN submit a Condition Report. (NO)

SAT [ ] UNSAT [ ]

Standards Operator determines that the Unidentified Leak Rate is not more negative than -0.1 gpm.

Notes/Comments:

22 Record information in Narrative Log. Procedure Step 7.2.11 SAT [ ] UNSAT [ ]

Simulation Cue(s) Assume another Operator will enter the information in the Narrative Log.

Notes/Comments:

>>>>> END OF EVALUATION <<<<<

STOP TIME __________

NAPS 2012 NRC EXAM Page: 12 of 12 ADMIN JPM - SRO- (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is in mode 5 for Refueling.

Unit 1 entered Mode 3 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> ago.

Unit is on a VCT float and VCT pressure is 15 psig.

RCS temperature is 102°F (based on RHR Discharge Temperature).

There are no maintenance openings in the RCS.

A Reactor Coolant loop has been isolated.

Reactor vessel level is at 74 inches with S/G tubes full.

Both Pressurizer PORVs are blocked open.

All Pressurizer Safety Valves are installed.

Main Feedwater and Main Condensate Systems are tagged out.

Auxiliary Feedwater System is available.

All Steam Generators are at 70% on the narrow-range indicator.

Steam Generator PORVs are available.

Steam Generator Manways are installed.

1-CH-P-1C (NORMAL) and 1-SI-P-1A are available with associated flow paths.

RWST level is 98% and temperature is 52°F.

1H and 1J EDGs and associated Emergency Buses are operable.

INITIATING CUE You are requested to perform an Alternate Core Cooling Assessment for normal surveillance using 1-GOP-13.0 and 1-GOP-13.1.

NAPS 2012 NRC EXAM ADMIN JPM (M) Page 1 of 6

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Perform an Alternate Core Cooling Assessment (1-GOP-13.0).

TASK STANDARDS Given 1-GOP-13.0 and 1-GOP-13.1, the completed assessment determines that Forced Feed and Spill is the primary back up cooling mode and the Time to Core Boiling is calculated to be 16.8 minutes (+/- .8 minutes).

K/A

REFERENCE:

G2.2.29 (1.6/3.8)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 27 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM ADMIN JPM (M) Page 2 of 6

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Unit 1 is in mode 5 for Refueling.

Unit 1 entered Mode 3 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> ago.

Unit is on a VCT float and VCT pressure is 15 psig.

RCS temperature is 102°F (based on RHR Discharge Temperature).

There are no maintenance openings in the RCS.

A Reactor Coolant loop has been isolated.

Reactor vessel level is at 74 inches with S/G tubes full.

Both Pressurizer PORVs are blocked open.

All Pressurizer Safety Valves are installed.

Main Feedwater and Main Condensate Systems are tagged out.

Auxiliary Feedwater System is available.

All Steam Generators are in wet layup at 70% on the narrow-range indicator.

Steam Generator PORVs are available.

NAPS 2012 NRC EXAM ADMIN JPM (M) Page 3 of 6

Steam Generator Manways are installed.

1-CH-P-1C (NORMAL) and 1-SI-P-1A are available with associated flow paths.

RWST level is 98% and temperature is 52°F.

1H and 1J EDGs and associated Emergency Buses are operable.

INITIATING CUE You are requested to perform an Alternate Core Cooling Assessment for normal surveillance using 1-GOP-13.0 and 1-GOP-13.1.

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT 1-GOP-13 1-GOP-13.1 Calculator NAPS 2012 NRC EXAM ADMIN JPM (M) Page 4 of 6

PERFORMANCE STEPS START TIME __________

1 Determine if Natural Circulation is available. Procedure Step 5.2 Critical Step SAT [ ] UNSAT [ ]

Standards Based on the following Guideline responses, Natural Circulation is determined to not be available.

• All S/Gs between 20-75% (YES)

• AFW available (YES)

• S/G PORVs available (YES)

• Hot Leg Stops operable/open (YES for B & C Loops)

• RCS press control (YES due to Letdown being available)

• RCS pressure > 50psig (NO due to PZR PORVS blocked open)

Notes/Comments 2 Determine if Reflux Boiling is available. Procedure Step 5.3 Critical Step SAT [ ] UNSAT [ ]

Standards Based on the following Guideline responses, Reflux Boiling is determined to not be available.

• All S/Gs between 20-75% (YES)

• AFW available (YES)

• S/G PORVs available (YES)

• Hot Leg Stops operable/open (YES for B & C Loops)

• RCS press control (YES)

• S/G Tubes drained (NO)

Notes/Comments NAPS 2012 NRC EXAM ADMIN JPM (M) Page 5 of 6

3 Determine if Forced Feed and Spill is available. Procedure Step 5.4 Critical Step SAT [ ] UNSAT [ ]

Standards Based on the following Guideline responses, Forced Feed and Spill is determined to be available.

• SI and Charging pump available (YES)

• Time after Shutdown > 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> with 2 Pressurizer PORVs blocked open (YES)

• Cold Leg and Hot Leg available (YES)

• RWST Level > 50% (YES)

Notes/Comments 4 Determine if gravity feed and spill is available. Procedure Step 5.5 Critical Step SAT [ ] UNSAT [ ]

Standards Based on the following Guideline responses, Gravity Feed and Spill is determined to not be available.

• Pressurizer Safety Valve removed (NO)

Notes/Comments 5 Calculate the estimated Time to Boiling. Procedure Step 5.6 Critical Step SAT [ ] UNSAT [ ]

Standards Time to Boiling is determined to be 16.8 minutes (+/- .8 minutes)

Notes/Comments: Operator may round down to a whole number. Rounding down to 16 or 17 would be within the standards stated tolerance.

>>>>> END OF EVALUATION <<<<<

STOP TIME __________

NAPS 2012 NRC EXAM ADMIN JPM (M) Page 6 of 6

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is in Mode 5 during a Refueling Outage.

A component walkdown is required to be performed by Operations personnel.

The component is located in the overhead inside the Unit 1 B Loop Room must be visually inspected and approached to within 30cm to complete the task .

INITIATING CUE You are directed to perform the following:

• Select the appropriate RWP and RWP Task for the operations personnel.

• Determine the required protective clothing for the job.

• Determine the required dosimetry for the job.

• Determine the dose alarm setpoint AND the dose rate alarm setpoint in effect under the RWP.

• Determine the maximum stay time based on reaching the dosimeter alarm setpoint (assume that a combined 10mrem total dose is accumulated in transit to and from the component location).

NAPS 2012 NRC EXAM Page: 1 of 6 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine Correct RWP, Stay Time, Dosimetry, and Dressout Requirements For A Given Task.

TASK STANDARDS Correct RWP/Task is selected, protective clothing and dosimetry are selected for the given RWP/Task, dose alarm and dose rate setpoints identified from the RWP/Task, and the maximum stay time calculated based on the alarm setpoints.

K/A

REFERENCE:

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 20 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM Page: 2 of 6 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Unit 1 is in Mode 5 during a Refueling Outage. Mode 6 has not yet been entered.

A component walkdown is required to be performed by Operations personnel.

The component is located in the overhead inside the Unit 1 B Loop Room must be visually inspected and approached to within 30cm to complete the task.

INITIATING CUE You are directed to perform the following:

• Select the appropriate RWP and RWP Task for the operations personnel

• Determine the required protective clothing for the job.

• Determine the required dosimetry for the job.

• Determine the dose alarm setpoint AND the dose rate alarm setpoint in effect under the RWP.

• Determine the maximum stay time based on reaching the dosimeter alarm setpoint (assume that a combned 10mrem total dose is accumulated in transit to and from the component location).

NAPS 2012 NRC EXAM Page: 3 of 6 ADMIN JPM - (M)

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT RWPs, Survey Map, Calculator PERFORMANCE STEPS START TIME __________

1 From the RWPs provided determine which RWP is applicable for Procedure Step the job. RWP 12-3229-2 Critical Step SAT [ ] UNSAT [ ]

Standards RWP 12-3229-2 for Task 2 is selected from the four RWPs provided.

Notes/Comments:

RWP 12-3203 is not correct since there is no fuel movement in progress.

RWP 12-3217 is not correct since it is Type C Testing activities.

RWP 12-3229-1 is not correct since it is for dose rates < 100mr/hr.

RWP 12-3229-2 is the correct RWP.

Operator is required to identify from the survey map that the area dose rates are

>100mrem/hr adjacent to the component.

NAPS 2012 NRC EXAM Page: 4 of 6 ADMIN JPM - (M)

2 From the RWPs provided, determine the protective clothing Procedure Step:

requirements. RWP 12-3229-2 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines that the area adjacent to the component in the overhead in the B Loop Room requires the following protective clothing requirements Protective Clothing Requirements:

1.0) Full Hood (assessing overhead in loop room)

One Pair Coveralls Rubber Boots High Top Shoe Covers Cotton Inserts One Pair Rubber Gloves Notes/Comments: HP does not require the use of facial protection in the B Loop Room overhead.

3 From the RWPs provided, determine the dosimetry required. Procedure Step:

RWP 12-3229-2 Critical Step SAT [ ] UNSAT [ ]

Standards Operator identifies that ED/SRD & TLD are required Notes/Comments: If asked, remote telemetrics dosimetry is not available.

NAPS 2012 NRC EXAM Page: 5 of 6 ADMIN JPM - (M)

4 From the RWPs provided, determine the dose alarm setpoint and Procedure Step:

dose rate alarm in effect under the RWP. RWP 12-3229-2 Critical Step SAT [ ] UNSAT [ ]

Standards Operator correctly identifies that the dose alarm is 50 mRem and the dose rate alarm is 500 mRem/hr Notes/Comments: Operator is required to identify from the survey map that task 2 setpoint must be used based on component location.

5 Determine the maximum stay time in minutes based on reaching Procedure Step:

the RWP dose alarm setpoint. RWP 12-3229-2 Critical Step SAT [ ] UNSAT [ ]

Standards

• Operator uses RWP to determine dose alarm is set at 50 mRem.

• Operator uses survey map to determine general area dose rate closest to the component is 410 mrem/hr.

• Operator subtracts 10 mrem from alarm setpoint due to travel to/from component. (50-10=40mrem)

• Operator then divides 40mrem by 410 mrem/hr to obtain a stay time of 5.85 minutes (+ .03 minutes) or 5 minutes 51 sec. (+

2 seconds)

(.0975 hrs x 60 minutes x 60 sec. = 351.2 seconds).

Notes/Comments:

END OF EVALUATION STOP TIME __________

NAPS 2012 NRC EXAM Page: 6 of 6 ADMIN JPM - (M)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is at 100% power steady state.

Unit 2 is in Mode 5 with the following conditions:

Pressurizer level is 28%.

RCS Loops are isolated.

RCS Temperature is 140°F degrees.

Personnel Hatch is open.

1 Pressurizer Safety Valve is removed.

LOSS OF RHR EVENT occurs on Unit 2 as follows: (timeline) 0910 RHR is determined to be lost.

0920 Containment Closure is established.

0925 RCS Temperature increases to greater than 200°F degrees.

0940 RHR is restored.

0942 RCS Temperature begins to decrease.

0955 RCS Temperature decreases to less than 200°F degrees.

INITIATING CUE You are requested to classify the emergency event in accordance with EPIP-1.01.

This is a time critical JPM.

(Record your results in the space provided)

Emergency Classification:____________________________________________

EAL Identifier:______________________________________________________

NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 1 of 7

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Classify an emergency event .

TASK STANDARDS Event is classified as an Unusual Event (CU3.1) in accordance with EPIP-1.01 and the applicable Emergency Level Action Matrix (Cold Conditions < 200°F); classification is required to be made within 15 minutes of starting the evaluation.

K/A

REFERENCE:

GEN-2.4.41 (2.9/4.6)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 12 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 2 of 7

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs 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.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Unit 1 is at 100% power steady state.

Unit 2 is in Mode 5 with the following conditions:

Pressurizer level is 28%.

RCS Loops are isolated.

RCS Temperature is 140°F degrees.

Personnel Hatch is open.

1 Pressurizer Safety Valve is removed.

LOSS OF RHR EVENT occurs on Unit 2 as follows: (timeline) 0910 RHR is determined to be lost.

0920 Containment Closure is established.

0925 RCS Temperature increases to greater than 200°F degrees.

0940 RHR is restored.

0942 RCS Temperature begins to decrease.

0955 RCS Temperature decreases to less than 200°F degrees.

INITIATING CUE You are requested to classify the emergency event in accordance with EPIP-1.01.

This is a time critical JPM.

NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 3 of 7

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT EPIP-1.01 EAL Matrix EAL Basis Document PERFORMANCE STEPS START TIME __________

START TIME IS CRITICAL: Start time begins the 15 minute clock for event classification (clock stops when classification is made - element 4 of JPM).

1 Operator determines the Event Category on the applicable Procedure Step _____

Emergency Action Level Matrix.

Critical Step SAT [ ] UNSAT [ ]

Standards Event is identified as a Cold Shutdown / Refuel System Malfunction, Category C, of the Cold Conditions < 200°F Matrix.

Notes/Comments NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 4 of 7

2 Operator reviews the Emergency Action Level Matrix associated Procedure Step _____

with the Event Category.

SAT [ ] UNSAT [ ]

Standards Category C reviewed to determine highest level of classification.

Notes/Comments 3 Operator uses available resources to obtain indications of Procedure Step _____

emergency conditions.

SAT [ ] UNSAT [ ]

Standards Category C emergency condition descriptions are compared to the Initial Conditions provided in JPM.

Table C-3 is reviewed correctly with the time duration beginning when RCS temperature exceeds 200°F, not when RHR is lost.

Hot Condition Matrix is not entered since the Loss of RHR initially occurred when RCS was below 200°F.

The RCS is determined to not be intact with a pressurizer safety valve removed.

Containment Closure is determined to be Established.

The asterisk below Table C-3 is reviewed and applied. (Since RHR was restored and RCS temperature was decreasing before the allowed time duration of EAL CA3.1 had expired, the Alert classification does not apply.)

Notes/Comments NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 5 of 7

4 Operator classifies event based on emergency action level being Procedure Step _____

exceeded.

Critical Step SAT [ ] UNSAT [ ]

Standards Event is classified as an Unusual Event IAW EAL Identifier CU3.1 within 15 minutes of the start of the evaluation.

Notes/Comments

>>>>> END OF EVALUATION <<<<<

STOP TIME __________

NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 6 of 7

SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

None NAPS 2012 NRC EXAM ADMIN JPM (NEW) - DRAFT Page 7 of 7