ML041700451

Initial Submittal of Administrative Jpms for D. C. Cook Initial Exam - March 2004

ML041700451
Person / Time
Site:	Cook
Issue date:	04/29/2004
From:	Bailey R American Electric Power Co
To:	NRC/RGN-III
References
50-315/OL04-301, 50-316/OL04-301
Download: ML041700451 (87)

Text

NRC2004-A1a TITLE Determination Of Reactor Shutdown Margin REVISION 0 PROGRAM NRC License Exam TIME 30 Minutes Revision 0: Initial Issue DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3 Revision 0

TITLE: NRC2004-A1a REVISION: 0 Determination Of Reactor Shutdown Margin REFERENCES Unit 2 Technical Data Book Cycle 14 2-OHP-4021-001-012 Rev 10a Determination of Reactor Shutdown Margin K/A Number: 001 A4.11 Ability to manually determine shutdown margin in the control room.

K/A IMPORTANCE: RO: 3.5 SRO: 4.1 Task Number:

EVALUATION SETTING Classroom or Office HANDOUTS Task Briefing Copy of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin Copy of Unit 2 Technical Data Book curves ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3 Revision 0

TITLE: NRC2004-A1a REVISION: 0 Determination Of Reactor Shutdown Margin TASK OBJECTIVES The net excess shutdown margin has been determined.

TASK BRIEFING You are an extra Control Room Operator on Unit 2.

The Unit Supervisor has directed you to calculate the SHUTDOWN MARGIN using Attachment 1 of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> ago. A Shutdown Margin Calculation Using Xenon Correction was performed to begin the cooldown. You are to calculate the required Shutdown Boron Concentration for the current RCS conditions without use of the optional Xenon Correction.

You are given the following:

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1600 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

• RCS Temperature is currently 215°F.

• NERDS is unavailable.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 Records cycle number 14 from Technical Data Book.

Enters Time and Date N/A - Optional Xenon Correction NOT required.

Page 1 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 PPC point U0035 is given in breifing.

Determines 8.5 GWD/MTU is burnup N/A - Obtained from PPC Enters RCS Temperature of 215°F P-11 and P-12 are blocked (Normal Cooldown Steps)

Mode 4 so penalty applies Page 2 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 N/A - Unit is in Mode 4 Following a Trip Uses Figure 4.5 Curve for Mode 4 and 5 with Boron Penalty (Top Line)

CT: Determines Uncorrected Boron Concentration is 1570 to 1590 PPM Page 3 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 Rod D-12 is stuck out at 105 steps.

CT: Enters 1 for 1 stuck rod CT: Determines worth of stuck rod is 895 to 915 pcm CT: Enters total stuck rod worth of 895 to 915 pcm N/A - Xenon Correction NOT used.

Page 4 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 CT: Enters total stuck rod worth of 895 to 915 pcm Enters 0 for Xenon reactivity CT: Enters Combined Reactivity of 895 to 915 pcm CT: Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F CT: Uses MOC line at Boron Concentration of ~ 1580 PPM to obtain Differential Boron Worth of -10.4 to -10.2 pcm/ppm.

Page 5 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 Enters Combined Reactivity of 895 to 915 pcm Enters DBW of -10.4 to -10.2 pcm/ppm CT: Calculates Delta Boron of -86 to -90 ppm Enters Uncorrected Boron Concentration is 1570 to 1590 ppm Enters Delta Boron of -86 to -90 ppm CT: Calculates Adjusted Boron Concentration of 1656 to 1680 ppm Page 6 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 CT: Uses figure 4.1.c since Combined Reactivity is >0 and RCS Temperature is 215°F CT: Uses MOC line at Adjusted Boron Concentration of ~

1668 PPM to obtain Differential Boron Worth of -10.3 to -

10.1 pcm/ppm.

Page 7 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 Enters Combined Reactivity of 895 to 915 pcm Enters DBW of -10.3 to -10.1 pcm/ppm CT: Calculates Delta Boron of -86.8 to -90.6 ppm Enters Uncorrected Boron Concentration is 1570 to 1590 ppm Enters Delta Boron of -86.8 to -90.6 ppm CT: Calculates Adjusted Boron Concentration of 1656.8 to 1680.6 ppm Page 8 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 N/A - Correction for Stuck rod is required.

N/A - Concentration is < 2200 PPM CT: Enters Required Boron Concentration of 1656 to 1681 ppm NOTE: If Candidate determines Minimum Boron Concentration is NOT MET and Emergency Boration is required, the JPM may be terminated.

Enters Current RCS Boron Concentration of 1600 PPM Enters sample time of Todays date and 30 minutes ago Page 9 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 CT: Enters Required Boron Concentration of 1656 to 1681 ppm Enters Current RCS Boron Concentration of 1600 PPM Determines Difference is 56 to 81 ppm CT: Informs US that Shutdown Margin is NOT met and that Emergency Boration is Required.

Terminate the JPM when the Candidate Determines that Emergency Boration is required since the Shutdown Margin is NOT met.

THIS JPM is COMPLETE Page 10 of 11 Revision 0

TITLE: NRC2004-A1a - Determination Of Reactor Shutdown Margin REVISION: 0 Page 11 of 11 Revision 0

Task Briefing You are an extra Control Room Operator on Unit 2.

The Unit Supervisor has directed you to calculate the SHUTDOWN MARGIN using Attachment 1 of 02-OHP-4021-001-012, Determination of Reactor Shutdown Margin.

The reactor tripped from 100% steady state operations 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> ago. A Shutdown Margin Calculation Using Xenon Correction was performed to begin the cooldown. You are to calculate the required Shutdown Boron Concentration for the current RCS conditions without use of the optional Xenon Correction.

You are given the following:

• PPC point U0035 indicates 8500 MWD/MTU

• RCS boron concentration is 1600 ppm per a chemistry sample taken 30 minutes ago.

• All Rods are fully inserted except Control Bank D Rod D-12 which indicates 105 steps.

• RCS Temperature is currently 215°F.

• NERDS is unavailable.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A1a.doc Page 1 of 1 Revision 0

NRC2004-A1b TITLE Perform Unit 1 LTOP Verification REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3 Revision 0

TITLE: NRC2004-A1b - Perform Unit 1 LTOP Verification REVISION: 0 References 01-OHP-4030-114-030 Daily and Shiftly Surveillance Checks Task: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 K/A: 2.1.33 Ability to recognize indications for system operating parameters that are entry-level conditions for technical specifications.

K/A IMPORTANCE: RO 3.4 SRO 4.0 Evaluation Setting Classroom Handouts Task Briefing Copy of 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Copy of Tech Data Book 12-Figure-18.4 Attachments None Simulator Setup N/A Page 2 of 3 Revision 0

TITLE: NRC2004-A1b - Perform Unit 1 LTOP Verification REVISION: 0 Task Objectives/Standards When directed by the Unit Supervisor, determine if the LTOP Requirements for Unit 1 are met per 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Task Briefing The US directs you to determine whether the Unit 1 LTOP Requirements are met per 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Equipment availability, as shown below:

Unit 1 Equipment Status COMPONENT NAME STATUS 1-NMO-152 PORV Block Valve Open & Energized 1-NMO-153 PORV Block Valve Open & Energized 1-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-152 1-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-153 1-IMO-128 Return from Hot Leg 2 Open & Energized 1-ICM-129 Return from Hot Leg 2 Open & Energized 1-SV-103 RHR Suction Relief Operable Annunciator Panel108 1-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel108 1-NRV-153 EMER AIR TANK NOT Lit Drop 28 PRESSURE LOW 1-PP-50E East Centrifugal Charging Pump Neutral (Racked In) 1-PP-50W West Centrifugal Charging Pump Running (Racked In) o Loop 2 WR Cold Leg RCS Lowest Cold Leg Temperature 185 F Temp 1-NLI-151 Pressurizer Level (Cold Cal) 68%

o 1-NTA-251 Pressurizer Liquid Temp 400 F NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3 Revision 0

TITLE: NRC2004-A1b - Perform Unit 1 LTOP Verification REVISION: 0 General CUES:

Provide a Copy of Field Copy of 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 CT: Student Marks page as shown [Xs] (Both PORVs are operable, RHR Suction Relief Operable, 2 CCPs Operable with o

Temperature >175 F and PRZ Level >50%)

{IF asked, then provide the following information for 1-NRV-153 and 1-NRV-152:}

CUE: Both PZR PORVs passed their required stroke time test.

Normal and Backup air supplies are available. Setpoints are within the functional testing criteria.

CT: Determines that LTOP Requirements are NOT Met.

Informs Unit Supervisor/Shift Manager That requirements are NOT Met and that they must reduce PRZ level to <50% or make 1 CCP inoperable within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> JPM IS COMPLETE.

Page 1 of 1

Task Briefing The US directs you to determine whether the Unit 1 LTOP Requirements are met per 01-OHP-4030-114-030, Daily and Shiftly Surveillance Checks, Data Sheet 20 Equipment availability, as shown below:

Unit 1 Equipment Status COMPONENT NAME STATUS 1-NMO-152 PORV Block Valve Open & Energized 1-NMO-153 PORV Block Valve Open & Energized 1-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-152 1-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 1-NRV-153 1-IMO-128 Return from Hot Leg 2 Open & Energized 1-ICM-129 Return from Hot Leg 2 Open & Energized 1-SV-103 RHR Suction Relief Operable Annunciator Panel108 1-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel108 1-NRV-153 EMER AIR TANK NOT Lit Drop 28 PRESSURE LOW 1-PP-50E East Centrifugal Charging Pump Neutral (Racked In) 1-PP-50W West Centrifugal Charging Pump Running (Racked In) o Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185 F 1-NLI-151 Pressurizer Level (Cold Cal) 68%

o 1-NTA-251 Pressurizer Liquid Temp 400 F NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A1b.doc Page 1 of 1 Revision 0

NRC2004-A2 TITLE Determine Isolation Boundaries for the REVISION 0 Refueling Water Purification Pump PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S.Pettinger 9/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

TITLE: NRC2004-A2- Determine Isolation Boundaries REVISION: 0 for the Refueling Water Purification Pump References OP-12-5136 Flow Diagram (P&ID)

Task TASK: 3000040101 Prepare a Clearance Permit K/A: 2.2.13 Knowledge of tagging and clearance procedures K/A IMPORTANCE: SRO 3.6 RO 3.8 Evaluation Setting Classroom / Simulator Handouts Task Briefing OP-12-5136 Flow Diagram (P&ID)

Attachments None Simulator Setup N/A Page 2 of 3

TITLE: NRC2004-A2- Determine Isolation Boundaries REVISION: 0 for the Refueling Water Purification Pump Task Objectives/Standards The candidate identifies the valves that must be closed to isolate the 12-SF-147, Refueling Water Purification Pump discharge check valve.

Task Briefing The Auxiliary Building Tour Operator notified the Control Room that a leak had developed on the pipe weld for 12-SF-147, Refueling Water Purification Pump discharge check valve. The operator reported stopping the pump, but the leak continues.

The Unit Supervisor directs you to research and identify the system valves closest to the leak source that will isolate the Refueling Water Purification Pump discharge check valve (12-SF-147) and stop the leak.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

TITLE: NRC2004-A2- Determine Isolation Boundaries for the Refueling Water REVISION: 0 Purification Pump Page 1 of 2

TITLE: NRC2004-A2- Determine Isolation Boundaries for the Refueling Water REVISION: 0 Purification Pump The candidate should locate OP-12-5136 Flow Diagram CUE: Provide copy of OP-12-5136 when candidate correctly locates micro fiche.

Locates 12-SF-147, Refueling Water Purification Pump discharge check valve Determines that the AEO must isolate the following Valves :

• CT: 12-SF-137 - Closed.

• CT: 12-SF-148 - Closed.

• CT: 1-SF-167 - Closed.

• CT: 1-WD-216 - Closed.

• CT: 2-SI-184 - Closed.

• CT: 2-SF-184 - Closed.

Refueling Water Purification Pump control switch to OFF Refueling Water Purification Pump control breaker to OFF 12-SF-145, Pump Casing Drain valve to OPEN 12-SF-146, Pump Casing Vent valve to OPEN Reports task completed.

JPM IS COMPLETE Page 2 of 2

Task Briefing The Auxiliary Building Tour Operator notified the Control Room that a leak had developed on the pipe weld for 12-SF-147, Refueling Water Purification Pump discharge check valve. The operator reported stopping the pump, but the leak continues.

The Unit Supervisor directs you to research and identify the system valves closest to the leak source that will isolate the Refueling Water Purification Pump discharge check valve (12-SF-147) and stop the leak.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A2.doc Page 1 of 1

NRC2004-A3 TITLE: Perform Containment Pressure Relief REVISION: 0 PROGRAM NRC License Exam TIME: 20 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3 Revision 0

TITLE: NRC2004-A3 REVISION: 0 Perform Containment Pressure Relief REFERENCES 02-OHP 4021.028.004, Rev. 13 Operation of the Containment Pressure Relief System TASK: 0280080101 Perform A Containment Pressure Relief K/A: 2.3.11 Ability to control radiation releases K/A IMPORTANCE: RO 2.7 SRO 3.2 Evaluation Setting Unit 2 Simulator Handouts Task Briefing 02-OHP 4021.028.004, Operation of the Containment Pressure Relief System ATTACHMENTS None SIMULATOR SETUP

1. Reset the simulator to Mode 1 IC37.

2. Place simulator in RUN.

3. MRF CHR16 to 29.65 (barometric pressure)

4. Verify Lower Containment pressure at ~ 0.14 psig.

Page 2 of 3 Revision 0

TITLE: NRC2004-A3 REVISION: 0 Perform Containment Pressure Relief Task Objectives Perform a containment pressure relief as directed by procedure including correctly determining status of the relevant radiation monitors and correctly performing a flow estimate per 12-PMP-6010.OSD.001, Offsite Dose Calculation manual.

Task Briefing Lower containment pressure has risen to approximately 0.14 psig due to atmospheric pressure changes. All RMS channels are operable.

The Unit Supervisor directs you to perform a containment pressure relief to lower containment pressure to 0 psig in accordance with 02-OHP-4021-028-004, Operation of Containment Pressure Relief System. All initial conditions are satisfied.

AFTER you have reviewed the precautions and contingencies outlined above, then perform the containment pressure relief to lower containment pressure using the LOWEST reading pressure channel.

Page 3 of 3 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 General Standards:

All actions are attempted in the prescribed sequence.

Unit Supervisor is promptly informed of abnormal conditions.

CUE: Procedure has been revision checked.

{NOTE: Not part of JPM.}

CUE: Precautions have been reviewed and discussed in the task briefing.

{NOTE: Not part of JPM.}

CUE: Initial conditions have been verified.

{NOTE: Not part of JPM.}

Page 1 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 Information in this note is reviewed and discussed in task briefing.

NOTE: Not part of JPM.

CUE: None of the planned evolution activities are scheduled during the time we will be performing the pressure relief.

{NOTE: JPM starts here.}

Operator verifies that all listed monitors are functioning properly Page 2 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 Operator determines that ALL channels are OPERABLE N/A N/A NOTE: This is reviewed and discussed as part of the task briefing.

CUE: Shift Manager deems NONE of these actions as necessary.

Page 3 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 Data is to be recorded on Section A of Data Sheet 1 Enter Next CPR number CUE: Next Containment Pressure Relief Number is 200403 CT: Record Vent Flow from 2-VFR-2510 or 2-VFR-315 on recorder 2-MR-54 and circles source CT: Record Containment Pressure CT: Record Radiation Monitor readings CT: Perform Source Check on 2-ERS-2305 CT: Perform Source Check on 2-ERS-2405 N/A Verify all Trip block switches in NORMAL

{NOTE: 2300/2305 and 2400/2405 TRIP/BLOCK is performed by one switch action.}

Initial Data Sheet 1 Page 4 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 N/A NOTE: These contingencies will be reviewed and discussed as part of the task briefing.

Page 5 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 Contingencies continued from previous page.

CT: Places 2-VCR-107 to OPEN and holds.

CT: Places 2-VCR-207 to OPEN and holds.

CUE: After VCR-107 and VCR-207 are open, US directs you to start HV-CPR-1, CNTMT Pressure Relief Vent Unit.

CT: 2-HV-CPR-1 Fan switch is placed in START.

N/A CT: Records start time in Section B Page 6 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0

{NOTE: When Containment pressure is ZERO (+/-0.05) psig, the candidate should perform the next step.}

CT: 2-HV-CPR-1 Fan switch is placed in STOP. (Fan is stopped before valves are closed.)

N/A Report pressure relief termination.

CT: Places 2-VCR-107 in CLOSE.

CT: Places 2-VCR-207 in CLOSE.

Operator records stop time on Section B.

JPM is COMPLETE Page 7 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 NOTE: Included for information only.

Page 8 of 10 Revision 0

TITLE: NRC2004-A3 - Perform Containment Pressure Relief REVISION: 0 Note: Included for information only.

Page 9 of 10 Revision 0

Task Briefing Lower containment pressure has risen to approximately 0.14 psig due to atmospheric pressure changes. All RMS channels are operable.

The Unit Supervisor directs you to perform a containment pressure relief to lower containment pressure to 0 psig in accordance with 02-OHP-4021-028-004, Operation of Containment Pressure Relief System. All initial conditions are satisfied.

AFTER you have reviewed the precautions and contingencies outlined above, then perform the containment pressure relief to lower containment pressure using the LOWEST reading pressure channel.

NRC2004-A3.doc Page 1 of 1 Revision 0

NRC2004-A4 TITLE Complete EMD-32a Nuclear Plant Notification Form REVISION 0 PROGRAM NRC License Exam TIME 10 Minutes Revision 0: Initial Issue DATE:

DEVELOPING Name: Steve Pettinger 10/23/2003 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

TITLE: NRC2004-A4 REVISION: 0 Complete EMD-32a Nuclear Plant Event Notification References Procedure: PMP-2080-EPP-107, Rev 18Notification Task: EPP 0030701 Perform Initial Offsite Notification K/A: 2.4.39 Knowledge of RO responsibilities in emergency plan implementation K/A IMPORTANCE: SRO 3.1 RO 3.3 Evaluation Setting Classroom Handouts Task Briefing & MIDAS Summary EMD-32a Nuclear Plant Event Notification (blank form)

Attachments None Simulator Setup None Page 2 of 3

TITLE: NRC2004-A4 REVISION: 0 Complete EMD-32a Nuclear Plant Event Notification Task Objectives/Standards Complete the EMD-32a, Nuclear Plant Event Notification form to notify of state/county agencies within 15 minutes.

Task Briefing You are an extra Control Room Operator on Unit 1.

At the beginning of your shift, Unit 1 was operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.

A loss of heat sink has occurred leading to the implementation of 01-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink. Operators have been dispatched to remove the clearance on the turbine-driven auxiliary feed water pump.

The Shift Manager has just declared a SITE AREA EMERGENCY per initiating condition S-5, Loss of Hot SD Sys. The plant is currently STABLE.

Classification Time is (Use Current Time _________ & have candidate enter on briefing handout)

THIS IS A TIME CRITICAL JPM The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval.

All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.

Meteorological Data - MIDAS Summary is provided.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

TITLE: NRC2004-A4 - Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval.

Drill box marked (for purposes of this JPM Actual Event is also acceptable) 1 entered since this is the initial notification (1CR is also acceptable)

Control Room box marked Plant number given, however other control room telephone numbers are acceptable CT: - SITE AREA EMERGENCY box MUST be marked CT: - Current date and time of Classification (Given during the briefing) MUST be filled in System Malfunction box marked CT: - S-5 MUST be filled in Stable box should be marked CT: - No box MUST be marked CT: - None box MUST be marked CT: Wind from 312 to 132 filled in CT: Wind speed 8 mph filled in Stability Class D filled in Precipitation Yes box marked Candidate reports complete and ready for SEC approval.

JPM IS COMPLETE.

Page 1 of 1

Task Briefing You are an extra Control Room Operator on Unit 1.

At the beginning of your shift, Unit 1 was operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.

A loss of heat sink has occurred leading to the implementation of 01-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink. Operators have been dispatched to remove the clearance on the turbine-driven auxiliary feed water pump.

The Shift Manager has just declared a SITE AREA EMERGENCY per initiating condition S-5, Loss of Hot SD Sys. The plant is currently STABLE.

Classification Time is (Enter Current Time _________ )

THIS IS A TIME CRITICAL JPM The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval.

All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.

Meteorological Data - MIDAS Summary is provided.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A4.doc Page 1 of 2

Meteorological Data - MIDAS Summary Delta Temperature - Main Tower -0.4°F Wind Direction 10M - Main Tower 312° Wind Speed 10M - Main Tower 8 mph Precipitation - Main Tower Rain Wind Direction 10M - Backup Tower 318° Wind Speed 10M - Backup Tower 10 mph Wind Direction 60M - Main Tower 321° Wind Speed 60M - Main Tower 11 mph Standard Deviation 10M Main 0° Standard Deviation 10M Backup 0° Standard Deviation 10M Main 0° Pasquill Category D Outside Temperature 50.2°F Lake Breeze NA NRC2004-A4.doc Page 2 of 2

NRC2004-A5a TITLE Calculate Reactor Vessel Void Vent Time REVISION 0 PROGRAM NRC License Exam TIME 10 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

TITLE: NRC2004-A5a REVISION: 0 Calculate Reactor Vessel Void Vent Time REFERENCES 2-OHP 4023 FR-I.3 Rev 7 Response to Voids in Reactor Vessel K/A Number: EPE: 009 EA2.38 Ability to interpret existence of head bubble during SBLOCA.

2.1.25 Ability to obtain and interpret station reference materials.

K/A IMPORTANCE: RO: 3.9 SRO: 4.3 2.8 3.1 Task Number: EOP1090512 Mitigate the effects of voids in the reactor vessel EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing Attachment a of FR-I.3 SIMULATOR SETUP None Page 2 of 3

TITLE: NRC2004-A5a REVISION: 0 Calculate Reactor Vessel Void Vent Time TASK OBJECTIVES/STANDARDS Reactor Vessel Void Vent time is appropriately determined (+10% error) based upon initial conditions.

TASK BRIEFING You are the extra SRO from Unit 1.

The Unit 2 Control Room team is responding to a SBLOCA and is currently implementing ES-1.2, Post LOCA Cooldown and Depressurization. There has been significant voiding in the RCS. The Unit Supervisor has implemented FR-I.3, Response to Voids in Reactor Vessel.

The Unit Supervisor directs you to determine the maximum vent time for the Reactor vessel using Attachment A of FR-I.3. You are to report the calculated vent time to the US.

The following containment parameters were noted on 2-SG-18, Containment Air Temperature Recorder:

Point # Point Id Noun Name Temperature (Deg F) 1 ETR-11 Upper Cont. 90 97 2 ETR-12 Upper Cont. 180 134 3 ETR-13 Upper Cont. 270 101 4 ETR-14 Upper Cont. 0 93 5 ETR-15 Lower Cont. Q1 173 6 ETR-16 Lower Cont. Q2 139 7 ETR-17 Lower Cont. Q3 129 8 ETR-18 Lower Cont. Q4 168 9 ETR-19 HV-CLV-1,4 Room 170 10 ETR-20 HV-CEQ-2 Room 151 11 ETR-21 HV-CLV-2,3 Room 146 12 ETR-22 INST Room 190 13 ETR-23 PZR Doghouse 367 RCS pressure is 1450 psig Containment hydrogen concentration is 0.8%.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

TITLE: NRC2004-A5a - Calculate Reactor Vessel Void Vent Time REVISION: 0 CT: Determines Average Temp is 126 Deg F. (Points 2, 4, &

10 as per note at bottom of page)

Determine 586 Deg R 3

Determines1.041 E6 ft 3

Determines 2.290 E4. Ft CT: Determines 3300 +/- 100 SCFM CT: Determines 6.9 (range of 6.2 - 7.6) minutes.

JPM TERMINATION: Reports to US a vent time Page 1 of 1

Task Briefing You are the extra SRO from Unit 1.

The Unit 2 Control Room team is responding to a SBLOCA and is currently implementing ES-1.2, Post LOCA Cooldown and Depressurization. There has been significant voiding in the RCS. The Unit Supervisor has implemented FR-I.3, Response to Voids in Reactor Vessel.

The Unit Supervisor directs you to determine the maximum vent time for the Reactor vessel using Attachment A of FR-I.3. You are to report the calculated vent time to the US.

The following containment parameters were noted on 2-SG-18, Containment Air Temperature Recorder:

Point # Point Id Noun Name Temperature (Deg F) 1 ETR-11 Upper Cont. 90 97 2 ETR-12 Upper Cont. 180 134 3 ETR-13 Upper Cont. 270 101 4 ETR-14 Upper Cont. 0 93 5 ETR-15 Lower Cont. Q1 173 6 ETR-16 Lower Cont. Q2 139 7 ETR-17 Lower Cont. Q3 129 8 ETR-18 Lower Cont. Q4 168 9 ETR-19 HV-CLV-1,4 Room 170 10 ETR-20 HV-CEQ-2 Room 151 11 ETR-21 HV-CLV-2,3 Room 146 12 ETR-22 INST Room 190 13 ETR-23 PZR Doghouse 367 RCS pressure is 1450 psig Containment hydrogen concentration is 0.8%.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A5a.doc Page 1 of 1

NRC2004-A5b TITLE Verify Appropriate LCO Action for Inoperable REVISION 0 Radiation Monitors PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

TITLE: NRC2004-A5b - Verify Appropriate LCO Action REVISION: 0 for Inoperable Radiation Monitors References 12-OHP-4024-139, Annunciator #139 Response: Radiation Tech Spec 3.3.3.1, Radiation Monitoring Instrumentation PMP-4030-EIS-001, Event-Initiated Surveillance Testing PMP-6010-OSD-001, Off-Site Dose Calculation Manual Task: ADM0370302 Verify Limiting Conditions for Operation are met in accordance with Technical Specifications.

ADM0420302 Verify Limiting Conditions for Operation are met in accordance with the Offsite Dose Calculation Manual.

K/A: 2.1.12 Ability to apply Technical Specifications for a system.

K/A IMPORTANCE: RO 2.9 SRO 4.0 Evaluation Setting Simulator Handouts Task Briefing 12-OHP-4024-139, Annunciator #139 Response: Radiation Drop 22 Tech Spec 3.3.3.1, Radiation Monitoring Instrumentation PMP-4030-EIS-001, Event-Initiated Surveillance Testing Data Sheet 1 Attachments None Simulator Setup N/A - May use IMF RM02Q3 to 0 to fail VRS-2505 Page 2 of 3

TITLE: NRC2004-A5b - Verify Appropriate LCO Action REVISION: 0 for Inoperable Radiation Monitors Task Objectives/Standards Respond to a failed RMS channel and determine the appropriate LCO actions in accordance with applicable procedures.

Task Briefing You are an extra SRO.

Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas has just went into failure (WHITE).

The Unit Supervisor directs you to investigate and perform any required actions.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 General CUES:

CUE: If contacted as Rad Protection, report Channel 2505 has failed.

Operator reviews conditions for WHITE light.

Page 1 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 Operator references T.S. Table 3.3-6 actions (1.C.i.a - See the ODCM)

CUE: If asked, Channel VRS-2505 is NOT Due to a low failure and will be out-of-service for at least 5 days.

CUE: Acknowledge report to RP of Channel Failure CUE: US will initiate eSat processing.

CT: Operator reports VRS-2505 as Inoperable and references PMP-4030-EIS-001, Attachment 1.

Page 2 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 ODCM Reference Attachment 3.4 Items 2.a and 4.a CT: Operator identifies applicability of Item 17.

Page 3 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 CUE: US will perform OHI-4030 actions as required.

CT: Operator identifies applicability of Item 17.

Notifies Chemistry of Required Surveillance requirements.

CUE: Chemistry acknowledges requirements Page 4 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 CUE: US has logged the event in the Control Room Long.

Completes DATA Sheet 1 Steps 1.1 through 1.7 Page 5 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 Operator references action item 6 for VRS-2505 being inoperable.

Operator references action item 9 for VRS-2505 being inoperable.

Page 6 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 CT: Operator reports requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (If Not returned in 30 days provide a description in Annual Report)

Page 7 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 Operator reports requirement that release may continue for up to 14 days provided contingency actions are taken.

CUE: Unit Supervisor acknowledges ability to continue release up to 14 days provide contingencies are met.

Page 8 of 9

TITLE: NRC2004-A5b - Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 CT: Enters Event #17, Event - Vent Stack Noble Gas Monitor VRS-2505 Inoperable , Unit 2 Enters Time and Date.

Enters 30 days / 14 days for releases CT: Enters 12-THP-6020-CHM-322 and 12-THI-2291-ADM-012 Determine Samples required once per shift and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per ODCM Attachment 3.4 action 6 Determine 2 Samples required with dual verification of calculations and lineups per ODCM Attachment 3.4 action 9 (Not required since no Gaseous Waste release is in progress)

Sign, Time and Date Notify Unit 1 CUE: Acknowledge Unit 1 has been notified JPM IS COMPLETE.

Page 9 of 9

Task Briefing You are an extra SRO.

Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas has just went into failure (WHITE).

The Unit Supervisor directs you to investigate and perform any required actions.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A5b.doc Page 1 of 1

NRC2004-A6 TITLE Perform Screen House Vulnerability REVISION 0 Determination PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

TITLE: NRC2004-A6 - Perform Screen House REVISION: 0 Vulnerability Determination References 12-OHP-5030-057-001 Screen House Vulnerability Determination Task: ADM1330202 Verify compliance with PSA/PRA prior to removing equipment from service.

K/A: 2.2.17 Knowledge of the process for managing maintenance activities during power operations.

K/A IMPORTANCE: RO 2.3 SRO 3.5 Evaluation Setting Simulator Handouts Task Briefing Copy of 12-OHP-5030-057-001, Screen House Vulnerability Determination National Weather Service Printout Attachments None Simulator Setup Page 2 of 3

TITLE: NRC2004-A6 - Perform Screen House REVISION: 0 Vulnerability Determination Task Objectives/Standards Perform a Screen House Vulnerability Determination, observing applicable precautions and limitations and procedural steps.

Task Briefing You are the Unit 1 SRO.

The North Screen Wash Pump Strainer motor has just broken. The Shift manager has asked you to perform a Screen House Vulnerability Determination based on current conditions.

Unit 1 and Unit 2 are both Operating at 100% power.

All CW pumps are operating except for #24 CW pump, which is tagged out for an Oil Change. The pump will be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at which time a post maintenance run is planned.

The last Mussel Kill was performed on February 2. No Preventative treatment is in progress nor planned.

The Fish deterrent System is NOT operable. The North Intake crib is isolated as divers are working on the deterrent system. Birds are NOT concentrating near the discharge.

Traveling screens 1-OME-1, 1-OME-2, and 1-OME-4 are tagged out due to motor failure. Stop Logs have NOT been installed for these screens. The remaining Unit 1 traveling screens auto started about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago and ran for 35 minutes. The Unit 2 Traveling screens are all available and have not auto started.

All Indications, Alarms and other equipment are functioning properly.

Environmental Report for Current Month:

Prey fish population report is 0 for current and 24 Hr prediction Local networking report is 0 for current and 24 Hr prediction NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

TITLE: NRC2004-A6 - Perform Screen House Vulnerability Determination REVISION: 0 General CUES:

CT: Determines that 6 pumps are currently running and 7 will running in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Current 24HR 3 3 CT: Determines that only 2 intakes will be available for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Current 24HR 6 6 Page 1 of 4

TITLE: NRC2004-A6 - Perform Screen House Vulnerability Determination REVISION: 0 CT: Determines that current ratio is (11/6) 1.8 and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> value is (11/7) 1.57 if #24 CW is started. Also note Logs NOT Installed Current 24HR 3 6 Determines that all D/P indications are available for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0 0 Determines that all Level indications are available for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0 0 Determines that all baskets are available for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0 0 CT: Determines that only ONE pump/strainer is available for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6 6 CT: Determines that Only Planned evolution is CW #24 start in next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0 6 Determines that fish deterrent is N/A since it is March.

0 (N/A) 0(N/A)

CT: Determines that Both units are in Mode 1 10 10 CT: Determines Plant Factors Subtotals Current 24HR 28 37 Page 2 of 4

TITLE: NRC2004-A6 - Perform Screen House Vulnerability Determination REVISION: 0 CT: Determines that Season factor is 6 for March Current 24HR 6 6 Determines that wind direction is N/A since it is March.

0 (N/A) 0(N/A)

CT: Determines that wave height projected to be 2 ft. for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 1 Determines that Birds are NOT concentrating 0 0 CT: Determines that Traveling Screens have started in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3 3 CUE: Environmental Report data conditions are both 0 0 0 0 0 Determines Environmental Factors Sub-totals 10 10 CT: Calculates Total Vulnerability Current 24HR Environ 10 10 Plant 28 37 Total 38 47 Page 3 of 4

TITLE: NRC2004-A6 - Perform Screen House Vulnerability Determination REVISION: 0 Initials that Sub-totals were calculated Initials that Total was calculated CT: Determines that while the Current Vulnerability is Level III and the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> predicted vulnerability is Level IV, the recorded vulnerability will be Level IV.

JPM IS COMPLETE.

Page 4 of 4

Task Briefing You are the Unit 1 SRO.

The North Screen Wash Pump Strainer motor has just broken. The Shift manager has asked you to perform a Screen House Vulnerability Determination based on current conditions.

Unit 1 and Unit 2 are both Operating at 100% power.

All CW pumps are operating except for #24 CW pump, which is tagged out for an Oil Change. The pump will be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at which time a post maintenance run is planned.

The last Mussel Kill was performed on February 2. No Preventative treatment is in progress nor planned.

The Fish deterrent System is NOT operable. The North Intake crib is isolated as divers are working on the deterrent system. Birds are NOT concentrating near the discharge.

Traveling screens 1-OME-1, 1-OME-2, and 1-OME-4 are tagged out due to motor failure. Stop Logs have NOT been installed for these screens. The remaining Unit 1 traveling screens auto started about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago and ran for 35 minutes. The Unit 2 Traveling screens are all available and have not auto started.

All Indications, Alarms and other equipment are functioning properly.

Environmental Report for Current Month:

Prey fish population report is 0 for current and 24 Hr prediction Local networking report is 0 for current and 24 Hr prediction NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A6.doc Page 1 of 1

NRC2004-A7 TITLE Review a Gaseous Waste Release Permit REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

COURSE NUMBER NRC2004-A7 REVISION: 0 AND TITLE:

Review a Gaseous Waste Release Permit References 12-OHP-4021-023-002, Rev 19 Release of Radioactive Waste from Gas Decay Tank PMP-6010-OSD-001, Rev 17a Offsite Dose Calculation Manual Task: 0230140102 Verify releases comply with the Offsite Dose Calculation Manual.

0230140103 Authorize a gaseous radioactive waste release.

K/A: 2.3.6 Knowledge of requirements for reviewing and approving release permit.

K/A IMPORTANCE: SRO 3.1 RO 2.1 Evaluation Setting Classroom / Simulator Handouts Task Briefing Prepared Release Package:

• 12-OHP-4021-023-002, Release of Radioactive Waste from Gas Decay Tanks:

• Attachment 2, Release of Radioactive Waste from Gas Decay Tanks

• Data Sheets 1, Gas Decay Tank Release Permit

• Figure 1, 12-RRV-306 Flow Rate @ 5 PSIG Inlet Pressure

• Gaseous Waste Release Worksheet Available References

• PMP-6010-OSD-001, Offsite Dose Calculation Manual Simulator Setup N/A Page 2 of 3

COURSE NUMBER NRC2004-A7 REVISION: 0 AND TITLE:

Review a Gaseous Waste Release Permit Task Objectives/Standards Identifying conditions that would prevent authorization of a gaseous release in accordance with Step 4.5 of 12-OHP-4021-023-002, Release of Radioactive Waste from Gas Decay Tanks.

Task Briefing You are the WCC SRO.

Given the following conditions:

• Both units are operating at 100% power

• Radiation Monitors 1-VRS-1500 and 2-VRS-2500 are OPERABLE

• Meteorological instrumentation is OPERABLE

• Gas Decay Tank # 6 is ready to be released.

• The gas decay tank release package is prepared for your review and authorization.

Authorize gas decay tank release (G-04-04) in accordance with Step 4.5 of 12-OHP-4021-023-002, Release of Radioactive Waste from Gas Decay Tanks. Ensure you mark any (and all) conditions that would prevent authorization of this release.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3

COURSE NUMBER NRC2004-A7 REVISION: 0 AND TITLE:

Review a Gaseous Waste Release Permit CT - Operator identifies that independent verification by two (different) operators was NOT performed for 12-RPC-305 (GDT Release Header to Vent Stack) valve was OPEN.

Operator reviews Data Sheet 1 information (Next Page)

Page 1 of 3

COURSE NUMBER NRC2004-A7 REVISION: 0 AND TITLE:

Review a Gaseous Waste Release Permit Candidate verifies sample date and time consistent with worksheet data.

Candidate verifies sample data is consistent with worksheet data.

Page 2 of 3

COURSE NUMBER NRC2004-A7 REVISION: 0 AND TITLE:

Review a Gaseous Waste Release Permit CT: Identifies that greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has elapsed since chemistry approved the release (Data Sheet 1, Section 2, Chemistry Approval Date/Time (Sample: 03/18/04 @ 0605; Exam: 03/19/04 after 0700)

Cue: If the candidate asks, the current time is as-is (real time).

Cue: Reports task completed.

JPM IS COMPLETE.

Page 3 of 3

Task Briefing You are the WCC SRO.

Given the following conditions:

• Both units are operating at 100% power

• Radiation Monitors 1-VRS-1500 and 2-VRS-2500 are OPERABLE

• Meteorological instrumentation is OPERABLE

• Gas Decay Tank # 6 is ready to be released.

• The gas decay tank release package is prepared for your review and authorization.

Authorize gas decay tank release (G-04-04) in accordance with Step 4.5 of 12-OHP-4021-023-002, Release of Radioactive Waste from Gas Decay Tanks. Ensure you mark any (and all) conditions that would prevent authorization of this release.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A7.doc Page 1 of 1

NRC2004-A8 TITLE Emergency Plan Classification with PAR REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes DATE:

DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR REFERENCES Procedure: PMP-2080-EPP-101 revision 4, Emergency Classification Task: EPP0020703 Classify an Emergency Condition K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications K/A IMPORTANCE: SRO 4.1 RO 2.3 Procedure: PMP-2080-EPP-100 revision 2, Emergency Response Task EPP0120703 Develop a Protective Action Recommendation K/A: 2.4.44 Knowledge of the emergency plan protective action recommendations K/A IMPORTANCE: SRO 4.0 RO 2.1 EVALUATION SETTING Classroom or office HANDOUTS Task Briefing ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR TASK OBJECTIVES/STANDARDS In accordance with procedures when an emergency event has occurred or changed, the operator will be able to:

1. Classify an Emergency Condition

2. Develop a Protective Action Recommendation TASK BRIEFING You are the Shift Manager.

A Large Break LOCA event with reduced ECCS flow capability has occurred. The crew has transitioned to OHP-4023-E-1, Loss of Reactor or Secondary Coolant, and is working their way through the procedure. The STA reports a RED CSFST indication on Core Cooling. The crew is transitioning to OHP-4023-FR-C.1, Response to Inadequate Core Cooling.

The following plant conditions exist:

Only Train A of ECCS equipment is running Operators had to manually initiate Containment Spray and Phase B isolation signal CETC readings of the five highest temperatures indicate 760 °F and rising RCS pressure is less than 100 psig Containment pressure is 10 psig and slowly lowering Containment radiation is 8 R/hr and slowly rising Containment Sump level (WR) indicates 35% and slowly rising The MET data indicates no precipitation with the wind from 320° at 6 mph and NO offsite release is occurring.

Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.

NOTE Simulator Indications are NOT applicable to this JPM Page 3 of 3 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR The trainee should refer to PMP-2080-EPP-101, Emergency Classification, Attachment 1, page 15 of 114.

Candidate determines LOSS of Fuel Clad Barrier based upon 1.1 Candidate determines LOSS of RCS Barrier based upon 2.1 Candidate determines POTIENTIAL LOSS of Containment based upon 3.6 (Next Page)

CT The classification for this event is General Emergency.

Page 1 of 5 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR Candidate determines POTENTIAL LOSS of Containment based upon 3.6 (Continued)

Page 2 of 5 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR Candidate determines PAR recommendations:

NOTE: A General Emergency requires a protective action recommendation be made to the state.

Page 3 of 5 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR Wind direction and speed is given in briefing:

Wind is from 320° at 6 mph.

Per briefing, NO offsite release is occurring.

Next page.

Page 4 of 5 Revision 0

TITLE: NRC2004-A8 REVISION: 0 Emergency Plan Classification with PAR CT Protective Action Recommendation is to evacuate areas 1 and 3.

Wind is from 320°. Downwind sector is G and adjacent sectors are sectors F and H.

CT Even though there is NO offsite release occurring, a protective action recommendation is still required based on the General Emergency classification.

Student informs examiner that this event is classified as a General Emergency with a Protective Action Recommendation to evacuate areas 1 and 3.

JPM IS COMPLETE Page 5 of 5 Revision 0

Task Briefing You are the Shift Manager.

A Large Break LOCA event with reduced ECCS flow capability has occurred. The crew has transitioned to OHP-4023-E-1, Loss of Reactor or Secondary Coolant, and is working their way through the procedure. The STA reports a RED CSFST indication on Core Cooling. The crew is transitioning to OHP-4023-FR-C.1, Response to Inadequate Core Cooling.

The following plant conditions exist:

Only Train A of ECCS equipment is running Operators had to manually initiate Containment Spray and Phase B isolation signal CETC readings of the five highest temperatures indicate 760 °F and rising RCS pressure is less than 100 psig Containment pressure is 10 psig and slowly lowering Containment radiation is 8 R/hr and slowly rising Containment Sump level (WR) indicates 35% and slowly rising The MET data indicates no precipitation with the wind from 320° at 6 mph and NO offsite release is occurring.

Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.

NOTE Simulator Indications are NOT applicable to this JPM NRC2004-A8.doc Page 1 of 1 Revision 0