ML103130223

10.

1C4AOP1

11.

13.

1ES-1.1

14.

15.

On the NIS panel, verify Scaler Timer power switch is in Off position.

5.

Boration Card -

6.

4701 5-01 03 Set Turbine Control HMI Displays as follows:

1.

2.

U1 Turb Aux Cont (48088) to:

Turb Overview

3.

DEHC alarms cleared Turbine Control in FSP mode U1 E-H Turb Cont STA 2 (48087) to:

U1 E-H Turb Cont STA 1 ( 48086) to:

Control Valve Overview On Line Control Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 25 of 29 2010 ILT NRC SIMULATOR EVALUATION #1, Rev. 0 Post-Scenario Checklist EOOS computer is cleared of information added during the scenario Computer generated PINGP 577 cleared.

Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

2.

F3-2.1 Bases -

3.

F3-2 COPY 275

-4.

SWI 0-28

5.

Boration Card -

6.

4701 5-01 03

16.

1C12.1 1 7.

4701 3-0305

18.

1C51.2

19.

1C4AOPl

20.

21.

-22.

1ES-1.1

23.

24.

Protected equipment tags in place:

1.

None Remove Caution Tags to the following control switches:

-1.

None Board-mounted EAL Table is cleaned All books, note pads, and calculators put away End Of Dav Checklist Signdplacards removed and put away unless normal simulator configuration Floor PCs logged off if simulator will not be used again that day Instructor station returned to normal with all books, paper, and etc. put away Headsets turned off and put away if simulator will not be used again that day Simulator reset to IC-1 0 unless another IC will be used for further training Simulator placed in DORT if simulator will not be used again that day Recorder power "OFF" if simulator will not be used again that day Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 26 of 29 201 0 ILT NRC SIMULATOR EVALUATION #1, Rev. 0 RAD MONITORS 00s OUTSTANDING SPS i

RETENTION: 7 Days DATE:

DAYNIGHT SHIFT: Day ANNUNCIATORS 00s FIRE DET / PROT EQP IMPAIRMENTS CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/FECH SPEC REQUIRED ACTION STATEMENTS I None I

OPERATIONAL PLANS FOR COMI~G SHIFT Raise power from 50% to 60%.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 27 of 29 2010 ILT NRC SIMULATOR EVALUATION #1, Rev. 0 Reactivitv Plan The crew has been directed to raise reactor power from 50% to 60%.

Prior to simulator:

verify the reactivity plan completed by the off going reactor operator complete a Pre-Job Brief Current conditions are:

Power level: 50%

Xenon: Increasing, diluting 40 gals approximately every 10 minutes Control Rod Position: Bank D Q 173 steps Boron Concentration: 1023 ppm Core Exposure: 10,000 MWD/MTU Target: Power Level: 60%

Rate: 0.5% /minute Control Mode: First Stage Pressure (FSP) with Rod Control in Manual BoratiodDilution: 60 gal dilutions every two minutes Reactivitv Prediction:

Change in Power Defect: 142 pcm Differential Boron Worth: -7.8 pcdppm Calculated RCS PPM change: 18.2 ppm Assumed half rods and half RMU addition Calculated Boric Acid / Reactor Makeup Water addition: 9 ppm change = 272 gals RMU Calculated final Control Rod Position : Bank D Q 182 steps Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 28 of 29 2010 ILT NRC SIMULATOR EVALUATION #1, Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

The scenario contains objectives for the desired tasks and relevant human performance tools.

The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Plant PRA initiating events, important equipment, and important tasks are identified.

Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

recommendations are clearly identified and fully addressed.*

The scenario includes related industry experience. SOER, SER and similar OE The scenario guide incorporates verification of Operator Fundamental application.*

Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes X

Yes Yes Yes Yes X

No No No No No No No No X

No X

No Developer and Reviewer: Once checklist is completed and deficiencies are correC.3dl sign i,,e cover page.

For evaluations these items may be marked NO without justification.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 29 of 29 2010 ILT NRC SIMULATOR EVALUATION #1, Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1.

2.

3.

4.

5.

6.

7.

The desired initial condition(s) could be achieved.

All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

During the simulator scenario, observed changes corresponded to expected plant response.

Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes X

No No No No No No No Discrepancies noted (Check none or list items found)

SMAR = Simulator Action Request X None SMAR:

SMAR:

Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 1 of 22

@ xce'Energy SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND 2010 ILT NRC SIMULATOR SEG #

EVALUATION #2 2010 ILT NRC SIMULATOR EVALUATION SEGTITLE:

2 REV.#

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

INITIAL LICENSE OPERATOR TRAINING FL-ILT TOTAL TIME: 1.5 HOUR Additional site-specific signatures may be added as desired.

Developed by:

Mike Fish 12/11/09 Instructor Date Reviewed by:

John DuBose l a 1 3/09 (Simulator Scenario Development Checklist.)

Instructor Date Validated by:

John DuBose l a 1 3/09 (Simulator Scenario Validation Checklist.)

Validation Lead Instructor Date Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 2 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Guide Reauirements Goal of Training:

Learn i n g 0 bjectives:

During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1.

During all plant operating conditions, demonstrate the ability to perform communications, verification practices (STAR and peer checks), procedure use, alarm response, reactivity control, and crew briefs in accordance with Operations Standards and Expectations.

Diagnose and respond to a Main Feedwater pump trip per C47.

Diagnose and respond to N44 failing high per C47 and 1C51.

Diagnose and respond to Loss of Instrument Bus 113 per 1 E-0, 1 ES-0.1, C47 and 1 C20.8 AOPl.

Diagnose and respond to MSLB per 1 E-0, 1 E-2, 1 E-1, and Diagnose and respond to a failure of both MSlVs to close per

2.

3.

4.

5.

6.

1 FR-P. 1.

1 E-0.

Prerequisites:

1.

NONE

1.

Full Scope Simulator

2.

Lead Evaluator

3.

Booth Operator

4.

Backup Communicator Training Resources:

References:

1.

NONE Commitments: 1.

NONE Eva1 uat io n Method:

This is an evaluation scenario Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 3 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 None - Evaluation Scenario Operating Experience:

Initiating Event with Core Damage Frequencv:

Related PRA None Information:

Important Components:

11 CC pump Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 4 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

None. This is an evaluation scenario and no credit will be taken for tasks performed.

GENERAL EXPECTATIONS Over the duration of the scenario, monitor conduct of operations standards and crew performance for adherence to the Operations department Standards and 0

Expectations:

0 0

Performance for adherence to 0

administrative procedural requirements and operations management expectations:

0 Communications Verification Practices (STAR and Peer Checks)

Procedure Use Alarm Response Reactivity Control Crew Briefs Reportability of the malfunction or event Notifications to the Operations Manager and NRC Resident Inspector per SWI-O-28 Notification to the Duty Station Manager per operations management request Tech Spec implementation; interpretation; and documentation of decision made, actions taken, and the basis for decisions made and actions taken Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 5 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 QUANTITATIVE AlTRlBUTES (Use this form for Evaluations only.)

Malfunctions:

Before Of Entry;

1. 1 1 Main Feedwater Pump Trip.

2. N44 Power Range NI Fails High

3. Loss of Power to Instrument Bus 113 After EOP Entry:

1. 1 1/12 MSlVs Fail to Automatically Close Normal Events:

1. None Abnormal Events:

1. 11 Main Feedwater Pump Trip.

2. N44 Power Range NI Fails High

3. Loss of Power to Instrument Bus 11 3 Maior Transients:

1. MSLB - 11 Steam Generator faults inside Containment Critical Tasks:

1. E-0 -- P: Manually close MSlVs before transition out of E-0.

2. E TCOA4 Control ARN flow within 38 minutes following a Reactor Trip.

(SWI 0-35 identified Time Critical Operator Action).

3. E-2 -- A: Isolate the faulted STEAM GENERATOR before transition out of E-2.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 6 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Standard (Specific) IC sets:

0, IC-25

2. The following equipment is 00s:

11 CC pump SEQUENCE OF EVENTS:

Event 1 : 11 Main Feedwater Pump Trip 0

11 Main Feedwater Pump trip.

0 The crew will respond per 1 C4 AOP1.

0 The crew will respond per C47.

Event 2: N-44 Power Ranne NI Fails High N-44 will fail high, resulting in automatic inward rod motion.

The crew will respond per C47 and 1C51 to remove the instrument from service.

Event 3: Loss of Power to Instrument Bus 113 0

The loss of power to Instrument Bus 113 will a cause reactor trip due to 2 of 4 logic with power range Nls due to N-44 being 00s.

0 The crew will respond to the reactor trip per 1 E-0 and transition to 1 ES-0.1.

0 The SS will have the Lead Operator perform actions in 1C20.8 AOP1 to restore power to Instrument Bus 113 from Panel 117.

Event 4: MSLB 0

11 Steam Generator faults inside Containment.

0 The crew will respond per 1 E-0, 1 E-2, 1 E-1, and 1 FR-P.l.

Event 5: 11M 2 MSlVs fail to automaticallv close During the Main Steam Line Break, 1 1/12 MSlVs fail to automatically close.

The crew will manually close 11 MSlV using Attachment L of 1 E-0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Page 7 of 22 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES INITIAL CONDITIONS:

0 Standard IC-25 Mode: 1 Exposure: MOC Power: 71%

Boron: (CB): 706 Temperature: 556°F Pressure: 2235 psig 0

Xenon: Increasing Generator: -388 MWe Rods: Bank D Q 187, all others at 228 CREW POS EXPECTEDSTUDENTRESPONSES Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 8 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1.

SIMULATOR SET UP

a. Set up the simulator to IC-25

b. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

c. Complete the Simulator Setup Checklist.

a. The Simulator Pre-Brief is conducted prior to the

2.

Simulator Pre-brief:

crew entering the simulator.

3.

COMPLETE TURNOVER:

a. UNIT 1 LPEO / PEO TURNOVER LOG.

b. PRA Printout.

a.

Verify crew performs walk down of control boards and reviews turnover checklists.

CREW-POS CREW EXPECTED STUDENT RESPONSES Review the following with the off-going operator:

Unit 1 LPEO / PEO Turnover Log PRA printout Walk-down the control boards and ask questions as appropriate Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 9 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ EVENT 1 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES I. When the crew has assumed the duty, and at the discretion of the Lead Evaluator, then enter the 11 Feedwater Pump trip (Relative Order 7, Trigger 7)

a. If asked to investigate the 11 FW pump lockout, acknowledge the request THEN wait 3 minutes and report overcurrent relay is actuated on BKR-11-3, 1 1 feedwater Pump.

b. If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

If contacted as the FIN Team Supervisor, inform the crew that you will write a work order and assign an Electrical Supervisor to investigate.

c.

CREW POS LEAD LEAD/

RO EXPECTEDSTUDENTRESPONSES 47010-0101,ll FEEDWATER PUMP LOCKED OUT 0

If reactor power is greater than 85%, then trip the reactor and go to 1 E-0.

0 If turbine power is greater than 330 MWe, then reduce to less than 330 MWe per 1 C1.4 AOP1.

1C1.4 AOP1, RAPID POWER REDUCTION 0

If any reactor or turbine trip setpoint is reached, then verify the reactor is tripped and go to 1 E-0.

Place or verify the following control systems in automatic or control in manual per C7:

o Rod control o Steamdump o Pressurizer pressure control o Pressurizer level control.

o Place pressurizer heaters ON.

o Reduce turbine load to the desired value using one of the following methods:

Automatic

. Manual Borate the RCS as necessary to maintain control rods above the insertion limit and control delta I within limits.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Paae 10 of 22 w

2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ EVENT 2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

5.

6.

When the crew has completed the power reduction, placed rod control in AUTO, and/or at the discretion of the Lead Evaluator, enter the N44 Power Range NI high failure (Relative Order 2, Event Trigger 2)

The following indications will be observed:

a.

Indicator N-44 indicates off-scale high

b.

Control Rods insert in AUTO

c.

Annunciators:

1) 47013-0101, NIS POWER RANGE POSITIVE FLUX RATE CHANNEL ALERT SETPOINT CHANNEL ALERT OVERPOWER ROD WITHDRAWAL STOP DEVIATION CHECK TYPER (Possible)

CHECK TYPER (Possible)

2) 47013-0102, NIS POWER RANGE HI

3) 47013-0103, NIS POWER RANGE

4) 47013-0203, NIS POWER RANGE CHANNEL

5) 4701 3-0303, COMPUTER ALARM DELTA I

6) 4701 3-0403, COMPUTER ALARM FLUX TILT

d.

If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 4 5 minutes.

(Note: the OTDT and OTDT rod stop bistables will not be tripped during this scenario. )

CREW POS RO LEAD LEAD ss EXPECTED STUDENT RESPONSES NOTE: As a plant stabilization action the crew is expected to take rod control to manual once instrument malfunction is diagnosed.

4701 3-01 01, NIS POWER RANGE POSITIVE FLUX RATE CHANNEL ALERT Determine initiating channel(@ by observing NIS indications If due to power range channel failure, Then refer to 1 C51 1 C51.4, INSTRUMENT FAILURE GUIDE Place rod control in manual and maintain Tave at Tref using rods. Adjust turbine load as necessary o Rod withdrawal will not be possible until after Rod Stop is bypassed Enter T.S. LCO 3.3.1 Condition A and Table 3.3.1-1 Functions 2a, 2b, 3a, 3b, 6, 16b.1, 16c, 16d, 16e.

Remove N-44 from service per C51 Restore Tavg to Tref using control rods and then place rod control to AUTO 0

Direct I&C to trip the bistables 0

Initiate temporary logs and required surveillance procedures per C51 0

Initiate repair activities Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

.r Paae 11 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ EVENT 3 3eten tion:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS INSTRUCTOR N E

7. When the crew has completed the actions associated with the N44 Power Range NI failure, and/or at the discretion of the Lead Evaluator, enter the Loss of Instrument Bus 1 13 (Relative Order 3, Event Trigger

8.

The reactor will receive a automatic trip due to N44 being 00s and the loss of the instrument bus. 2 of 4 PR NI will reach the reactor trip setpoint due to the failure.

9.

The crew will perform actions to restore power to Instrument Bus 113 once the plant is stable in 1 ES-0.1. The SS should assign the LEAD operator to perform actions in 1C20.8 AOP1 and the SS should continue in 1 ES-0.1.

3).

10. Upon hearing the announcement of Reactor Trip, or when called as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, enter CAEP - Att E-O to start the isolation (Relative Order Sa). When the isolation is complete, inform the crew that MSRs are isolated.

ife of Plant CREW POS CREW CREW Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES 1 E-0, REACTOR TRIP OR SAFETY INJECTION Verify Reactor Trip 0

Verify turbine Trip Verify Both Safeguards Buses - Energized 0

Check if SI is actuated o Transition to 1 ES-0.1, Reactor Trip Recovery, due to no SI.

0 Continue actions in 1 ES-0.1 1 ES-0.1, REACTOR TRIP RECOVERY Check RCS Temperatures.

Check FW Status.

Note: Due to the loss of Instrument Bus 113 the crew must take manual control of Pressurizer level and pressure.

Check PRZR Level Control.

Check PRZR Pressure Control.

Critical Task: TCOA4 Control AFW flow within 38 minutes following a Reactor Trip.

(S WI 0-35 identified Time Critical Operator Action).

Check SG Levels.

Verify Offsite Power Available.

Check RCP Status - At Least One Running.

Check If Source Range Detectors Should Be Energized.

Announce Unit 1 Reactor Trip.

Transfer Steam Dump To Pressure Mode.

Check Cooling Water Header Pressures.

Notify turbine Building Operator To Isolate Unit 1 MSRs Per Attachment J.

Verify All Control Rods Inserted.

QF-1075-02 Rev. 3 (FP-T-SAT-75) e Pane 12 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS INSTRUCTOR NOTES

11. When Turbine Building operator is contacted to transfer the source breaker to the INTERRUPTABLE PANEL 117 position for Instrument Bus 1 13 enter (Relative Order 4, Event Trigger 4) in 1 minute.

CREW POS CREW LEAD LEAD EXPECTEDSTUDENTRESPONSES Maintain Stable Plant Conditions.

Open Turbine Drain Valves.

Align AMSAC/DSS System.

Perform Administrative Notifications.

Check If AFW Pumps Can Be Stopped.

Align Generator Breakers.

Complete Part A Of PINGP 662, Reactor Trip Report Perform Applicable Shutdown Steps Of 1 C1.4.

Determine If Natural Circulation Cooldown Is Required.

47005-0307, PNL 11 3 INSTR BUS 11 1 (BLUE) LOSS OF VOLTAGE Verify bus undervoltage Place Rod Control in MANUAL At the instrument bus panel, transfer the main breaker for Panel 113 (Blue) to PANEL 117 ALTERNATE SOURCE Position per 1 C20.8 AOPl, ABNORMAL OPERATION, INSTRUMENT AC INVERTERS 1 C20.8 AOP1, ABNORMAL OPERATION, INSTRUMENT AC INVERTERS 0

If a loss of voltage to Instrument Bus 11 3 has occurred, Then perform the following:

o Place Rod Control in MANUAL o At the instrument Bus 113 Panel, transfer the source breaker to the INTERRUPTABLE PANEL 1 17 position Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) a Pane 13 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ EVENT 4 SCENARIO TIME-LINE:

SE~UENCE OF EVENTSTNSTRUCTOR NoTEs 1 1. When the crew has restore power to Instrument Bus 1 13, and/or at the discretion of the Lead Evaluator enter the 11 S/G Main Steam Line Break (Relative Order 5, Trigger 5).

a.

When called as the Turbine Building Operator to verify the status of Turbine Building Roof Exhausters, report that the Turbine Building Roof Exhausters are all secured.

Upon hearing the announcement of Reactor Trip, or wfim m W as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, enter CAEP - Att E-0 to start the isolation (Relative Order Sa). When the isolation is complete, inform the crew that MSRs are isolated.

b.

NOTE: As part of Att. L step 6b the crew will also manually close the Instrument Air to Containment Valves as part of the Failure of the MSIVs to isolate.

12. 1 E-2 response

a.

If asked as the chemist to take secondary samples, state that you will begin samples immediately.

CREW POS CREW LEAD LEAD CREW EXPECTEDSTUDENTRESPONSES 1 E-0, REACTOR TRIP OR SAFETY INJECTION 0

Verify Reactor Trip.

Verify Turbine Trip.

0 Verify Both Safeguards Buses Energized.

Check if SI is actuated.

0 Check if SI is required.

Critical Task: Manually close MSIVs before transition 0

Verify Status of Equipment on Attachment L.

Critical Task: TCOAJ Control AFW flow within 38 minutes following a Reactor Trip.

(S WI 0-35 identified 7Tme Critical Operator Action).

0 Check AFW Status.

0 Check RCS Temperatures.

0 Check PRZR PORVs and Spray Valves.

0 Check if RCPs should be stopped.

0 Check if SGs are not faulted.

0 Go to 1 E-2, Faulted Steam Generator Isolation.

Out of 1E-0.

1 E-2, FAULTED STEAM GENERATOR ISOLATION Critical Task: Isolate the faulted Steam Generator before transition out of 1 E-2.

0 Check MSlV and Bypass Valve on affected SG(s) -

CLOSED.

0 Check if either SG is not faulted.

0 Identify faulted SG.

0 Isolate faulted SG.

0 Isolate Main Feedline 0

Isolate AFW flow 0

Close steam supply valve to TDAFWP Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Paae 14 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS CREW CREW EXPECTEDSTUDENTRESPONSES 0

Verify SG PORV closed.

0 Verify SGB isolation valve closed.

0 Check CST level greater than 10000 gallons.

0 Check secondary radiation.

GO to 1E-1.

1 E-1, LOSS OF REACTOR OR SECONDARY COOLANT 0

Check If RCPs Should Be Stopped.

0 Check If SGs Are Not Faulted.

0 Check Intact SG Levels.

0 Check Secondary Radiation - Normal.

0 Check PRZR PORVs And Block Valves.

0 Reset SI.

0 Reset Containment Isolation.

0 Established Instrument Air To Containment.

0 Check Power Supply To Charging Pumps - Offsite Power Available.

0 Check If Charging Flow Has Been Established.

0 Check If SI Flow Should Be Terminated.

Note: Crew may transition to 1 ES-0.2, SI Termination based on Information Page.

o Go To 1 ES-0.2, SI Termination 1 ES-0.2, SI TERMINATION 0

Reset SI.

0 Reset Containment Isolation.

0 Established Instrument Air To Containment.

0 Stop Safeguards Pumps.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Page 15 of 22 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES Note: Crew may transition to 1 FR-P.l due to a integrity CSFST orange or red path.

13. When the crew has stopped safeguards pumps in 1 ES-0.2 or 1 FR-P.l, or at the discretion of the lead evaluator, then place the simulator in FREEZE and inform the crew that training has the duty.

14. E_mergency Plan Classification 0'

None CREW POS CREW EXPECTEDSTUDENTRESPONSES 1 FR-P.l, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION.

~

Check RCS pressure - greater than 550 psig.

Check RCS cold leg temperatures - stable or increasing.

Check PORV block valves - power available and at least one block valve open.

Check if PORVs should be closed.

Checkif-SI shouldbet&mxGd.-

Reset SI.

Reset Containment Isolation.

Establish Instrument Air to Containment.

Stop Safeguards pumps.

Check SI pumps - any running.

~

-~

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Type MALF MALF MALF Page 16 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Code RP06 M I 1 3A N105D I

2 I

SIMN103 Severity Or Value I

I Event Trigger Timing 1

5 1

100 I

5a I

5 Main Steam Line Break Perform Attachment J SIMULATOR INPUT

SUMMARY

I I

ED1 68 MSO1 A 100 I

2 I

Description MSlVs fail to isolate 11 RN pump trip N44 Summing Amp failure high PNL117 I Source to 125VAC Panel 11 3 Transfer Switch Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 17 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 SIMULATOR SETUP CHECKLIST Standard IC-25 Before Training Simulator Status:

1.

"Training Load"

2.

Step counters "ON"

3.

Alarm sound "ON"

4.

Reset to IC-25

5.

Speed: "REAL" Cycle recorder power "OFF" then back "ON" to clear Yokogawa recorder memory Verify Summary matches Simulator Input Summary page in the SEG Boric Acid/RMU integrators set to: BA: 3, RMU: l0, and reset MOC AI sheet displayed on C panel Check all ERCS alarms are cleared (ATWS scenario)

MOC Reactivity Briefing sheet available at Reactor Operator Desk Chart recorders operating and forwarded Turnover sheet/PRA sheet Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

Update Control Board Placards:

1.

High Flux At Shutdown Alarm Setpoint placards: 1400 cps

2.

Feedwater regulating valve position placard: 66/65. 67/64

3.

RCS boron on the CVCS panel placard: 734 ppm

4.

Turbine referenceketter values on the CVCS panel set to current (Target/Demand on-line positions)

5.

Shift Reactivity Guidance placard: BA: 2.3 gallons, RMU: 67 gallons Magnetic placards in place:

1.

2.

3.

4.

Protected equipment tags in place:

1.

12CCpump Attach Caution Tags to the following control switches:

1.

Place CS-46036, 11 CC pump control switch in "PULLOUT" and attach caution tag ERCS driven recorders are on-scale (RCS temperature scaled to 5508 F to 5609 F)

ERCS alarm screen operating and alarms reset All ERCS terminals operating and set as follows:

11 BA TANK "Lined Up For Service" 11 BA PUMP "Lined Up To 11 BA Tank" CC TO SFP MV-32115 "In Service" Blowdown 46470 "SGB To CDSR" VARS Alarm Summary Page Group OP31-Ul AFD SAS (XS11)

TPM Group QP CCDATA QP LOADFOLL Group RADMON-U1 Alarm Summary Page Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 18 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0

- - ERCS single point displays:

1 T0499A 1 U1613A 1 V4501 A 1 Q0340A ERCS TPM set (NIS - Auto Scaling - LEFM)

- - Pens/Paper/Markers available on the simulator

- - Board-mounted EAL Table is cleaned

- EAL sticker books in F3-2 are checked for missing stickers

- Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

2.

F3-2.1 Bases -

3.

F3-2 COPY 275

-4.

SWI 0-28

-5.

Boration Card -

6.

7.

1ES-0.1

8.

1E-2

9.

10.

1ES-0.2

11.

12.

C47010-0101

13.

C47013-0101 -

14.

C47013-0102 -

15.

C47005-0307

18.

TS 3.3.1

16.

1C4AOPl

17.

lC51.4

19.

TS 3.8.7

20.

lC20.8AOPl -

21.

- - Set Turbine Control HMI Displays as follows:

- On the NIS panel, verify Scaler Timer power switch is in Off position.

1.

2.

U1 Turb Aux Cont (48088) to:

Turb Overview

3.

- - DEHC alarms cleared U1 E-H Turb Cont STA 2 (48087) to:

U1 E-H Turb Cont STA 1 ( 48086) to:

Control Valve Overview On Line Control Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 19 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Post-Scenario Checklist EOOS computer is cleared of information added during the scenario Computer generated PINGP 577 cleared.

Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

-2.

F3-2.1 Bases -

3.

F3-2 COPY 275

5.

Boration Card -

6.

-4.

SWI 0-28

7.

1ES-0.1

8.

1E-2

-9.

10.

1ES-0.2

11.

12.

C47010-0101

13.

C47013-0101 -

14.

C47013-0102 -

15.

C47005-0307

17.

1C51.4

18.

TS 3.3.1

16.

1C4AOP1

19.

TS 3.8.7

20.

1C20.8AOPl -

21.

Protected equipment tags in place:

1.

Remove Caution Tags to the following control switches:

1.

11 CCpump Board-mounted EAL Table is cleaned All books, note pads, and calculators put away End Of Dav Checklist

- - Signs/placards removed and put away unless normal simulator configuration Floor PCs logged off if simulator will not be used again that day Instructor station returned to normal with all books, paper, and etc. put away Headsets turned off and put away if simulator will not be used again that day Simulator reset to IC-10 unless another IC will be used for further training Simulator placed in DORT if simulator will not be used again that day Recorder power "OFF" if simulator will not be used again that day Remove tag from 12 CC pump Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 RAD MONITORS 00s 0 UTSTAN DI NG S PS Page 20 of 22 ANNUNCIATORS 00s FIRE DET / PROT EQP IMPAIRMENTS RETENTION: 7 Days DATE:

DAYNGHT S H R : Day CAT 1 VENT OPENINGS: 0 ft?

SYSTEM CONDITION: GREEN

~

~~

SAFEGUARDS EQUIPMENT OOSFECH SPEC REQUIRED ACTION STATEMENTS 11 CC pump is 00s for pump seal replacement. Entered T.S. 3.7.7 Condition A at 0400 with OPERATIONAL PLANS FOR COMtNG SHIFT Suspend Tech Spec required shutdown due to repair of 12 SI Pump.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 21 of 22 201 0 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

X Yes

2. The scenario identifies key parameter response, expected alarms, and Yes X

automatic actions associated with the induced perturbations.

3. The scenario content adequately addresses the desired tasks, through Yes X

simulator performance, instruotor-led training freezes, or both.

4. Plant PRA initiating events, important equipment, and important tasks are Yes identified.

X

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Yes Assessment.

X

6. The scenario contains procedurally driven success paths. Procedural Yes discrepancies are identified and corrected before training is given.

X

7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes x

Yes

9. The scenario guide incorporates verification of Operator Fundamental Yes application.*

10. Training elements and specific human performance elements are addressed Yes in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

11. For evaluations, it has been verified that without operator action the critical Yes tasks will be failed.

X No No No No No No No No X

No X

No Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 22 of 22 2010 ILT NRC SIMULATOR EVALUATION #2, Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved.

2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

5. During the simulator scenario, observed changes corresponded to expected plant response.

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request

7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes X

No No No No No No No Discrepancies noted (Check "none" or list items found)

SMAR = Simulator Action Request None SMAR:

SMAR:

Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 1 of 26

@ xce'Energy SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND 2010 ILT NRC SIMULATOR SEG #

EVALUATION #3 2010 ILT NRC SIMULATOR EVALUATION SEG TITLE:

3 REV.#

0 PROGRAM:

INITIAL LICENSE OPERATOR TRAINING FL-ILT COURSE:

INITIAL LICENSE OPERATOR TRAINING FL-ILT TOTAL TIME: 1.5 HOUR Additional site-specific signatures may be added as desired.

Developed by:

John DuBose 10/30/09 Instructor Date Reviewed by:

Mike Fish 12/1 3/09 (Simulator Scenario Development Checklist.)

Validated by:

Mike Fish 12/13/09 (Simulator Scenario Validation Checklist.)

Instructor Date Validation Lead Instructor Date Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 2 of 26 Goal of Training:

Learning 0 bject ives:

201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Guide Requirements During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1.

During all plant operating conditions, demonstrate the ability to perform communications, verification practices (STAR and peer checks), procedure use, alarm response, reactivity control, and crew briefs in accordance with Operations Standards and Expectations.

Raise power to the Point of Adding Heat IAW 1C1.2.

Transfer running Condensate Pumps per 1 C28.3.

Diagnose and respond to failure of 122 instrument Air Compressor per C47 and 1 C34 AOP1.

Diagnose and respond to a Pressurizer Heater Backup Group 1 B Breaker Trip per 1 C20.6.

Diagnose and respond to PT-431 blue channel Pressurizer Pressure failure per C47 and 1 C51.3.

Diagnose and respond to a Steam Generator Tube Rupture per 1 E-0 and 1 E-3.

Diagnose and respond to a Cooling Water pump failing to auto start per 1 E-0 Attachment L.

2.

3.

4.

5.

6.

7.

8.

Prerequisites:

1.

NONE

1.

Full ScopeSimulator

2.

Lead Evaluator

3. Booth Operator

4.

Backup Communicator Training Resources :

References:

1.

NONE Commitments:

1.

NONE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 3 of 26 Evaluation Method:

2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 This is an evaluation scenario Operating Experience:

None - Evaluation Scenario Related PRA Information:

lnitiatinn Event with Core Damage Frequencv:

SGTR (2%)

Important Components:

11 CLG WTR PMP 12 DD CLG WTR PMP 121 MD CLG WTR PMP 122 STA AIR COMPR 123 STA AIR COMPR Important Operator Actions with Task Number:

Cooldown and depressurize RCS from SGTR before SG overfill (2%)

CRO 3010040601 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 4 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

None. This is an evaluation scenario and no credit will be taken for tasks performed.

GENERAL EXPECTATIONS Over the duration of the scenario, monitor crew performance for adherence to the conduct of operations standards and Operations department Standards and Expectations:

Performance for adherence to administrative procedural requirements and operations management expectations:

e e

0 e

e e

e 0

Communications Verification Practices (STAR and Peer Checks)

Procedure Use Alarm Response Reactivity Control Crew Briefs Reportability of the malfunction or event Notifications to the Operations Manager and NRC Resident Inspector per SWI-O-28 Notification to the Duty Station Manager per operations management request Tech Spec implementation; interpretation; and documentation of decision made, actions taken, and the basis for decisions made and actions taken Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 5 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 QUANTITATIVE AITRIBUTES Malfunctions:

Before EOP Entry:

1. 122 Air Compressor fails.

2. Pressurizer Heater Backup Group 1 B Breaker Trip.

3. PT-431 Blue Channel Pressurizer Pressure fails.

After EOP Entry:

1. Failure of the SI signal to the Cooling Water system.

Normal Events:

1. Raise power to the Point of Adding Heat.

2. Transfer running Condensate Pumps.

Ab nor mal Events :

1. 122 Instrument Air Compressor fails.

2. Pressurizer Heater Backup Group 1 B Breaker Trip.

3. PT-431 Blue Channel Pressurizer Pressure fails Maior Transients:

1. SGTR Critical Tasks:

1. E TCOA4: Control A f W flow within 38 minutes following a Reactor trip.

(SWI 0-35 identified Time Critical Operator Action).

2. E A: Isolate feedwater flow into and steam flow from the ruptured Steam Generator before a transition to ECA-3.1 occurs.

3. E 6: Establish/maintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or such that an extreme or severe challenge to the Subcriticality and/or the Integrity CSF occurs.

4. E C: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.

5. E D: Terminate SI prior to overfilling the ruptured Steam Generator.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 6 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Standard IC sets:

IC-26

2. The following equipment is 00s:

13 Charging Pump 00s SEQUENCE OF EVENTS:

Event 1 : Raise power to the POAH Candidates will perform a pre-job brief prior to entering the Control Room.

Power will be raised to the POAH.

The crew will start 12 Condensate Pump and stop 11 Condensate Pump for Filter Demin Support.

Event 2: 122 Air compressor fails.

122 Instrument Air Compressor fails and 123 Instrument Air Compressor fails to function au tomatical I y.

The Crew will respond per C47 and C34 AOP1, Loss of Instrument Air to start 123 Instrument Air Compressor.

Event 3: Pressurizer Heater Backup Group 1 B Breaker Trip Pressurizer Heater Backup Group 1 B Breaker Trips.

The crew will respond to breaker failure per 1C20.6.

Event 4: PT-431 Pressurizer Pressure Channel fails high PT-431 fails high.

Both Pressurizer spray valves will fully open and Pressurizer heaters will de-energize.

The crew will take manual control of spray valves and close them.

The crew will respond per C47 and 1 C51.3 to change the controlling pressure channel and restore pressure.

Event 5: 12 Steam Generator tube rupture The Steam Generator tube leak will escalate to 400 GPM tube rupture.

The Crew will respond per 1 E-0 and 1 E-3.

Event 6: SI Siqnal to CL Svstem Fails To Actuate The SI signal to the Cooling Water system will fail.

The crew will manually align the Cooling Water system.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 7 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO TIME-LINE:

IC-26 Mode:2 0

Exposure: ZBC 0

Power: 1 E-8 amps 0

Boron: 1822 ppm 0

Temperature: -548°F 0

Pressure: -2235 psig 0

Xenon: Free 0

Rods: D Q 140 0

Generator: OFFLINE kRO)

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTEDSTUDENTRESPONSES POS INITIAL CONDITIONS:

(RO/LO Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

EVENT 1 a

Page 8 of 26

4.

When the crew has assumed the duty allow the crew to raise power to the point of adding heat and start 12 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1.

SIMULATOR SET UP

a. Set up the simulator to IC-26.

b. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary.

c. Comdete the Simulator SetuD Checklist.

2.

Simulator Pre-brief:

a.

b.

The Simulator Pre-Brief is conducted prior to the crew entering the simulator.

The crew will brief the power change and swapping of running condensate pumps prior to entering to Control Room.

3.

COMPLETE TURNOVER:

qetention: Life of Plant CREW POS CREW RO Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES

~~

Review the following with the off-goingoperator:

0 0

PRA printout 0

1 C1.2 UNIT 1 STARTUP PROCEDURE Unit 1 LPEO / PEO Turnover Log Walk-down the control boards and ask questions as appropriate 0

Starting at step 5.10.18 o Raise power to the POAH o When one or more intermediate range indicates greater than 1 E-9 amps, THEN verify ERCS is in Mode 2.

o Using ERCS display XS02 and C41, verify the Subcriticality CSF Activation Status is INACTIVE.

o Maintain reactor power between 0.5 and 2.0%.

QF-1075-02 Rev. 3 (FP-T-SAT-75) a Page 9 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SEQ letention:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

5. Follow along in 1 C28.3 step 5.6 and report back all local actions and checks are complete as requested after 2 minutes. None of the local checks are modeled in the simulator.

CREW POS LEAD ife of Plant EXPECTEDSTUDENTRESPONSES 1C28.3, UNIT 1 CONDENSATE SYSTEM Step 5.6 Swapping Condensate Pumps Checkcondensate pump oil cooling water flow using cooling water return sight glass.

Check condensate pump gland seal water flow using the following:

Flow through the gland seal water sight glass - local.

Seal water pressure is 18-24 psig -

local.

=

Following annunciators NOT LIT:

PUMP SEAL WATER LO PRESS PUMP SEAL WATER LO PRESS PUMP SEAL WATER LO PRESS Ensure the motor bearing of the condensate pump have the proper oil level - local.

Verify all condensate pump suction valves are open - local.

Notify the duty chemist that a condensate pump is being started and secondary chemistry may be affected.

Place the desired condensate pump selector switch in "MANUAL".

Start the desired condensate pump by placing 47009-0402,ll CONDENSATE 47009-0403,12 CONDENSATE 47009-0404,13 CONDENSATE Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Paae 10 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO TIME-LINE:

SEQ I SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS LEAD EXPECTEDSTUDENTRESPONSES the control switch to the START position.

Check the pump visually for excessive vibration or seal leakage.

Check the bearing temperatures and motor stator temperatures on ERCS Close the discharge vent of the running condensate pump - local.

Verify pump gland seal water pressure is 18-24 psig - local.

Verify heat removal fans have started - local.

Check condensate header pressure approx.

440 psig on 41 221 01,11/12/13 CD PMP DISCH HDR PI.

Stop the desired condensate pump by placing the control switch to the STOP position.

If desired, Then place a condensate pump selector switch in STANDBY.

Open the discharge vent valve of the condensate pump that was stopped - local.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 a

Page 11 of 26 SEQ EVENT 2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

6. When the crew has stabilized power at the POAH, and/or at the discretion of the Lead Evaluator enter the failure of 122 Air compressor.

(Relative Order 1, Trigger 1)

NOTE: The Booth operator MUST remove the fault on 123 Air Compressor when actions are taken to start 123 Air Compressor (Relative Order Ib)

a.

If directed to investigate 122 Air Compressor trip, local alarm, and/or C70551 Panel alarm, after 2 minutes perform (Relative Order la) report the following:

1 )

2)

If directed to investigate C47023-0101, 121 AIR COMPRESSOR LOCAL ALARM, after 2 minutes report the following:

1) 121 Air Dryer Purge Exhaust Isolation CV-31 960 Closed alarm was flashing on C75550 Panel and cleared when the alarm was acknowledged.

122 Air Compressor Low Oil Pressure alarm on Panel 70551.

122 air compressor appears intact with no visible damage

b.

c.

If directed to investigate 123 Air Compressor after it has been started, after 3 minutes, report the air compressor and air dryer are operating normally.

If contacted as the FIN team supervisor, inform the crew that you will write a work order and assign an Electrical Maintenance supervisor to investigate.

If desired, allow the crew to hold a crew brief.

d.

e.

CREW POS LEAD LEAD LEAD Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES NOTE: 123 Air Compressor may be manually started as a plant stabilization action.

0 Check station and instrument air header pressures.

0 Start addition compressors as necessary.

0 Dispatch operator to Panel 70551, 122 Station Air Compressor Annunciator Panel to perform the following:

C47023-0102,122 AIR COMPRESSOR LOCAL ALARM o Determine the initiating alarm.

o Respond per C70551,122 STATION AIR COMPRESSOR REMOTE ALARM RESPONSE.

C47023-0202,122 AIR COMPRESSOR AUTOMATIC START OR STOP 0

Check station and instrument air header pressures.

If alarm is due to normal cycling of standby air.

If instrument air pressure is low, then refer to C34 AOP1, LOSS OF INSTRUMENT AIR.

NOTE: The crew might refer to C34 AOP1, but no actions should be required. The loss of air is NOT expected to cause a reactor trip.

C47023-0101,121 AIR COMPRESSOR LOCAL ALARM 0

Check station and instrument air header pressures.

Start addition compressors as necessary.

Dispatch operator to Panel 70550, 121 Station Air Compressor Annunciator Panel to perform the following:

o Determine the initiating alarm.

Respond per C70550,122 STATION AIR COMPRESSOR REMOTE ALARM RESPONSE.

QF-1075-02 Rev. 3 (FP-T-SAT-75) a Page 12 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SEQ EVENT 3 qetention:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

7.

When the crew has completed actions for the 122 Air Compressor failure, and/or at the discretion of the Lead Evaluator enter the Pressurizer Heater Backup Group 1 B breaker failure (Relative Order 2, Trigger 2).

a.

If asked to investigate 122C breaker tripping, after 2 minutes report back the following:

1) Report workers in the Bus 122 room dropped a latter which hit the 122C breaker.

2) The 122C breaker has significant damage.

8.

9.

When crew places CS-46242 PRZR HEATER BACK-UP GROUP 1 B, to OFF remove OVERRIDE on control switch. (Relative Order 2 4 When crew informs Turbine Building operator to transfer to backup power supply Bus 180 per 1 C20.6 wait 3 minutes and then perform (Relative Order 3, Trigger 3).

ife of Plant CREW POS CREW RO LEAD ss RO Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01 EXPECTEDSTUDENTRESPONSES 0 Crewwill respond to ERCS alarm:

0 Determine Pressurizer Heater Backup Group 1 B breaker tripped BKRCHK: 1 YB122C PZR BU-HTR 1C20.6 UNIT 1 - 480V SYSTEM 0

Transfer Unit 1 Pressurizer Heater Group B from Bus 122 to Bus 180 per step 5.35 o

Enter T.S. LCO 3.4.9 Condition B.

o Place CS-46242 PRZR HEATER BACK-UP GROUP 1 B, to OFF.

o Have Turbine Building operator transfer power supplies locally o Place CS-46242 PRZR HEATER BACK-UP GROUP lB, to0N.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 13 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SEQ

~

EVENT 4 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

~

10. When the crew has completed actions for the pressurizer heater breaker failure, and/or at the discretion of the Lead Evaluator, then enter the Blue Channel Pressurizer pressure failing high (Relative Order 4, Trigger 4).

a.

If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 4 5 minutes.

(Note: bistables will not be tripped during this scenario.)

b. If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC Resident Inspector, Duty Station Manager, etc., as asked.

If contacted as the FIN team supervisor, inform the crew that you will write a work order and assign an I&C supervisor to investigate.

If desired, allow the crew to hold a crew brief.

c.

d.

CREW POS RO LEAD/

RO LEAD/

RO ss EXPECTEDSTUDENTRESPONSES NOTE: As a plant stabilization action the crew is expected to take manual control of the Pressurizer Spray Valves and close them.

0 0

C47012-0408, PRZR HVLO PRESS CHANNEL ALERT If necessary, then refer to 1 E-0 Check pressurizer pressure high or low.

Restore pressure to normal through use of heaters or sprays.

If necessary, then refer to 1 C51.

1 C51.3, Pressurizer Pressure 1 P-431 - HIGH 0

If the blue channel is selected on the przr pressure control selector switch then:

o Place pressurizer pressure controller in manual and stabilize pressure.

o Select position 2-1 (WHITE-RED) on channel selector switch.

o When pressure returned to normal with no deviation from setpoint, then return pressure control to automatic.

Verify pressurizer pressure recorder not selected to blue channel.

0 Refer to the following technical specification requirements:

o T.S. LCO 3.3.1 condition A & Table 3.3.1 -1 Functions 6, 8a, 8b.

o T.S. LCO 3.3.2 Condition A & Table 3.3.2-1 Function 1d.

o T.S. LCO 3.4.1.a 0

Trip bistables.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Pane 14 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO TIME-LINE:

SEQ EVENT 5 qetention:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

11. When the crew has completed actions for the pressurizer pressure channel failing high, and/or at the discretion of the Lead Evaluator, then enter the 12 Steam Generator Tube Rupture (Relative Order 5, Trigger 5).

a.

b.

C.

d, Upon hearing the announcement of reactor trip, or when called as Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, then enter Relative Order 6 (Schedule file E-0-Att-Jsch)

When called as the Turbine Building Operator to verify the status of Turbine Building Roof Exhausters, report that the Turbine Building Roof Exhausters are all secured.

Based on crew composition, at the discretion of the Lead Evaluator, personnel may be provided to perform Attachment L upon completion of all applicable critical tasks.

If asked to open FCU CLG WTR RTN BP VLVs perform (Relative Order 7, Trigger 7).

fe of Plant CREW POS CREW LEAD CREW Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES 1 E-0, REACTOR TRIP OR SAFETY INJECTION Verify Reactor Trip...

Verify Turbine Trip...

Verify Both Safeguards Buses - ENERGIZED.

Check if SI is actuated...

0 Verify status of equipment on ATTACHMENT L: SI alignment verification.

NOTE: During Att. L the failure of the SI signal to the cooling water system will require it to be aligned appropriately.

Critical Task: Control AFW flow within 38 minutes following a Reactor Trip. (S WI 0-35 identified Time Critical Operator Action).

Check AFW status:

o Verify total AFW flow - Greater than 200 gpm If SG wide range level greater than 50% in either SG...

If SG wide range level less than 50% in both SGs, then manually start AFW pumps and align valves, as necessary.

o Verify AFW pumps discharge pressure - greater than 900 psig.

o Check SG levels - Narrow range greater than 5%

o Control feed flow to maintain narrow range SG level between 5% and 50%

Critical Task: Establish and maintain 200 GPM A FW flow to the Steam Generator@) before transition out of E-0, unless the transition is to FR-H. 1, in which case the task must be initiated

QF-1075-02 Rev. 3 (FP-T-SAT-75) a Page 15 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SEQ 7

qetention:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES NOTE: Due to Zero Burn CordLow RCS activity and low initial reactor power radiation monitors may NOT alarm.

The crew may NOT identify the SGTR at step 11. Crew will identify ruptured SG at step 15 and go to 1 E-3.

fe of Plant CREW POS CREW CREW EXPECTED STUDENT RESPONSES before RCPs are manually tripped in accordance with step 2 of FR-H. 7.

Check RCS temperatures Check PRZR PORVs and Spray Valves...

Check if RCPs should be stopped...

Check if SGs are not faulted...

Check if SG tubes are not ruptured:

o Condenser air ejector radiation - normal o SGB radiation - normal o Main steamline radiation - normal Check if RCS is intact Check if SI flow should be terminated Initiate montoring of critical safety function status trees o NR level > 5%

o Control feed flow to maintain NR levels 5 - 50%

Check SG levels

=

If SG NR level in one SG continues to increase in an uncontrolled manner, GENERATOR TUBE RUPTURE, Step 1.

THEN go to 1 E-3, STEAM 1 E-3, STEAM GENERATOR TUBE RUPTURE Check if RCPs should be stopped...

Identify Ruptured SG...

Critical Task: Isolate feedwater flow into and steam flow from the ruptured Steam Generator before a Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Pane 16 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SCENARIO TIME-LINE:

SEQ I SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS CREW Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES transition to ECA-3.1 occurs.

0 Isolate flow from ruptured SG...

Check ruptured SG level...

Reset SI 0

Check ruptured SG pressure - Greater than 21 0 psig Critical Task: Establiswmaintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or such that an extreme or severe challenge to the Subcriticality andor the Integrity CSF occurs.

Initiate RCS Cooldown...

Note: During the cooldown, the SS must continue with step 8 to prepare the plant for depressurization.

Check intact SG level...

Check PRZR PORVs and Block Valves...

Reset SI Reset Containment Isolation Establish Instrument Air to containment Check if RHR pumps should be stopped...

Establish Charging flow...

Check if RCS Cooldown should be stopped...

Check Ruptured SG pressure - Stable or increasing Check RCS subcooling based on core exit T/Cs -

greater than 40°F Critical Task: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.

Depressurize RCS to minimize break flow and refill PRZR...

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 17 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

12. When the crew has stopped SI and verified it is not required, or at the discretion of the Lead Evaluator, then place the simulator in FREEZE and inform the crew that training has the duty.

13. Emergency Plan Classification Site Area Emergency - EAL SS1.l CREW POS CREW EXPECTED STUDENT RESPONSES Critical Task: Terminate SI prior to overfilling the ruptured Steam Generator.

Stop SI pumps Establish Charging flow...

Verify SI flow not required...

Check if SI flow should be terminated...

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Relative Order 0

0 0

1 1

la l b 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 System Or Severity Event Panel Drawing Type Code Or Value Trigger Timing Description FAILURE OF #123 AIR COMPRESSOR AUTO OVRD DI-46098SP TRUE MALF RP12 SI SIGNAL TO CL WATER MALF IA02 5

AIR USAGE IN PLANT MALF IA03B 1

1 LOSS OF AIR COMPRESSOR #122 122 AIR COMPRESSOR LOCAL ALRM 122 AIR COMPRESSOR LOCAL ALRM REMOVE FAULT ON #123 AIR COMPRESSOR CRY ANN MALF M47023:0102W ANN MALF M47023:0102W REMOVE OVRD DI-46098SP REMOVE Page 18 of 26 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Relative Order 7

Page 19 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 System Or Severity Event Panel Drawing Type Code Or Value Trigger Timing Description 11/13 FCU CLG WTR RTN BP VLV REMOTE CL105 OPEN 7

SIMULATOR INPUT

SUMMARY

I 7

12/14 FCU CLG WTR RTN BP VLV REMOTE CL106 OPEN 7

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 20 of 26 Page 20 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 SIMULATOR SETUP CHECKLIST Standard IC-26 Before Training Simulator Status:

1.

"Training Load"

2.

Step counters "ON"

3.

Alarm sound "ON"

4.

Reset to IC-26

5.

Speed: "REAL" Cycle recorder power "OFF then back "ON" to clear Yokogawa recorder memory Verify Summary matches Simulator Input Summary page in the SEG Boric Acid/RMU integrators set to: BA: 3, RMU: 10, and reset AI sheet displayed on C panel Check all ERCS alarms are cleared.

ZBC Reactivity Briefing sheet available at Reactor Operator Desk Chart recorders operating and forwarded Turnover sheet/PRA sheet Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

Update Control Board Placards:

1.

High Flux At Shutdown Alarm Setpoint placards: 1400 cps

2.

Feedwater regulating valve position placard: BLANK

3.

RCS boron on the CVCS panel placard: 1822 ppm

4.

Turbine referencehetter values on the CVCS panel set to current (Target/Demand on-line positions)

5.

Shift Reactivity Guidance placard: BA: 6.0 gallons, RMU: 67 gallons Magnetic placards in place:

1.

2.

3.

4.

11 BA TANK "Lined Up For Service" 11 BA PUMP "Lined Up To 11 BA Tank" CC TO SFP MV-32115 "In Service" Blowdown 46470 "SGB To CDSR" Protected equipment tags in place:

-1.

None Attach Caution Tags to the following control switches:

2.

13 Charging Pump in Pullout

1.

2.

3.

4.

CS-46362,4.16KV BUS 11 1 M XFMR CS-46363,4.16KV BUS 12 1 M XFMR CS-46364,4.16KV BUS 13 1 M XFMR CS-46365,4.16KV BUS 14 1 M XFMR ERCS driven recorders are on-scale (RCS temperature scaled to 54P F to 555'! F)

- - ERCS alarm screen operating and alarms reset All ERCS terminals operating and set as follows:

CONF VARS R02 Alarm Summary Page CONE1 Group OP31-Ul R03 AFD CONC SAS (XS11)

R04 TPM CONG1 Group QP CCDATA R05 QP LOADFOLL ERCS-RO1 Group RADMON-U1 R06 Alarm Summary Page Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 21 of 26 Page 21 of 26 e

e a

2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 ERCS single point displays:

CONB 1 T0499A 1U1613A CONE2 1 V4501 A 1 Q0340A ERCS TPM set (NIS - Auto Scaling - LEFM)

Pens/Paper/Markers available on the simulator Board-mounted EAL Table is cleaned EAL sticker books in F3-2 are checked for missing stickers Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

-2.

F3-2.1 Bases -

3.

F3-2 COPY 275

-4.

SWI 0-28

5.

Boration Card -

6.

C47012-0408

-7.

C47022-0108 -

8.

C47023-0202 -

9.

C47048:l R-15

-10.

C34AOP1

11.

1C20.6

12.

1C51.3

13.

14.

1E-3

15.

On the NIS panel, verify Scaler Timer power switch is in Off position.

Set Turbine Control HMI Displays as follows:

1.

2.

U1 Turb Aux Cont (48088) to:

Turb Overview

3.

U1 E-H Turb Cont STA 2 (48087) to:

U1 E-H Turb Cont STA 1 ( 48086) to:

Control Valve Overview On Line Control DEHC alarms cleared Markup 1 C1.2, UNIT 1 STARTUP PROCEDURE thru step 5.1 0.1 7 as complete Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 22 of 26 Page 22 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Post-Scenario Checklist EOOS computer is cleared of information added during the scenario Computer generated PINGP 577 cleared.

Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

-2.

F3-2.1 Bases -

3.

F3-2 COPY 275

4.

SWI 0-28

-5.

Boration Card -

6.

C47012-0408

-7.

C47022-0108 -

8.

C47023-0202 -

9.

C47048:l R-15

10.

C34AOPl

11.

1C20.6

12.

1C51.3

13.

14.

1E-3

15.

Protected equipment tags in place:

-1.

None Remove Caution Tags to the following control switches:

1.

13 Charging Pump

2.

3.

4.

5.

CS-46362,4.16KV BUS 11 1 M XFMR CS-46363,4.16KV BUS 12 1 M XFMR CS-46364,4.16KV BUS 13 1 M XFMR CS-46365,4.16KV BUS 14 1 M XFMR Board-mounted EAL Table is cleaned All books, note pads, and calculators put away End Of Dav Checklist Signs/placards removed and put away unless normal simulator configuration Floor PCs logged off if simulator will not be used again that day Instructor station returned to normal with all books, paper, and etc. put away Headsets turned off and put away if simulator will not be used again that day Simulator reset to IC-10 unless another IC will be used for further training Simulator placed in DORT if simulator will not be used again that day Recorder power "OFF" if simulator will not be used again that day Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 23 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Page 23 of 26 RETENTION: 7 Davs DATE:

DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS SYSTEM CONDITION: GREEN None I

PROTECTED EQUIPMENT I

None RAD MONITORS 00s ANNUNCIATORS 00s OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS OTHER EQUIPMENT 00s / STATUS 13 Charging Pump is 00s for motor replacement.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE Main Feedwater is in service.

Raise Power to Point of Adding Heat per 1C1.2, Unit 1 Start Procedure.

Start 12 Condensate Pumr, and stor, 11 Condensate mmr, for Filter Demin SUDDO~~.

NEW PROCEDURES / INSTRUCTIONS Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 24 of 26 Page 24 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Simulator session will include a power change.

Prior to simulator:

Provide crew a copy of 1C1.2, Unit 1 Startup Procedure marked up to step 5.10.17.

0 The crew should prepare a reactivity plan to raise power to Point of Adding Heat.

0 The crew should complete a Pre-Job Brief for the power increase.

Current conditions are:

Power level - 1 E-8 amps Xenon-None Control Rod Position - CBD Q 140 steps Boron Concentration - 1822 ppm Core Exposure - ZBC Desired Endpoint:

Power Level 2%

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 25 of 26 201 0 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Simulator Scenario Development Checklist Mark with an justification for the no answer or the corrective action needed to correct the discrepancy after the item.

Yes or No for any of the following. If the answer is No, include

1.

2.

3.

4.

5.

6.

7.

8.

9.

The scenario contains objectives for the desired tasks and relevant human performance tools.

The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Plant PRA initiating events, important equipment, and important tasks are identified.

Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

The scenario guide incorporates verification of Operator Fundamental application.*

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

tasks will be failed.

11. For evaluations, it has been verified that without operator action the critical Yes X

Yes X

Yes Yes Yes Yes X

No No No No No No No No X

No X

No Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 26 of 26 2010 ILT NRC SIMULATOR EVALUATION #3, Rev. 0 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1.

2.

3.

4.

5.

6.

7.

The desired initial condition(s) could be achieved.

Yes No X

All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes X

No All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X

No All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes No X

During the simulator scenario, observed changes corresponded to Yes No expected plant response.

X Did the scenario satisfy the learning or examination objectives without approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Yes No any significant simulator performance issues, or deviations from the X

Evaluation: The simulator is capable of being used to satisfy learning discrepancies, or deviation from the approved scenario sequence.

Yes No or examination objectives without exceptions, significant performance X

Discrepancies noted (Check none or list items found)

SMAR = Simulator Action Request 0 None SMAR:

SMAR:

Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 1 of 28

@ xce'Ener9y SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND 2010 ILT NRC SIMULATOR SEG #

EVALUATION #4 SEG TITLE:

PROGRAM:

COURSE:

2010 ILT NRC SIMULATOR EVALUATION

4 REV.#

0 INITIAL LICENSE OPERATOR TRAINING FL-ILT INITIAL LICENSE OPERATOR TRAINING FL-ILT TOTAL TIME: 1.5 HOUR Additional site-specific signatures may be added as desired.

Developed by:

Mike Fish 1 011 2/09 Instructor Date Reviewed by:

John DuBose 12/13/09 (Simulator Scenario Development Checklist.)

Validated by:

John DuBose 12/13/09 (Simulator Scenario Validation Checklist.)

Instructor Date Validation Lead lnstructor Date Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

I.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 2 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Guide Requirements During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

Goal of Training:

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

During all plant operating conditions, demonstrate the ability to

~

1.

Learning Objectives:

2.

3.

4.

5.

6.

7.

perform communications, verification practices (STAR and peer checks), procedure use, alarm response, reactivity control, and crew briefs in accordance with Operations Standards and Expectations.

Perform power reduction per 1 C1.4.

Remove Heater Drain Pump from service per 1 C28.4.

Diagnose and respond to a Loss of Bus 16 per C47 and 1C20.5 AOP2.

Diagnose and respond to a failed Steam Generator pressure transmitter per C47 and 1 C51.

Diagnose and respond to a Tave instrument failure per C47 and C51.

Diagnose and respond to a failure of the Reactor to automatically trip and an ATWS condition per 1 E-0 and 1 FR-s.1.

Prerequisites:

1.

NONE

1.

Full Scope Simulator

2.

Lead Evaluator

3.

Booth Operator

4.

Backup Communicator Training Resources:

References:

1.

NONE

~

~~

Commitments:

1.

NONE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 3 of 28 Eva I uat io n Method:

201 0 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 This is an evaluation scenario Operating Experience:

~

None - Evaluation Scenario Related PRA Information:

Initiating Event with Core Damage Frequencv:

None Important Components:

11 TDAFW pump Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

Page 4 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 None. This is an evaluation scenario and no credit will be taken for tasks performed.

GENERAL EXPECTATIONS Over the duration of the scenario, monitor crew performance for adherence to the conduct of operations standards and Operations department Standards and Expectations:

Performance for adherence to ad minist rative procedural requirements and operations management expectations:

Communications Verification Practices (STAR and Peer Checks)

Procedure Use Alarm Response Reactivity Control Crew Briefs Reportability of the malfunction or event Notifications to the Operations Manager and NRC Resident Inspector per SWI-O-28 Notification to the Duty Station Manager per operations management request Tech Spec implementation; interpretation; and documentation of decision made, actions taken, and the basis for decisions made and actions taken Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 5 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 QUANTITATIVE ATTRIBUTES a

Malfunctions:

Before Of Entry:

1. Loss of Bus 16

2. Steam Generator Pressure Transmitter PT-478 fails high (12 SG PORV Fails Open)

3. Tavg instrument fails high

4. Turbine Trip with ATWS After EOP Entry:

1. 11 TDAFW Pump Fails to Auto Start Normal Events:

1. Reduce power from 100% to 90% per 1 C1.4.

2. Stop 12 Heater Drain Pump for Brush inspection per 1C28.4.

Abnormal Events:

1. Loss of Bus 16

2. Steam Generator Pressure Transmitter PT-478 fails high

3. Tavg instrument fails high (1 2 SG PORV Fails Open)

Maior Transients:

1. Turbine Trip with ATWS Critical Tasks:

1. E F: Establish and maintain 200 gpm AFW flow to the Steam Generator@)

before transition out of E-0, unless the transition is to FR-H.1, in which case the task must be initiated before RCPs are manually tripped in accordance with step 2 of FR-H.l.

2. FR-S.1 - C: Insert negative reactivity into the core by inserting rods or establishing emergency boration flow to the RCS during the performance of FR-S.l.

e Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 6 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Standard (Specific) IC sets:

. IC-10

2. The following equipment is 00s:

12 Motor Driven ANVP 13 Heater Drain Pump SEQUENCE OF EVENTS:

Event 1: Reduce power from 100% to 90% usinq 1C1.4 The crew will reduce reactor power from 100% to 90% in accordance with 1C1.4, Unit 1 Power Operation, for Main Turbine Valve Testing.

The crew will remove 12 Heater Drain Pump from service for brush inspection per 1 C28.4.

Event 2: Loss of Bus 16 The normal supply breaker to Bus 16 will trip open due to operator error.

The Bus 16 sequencer will fail to re-energize Bus 16.

The crew will respond per 1C20.5 AOP 2 to re-energize the bus.

The sequencer failure will not be addressed in this scenario.

Event 3: Steam Generator Pressure Transmitter PT-478 Fails High B Steam Generator PORV will open.

The crew will manually close the PORV.

The crew will respond per C47 and 1 C51.

Event 4: Tavq instrument Fails Hiah Blue channel Thot fails high.

Control rods will insert in automatic The crew will place rod control in manual The crew will place running charging pumps in manual The crew will respond per C47 and C51.

Event5: ATWS The Turbine will trip, but the Reactor will not automatically trip.

The reactor cannot be tripped from the Control Room and the crew will enter 1 FR-S.1 and manually trip the reactor.

The crew will perform 1 FR-S.l and locally trip the Reactor.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 201 0 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Event 6: 11 TDAFW Pump Fails to Automaticallv Start 11 TDAFW Pump will not auto start during the ATWS event.

The crew will manually start the 11 TDAFW Pump per 1 FR-S.l.

Page 7 of 28 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

SEQUENCE OF EVENTS / INSTRUCTOR NOTES INITIAL CONDITIONS:

Page 8 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0

~~~

~

CREW-(RO/LO POS _.

SCENARIO TIME-LINE:

SEQ IC-10 Mode: 1 Exposure: MOC Power: 100%

Boron: (CB): 669 ppm Temperature: -560°F Pressure: -2235 psig Xenon: Equlibrium Rods: D 8 218 Generator: 571 MW

/SRO)

EXPECTEDSTUDENTRESPONSES Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

CREW POS Page 9 of 28 EXPECTEDSTUDENTRESPONSES 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1.

SIMULATOR SET UP

a. Set up the simulator to IC-10.

b. Enter the malfunctions, remotes, and overrides, as specified by the "Simulator Input Summary."

c. Complete the "Simulator Setup Checklist."

a.

The Simulator Pre-Brief is conducted prior to the crew enterinq the simulator.

2.

Simulator Pre-brief:

Inform the crew a power reduction to 90% is necessary to remove 12 Heater Drain Pump from service for brush inspection.

Provide the crew a marked up copy of 1 C1.4 section step 5.2 a)

N/A steps 5.2.1 b) Sign off step 5.2.2 (these notifications are not necessary)

Provide the crew a reactivity plan developed by the off going RO for the power reduction from 100% to 90%.

Inform the crew to verify the reactivity plan developed by the off going reactor operator.

Inform the crew that Nuclear Engineering was not available to provide a reactivity prediction.

Have SRO candidate perform the pre-job brief for the power reduction.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 201 0 ILT NRC SIMULATOR EVALUATION #4. Rev. 0 Page 10 of 28 SEQ EVENT 1 qetention:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

3.

When the crew has assumed the duty they will proceed with a power reduction to 90% in accordance with 1C1.4, Unit 1 Power Operation.

ife of Plant CREW POS CREW LEAD RO Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES Crew should start the power reduction to 90% IAW 1C1.4, Unit 1 Power Operation, at section 5.2, step 5.2.6.

Notify Duty Chemist of the load decrease Turn ON all pressurizer heaters Increase letdown flow if desired (80 gpm letdown flow will already be established, no actions will be needed)

If desired, THEN transfer Heating System to Unit 2 or to heating boiler (No actions will be needed since power reduction is only to 90%)

If desired, THEN place CS-46280, ROD BANK SELECTOR, in MANUAL. Refer to precaution 3.7 Start the load decrease as follows:

a.

b.

C.

d.

e.

Using the On Line Control screen, select the desired Control Mode (VPC,FSP or LOAD).

Using the On Line Control screen, select the desired rate.

Set the desired Target setting using the Target increase/decrease controls using the On Line Control screen.

Initiate a negative reactivity addition by using control rods or boration of the RCS per C12.5 WHEN Tave shows a decrease, THEN select Go on the On Line Control screen to initiate the load decrease.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 (h

Page 11 of 28 SCENARIO TIME-LINE:

SEQ Retention:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

4.

The crew should stop the load decrease at 90% IAW 1 C1.4, Unit 1 power Operation.

5.

When power is less than 95% the Lead operator should remove 12 Heater Drain Pump from service per 1C28.4.

a.

The crew may choose to start a additional condensate pump.

fe of Plant CREW POS RO LEAD -

Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01 EXPECTEDSTUDENTRESPONSES

f.

Vary the boration rate or batch borate as necessary to maintain Tave and Tref within the desired +/- 15°F band.

g. To suspend the load decrease, perform the following:

i. Select Hold on the On Line Control screen.

ii. Stop the boration per C12.5, if necessary iii. If reduced power steady state operation is anticipated, THEN, change ERCS TPM Power Source from NIS to calorimetric (LEFM preferred source) when steady state conditions are attained.

iv. Place CS-46300, MAKE-UP MODE SELECTOR, in AUTO.

v. Momentarily turn CS-46457, BORIC ACID MAKE-UP CONTROL, to START.

SELECTOR, is returned to AUTO.

vi. Verify CS-46280, ROD BANK 1C28.4, UNIT 1 HEATER DRAINS Step 5.7, Single Heater Drain Pump Operation with Reactor Power Greater Than 50%

a. Verify reactor power is less than or equal to 95%.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 12 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQ Retention:

SCENARIO TIM E-LI N E :

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

b.

When requested to open the discharge vent on 12 HD Pump wait 2 minutes and report valve is open.

This action is not modeled on the simulator.

ife of Plant CREW POS LEAD Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES

b.

C.

d.

e.

f.

9.

h.

i.

Place all three HTR DRN Pump selector switches to MANUAL.

IF Auto Speed Control if available, Then verify HTR DRN Pump Speed Selector switch for HDT Pump to be left running is in AUTO.

Verify the HDT DRN Pump Speed Selector switch for the pump to be stopped is in MANUAL.

Gradually lower the speed of the HDP to be removed from service to minimum while verifying the speed of the HDP to remain in service is increasing.

Throttle open 15 MI heater drains to the condenser approximately equal amounts to maintain 15 MI HTR levels normal with HDT level stable or increasing.

Stop the Heater Drain Pump to be removed form service.

Open the discharge vent on the HTR DRN pump that was stopped, If necessary, Then start the standby condensate pump.

QF-1075-02 Rev. 3 (FP-T-SAT-75) e Paae 13 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SCENARIO TIME-LINE:

SEQ EVENT 2 qetention:

SEQUENCE OF EVENTS / INSTRUCTOR N O T E

6.

When the crew has removed 12 Heater Drain Pump

7.

8.

from service, reduced power to 90% and/or at the discretion of the Lead Evaluator, enter the de-energization of Bus 16 (Relative Order 7, Event Trigger 7)

After the bus 16 is deenergized, verify override DI-46924T auto DELETES(Relatiwe Order 7) This restores light indication on the CT11 supply breaker.

The following indications will be observed:

a.

Bus 16 will be de-energized

b.

All bus 16 source breakers indicate open

c.

D2 EDG will auto start

d.

11 Charging pump trips, seal injection and charging flows decrease

e.

Multiple annunciators associated with loss of Bus 16, including:

1) 47024-0204 BUS 16 4.1 6 KV UNDERVOLTAGE

2)

3)

4) 47024-0205 BUS 122 480V UNDERVOLTAGE 47024-0206 BUS 121 480V UNDERVOLTAGE 47024-0704 BUS 16 SEQUENCER CHANNEL ALERT

5) 47024-0904 BUS 16 SEQUENCER FAILURE ife of Plant CREW POS RO Lead ss -

Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES As plant stabilization action SS may direct the RO to removing a letdown orifice from service IAW 1C12.1 since only one charging pump is running.

Respond to loss of 11 charging pump using C12.1 AOP 1 or by increasing the speed of 12 charging pump in manual Respond to loss of Bus 16 per C47024-0204 and 1 C20.5 AOP 2 e

e e

e Record alarms and bus targets Determine cause of de-energization (local operator error)

Isolate and repair the problem, no repairs are needed Place Bus 16 sequencer in MANUAL Determine desired voltage source for bus 16 (CT-11 is preferred)

Place source breakers in MANUAL Place loads in pullout Re-energize bus Restore loads SS should enter T.S. 3.8.9 Condition A and T.S.

3.8.4 Condition A for Bus 16 inoperable(de-energized).

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Paae 14 of 28

.d 201 0 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQ SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

6) 47024-1206 D2 EMERGENCY GENERATOR

7)

LOCAL ALARM SERVICE when sequencer placed in MANUAL 47024-1003 BUS 16 SEQUENCER NOT IN

9.

Perform the following actions as directed to simulate actions of personnel outside the Control Room:

a.

b.

C.

d.

1 minutes after the bus de-energizes, call the control room as the Turbine Building operator and inform them that you inadvertently tripped breaker 16-8 while performing OJT When asked to check bus 16 breakers and targets, report UV relays are the only targets showing and that all bus breakers are open If asked as the system engineer for a recommendation regarding re-energizing the bus, recommend re-energizing the bus from CT-11 If directed to investigate D2 Local alarm, acknowledge the alarm (Relative Order 2, Event Trigger21 and report the alarm is due to failure of the constant lube oil alarm NOTE :

When the crew responds to 47024-0904 BUS 16 SEQUENCER FAILURE and goes to 1C20.7 AOP3, BUS 16 LOAD SEQUENCER OUT OF SERVICE have Unit 2 take over required actions. Completing these actions is not part of this scenario.

CREW POS ss EXPECTEDSTUDENTRESPONSES After Bus 16 power is restored the crew will respond to 47024-0904 BUS 16 SEQUENCER FAILURE and go to 1 C20.7 AOP3, BUS 16 LOAD SEQUENCER OUT OF SERVICE Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) e Page 15 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQ EVENT 3 SCENARIO TIME-LINE:

~~

SEQUENCEOFEVENTS/ INSTRUCTOR NOTES

10. When the crew has restored power to Bus 16 or at the discretion of the Lead Evaluator, then enter the Steam Generator Pressure Transmitter PT-478 (blue) high failure. (Relative Order 3, Event Trigger 3).

a.

b.

C.

d.

e.

f.

g.

If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 4 5 minutes.

(Note: bistables will not be tripped during this scenario.)

If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC Resident Inspector, Duty Station Manager, etc., as asked.

If contacted as the FIN team supervisor, inform the crew that you will write a work order and assign an I&C supervisor to investigate.

If contacted as computer group, acknowledge the information and agree to investigate if further actions are warranted.

If desired, allow the crew to hold a crew brief.

Ensure rods are in auto prior to moving to next event.

Ensure charging is in auto prior to the next step.

CREW POS LEAD LEAD LEAD ss EXPECTED CUDENT RESPONSES Note: As a plant stabilization action the crew may close the By Steam Generator PORV prior to ARP entry.

Veriiy Steam Generator Level Control operating properly in automatic.

Control level in manual for any Steam Generator which has shifted to manual.

Refer to 1 C51 Instrument Failure Guide.

C47011-0405. Fw CONTROL SYSTEM TROUBLE 1C51.3 12 STEAM GENERATOR PRESSURE 1P-478 HIGH 0

Take manual control of 12 SG PORV and ensure valve is closed.

Verify SG Level Control operating properly in automatic.

0 Refer to T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 Function 1 e. (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip BE) 0 Trip and concurrently verify the following bistables...

0 If the Thermal Power Monitor is selected to Calorimetric input, then perform the following:

o Check if TPM power is affected by the steam pressure channel failure.

o If TPM power is affected, then change TPM power source input from Calorimetric to NIS and notify the computer group.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Page 16 of 28 SCENARIO TIME-LINE:

SEQ EVENT 4 SEQUENCE OF EVENTS / INSTRUCTOR NOTES

11. When the crew has completed actions for the Steam Generator Pressure transmitter failure or at the discretion of the Lead Evaluator, enter the malfunction to cause the Blue channel of Thot to fail high (Relafive Order 4, Event Trigger 4).

a.

b.

C.

If contacted as I&C to trip bistables, acknowledge the request and inform the Control Room that you will have two technicians available in 45 minutes.

(Note: bistables will not be tripped during this scenario.)

If contacted as Operations Management, acknowledge the report of the failure, and agree to make other notifications to the NRC, Duty Station Manager, etc. as asked.

If contacted as the FIN Team Supervisor, inform the crew that you will write a work order and assign an Electrical Supervisor to investigate.

CREW POS RO LEAD LEAD/

RO Retention: Life ofplant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01 EXPECTEDSTUDENTRESPONSES Note: As a plant stabilization action, the crew should diagnose the failure and place Rod Control in manual.

C47012-0104, REACTOR COOLANT SYSTEM LO-LO TAVG Check RCS Tavg.

If due to an instrument malfunction, then:

Place rod control in MANUAL and adjust rod position as necessary.

Shift charging pump control to MANUAL and adjust speed as necessary.

Verify steam dumps are not armed. If armed and open, then:

Place steam dump controller in MANUAL.

If necessary, then close steam dumps using manual controller.

Refer to 1 C51.

1C51.3 (Tavg Loop 1B 1T-403 - High)

Place rod control in MANUAL and-maintain Tavg at Tref.

Place charging pump speed control in MANUAL and maintain pressurizer level.

If necessary, then take manual control of steam dump.

Select Blue channel on the Tavg defeat switch and Return the following to AUTO:

Rod control Charging pump speed control Steam dump control.

pull out.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

SEQ 201 0 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQUENCE OF EVENTS / INSTRUCTOR NOTES Page 17 of 28 SCENARIO TIME-LINE:

CREW POS ss EXPECTEDSTUDENTRESPONSES 0

Refer to Technical Specifications.

0 TS LCO 3.3.1 Condition A and Table 3.3.1 -1 Functions 6,7 TS LCO 3.3.2 Condition A and Table 3.3.2-1 Function 4d TRM LCO 3.3.3 Condition A Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 e

Page 18 of 28 SEQ EVENT 5 qetention:

SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

12. When the crew has completed actions for the Tave high failure or at the discretion of the Lead Evaluator, enter the malfunction to cause the Turbine to Trip and the Failure of the reactor to trip/ATWS (Relative Order 5, Event Trigger 5.

a.

Upon hearing the announcement of Reactor Trip, or when called as the Turbine Building Operator to isolate the Unit 1 MSRs per Attachment J, enter CAEP - Att E-0 to start the isolation (Relative Order 5a). When the isolation is complete, inform the crew that MSRs are isolated.

b. When called as the Turbine Building Operator to open the reactor trip breakers, verify RO is driving in rods, wait 1 minute, and delete the malfunctions to prevent opening the Reactor Trip Breakers (Relative Order 6)

13. 11 TDAFW pump fails to auto start ife of Plant CREW POS CREW CREW LEAD/

RO LEAD LEAD Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

EXPECTEDSTUDENTRESPONSES 1 E-0, REACTOR TRIP OR SAFETY INJECTION Verify Reactor Trip Manually trip the reactor.

1 FR-S.l, RESPONSE TO NUCLEAR GENERATION/ATWS Verify Reactor Trip.

Critical Task: Insert negative reactivity into the core by inserting rods or establishing emergency boration flow to the RCS during the performance of FR-S. 1.

Verify automatic control rod insertion OR manually insert Control Rods.

Verify Turbine Trip.

Critical Task: Establish and maintain 200 gpm AFW flow to the Steam Generator(@ before transition out of E-0, unless the transition is to FR-H.1, in which case the task must be initiated before RCPs are manually tripped in accordance with step 2 of FR-H. 1.

Check AFW Pumps running. (Lead will need to manually start the TDAFW pump)

Manually start AFW pumps if required.

(Lead will need to manually start the 11 TDAFW pump, 12 MDAFW pump is 00s)

Initiate normal boration of RCS at 12 to 15 gpm

Check if a Reactor Trip and a Turbine Trip have occur red.

Dispatch operator to locally open Reactor Trip Breakers OR locally open Rod Drive MG Set Motor and Generator Breakers.

Check if Reactor is subcritical.

Power Range Channels (NFM less than 5%.)

If power is greater than 5%, then go to 1 FR-S.l

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 19 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SEQ SCENARIO TIM E-LIN E:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES

14. When the crew has returned to 1 E-0, or at the discretion of the lead evaluator, then place the simulator in FREEZE and inform the crew that training has the duty.

15. Emergency Plan Classification Site Area Emergency - EAL SS2.1 CREW POS CREW EXPECTEDSTUDENTRESPONSES Intermediate Range Channels (NFM) - NEGATIVE STARTUP RATE.

Go to step 15.

Return to procedure and step in effect, 1 E-0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

RXO5C 4

Blue Channel Thot fails high I

Page 20 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Relative Order System Or Panel Drawing Type O

I RP07B Block True D 1-464478 I

MALF B Rx Trip Breaker mech failure AMSAC Switch to Block 1

OVRD DI False Dl-464471 Initiate O

I Disable AMSAC Switch I OVRDDI M47014:0606B CP-1 YO501 D ANN MALF ERCS PT DISABLE Disable AMSAC Annunciator RESET Disable AMSAC in Test 0

1 1

ERCSPT ED1 7B NV34A SIM ED04 SIMFW08 Bus 16 sequencer failure 11 TDAFWP auto start failure I ~~

I 1

SI M ED04 OVRD DI SlMDGO2 REMOTE DI-46924T 3

1 5 second DELETE bus 16 Open breaker 16-8, CT-11 to TRUE 1

I MALF DG107 RX216 I

I SILENCE 2

Acknowledge D2 local alarm 12SG LOOP B (CHNL 111 -

1400 3

BLU) P XMTR (1 PT-478)

FAILS HIGH 4

SIMULATOR INPUT

SUMMARY

MALF Code I Severity 1 Event 1

Or Value Trigger Timing Description RP07A I

A Rx Trip Breaker mech failure CP-1Y0500D I SET I I

Disable AMSAC Trouble schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Code TC12 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Severity Event Or Value Trigger Timing Description 5

Turbine Trip Page 21 of 28 RP07A & B SIMULATOR INPUT

SUMMARY

DELETE Delete Reactor Trip Bkr Failures Relative Order r-System Or Panel Drawing Type MALF I

SIMMS03A 1 I

Perform Attachment J EO-AT. J.sch 1 I

I Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 22 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 SIMULATOR SETUP CHECKLIST Standard IC-1 0 Before Traininq Simulator Status:

1.

"Training Load"

2.

Step counters "ON"

3.

Alarm sound "ON"

4.

Reset to IC-10

5.

Speed: "REAL" Cycle recorder power "OFF then back "ON" to clear Yokogawa recorder memory Verify Summary matches Simulator Input Summary page in the SEG Boric AcidRMU integrators set to: BA: 3, RMU: 10, and reset MOC AI sheet displayed on C panel Check all ERCS alarms are cleared MOC Reactivity Briefing sheet available at Reactor Operator Desk Chart recorders operating and forwarded Turnover sheetlPRA sheet Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

Update Control Board Placards:

1.

High Flux At Shutdown Alarm Setpoint placards: 1400 cps

2.

Feedwater regulating valve position placard: 66/65, 67/64

3.

RCS boron on the CVCS panel placard: 669 ppm

4.

Turbine referenceketter values on the CVCS panel set to current (TargeVDemand on-line positions)

5.

Shift Reactivity Guidance placard: BA: 2.1 gallons, RMU: 67 gallons Magnetic placards in place:

1.

2.

3.

4.

Protected equipment tags in place:

1.

11 TDAFW pump Attach Caution Tags to the following control switches:

1.

2.

3.

4.

5.

ERCS driven recorders are on-scale (RCS temperature scaled to 55!jg F to 5 6 9 F)

ERCS alarm screen operating and alarms reset All ERCS terminals operating and set as follows:

Dilutions Q 10 gal RMU, 1-2 times per shift 11 BA TANK "Lined Up For Service" 11 BA PUMP "Lined Up To 11 BA Tank" CC TO SFP MV-32115 "In Service" Blowdown 46470 "SGB To CDSR" Place CS-46439, 12 MD AFWP selector switch in "MANUAL" Place CS-46425, 12 MD AFWP control switch in "PULL TO LOCK Place CS-46483,13 HTR DRN PUMP in "PULL TO LOCK" Place CS-46464,13 HTR DRN PUMP SPEED SELECTOR in "MANUAL" Place CS-46103,13 HTR DRN PUMP SELECTOR in "MANUAL" VARS Alarm Summary Page Group OP31-Ul AFD SAS (XS11)

TPM Group QP CCDATA QP LOADFOLL Group RADMON-U1 Alarm Summary Page Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 23 of 28 2010 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 ERCS single point displays:

1 T0499A 1 U1613A 1 V4501 A 1 Q0340A ERCS TPM set (Calorimetric - Auto Scaling - LEFM)

Pens/Paper/Markers available on the simulator Board-mounted EAL Table is cleaned EAL sticker books in F3-2 are checked for missing stickers Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

2.

F3-2.1 Bases -

3.

F3-2 Copy 275

4.

SWIO-28

5.

Boration Card

-6.

-10.

lC20.5AOP2 -

11.

T.S. 3.8.9

12.

T.S. 3.8.4

13.

C47011-0405 -

14.

1C51.3

15.

T.S. 3.3.1

16.

T.S. 3.3.2

17.

TRM 3.3.3

18.

1C28.4

-19.

C47024-0904 -

20.

21.

7.

1FR-S.l

8.

1C1.4

9.

47024-0204 On the NIS panel, verify Scaler Timer power switch is in Off position.

Set Turbine Control HMI Displays as follows:

1.

2.

U1 Turb Aux Cont (48088) to:

Turb Overview

3.

U1 E-H Turb Cont STA 2 (48087) to:

U1 E-H Turb Cont STA 1 ( 48086) to:

Control Valve Overview On Line Control DEHC alarms cleared Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75)

Page 24 of 28 201 0 ILT NRC SIMULATOR EVALUATION #4, Rev. 0 Post-Scenario Checklist EOOS computer is cleared of information added during the scenario Computer generated PINGP 577 cleared.

Procedures to be used during scenario are cleaned of any place keeping marks

1.

F3-2

2.

F3-2.1 Bases -

3.

F3-2 COPY 275

7.

1FR-S.l

8.

1C1.4

9.

47024-0204

-4.

SWI 0-28

5.

Boration Card

-6.