NRC 2009-0022, 2009 Point Beach Initial License Examination Proposed Dynamic Simulator Scenarios

2009 Point Beach Initial License Examination Proposed Dynamic Simulator Scenarios

ML100920278
Person / Time
Site:	Point Beach
Issue date:	05/11/2009
From:	Bielby M E NRC/RGN-III/DRS/OLB
To:	Florida Power & Light Energy Point Beach
References
NRC 2009-0022
Download: ML100920278 (142)

Text

A ppendix D Scenario Outline Form ES-D-1 Facility: __Point Beach_______ Scenario No.: ___

1___ Op-Test No.:

2009-01 Examiners: ____________________________ Operators: _____________________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions: ___Unit 1 EOL 75% power following a load reduction for load control.

_1P-29 TDAFW OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for turbine bearing replacement. 1P-2B Charging Pump is OOS due to repairs on the variable frequency drive system. Fan 1W-45 B Bus Duct Cooling fan is OOS due to motor failure.

Turnover: OP 1C, "Startup to Power Operation Unit 1" is in effect at step 5.133. Pressurizer Backup Heater group B is energized and an additional letdown orifice is in service. Protected equipment includes 1P-2A Charging Pump, 1P-2C Charging Pump, P-38A MDAFW Pump and P-38B MDAFW Pump. TSAC 3.7.5.B to restore 1P-29 to OPERABLE in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. The goal of the shift is to maintain current plant conditions.

Event No. Malf. No. Event Type* Event Description 1 C-BOP C-SRO TS-SRO 1P-11A CCW pump trip with failure of 1P-11B auto start 2 I-RO I-SRO VCT level transmitter 112 fails low 3 C-BOP TS-SRO Trip of Accident Fan W1B1 4 R-RO N-BOP N-SRO B SGFP high bearing temp and associated power reduction 5 M-ALL B S/G feed line rupture inside containment requiring plant trip and subsequent entry into CSP-H.1. (P-38A MDAFW Pump fails to auto start and trips after start. P-38B MDAFW Pump fails to start) 6 C-RO Rx Trip buttons fail on panel 1C04

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 1 of 36

Reference:

FP-T-SAT-75 SITE: POINT BEACH SEG # PBN-LOI-NRC-001E SEG TITLE: 2009 NRC EXAM SCENARIO #1 REV. # 0

PROGRAM: INITIAL LICENSE TRAINING #: PB-ILT

COURSE: #:

TOTAL TIME:2.0 Additional signatures may be added as desired.

Developed by: Andrew Zommers Instructor Date Reviewed by: Sam Hall Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Validated by: Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 2 of 36

Reference:

FP-T-SAT-75 Guide Requirements Goal of Training:

To have the crew successfully res pond to a failure of a CCW pump, VCT level transmitter failure, Acci dent Fan trip, Loss of a SG Feed Pump, feed line rupture in contai nment, failure of MDAFW pumps and reactor trip buttons in the Control Room. Embedded within these events is the expectation to properly utilize Technical

Specifications.

Learning Objectives:

None Prerequisites:

1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

2. Floor Instructor as Shift Technical Advisor

3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

References:

1. OP 1C Startup to Power Operation Unit 1

2. AOP 1D CVCS Malfunction Unit 1

3. AOP 2A Secondary Coolant Leak Unit 1

4. AOP 2B Feedwater System Malfunction Unit 1

5. AOP 17A Rapid Load Reduction Unit 1

6. AOP 9B Component Cooling Sy stem Malfunction Unit 1

7. EOP 0 Reactor Trip or Safety Injection

8. EOP 2 Faulted Steam Gener ator Isolation Unit 1

9. CSP-H.1 Loss of Heat Sink Unit 1

10. Technical Specifications

11. Technical Requirements manual

12. Alarm Response Book Commitments:

None Evaluation

Method: Simulator performance will be evaluated by NRC Examiners IAW

NUREG-1021 Operating Experience:

None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 3 of 36

Reference:

FP-T-SAT-75 Related PRA Information: Initiating Event with Core Damage Frequency:

Feedline Rupture in Containment CDF 9.8E-07 Important Components:

Important Operator Actions with Task Number:

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Reference:

FP-T-SAT-75 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry: 1. Loss of 1P11A CCW Pump wit h 1P11B failure to auto start 2. VCT Level transmitter LT-112 fails LOW 3. Loss of 1W1B Accident Fan 4. High bearing temper ature on SGFP P-28B 5. 'B' Feed line rupt ure inside containment

After EOP Entry: 1. Failure of reactor trip buttons in control 2. Failure of P38A MDAFW Pump to start

3. Failure of P38B MDAFW Pump, trips after start

Abnormal Events:

1. CCW Pump failure 2. SGFP failure

Major Transients:

1. 'B' Feed line rupture inside cont ainment with transition to CSP-H.1

Critical Tasks:

1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to 5 psig in containment 2. FR-H.1 A Restore feedwater flow into at least one steam generator before RCS bleed and feed is required

.

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Reference:

FP-T-SAT-75 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from t he following Standard (Specific) IC sets: IC-102 , created from IC-03

2. The following equipment is OOS: 1W45B Bus Duct Cooling Fan 1P-29 TDAFW Pump 1P-2B Charging Pump P-38A and P-38B MDAFW Pumps are protected equipment 1P-2A and 1P-2C Charging Pu mps are protected equipment 1W-45A Bus Duct Cooling Fan is protected equipment SEQUENCE OF EVENTS:

Event 1: Failure of 1P11A CCW Pump wit h 1P-11B failure to auto start Crew responds to loss of CCW and manually starts standby CCW pump Crew Enters AOP-9B to address malfunction SRO addresses Technical Specifications Event 2: Failure of 1LT-112 VCT Level Transmitter LOW Crew responds to loss of transmitter by stopping auto make up Crew Enters AOP-1D to address malfunction SRO addresses Technical Requirements Manual Event 3: Accident Fan 1W1B trips Crew addresses loss of 1W1B Accident Fan Crew starts the standby Accident Fan Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 6 of 36

Reference:

FP-T-SAT-75 SRO addresses Technical Specifications Event 4: 1P-28B Main Feed Pump high bearing temperature Crew addresses high SGFP bearing temp per AOP-2B Crew starts reducing power per AOP-17A to <60% turbine load Event 5: 'B' feed line ruptures inside containment Crew enters AOP 2A to address feed rupture SRO addresses Technical Specifications Crew trips reactor based on cont ainment pressure nearing 2 psig Crew enters EOP 0 and per forms immediate actions Transition is made to C SP-H.1 Loss of Heat Sink Event 6: Reactor trip buttons fail to operate in Control Room RO directs the BOP to de-energize 1B01 and 1B02 to trip the reactor RO directs BOP to restore busses and loads as time permits Event 7: P38A and P38B MDAFW pumps fail to operate as designed

BOP informs SRO both MDAFW pumps are not operating BOP may try to start P-38A

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Reference:

FP-T-SAT-75 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES INITIAL CONDITIONS:

Standard IC-102

Unit 1 Mode: 1 Burnup: 14200 MWD/MTU Power: 75% Boron: 88 ppm (EOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 181 steps Generator: 410 Mwe Unit 2 Mode: 1 Burnup: 4500 MWD/MTU Power: 26% Boron: 1109 ppm (MOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 158 steps Generator: 136 Mwe Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES

1. SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

1W-45B Bus Duct Cooling Fan 1P-29 TDAFW Pump (OOS tag) 1P-2B Charging Pump (OOS tag)

Protected equipment tags on P-38A and P-38B Protected equipment tags on 1P-2A and 1P-2C.

2. Simulator Pre-brief: a. Inform the crew that this session will be performed in the evaluation mode per NUREG 10201. b. If required, inform the crew of differences between the simulator and actual plant equipment. c. Crew positions

3. COMPLETE TURNOVER: a. Review applicable current Unit Status.

b. Review relevant At-Power Risk status.

c. Review current LCOs not met and Action Requirements. d. Verify crew performs walk down of control boards and reviews turnover checklists. e. Crew takes the shift.

TSAC 3.7.5.B applicable with 1P-29 OOS.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1: Failure of 1P11A CCW Pump with 1P-11B failure to auto start

Communications: If asked, the PAB AO reports the 'A' CCW Pump inboard motor bearing is hot to the touch.

If asked, the PAB AO will report nothing unusual with

the 'B' CCW Pump discharge pressure indicator, it reads 125 psig locally.

If asked, the TH AO will report the 'A' CCW Pump breaker has tripped on overcurrent.

NOTE: Crew may elect to place 1P-11A in pullout to clear 'Motor Breaker Trip' alarm.

End of evolution:

Proceed to next event at Lead Examiner discretion.

BOP/SRO Crew

SRO BOP/RO SRO BOP identifies the 'A' CCW Pump failure with the 'B' CCW Pump not auto starting. BOP requests from the SRO to start 'B' CCW Pump manually. BOP or RO address ARB's as applicable.

Enter AOP 9B CCW malfunction to address the lost CCW Pump. BOP will verify adequate tank level and start 1P-11B CCW Pump. Crew will address surge tank level which will require no action. Crew will address system leakage requiring no action.

Chemistry will be requested to analyze CCW.

OS1 will ask the SM to call DCS and Emergency Plan.

Send AO's out locally to the pump/breaker and discharge pressure indicator to find any problems.

Address LCO 3.7.7 CCW and enter 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSAC 3.7.7.A

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 10 of 36

Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2: Failure of 1LT-112 VCT Level Transmitter LOW NOTE: Crew may go to AOP-24 to address instrument failure. If AOP-24 is used go to next page of the SEG.

Communications: If asked, the APB AO reports nothing abnormal locally with LT-112.

Communications:

If SM is contacted regarding DCS and I&C reply the notifications are taking place.

End of evolution:

Proceed to next event at Lead Examiner discretion.

RO/SRO Crew RO SRO RO SRO/RO SRO RO identifies LT-112 failed low due to auto make up occurring and not required. Requests from the SRO to

take make up to off. Crew enters AOP-1D CVCS Malfunction to address the level transmitter failure. RO determines no RCS leak in progress Determines malfunction to be LT-112 and goes to step 58 VCT Divert valve to VCT.

Make up controls to STOP.

VCT level control in manual should be discussed. SRO addresses Technical Requirements Manual for the failed transmitter. There are no implications due to LT-141 still being operable. OS1 will ask the SM to Inform DCS and I&C Duty and Call.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Failure of 1LT-112 VCT Level Transmitter LOW (cont'd)

End of evolution:

Proceed to next event at Lead Examiner discretion.

SRO RO RO SRO Crew enters AOP-24 for instrument failure. Identify failed instrument.

Check if failed instrument is controlling, the RO should determine LT-112 is controlling. Establish manual control as desired. RO takes VCT Divert valve to VCT and make up controls to STOP.

Return affected parameters to normal Determine if failed instrument affects RTO, which LT-112 does not. Remove instrument from service, which cannot be done for LT-112. Return controls to automatic, which cannot be done. VCT level control in manual should be discussed Check for TS or TRM applicability. Address Technical Requirements Manual for the failed transmitter. There are no implications due to LT-141 still being operable.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3: Trip of Accident Fan 1W1B

NOTE: Have an OI-72 marked up and available if crew elects to start 1W-1A1.

NOTE: Next event takes several minutes to bring in an alarm.

End of evolution:

Proceed to next event at Lead Examiner discretion.

BOP SRO BOP responds to board alarms for Low Air Flow associated with the 1W1B Accident Fan and Motor

Breaker Trip. BOP references ARP(s) for Low Air Flow and/or Motor Breaker Trip to validate alarm(s). SRO may elect to start 1W-1A1 to maintain a normal alignment with 3 Accident Fans running. At a minimum, they should discuss monitoring RCP and Containment conditions if two fans are left operating. SRO addresses TS 3.6.6 and enters TSAC 3.6.6.C for the B Accident Fan, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 13 of 36

Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4: 1P-28B Main Feed Pump high bearing temperature Communication: If asked reply with the following as requested by the control room. The U1 TH AO reports the 1P-28B SGFP inboard motor bearing is hot to the touch and the paint is slightly discolored. Oil temperature was 95

ûF at the start of watch and is now 105ûF. There is lower than normal oil flow since rounds were taken. Normal service water flow, oil reservoir level normal, oil pressure is normal, seal water flow/temperature normal and no smoke.

RO BOP SRO RO BOP SRO RO acknowledges the 1TR-2000B Recorder alarm.

RO/BOP address ARB's as applicable.

Goes behind the boards to determine affected component.

Send out an AO to investigate 1P-28B status.

Crew enters AOP-2B Feedwater System Malfunction (CA STEP) maintain power <100% Check FRV response normal Check S/G level <78%

Check MFP's running

Check Condensate pumps running Check MFP's normal, crew should determine the RNO column is applicable. Crew ramps Unit to <60% load per

AOP 17A.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 1P-28B Main Feed Pump high bearing temperature (cont'd)

NOTE: Acknowledge SRO request to have SM notify PSS.

End of evolution:

Proceed to next event at Lead Examiner discretion.

SRO RO SRO RO

BOP RO BOP Determine power level to be met. Crew determines ramp to <60% turbine load. OS1 asks the SM to notify PSS of load ramp.

Check control rod system in AUTO.

Select ramp reduction method and rate. (CA STEP) Borate to keep rods above insertion limits. (CA STEP) Check PZR Pressure normal. (CA STEP) Check PZR Level normal. (CA STEP) Check S/G level controlling in AUTO. (CA STEP) Maintain RCS Tave. Check SGFP Seal Water pumps operating.

Event 5: 'B' feed line ruptures inside containment RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to 5 psig in containment Crew SRO Diagnose a secondary leak with containment humidity rising, Sump A level rising, containment pressure rising and no RMS alerts or alarms. Enter AOP 2A and will eventually trip reactor based on approaching 2 psig inside containment. SRO will direct a plant trip and enter EOP 0.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6: Reactor trip buttons fail to operate in Control Room

RO

CREW BOP RO/BOP CREW When the Unit trip is called for, the RO recognizes the RX trip breakers do not function on 1C04. RO continues with immediate actions

Verify Turbine Trip Verify Safeguards busses energized Check Safety Injection is actuated - most likely will have to manually actuate due to low pressurizer level. (CA STEP) Monitor folder page criteria

- Should identify adverse containment conditions

- Should isolate feed flow to the B S/G Verify Automatic Actions per Attachment A Verify Secondary Heat Sink Available Crew should notice the Heater Drain Tank and Condensate Pumps did NOT trip off at 5# containment pressure. When noted, the HDT pumps can be secured and the Condensate Pumps placed in Pullout.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7: P-38A and P-38B fail to operate as designed.

Communication: If asked, the TH AO reports nothing abnormal with P38B MDAFW Pump, Motor or associated breaker.

Communication: If asked, the TH AO reports P-38A MDAFW Pump motor is very hot to the touch and if asked the breaker tripped on overcurrent.

Communication: STA acknowledges request to monitor CSP status trees for Unit 1.

BOP SRO BOP determined the A and B MDAFW Pumps are not operating as designed.

BOP and SRO may elect to attempt 1 restart of P-38A MDAFW Pump.

SRO should determine entry into CSP-H.1 Loss of Heat

Sink is required.

BOP should stop performing actions in EOP 0 Attachment A after transition to CSP-H.1.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES P-38A and P-38B fail to operate as designed (cont'd)

Communication:

AO will be contacted to locally align AFW per Attachment B of CSP H.1. Acknowledge the request; however, valve lineups do not affect the

scenario and do not need to be performed

NOTE: Crew may or may not have to start a condensate pump based on their actions from the previous failure.

CREW BOP RO RO SRO RO RO RO/BOP (CA STEP) Monitor folder page criteria SRO should direct completion of Attachment C Check if Heat Sink is required Check if RCS Bleed and Feed is required. Crew should determine there is adequate S/G level and delta T's in the RCS loops. Verify S/G sample and Blowdown valves shut Check control room indications for cause of loss of AFW Check total feed flow greater than 200 GPM. SRO should assign an AO to perform Attachment B for local valve alignments.

Stop Both RCPs

Check Condensate Pumps - AT LEAST ONE RUNNING

(CA STEP) Maintain hotwell level greater than 5 inches

Check condensate and feedwater piping intact

- Should identify that 'B' feed line is faulted and align 'A' to restore S/G level.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES P-38A and P-38B fail to operate as designed (cont'd)

FR-H.1 A Restore feedwater flow into at least one steam generator before RCS bleed and feed is required.

NOTE: EOP 0 Attachment A should be recommenced after exiting CSP-H.1. RO/BOP

SRO RO

SRO RO/BOP Establish feedwater flow path. Crew will reset SI and verify a flow path for 'A' S/G. Check main Feed Pumps at least 1 running. With no feed pumps running and the 'B' being OOS, the crew will start

'A' MFP. Check SGFP Discharge MOV open. Establish S/G levels. Crew will feed the 'A' S/G to restore level. Return to procedure step in effect. SRO directs return to EOP-0 step 6. Verify RCP Seal cooling (CA STEP) Verify RCS Temperature Control Check PZR PORV's shut

Check PZR Sprays shut Check if RCP's should remain running Start monitoring Critical Safety Function Status Trees (CA STEP) Verify Containment Sump Recirculation not Required Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES P-38A and P-38B fail to operate as designed (cont'd)

NOTE: Lead Evaluator can terminate scenario at any point after entry into EOP-2.

BOP SRO RO BOP Check if Secondary System is intact - NO Transition to EOP-2 Check RCS Hot Leg wide range temperatures stable Isolate both MSIV's

Check if any S/G is not faulted CSP H.1 Attachme nt C actions

BOP Verify Safeguards busses energized.

Verify Feedwater Isolation.

Verify Containment Isolation.

Check SI Pumps - Both running.

Check RHR Pumps - Both running.

Check CCW Pumps - Only 1 running.

Verify SW system alignment. Verify Containment Accident Fan Units running.

Check Control room ventilation in Accident Mode

Check if MSIV's can remain open.

Verify Containment Spray is not required. Check 4160 VAC safeguards busses energized by offsite.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation valves are both shut.

BOP Verify feedwater isolation.

Verify containment isolation

Verify AFW actuation. BOP should not perform any actions with 1P-29 TDAFW pump due to it being OOS.

Check SI pumps running.

Check RHR pumps running.

Check only 1 CCW pump running.

Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves and isolate loads per Event 8 below.

Verify containment accident cooling.

Check CR ventilation in accident mode.

Check if main steam lines can remain open.

Verify proper SI valve alignment.

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Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A (cont'd)

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the Computer Room is 72

ûF. Wait 2 more minutes and report CWPH temperature at 65

ûF.

BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

(CA STEP) Check AFW Area temperature.

(CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 22 of 36

Reference:

FP-T-SAT-75 EVENT 1: Failure of 1P11A CCW Pump with 1P-11B failure to auto start Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload MGA MAL MAL1MGA005B -

1W-45B Bus Duct Fan OOS Preload SGN VLV VLV1SGN015 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2019)

Preload SGN VLV VLV1SGN016 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2020)

Preload CVC BKR BKR1CVC006 6- Fail CP Fuse 1P-2B Charging Pump OOS Preload AFW VLV VLVAFW031 1- Fail CP Fuse 1AF-4000 OOS Preload AFW VLV VLVAFW032 1- Fail CP Fuse 1AF-4001 OOS PLE CCW PMP PMP1CCW001 2-shaft seizure 1 1P-11A CCW Pump CCW BKR BKR1CCW002 4-fail to auto close Preload 1P-11B CCW Pump Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 23 of 36

Reference:

FP-T-SAT-75 Expected Communications If asked, wait one minute and have the PAB AO reports the 'A' CCW Pump inboard motor b earing is hot to the touch If asked, wait one minute and have the PAB AO will report nothing unusual with the 'B' CCW Pump discharge pressure indicator, it reads 125 psig locally If asked, wait one minute and have the TH AO will re port the 'A' CCW Pump breaker has tripped on overcurrent

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 24 of 36

Reference:

FP-T-SAT-75 EVENT 2: Failure of 1LT-112 VCT Level Transmitter LOW Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description CVC XMT XMT1CVC019A0 3 15 sec VCT LT-112 Expected Communications If asked, wait one minute and have the PAB AO reports nothing abnormal locally with LT-112

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 25 of 36

Reference:

FP-T-SAT-75 EVENT 3: Loss of 1W-1B1 Accident Fan Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description CNM BKR BKR1CNM002 1-Trip 11 1W-1B1 Fan Trip Expected Communications If asked, wait one minute and have the TH AO reports breaker for 1W-1B1 is tripped on overcurrent

.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 26 of 36

Reference:

FP-T-SAT-75 EVENT 4: 1P-28B Main Feed Pump high bearing temperature Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description CFW XMT XMT1CFW038A 225 5 10 min 1P-28B Inboard Motor Bearing Expected Communications Communication: If asked reply with the following as requested by the control room. The U1 TH AO reports the 1P-28B SGFP inboard motor bearing is hot to the touch and the paint is slightly discolored. Oil temperature was 95

ûF at the start of watch and is now 105

ûF. There is lower than normal oil flow since rounds were taken. Normal service water flow, oil reservoir level normal, oil pressure is normal, seal water flow/t emperature normal and no smoke

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 27 of 36

Reference:

FP-T-SAT-75 EVENT 5: 'B' feed line ruptures inside containment Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload PPL BST BST1PPL056 1-fail as is 1PC945A SI Cont Pres bistable Preload PPL BST BST1PPL060 1-fail as is 1PC947A SI Cont Pres bistable PLE CFW FLX FLX1CFW031 5000 9 900 sec 'B' feedline break inside containment Expected Communications None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 28 of 36

Reference:

FP-T-SAT-75 EVENT 6: Reactor trip buttons fail to operate in Control Room Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload PPL OVR OVR1PPL033 Off Reactor trip Button 1C04 Preload PPL OVR OVR1PPL034 Off Reactor trip Button 1C04 Expected Communications None

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 29 of 36

Reference:

FP-T-SAT-75 EVENT 7: P38A and P38B MDAFW pum ps fail to operate as designed Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload AFW BKR BKR1AFW001 1-Trip 15(JCRFTR) 60 sec delay P-38A MDAFW Pump trips Preload AFW BKR BKR1AFW002 5-fails as is P-38B MDAFW Pump fails to start Expected Communications If asked, the TH AO reports P38A MDAF W Pump, Motor hot to the touch and ass ociated breaker tripped on overcurrent. If asked, the TH AO reports nothing abnormal with P-38B MDAFW Pump Motor or associated breaker. AO will be contacted to locally align AFW per Attachment B of CSP H.1. Acknowledge the request; however, valve lineups do not affect the scenario and do not need to be performed. When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation valves are both shut.

When contacted, wait 2 minutes and have the AO repo rt room temperatures for the Computer Room is 72

ûF. Wait 2 more minutes and report CWPH temperature at 65

ûF.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 30 of 36

Reference:

FP-T-SAT-75 VERIFY the simulator setup for training mode scenario (for evaluated scenarios use PBF-6801):

Rod counters reset

Training signs installed Watchstation nametags assigned

Horns on All CO station books in proper places Instrument noise on Digital Displays set appropriately

STA CSFST Sheets available All mimic bus magnets in proper positions

MCB / instrument rack doors shut, lights off Sim 20 lighting breakers closed

Radios available and operable

TR-2000 series recorders in Data (auto) /

Scan (auto) SPDS computers restarted Startup Fireworks PC at 1C20 workst ation, if required after initial startup of MST Scenario specific props (tags, protected equipment magnets, etc.) installed: None Ensure the Simulator Base Station is set to Simulator

Talk Group 1. (Clear screen saver by moving mouse. Simulator Group 1 should be outlined in green)

[Ref. CAP 01039821, Item 4]

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 31 of 36

Reference:

FP-T-SAT-75 Post Scenario Simulator Restoration P&Ids cleaned and restored Marked up procedures replaced

Marked up ARBs/ARPs cleaned Simulator restored to appropr iate IC (default is IC2)

Scenario specific prop s (tags, protected equipment signs, etc.) removed Mimic bus magnets restor ed to appropriate IC I F last session of the day, THEN Depost access doors Replace burned out lights

Replace spent charts Shutdown MST

SHIFT TURNOVER INFORMATION Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 32 of 36

Reference:

FP-T-SAT-75 1.0 PLANT CONDITIONS

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

14200 4500 Reactor power (%):

75% 26% Boron concentration (ppm): 88 ppm 1109 ppm Rod height (CBD @): CBD @ 181 CBD @ 158 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC Description Reason 3.7.5.B One turbine driven AFW pump system inoperable in MODE 1, 2 or 3 for reasons other than Condition A.

Restore turbine driven AFW pump system to

OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1P-29 TDAFW Pump was placed OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for bearing replacement on the

turbine. 3.0 EQUIPMENT OUT OF SERVICE

1P-29 TDAFW pump OOS for bearing replacement. 1AF-4000 and 1AF-4001 TDAFW Discharge MOV's are shut with power removed. 1W-45B Bus Duct Cooling fan OOS due to motor failure. 1P-2B Charging Pump is OOS for variable frequency drive maintenance.

4.0 PLANNED EVOLUTIONS

Maintain current power level.

SHIFT TURNOVER INFORMATION Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 33 of 36

Reference:

FP-T-SAT-75 5.0 TURNOVER INFORMATION

Unit 1 was reduced to 75% power 3 days ago for system load control. Procedure step in effect is OP-1C, Startup to Power Operation Unit 1, step 5.133. Pressurizer backup heater Group B is energized and an additional orifice is in service. Safety Monitor is Green. P-38A and P-38B MDAFW Pumps are protected equipment. 1P-2A and 1P-2C Charging Pumps are protected equipment. 1W-45A Bus Duct Cooling fan is protected equipment. Clock time is real time and you have the normal shift complement. There is a Maintenance crew and supervisor on site working 1P-29 TDAFW pump.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 34 of 36

Reference:

FP-T-SAT-75 Attach the following information as necessary: Simulator Set-up Checklist (before and after training) Pre-evaluation Brief Guide (for evaluations only) Post-evaluation Critique (for evaluations only) Turnover Log Historical Record:

(Optional) This SEG is being developed for the ILT 2009 NRC

Exam.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 35 of 36

Reference:

FP-T-SAT-75 Simulator Scenario Development Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include justification for the answer or the corrective action needed to correct the discrepancy after the item. Yes No 1. The scenario contains objectives for the desired tasks and relevant human performance tools.

X Yes NoN/A 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEG's new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.) X Yes No 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both. X Yes No 4. Plant PRA initiating events, important equipment, and important tasks are identified. X Yes NoN/A 5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. X Yes No 6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given. X Yes NoN/A 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. X Yes NoN/A 8. The scenario includes related industry experience.

X Yes NoN/A 9. 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. X Yes NoN/A 10. Scenario requires an Emergency Preparedness NARS to be completed. (If YES, a NARS answer key validated by EP personnel is attached to the SEG.) Reference CAP 01021167 - 02. X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the

cover page.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 36 of 36

Reference:

FP-T-SAT-75 Simulator Scenario Validation Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include an explanation after the item.

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

Yes X No 2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes X No 3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X No 4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes X No 5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes X No 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 Yes X No 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 N/A 8. NARS form is accurate for the classification and release conditions presented during the scenario. (MET data is variable based on instrument noise) Reference CAP 01021167 - 02.

Yes No N/A X Discrepancies noted (Check "none" or list items found)

None SMAR = Simulator Action Request

SMAR: SMAR: SMAR: SMAR: Comments: No was selected for several training items on the development checklist. These items will remain 'NO' due this SEG being developed IAW NUREG 1021 for an Initial NRC license exam. No was selected for step 2 of the development checklist due to this being N/A for our plant.

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

A ppendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.: __

2_____ Op-Test No.:

2009-01 Examiners: ____________________________ Operators: _____________________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions: ___Unit 1 MOL 100% power. 1P-29 TDAFW OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for turbine bearing replacement. 1P-2B Charging Pump is OOS due to repairs on the variable frequency drive system. Fan 1W-45 B Bus Duct Cooling fan is OOS due to motor failure.

Turnover: Protected equipment includes 1P-2A Charging Pump, 1P-2C Charging Pump, P-38A MDAFW Pump and P-38B MDAFW Pump. TSAC 3.7.5.B to restore 1P-29 to OPERABLE in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. The goal of the shift is to maintain current plant conditions.

Event No. Malf. No. Event Type* Event Description 1 C-RO C-SRO CV-135 controller malfunction AOP 1D 2 TS-SRO Control power relay alarm/failure B SI pump 3 C-RO C-SRO TS-SRO Small RCS leak on B RTD loop 4 R-RO N-BOP N-SRO Bus Duct fan failure drives downpower due to inadequate bus cooling 5 M-ALL Large break LOCA requiring plant trip and containment sump recirc 6 C-BOP C-SRO Failure of 1P-15A SI pump auto start 7 C-BOP Failure of SI-852A Core Deluge to auto open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

Retention: Life of Plant SITE: POINT BEACH SEG # PBN-LOI-NRC-002E SEG TITLE: 2009 NRC EXAM SCENARIO #2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING

1. PB-ILT COURSE: #: TOTAL TIME:

2.0 Additional signatures may be added as desired.

Developed by: Andrew Zommers Instructor Date Reviewed by:

Sam Hall Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Validated by:

Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 1 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Guide Requirements Goal of Training:

To have the crew successfully respond to a failure of a CV-135, B SI pump control power failure, loss of bus duct cooling resulting in a downpower, small RCS leak, LOCA, fa ilure of P-15A to start, non-essential SW isolation failure and SI-852 to open. Embedded within these events is the expectation to properly utilize Technical

Specifications.

Learning Objectives:

None Prerequisites:

1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

2. Floor Instructor as Shift Technical Advisor

3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

References:

1. AOP 1D CVCS Malfunction Unit 1

2. Alarm Response Books

3. AOP 1A Reactor Coolant System Leak Unit 1

4. AOP 17A Rapid Load Reduction Unit 1

5. EOP 0 Reactor Trip or Safety injection Unit 1

6. EOP 1.3 Containment Sump Reci rculation - Low Head Unit 1

7. Technical Specifications

Commitments:

None Evaluation

Method: Simulator performance will be evaluated by NRC Examiners IAW

NUREG-1021 Operating Experience:

None Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 2 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Related PRA Information: Initiating Event with Core Damage Frequency:

Large LOCA CDF 3.4E-08 Important Components:

Important Operator Actions with Task Number:

Operator fails to align for LHR Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 3 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Failure of CV-135 Letdown Backpressure Controller

2. Failure of 1P-15B SI Pump control power

After EOP Entry:

1. Failure of 1P-15A SI Pump to auto start

2. Failure of 1SI-852A Core Deluge to auto open

Abnormal Events:

1. 10 gpm RCS leak on B RTD manifold

2. Failure of 1W-45A Bus Duct Cooling Fan

Major Transients:

1. Large break LOCA Critical Tasks:

1. RT-7, When a reactor trip is procedurally called for, init iate a manual reactor trip prior to pressurizer level reaching 10%

2. E0-I Manually start 1P-15A prior to exiting EOP 0 Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 4 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from t he following Standard (Specific) IC sets: IC-101, created from IC-02

2. The following equipment is OOS: 1W-45B Bus Duct Cooling Fan 1P-29 TDAFW Pump 1P-2B Charging Pump P-38A and P-38B MDAFW Pu mps are protected equipment 1P-2A and 1P-2C Charging Pu mps are protected equipment 1W-45A Bus Duct Cooling Fan is protected equipment SEQUENCE OF EVENTS:

Event 1: Failure of CV-135 Letdown Backpressure Controller RO takes manual control and stabilizes system parameters SRO directs crew response with AOP 1D Event 2: Failure of 1P-15B SI Pump control power BOP addresses ARB and reports to SRO SRO addresses Technical Specifications Event 3: 10 gpm RCS leak B RTD manifold RO estimates leak size based on indications Crew enters AOP-1A to respond to leak SRO addresses Technical Specifications Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 5 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 6 of 35

Reference:

FP-T-SAT-75 Crew will start to troubleshoot leak location Event 4: Failure of 1W-45A Bus Duct Cooling Fan BOP responds per ARB With no bus duct cooling, crew performs unit downpower per AOP-17A Event 5: Large LOCA, Rx trip, Tran sfer to sump recirculation Crew enters EOP-0 following Rx trip and Safety Injection SRO directs transition to EOP-1.3 Event 6: Failure of 1P-15A SI Pump to auto start BOP identifies failure SRO directs manual start of pump Event 7: Failure of 1SI-852A Core Deluge to auto open BOP identifies failure SRO directs valve be manually opened

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES INITIAL CONDITIONS:

Standard IC-101

Unit 1 Mode: 1 Burnup: 7800 MWD/MTU Power: 100% Boron: 735 ppm (MOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 220 steps Generator: 533 Mwe Unit 2 Mode: 1 Burnup: 320 MWD/MTU Power: 100% Boron: 1322 ppm (BOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 220 steps Generator: 535 Mwe Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 7 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ CREW POS EXPECTED STUDENT RESPONSES SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1. SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

1W-45B Bus Duct Cooling Fan 1P-29 TDAFW Pump (OOS tag) 1P-2B Charging Pump (OOS tag)

Protected equipment tags on P-38A and P-38B Protected equipment tags on 1P-2A and 1P-2C

2. Simulator Pre-brief:

a. Inform the crew that this session will be performed in the evaluation mode.

b. If required, inform the crew of differences between the simulator and actual plant equipment.

3. COMPLETE TURNOVER:

a. Review applicable current Unit Status.

b. Review relevant At-Power Risk status.

c. Review current LCOs not met and Action Requirements.

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

e. Crew takes the shift.

TSAC 3.7.5.B applicable with 1P-29 OOS Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 8 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1: Failure of CV-135 Letdown Backpressure Controller

Communications:

If asked, the PAB AO reports there is nothing abnormal with CV-135.

NOTE: AOP-24 may be utilized in addition to AOP-1D. (see next page for AOP-24 actions)

End of evolution:

Proceed to next event at Lead Examiner discretion.

RO/SRO SRO RO SRO RO SRO BOP RO identifies CV-135 pressure controller malfunction and takes controller to manual to control back pressure. Addresses ARB for Letdown High Pressure.

Enter AOP 1D to address the malfunction and verify actions taken. Check RCS leak not in progress. Reviews foldout page criteria Determine CVCS malfunction - CV-135 pressure control which directs transition to step 36. Establish manual control of CV-135 Request SM to notify DCS and I&C Duty and Call The crew will have to keep CV-135 in manual control and discuss how this will be done. (may review step 36 RNO) May send out the PAB AO to look at CV-135 locally

. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 9 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Failure of CV-135 Letdown Backpressure Controller (cont'd)

End of evolution:

Proceed to next event at Lead Examiner discretion.

SRO RO RO SRO Crew enters AOP-24 for instrument failure.

Identify failed instrument/controller.

Check if failed instrument is controlling, the RO should determine CV-135 is controlling. Establish manual control as desired. RO takes controller to manual and controls pressure.

Return affected parameters to normal Determine if failed instrument affects RTO, which CV-135 does not. Remove instrument from service, which cannot be done for CV-135. Return controls to automatic, which cannot be done. Letdown pressure control in manual should be discussed Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 10 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2: Failure of 1P-15B SI Pump control power

Communications:

If AO's are sent to electrical busses or specific components wait 1 minute then report (as requested) critical control power relays normal with the light lit with the exception of 1P-15B Safety Injection Pump (Relay 1-74/A85FM located on 1A52-85)

If Maintenance is notified inform the SRO an Electrician is on the way to investigate.

NOTE: If the relay is to be removed, then clear the malfunction and report relay 1-74/A85FM is removed.

End of evolution:

Proceed to next event at Lead Examiner discretion.

BOP

SRO Responds to critical control power relay with ARB. Sends AO's in the field to determine cause of alarm.

Checks relays on CO1R for 1B03 and 1B04 (ARB actions)

Informs the SRO which component is affected, 1P-15B.

Determines LCO 3.5.2 is not met and TSAC 3.5.2.A is entered with 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the pump to operable.

OS1 should ask the SM to notify Maintenance to determine cause of failure and repair.

Crew may ask the relay to be pulled to clear the critical control power relay to allow other potential alarms process through.

Crew may elect to place 1P-15B control switch to pullout. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 11 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3: 10 gpm RCS leak B RTD manifold

The OS must differentiate between a primary and secondary leak. With this small of an RC leak, it will take about 4-5 minutes before an RMS alert is

received.

CREW RO

SRO Identifies RMS trends, lowering VCT level and Sump A rising which indicates an RCS leak.

Enter AOP 1A RCS leak to stabilize plant parameters.

RO controls charging as needed to determine an RCS leak rate.

(CA STEP) Check SI not required. Crew should not SI, leak is small.

(CA STEP) Check reactor trip not required. Crew should not trip, leak is small.

(CA STEP) Check PZR level. RO should take control of charging to restore and maintain pressurizer level. Letdown isolation should not be needed.

Check pressurizer pressure. RO should have to take no action for this step.

Determines LCO 3.4.13 is not met and TSAC 3.4.13.A is entered with 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce leakage.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 12 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 10 gpm RCS leak B RTD manifold (cont'd)

Communications: Shift Manager will be asked to notify DCS and implement E-Plan

NOTE: The next failure will have approximately 1 minute delay between the trigger and the first control room indication (alarm). Trigger for event 4 should be inserted just prior to diagnostic steps of AOP-1A.

End of evolution

Proceed to next event at Lead Examiner discretion.

RO SRO BOP RO Check make up controls set at desired value

OS1 should ask the SM to notify DCS and implement Emergency plan Check S/G tubes intact Check RCP seal leakoff normal

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 13 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4: Failure of 1W-45A Bus Duct Cooling Fan NOTE: Bus Duct Cooling Air Temp High alarm is received about 3 minutes after initial fan failure.

Communications:

TH1 AO reports back that the fan 1W-45A has thrown its belts due to the motor pulley

falling off.

PAB and TH AO's will be notified to monitor the changing plant conditions due to the downpower.

BOP SRO

RO SRO RO

Address ARB and direct the TH1 AO to investigate alarm.

Informs the SRO of equipment status and the need for unit ramp Enter AOP-17A and perform approximately a 5%/min ramp to <12,000 amps on the generator output.

Determine power level and desired ramp rate. Ramp should be 5%/min until < 12,000 amps.

OS1 should inform the SM to notify PSS of load reduction.

Check rod control in auto. RO should inform the SRO rods are already in auto.

Select rate reduction method and reduce load.

(CA STEP) Borate to maintain rods above the low-low insertion limit.

(CA STEP) Check Pressurizer pressure Stable at OR trending to 2235 psig.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 14 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Failure of 1W-45A Bus Duct Cooling Fan (cont'd)

Communications: Unit 1 TH AO will be requested to start 1P-99A and B and will report back when complete.

End of evolution

Proceed to next event after an appropriate load reduction per Lead Examiner discretion.

RO BOP RO BOP SRO RO SRO (CA STEP) Check Pressurizer Level Stable at OR trending to program level. (CA STEP) Check Steam Generator Level controlling - IN AUTO (CA STEP) Maintain RCS Tavg Check Main Feed Pump Seal Water Pump - RUNNING. BOP will have AO start 1P-99A and 99B. Determine Desired end point - LESS THAN 50% TURBINE LOAD. SRO will determine this is NO. (CA STEP) Check if boration can be stopped.

OS1 will ask the SM to contact Chemistry to sample the RCS for Iodine within 2-6 hours following the power

change. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 15 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5: Large LOCA, Rx trip, Transfer to sump recirculation

CRITICAL TASK: RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to pressurizer level reaching 10%

RO RO/SRO

CREW SRO/BOP RO Determines RCS leak has gotten worse and plant trip is required.

Recommend trip of the unit with manual SI/CI per continuous action step 1 of AOP 1A.

RO should manually trip Unit 1 reactor, SI and CI.

RO should perform EOP 0 immediate actions and verify them with the SRO. RO should perform RNO for step 4 IA's with no SI pumps running. - perform manual SI and CI When reviewing foldout page criteria the crew should determine RCP's need to be tripped and adverse containment conditions exist. - SI pump should be manually started with injection verified prior to RCP securing Direct EOP 0 Attachment A to be completed Verify secondary heat sink Verify RCP Lab seal D/P Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 16 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Large LOCA, Rx trip, Transfer to sump recirculation (cont'd)

Communications: STA will be asked to commence monitoring Status Trees, acknowledge request. NOTE: CSP-P.1 will be identified as requiring entry by the STA. Depending on the timing of the notification; the Crew may or may not transition to CSP-P.1. If they do transition prior to transition to EOP 1.3, step 1 of CSP-P.1 sends them back to procedure step in effect.

RO

SRO RO SRO (CA STEP) Verify RCS temperature control.

Check PORV's shut.

Check Spray valves shut.

Check if RCP's should remain running. RCP's should have been secured per foldout page criteria, if not they should be secured here.

Start monitoring CSFST's. SRO should direct the STA to perform this function.

(CA STEP) Verify containment sump recirc not required.

Transition to EOP 1.3 containment sump recirc.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 17 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Large LOCA, Rx trip, Transfer to sump recirculation (cont'd)

Communication:

AO will be contacted to complete Attachment A of EOP 1.3 Transfer to Containment Sump Recirc. Acknowledge request and then insert trigger 13. No follow up report is required because the attachment will not be complete prior to the end of the scenario. BOP RO BOP BOP BOP RO BOP RO/BOP BOP RO/BOP

Reset SI Check RCS break size.

Check if containment sump pH should be adjusted. Check if train A SI flow should be stopped. - stop train A ECCS system Check if Train B should be stopped - go to step 6 (CA STEP) Monitor Core Cooling Direct PAB operator to perform Attachment A Direct unnecessary personnel to evacuate the PAB

Check Control Room fans armed Isolate CCW to containment Isolate CCW to NRHX

Check SW Pumps 6 running Check SW header a continuous flowpath Establish CCW to RHR HX's

Ensure Core Deluge valves are open Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 18 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Large LOCA, Rx trip, Transfer to sump recirculation (cont'd)

Communication:

AO will be contacted to complete step 16.b in EOP 1.3 to locally shut both SI test line return isolation valves. Acknowledge report and then insert trigger 15. Report when valves are shut.

End of scenario

Lead Evaluator can end evaluation any time after sump recirc line up is established and crew is waiting for RWST level to reach 34%.

RO/BOP

SRO BOP Align SI test lines for recirc Align RHR pump suction valves Check Train A ready for recirculation - yes Check Train B ready for recirculation - no Check at least 1 train ready for recirculation - yes train A Note reference for other procedures are now applicable that do not interfere with EOP 1.3 Check RWST level <

34%

NOTE: Crew may have to transition to CSP-P.1 if not done earlier and stop after step 1. The next transition that should occur is 'procedure step in effect' which is EOP-0

Step 14. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 19 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A

CRITICAL TASK: E0-I Manually start 1P-15A prior to exiting EOP 0

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation

valves are both shut.

BOP Verify feedwater isolation.

Verify containment isolation

Verify AFW actuation. BOP should not perform any actions with 1P-29 TDAFW pump due to it being OOS.

Check SI pumps running. If not previously started 1P-15A should be manually started. 1P-15B is OOS. The BOP should isolate the suction source and place pump in pullout.

Check RHR pumps running.

Check only 1 CCW pump running.

Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves.

Verify containment accident cooling.

Check CR ventilation in accident mode.

Check if main steam lines can remain open.

Verify proper SI valve alignment. If not previously done, 1SI-852A should be opened at this time.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 20 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A (cont'd)

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the Computer Room is 72

ûF. Wait 2 more minutes and report CWPH temperature at 65

ûF.

BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

(CA STEP) Check AFW Area temperature.

(CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Event 6: Failure of 1P-15A SI Pump to auto start Communication: If an AO is requested to locally check the pump or breaker report there is nothing abnormal from the field.

CRITICAL TASK: E0-I Manually start 1P-15A prior to exiting EOP 0 BOP SRO Determine that 1P-15A SI pump did not auto start. Action should not be taken to manually start the pump until after immediate actions are completed and verified.

This pump can be started per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 will check this equipment.

This pump should be started when the crew has to trip the RCP's due to loss of subcooling on foldout page criteria EOP 0. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 21 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 22 of 35

Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7: Failure of 1SI-852A Core Deluge to auto open Communication: If an AO is requested to locally check the valve breaker report there is nothing abnormal from the field.

BOP Determine that 1SI-852A core deluge did not auto open.

Action should not be taken to manually open the valve until after immediate actions are completed and verified.

This valve can be opened per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 will check this valve in the proper position.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 1: Failure of CV-135 Letdown Backpressure Controller Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload MAL1MGA005B

- 1W-45B Bus Duct Fan OOS Preload SGN VLV VLV1SGN015 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2019)

Preload SGN VLV VLV1SGN016 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2020)

Preload CVC BKR BKR1CVC006 6- Fail CP Fuse 1P-2B Charging Pump OOS Preload AFW VLV VLVAFW031 1- Fail CP Fuse 1AF-4000 OOS Preload AFW VLV VLVAFW032 1- Fail CP Fuse 1AF-4001 OOS PLE CVC CNH CNH1CVC014F 50 1 CV-135 controller oscillations in automatic Expected Communications If PAB AO is sent out, inform control room there is nothing abnormal at valve 1CV-135 Letdown backpressure control valve LOAs used

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 23 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 EVENT 2: Failure of 1P-15B SI Pump control power Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE SIS BKR BKR1SIS002 6-fail cntrl pwr fuse 3 1P-15B control power fuse faiure PLE ANN C02 ANN-C02D-D06 OFF 20 Clear control power failure alarm window Expected Communications If AO's are sent to electrical busses or specific components wait 1 minute then report (as requested) critical control power relays normal with the light lit with the exception of 1P-15B Safety Injection Pump (Relay 1-74/A85FM located on 1A52-85) If the relay is to be removed (insert trigger 20), and report relay 1-74/A85FM is removed on 1A52-85. If Maintenance is notified inform the SRO an Electrician is on the way to investigate.

LOAs used None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 24 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 3: 10 gpm RCS leak B RTD loop Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS MAL MAL1RCS003E 10 gpm 5 60 sec ramp RCS loop B RTD manifold leak

Expected Communications None LOAs used None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 25 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 4: Failure of 1W-45A Bus Duct Cooling Fan Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE MGA BKR BKR1MGA0086-fail CP fuse 7 1W-45A failure As requested CFW LOA LOA1CFW083 ON 9 Start 1P-99A SGFP Seal Water Injection Pump As requested CFW LOA LOA1CFW084 ON 9 30 sec delay Start 1P-99B SGFP Seal Water Injection Pump Expected Communications After 1 minute, the TH1 AO reports back that the fan 1W-45A has thrown its belts due to the motor pulley falling off. PAB and TH AO's will be notified to monitor the changing plant conditions due to the downpower. After starting 1P-99A/B report back to Control Room status of pumps.

LOAs used

When TH1 AO requested to start 1P-99A and B, wait 2 minutes and insert trigger 9.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 26 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 5: Large LOCA, Rx trip, Tran sfer to sump recirculation Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS MAL MAL1RCS002F 80 11 360 sec ramp LOCA B RCS INT Loop As requested LOA LOA1CCW016 0 13 60 sec Ramp 1 CC740A As requested LOA LOA1CCW021 0 13 120 sec Delay 60 sec Ramp 1 CC750A As requested LOA LOA1SIS030 0 15 60 sec Ramp 1 SI 897A As requested LOA LOA1SIS031 0 15 60 sec Delay 60 sec Ramp 1 SI 897B Expected Communications When the PAB AO is contacted, the P AB AO informs the Control Room SW-LW-61 and 62 SW Radwaste isolations are both shut. When contacted, wait 2 minutes and have the AO repo rt room temperatures for the Computer Room is 72

ûF. Wait 2 more minutes and report CWPH temperature at 65

ûF. AO will be contacted to complete Attachment A of EOP 1.3 Transfer to Containment Sump Recirc. Acknowledge request and then insert trigger 13. No follow up report is required because the attachment will not be complete prior to the end of the scenario. AO will be contacted to complete step 16.b in EOP 1.3 to locally shut both SI test line return isolation valves. Acknowledge report and then insert trigger 15. Report when valves are shut.

LOAs used Trigger 13: Attachment A EOP 1.3 Trigger 15: EOP 1.3 Step 16.b to shut 1SI 897A and B Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 27 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 6: Failure of 1P-15A SI Pump to auto start Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload SIS BKR BKR1SIS001 4-fails to auto close 1P-15A fails to auto start

Expected Communications If an AO is requested to locally check 1P-15A pump or br eaker report there is nothing abnormal from the field.

LOAs used None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 28 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 29 of 35

Reference:

FP-T-SAT-75 Event 7: Failure of 1SI-852A Core Deluge to auto open Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload SIS VLV VLV1SIS027 4-fails to auto open 1SI-852 core deluge

Expected Communications If PAB AO sent to look at breaker locally, nothing abnormal should be reported to control room. LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 VERIFY the simulator setup for training mode scenario (for evaluated scenarios use PBF-6801):

Rod counters reset

Training signs installed Watchstation nametags assigned

Horns on All CO station books in proper places Instrument noise on Digital Displays set appropriately

STA CSFST Sheets available All mimic bus magnets in proper positions

MCB / instrument rack doors shut, lights off Sim 20 lighting breakers closed

Radios available and operable

TR-2000 series recorders in Data (auto) /

Scan (auto) SPDS computers restarted Startup Fireworks PC at 1C20 workst ation, if required after initial startup of MST Scenario specific props (tags, protected equipment magnets, etc.) installed: None Ensure the Simulator Base Station is set to Simulator

Talk Group 1. (Clear screen saver by moving mouse. Simulator Group 1 should be outlined in green)

[Ref. CAP 01039821, Item 4]

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 30 of 35

Reference:

FP-T-SAT-75

SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

7800 320 Reactor power (%):

100% 100% Boron concentration (ppm): 735 ppm 1322 ppm Rod height (CBD @): CBD @ 220 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC Description Reason 3.7.5.B One turbine driven AFW pump system inoperable in MODE 1, 2 or 3 for reasons other than Condition A.

Restore turbine driven AFW pump system to

OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1P-29 TDAFW Pump was placed OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for bearing replacement on the

turbine. 3.0 EQUIPMENT OUT OF SERVICE

1P-29 TDAFW pump OOS for bearing replacement 1AF4000 and 1AF-4001 TDAFW Discharge MOV's are shut with power removed 1W-45B Bus Duct Cooling fan OOS due to motor failure 1P-2B Charging Pump is OOS for variable frequency drive maintenance

4.0 PLANNED EVOLUTIONS

None

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 31 of 35

Reference:

FP-T-SAT-75

SHIFT TURNOVER INFORMATION Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 32 of 35

Reference:

FP-T-SAT-75 5.0 TURNOVER INFORMATION

Safety Monitor is Green. P38A and P38B MDAFW Pumps are protected equipment. 1P-2A and 1P-2C Charging Pumps are protected equipment. 1W-45A Bus Duct Cooling fan is protected equipment. Clock time is real time and you have the normal shift complement. There is a Maintenance crew and supervisor on site working 1P-29 TDAFW pump.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Attach the following information as necessary: Simulator Set-up Checklist (before and after training) Pre-evaluation Brief Guide (for evaluations only) Post-evaluation Critique (for evaluations only) Turnover Log Historical Record:

(Optional) This SEG is being developed for the ILT 2009 NRC

Exam.

Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 33 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Simulator Scenario Development Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include justification for the answer or the corrective action needed to correct the discrepancy after the item. Yes No 1. The scenario contains objectives for the desired tasks and relevant human performance tools.

X Yes No N/A 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEG's new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

X Yes No 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

X Yes No 4. Plant PRA initiating events, important equipment, and important tasks are identified.

X Yes No N/A 5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. X Yes No 6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

X Yes No N/A 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. X Yes No N/A 8. The scenario includes related industry experience.

X Yes No N/A 9. 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.

X Yes No N/A 10. Scenario requires an Emergency Preparedness NARS to be completed. (If YES, a NARS answer key validated by EP personnel is attached to the SEG.) Reference CAP 01021167 - 02.

X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the

cover page. Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 34 of 35

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 35 of 35

Reference:

FP-T-SAT-75 Simulator Scenario Validation Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include an explanation after the item.

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

Yes X No 2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes X No 3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X No 4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes X No 5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes X No 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 Yes X No 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 N/A 8. NARS form is accurate for the classification and release conditions presented during the scenario. (MET data is variable based on instrument noise) Reference CAP 01021167 - 02.

Yes No N/A X Discrepancies noted (Check "none" or list items found)

None SMAR = Simulator Action Request

SMAR: SMAR: SMAR: SMAR: Comments: No was selected for several training items on the development checklist. These items will remain 'NO' due this SEG being developed IAW NUREG 1021 for an Initial NRC license exam. No was selected for step 2 of the development checklist due to this being N/A for our plant.

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

A ppendix D Scenario Outline Form ES-D-1 Facility: ____Point Beach______ Scenario No.: ___

3_____ Op-Test No.:

2009-01 Examiners: ____________________________ Operators: _____________________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions: ___Unit 1 MOL 28% power hold for Chemistry and Reactor Engineering testing from a trip 6 days ago. Control Rods are in manual for the start up. 1P-29 TDAFW OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for turbine bearing replacement. 1P-2B Charging Pump is OOS due to repairs on the variable frequency drive system. Fan 1W-45 B Bus Duct Cooling fan is OOS due to motor failure.

Turnover: OP 1C, "Startup to Power Operation Unit 1" is in effect at step 5.120. Pressurizer Backup Heater group B is energized and an addition letdown orifice is in service. Protected equipment includes 1P-2A Charging Pump, 1P-2C Charging Pump, P-38A MDAFW Pump and P-38B MDAFW Pump. TSAC 3.7.5.B to restore 1P-29 to OPERABLE in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. The 28% power hold is cleared and you are directed to raise power to 47% per step 5.120 at a rate of 15% per hour Event No. Malf. No. Event Type* Event Description 1 R-RO N-BOP N-SRO Raise power per OP-1C 2 TS-SRO G02 EDG alarm, low starting air pressure 3 I-RO TS-SRO I-SRO PT-431 failing high 4 M-ALL B SGTR requiring plant trip 5 C-BOP SW-2907/2908 fail to auto open 6 C-BOP P32E SW Pump failure to auto start

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

Retention: Life of Plant SITE: POINT BEACH SEG # PBN-LOI-NRC-003E SEG TITLE: 2009 NRC EXAM SCENARIO #3 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING

1. PB-ILT COURSE: #: TOTAL TIME:

2.0 Additional signatures may be added as desired.

Developed by: Andrew Zommers Instructor Date Reviewed by: Sam Hall Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Validated by:

Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 1 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Guide Requirements Goal of Training:

To have the crew successfully raise reactor power, respond to a

failure of PT-431, GO2 EDG alarm, SGTR requiring plant trip, failure of SW 2907/2908 to open and P-32E to start. Embedded within these events is the expectation to properly utilize Technical

Specifications.

Learning Objectives:

None Prerequisites:

1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

2. Floor Instructor as Shift Technical Advisor

3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

References:

1. OP 1C Startup to Power Operation Unit 1

2. 0-SOP-IC-001-BLUE, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor From Service - Blue Channels

3. AOP 24 Response to Instrument Malfunctions

4. Alarm Response Books

5. EOP 0 Reactor Trip or Safety Injection Unit 1

6. EOP 3 Steam Generator Tube Rupture Unit 1

7. Technical Specifications and Bases Commitments:

None Evaluation Method: Simulator performance will be evaluated by NRC Examiners IAW

NUREG-1021 Operating Experience:

None Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 2 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Related PRA Information:

Initiating Event with Core Damage Frequency:

SGTR, 1.8E-06 Important Components:

NA Important Operator Actions with Task Number:

HEP-ODC-EOP-3-21, Operator fails to cooldown and depressurize the intact SG in one hr following a SGTR Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 3 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. G02 EDG alarm, low starting air pressure After EOP Entry:

1. Failure of SW-2907/2908 to auto open

2. Failure of P-32E SW Pump to auto start

Abnormal Events:

1. Failure of Pressurizer pressure transmitter PT-431 Major Transients:

1. SGTR requiring plant trip Critical Tasks:

1. E-3 A Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

2. E3-D Terminate SI before a RED simulator Out Of Limits alarm reached (S/G full to MSIV) and control RCS pressure and make up flow so that primary and secondary inventory are stable before the end of the scenario. Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 4 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from t he following Standard (Specific) IC sets: IC-103, created from IC-05

2. The following equipment is OOS: 1W-45B Bus Duct Cooling Fan 1P-29 TDAFW Pump 1P-2B Charging Pump P-38A and P-38B MDAFW Pumps are protected equipment 1P-2A and 1P-2C Charging Pu mps are protected equipment SEQUENCE OF EVENTS:

Event 1: Raise power per OP-1C Crew raises power per OP-1C Event 2: G02 EDG alarm, low starting air pressure Crew responds per ARB's SRO declares G02 OOS SRO addresses Technical Specifications Event 3: Failure of Pressurizer pressure transmitter PT-431 RO identifies malfunction, takes m anual control and restores pressure Crew enters AOP-24 to address malfunction Shift pressure control to auto per ARB SRO addresses Technical Specifications Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 5 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 6 of 34

Reference:

FP-T-SAT-75 Event 4: B SGTR requiring plant trip Crew unable to mitigate SGTR Crew trips the unit and responds per EOP set Event 5: Failure of SW-2907/2908 to auto open BOP identifies failure SRO directs valves be manually opened Event 6: Failure of P-32E SW Pump to auto start BOP identifies failure SRO directs pump be manually started

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES INITIAL CONDITIONS:

Standard IC-103 Unit 1 Mode: Burnup: 4150 MWD/MTU Power: 28 % Boron: 1065 ppm (MOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 166 steps Generator: 146 Mwe Unit 2 Mode: Burnup: 120 MWD/MTU Power: 100% Boron: 1321 ppm (BOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 220 steps Generator: 535 Mwe Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 7 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ CREW POS EXPECTED STUDENT RESPONSES SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1. SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

1W-45B Bus Duct Cooling Fan 1P-29 TDAFW Pump (OOS tag) 1P-2B Charging Pump (OOS tag)

Protected equipment tags on P-38A and P-38B Protected equipment tags on 1P-2A and 1P-2C

2. Simulator Pre-brief:

a. Inform the crew that this session will be performed in the evaluation mode.

b. If required, inform the crew of differences between the simulator and actual plant equipment.

3. COMPLETE TURNOVER:

a. Review applicable current Unit Status.

b. Review relevant At-Power Risk status.

c. Review current LCOs not met and Action Requirements.

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

e. Crew takes the shift.

TSAC 3.7.5.B applicable with 1P-29 OOS. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 8 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1: Raise power per OP-1C

End of evolution:

Proceed to next event at Lead Examiner discretion.

Crew RO Briefing on power ascension may be performed in classroom prior to beginning of the scenario. Withdraws rods and/or Dilute in addition to adjusting steam demand as needed to establish power increase.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 9 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2: G02 EDG alarm, lo w starting air pressure

Communication: When sent out, have the TH1 AO wait 2 minutes and report that G02 south bank air pressure is 190 psig and stable with the north bank 160 psig and slowly lowering. The north bank air compressor is running with one of the bank relief valve leaking by.

(ARB C65A C35 P7)

End of evolution:

Proceed to next event at Lead Examiner discretion.

BOP SRO

Address G02 alarm on panel C02. Dispatches AO to determine local alarm that is in.

When the report comes back to Control the SRO should determine that G02 EDG is OOS.

LCO 3.8.3 not met, enter TSAC 3.8.3.D immediately and declare G02 OOS.

LCO 3.8.1 not met, enter TSAC 3.8.1.E for required standby emergency power sources inoperable.

Determine the need to align G01 to both 1A05 and 2A05.

Call in Maintenance to troubleshoot and fix.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 10 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3: Failure of Pressurizer pressure transmitter PT-431

NOTE: IF asked for guidance, the Shift Manager will state OS2 will prepare the required paperwork per 0-SOP-IC-001 BLUE to remove PT-431 from service. Prompt OS1 to complete additional actions while OS2 prepares the paperwork.

RO RO/SRO BOP SRO RO

SRO Recognizes PT-431 failing high causing spray valves to open lowering RCS pressure. Take manual control of PT-431 and control pressurizer pressure manually. Address the low pressure condition with the ARB's. - Controlling channel can be changed over per ARB 1C04 1C 1-2 step 6.6.

- PORV's and spray controller to manual prior to

defeating PT-431 Blue

- Return affected parameters to Automatic Enter AOP 24 for instrument malfunction. Identify failed instrument. Check if failed instrument is controlling, the RO should determine PT-431 is controlling. Establish manual control as desired. RO takes manual control of HC-431.

Return affected parameters to normal Determine if failed instrument affects RTO, which PT-431 does not.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 11 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Failure of Pressurizer pressure transmitter PT-431 (cont'd)

End of evolution:

Proceed to next event at Lead Examiner discretion. Intent is to NOT take the instrument OOS per 0-SOP IC 001-Blue, shift to auto control per ARB

is desired.

SRO Remove instrument from service per 0-SOP-IC-001 Address Technical Specifications for PT 431 using 0-SOP-IC-002. TSAC 3.3.1.A enter table 3.3.1-1 immediately.

Take PT-431 to trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 3.3.1.D and 3.3.1.K.

TSAC 3.3.2.A enter table 3.3.2-1 immediately. Take PT-431 to trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 3.3.2.D.

If applicable, TSAC 3.4.1.A restore RCS pressure >2205 (TRM 2.1 COLR) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 12 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4: B SGTR requiring plant trip

CREW SRO RO CREW Identifies the SGTR.

OS1 suspends any ongoing activities and may implement AOP-3 if time permits.

Crew may adjust charging to maintain pressurizer level and attempt to determine leak rate.

Monitors pressurizer level for trip criteria.

Determine the SGTR size and report to SRO.

Determines SGTR on B S/G and recommends plant trip.

Trip reactor, manual SI and CI, then enter EOP 0 for immediate actions.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 13 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

RO CREW SRO/BOP RO

Perform immediate actions of EOP 0 and verify with the SRO.

Address foldout page criteria. Isolate ruptured S/G

Direct EOP 0 Attachment A to be completed Verify secondary heat sink. RO should feed B S/G until at least 29% level.

Verify RCP Lab seal D/P (CA STEP) Verify RCS temperature control.

Check PORV's shut.

Check Spray valves shut.

Check if RCP's should remain running.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 14 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

SRO RO

SRO RO

BOP Start monitoring CSFST's. SRO should direct the STA to perform this function.

(CA STEP) Verify containment sump recirc not required.

Check if secondary is intact. RO should verify this to be true.

Check if S/G tubes are intact. RO should determine tubes are NOT intact.

Transition to EOP 3 SGTR.

(CA STEP) Check if RCP's should remain running.

Identify ruptured S/G.

Shut MSIV's for ruptured S/G.

Reset LOFWTT

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 15 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

Critical Tasks:

E-3 A Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

BOP

SRO RO RO/BOP Minimize steam dump from ruptured S/G.

Isolate flow from ruptured S/G.

(CA STEP) Check if feed flow to ruptured S/G should be stopped.

- Unit 2 will enter TSAC 3.7.5.A when P-38B is placed in pullout to isolate AFW to the B generator.

Check ruptured S/G isolation.

Check ruptured S/G >430 psig

Determine target CET.

Cooldown to target temperature Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 16 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

RO BOP

RO (CA STEP) Check PORV and PORV block valves.

Check PZR safeties shut

Stabilize intact S/G level Check SI signal status (previously locked in)

Reset SI Reset CI Reset 1B03/B04 lockouts

Check 4160 safeguards busses energized by offsite

Re-establish IA to containment

Check if RHR should be stopped

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 17 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

RO BOP

BOP RO

Verify charging flow

Check if cooldown should be stopped

Check ruptured S/G pressure stable Check RCS subcooling

Depressurize RCS and refill using spray (or PORV's) or aux spray Check if SI should be terminated

Stop both SI pumps

Verify charging flow Verify SI not required

Check reactor make up controls Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 18 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B SGTR (cont'd)

Critical Tasks:

CRITICAL TASK: Terminate SI before a RED simulator Out Of Limits alarm reached (S/G full to MSIV) and control RCS pressure and make up flow so that primary and secondary inventory are stable before the end of the scenario.

End of evolution: End the simulator session per lead evaluator when sufficient actions are taken to equalize S/G and RCS pressures.

Check if Letdown should be established (CA STEP) Align charging pump suction to VCT

(CA STEP) Control RCS pressure and charging to minimize S/G tube leakage.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 19 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5: Failure of SW-2907/2908 to auto open Communications: If asked, the PAB AO reports nothing abnormal with SW-2907/2908.

BOP

Determine that SW-2907/2908 did not auto open. Action should not be taken to manually open the valves until after immediate actions are completed and verified.

These valves can be opened per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 will check this equipment.

Unit 2 will enter TSAC 3.7.8.F when these valves are opened. Event 6: Failure of P-32E SW Pump to auto start

Communications:

If asked, the AO reports nothing abnormal with P-32E Pump or Breaker.

Determine that P-32E Service Water pump did not auto start. Action should not be taken to manually start the pump until after immediate actions are completed and verified.

This pump can be started per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 will check this equipment.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 20 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation

valves are both shut.

BOP Verify feedwater isolation.

Verify containment isolation

Verify AFW actuation. BOP should not perform any actions with 1P-29 TDAFW pump due to it being OOS.

Check SI pumps running. If not previously started 1P-15A should be manually started. 1P-15B is OOS. The BOP should isolate the suction source and place pump in pullout.

Check RHR pumps running.

Check only 1 CCW pump running.

Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves.

Verify containment accident cooling.

Check CR ventilation in accident mode.

Check if main steam lines can remain open.

Verify proper SI valve alignment. If not previously done, 1SI-852A should be opened at this time.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 21 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 22 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A (cont'd)

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the Computer Room is at 72

ûF. Wait 2 more minutes and report CWPH temperature is at 65

ûF.

BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

(CA STEP) Check AFW Area temperature.

(CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 1: Raise power per OP-1C Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload MAL1MGA005 B - 1W-45B Bus Duct Fan OOS Preload SGN VLV VLV1SGN015 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2019)

Preload SGN VLV VLV1SGN016 1-Fail CP Fuse 1P-29 TDAFW Pump OOS (1MS-2020)

Preload CVC BKR BKR1CVC006 6- Fail CP Fuse 1P-2B Charging Pump OOS Preload AFW VLV VLVAFW031 1- Fail CP Fuse 1AF-4000 OOS Preload AFW VLV VLVAFW032 1- Fail CP Fuse 1AF-4001 OOS Expected Communications None LOAs used

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 23 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 2: Failure of Pressurizer pressure transmitter PT-431 Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE PCS XMT1RCS019A 2500 1 10 PT-431 failing high in auto Expected Communications None

LOAs used

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 24 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 3: G02 EDG alarm, low starting air pressure Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE G02 ANN ANN-C02F-B01 0-ON 3 G02 EDG alarm Expected Communications When sent out, have the TH1 AO wait 2 minutes and report that G02 south bank air pressure is 190 psig and stable with the north bank 160 psig and slowly lowering. The north bank air compressor is running with one of the bank relief valve leaking by.

LOAs used None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 25 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 4: B SGTR requiring plant trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE 1RCS1 MAL MAL1RCS008B 9 7 Ramp 360 sec S/G B Tube Rupture Preload 1SGN2 LOA LOA1SGN025 0 9 Ramp 120 1MS-237 Expected Communications When sent to locally check Radwaste SW valves SW-LW-61 & 62 shut, report that both valves are shut. When contacted, wait 2 minutes and have the AO repo rt room temperatures for the Computer Room is 72

ûF. Wait 2 more minutes and report CWPH temperature is 65

ûF. When directed to locally shut 1P-29 AFP/RW steam isolation, 1MS-237, & MS trap isolation, 1MS-238, insert trigger 9. Report valves closed. If surveys are requested for the steam lines, RP can report after 5 minutes that B steam line is slightly above background and A steam line is background LOAs used LOA1SGN025 to shut 1MS-237. No LOA for 1MS-238, valve is not modeled.

• • Simulator Booth to track these val ues for monitoring critical task.

• • VSGNV1 (1) S/G A Volume

• • VSGNV1 (2) S/G B Volume

• • 2600 YELLOW

• • 2685 RED **2691 SOLID Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 26 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 5: Failure of SW-2907/2908 to auto open Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload SWS VLV VLV1SWS0394-fail to auto open 1SW-2907 fail to auto open Preload SWS VLV VLV1SWS0404-fail to auto open 1SW-2908 fail to auto open

Expected Communications If asked, the PAB AO reports nothing abnormal with SW-2907/2908.

LOAs used

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 27 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Event 6: Failure of P-32E SW Pump to auto start Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload SWS BKR BKR1SWS0054-fail to auto close P32E fails to auto start

Expected Communications If asked, the AO reports nothing abnormal with P-32E Pump or Breaker.

LOAs used

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 28 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 29 of 34

Reference:

FP-T-SAT-75 VERIFY the simulator setup for training mode scenario (for evaluated scenarios use PBF-6801):

Rod counters reset

Training signs installed Watchstation nametags assigned

Horns on All CO station books in proper places Instrument noise on Digital Displays set appropriately

STA CSFST Sheets available All mimic bus magnets in proper positions

MCB / instrument rack doors shut, lights off Sim 20 lighting breakers closed

Radios available and operable

TR-2000 series recorders in Data (auto) /

Scan (auto) SPDS computers restarted Startup Fireworks PC at 1C20 workst ation, if required after initial startup of MST Scenario specific props (tags, protected equipment magnets, etc.) installed: None Ensure the Simulator Base Station is set to Simulator

Talk Group 1. (Clear screen saver by moving mouse. Simulator Group 1 should be outlined in green)

[Ref. CAP 01039821, Item 4]

SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

4150 120 Reactor power (%):

28% 100% Boron concentration (ppm): 1065 ppm 1321 ppm Rod height (CBD @): CBD @ 166 CBD @ 220

2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC Description Reason 3.7.5.B One turbine driven AFW pump system inoperable in MODE 1, 2 or 3 for reasons other than Condition A.

Restore turbine driven AFW pump system to

OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1P-29 TDAFW Pump was placed OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for bearing replacement on the turbine. 3.0 EQUIPMENT OUT OF SERVICE

1P-29 TDAFW pump OOS for bearing replacement. 1AF-4000 and 1AF-4001 TDAFW Discharge MOV's are shut with power removed. 1W-45B Bus Duct Cooling fan OOS due to motor failure. 1P-2B Charging Pump is OOS for variable frequency drive maintenance.

4.0 PLANNED EVOLUTIONS

Continue power escalation to 47% power with a 15%/hr ramp rate per OP-1C, Startup to Power Operation Unit 1. Current step in effect is OP 1C Step 5.120.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 30 of 34

Reference:

FP-T-SAT-75

SHIFT TURNOVER INFORMATION Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 31 of 34

Reference:

FP-T-SAT-75 5.0 TURNOVER INFORMATION

Safety Monitor is Green

. Clock time is real time and you have the normal shift complement. The Unit tripped 7 days ago and we are holding at 28% power Xe equillibrium for chemistry and flux mapping. P-38A and P-38B MDAFW Pumps are protected equipment. 1P-2A and 1P-2C Charging Pumps are protected equipment. There is a Maintenance crew and supervisor on site working 1P-29 TDAFW pump. Control Rods are in manual per OP-1C P&L 3.3.8 Pressurizer backup heater bank B is energized and an additional orifice in service.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Attach the following information as necessary: Simulator Set-up Checklist (before and after training) Pre-evaluation Brief Guide (for evaluations only) Post-evaluation Critique (for evaluations only) Turnover Log Historical Record:

(Optional) This SEG is being developed for the ILT 2009 NRC

Exam.

Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 32 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Simulator Scenario Development Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include justification for the answer or the corrective action needed to correct the discrepancy after the item. Yes No 1. The scenario contains objectives for the desired tasks and relevant human performance tools.

X Yes No N/A 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEG's new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

X Yes No 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

X Yes No 4. Plant PRA initiating events, important equipment, and important tasks are identified.

X Yes No N/A 5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. X Yes No 6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

X Yes No N/A 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. X Yes No N/A 8. The scenario includes related industry experience.

X Yes No N/A 9. 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.

X Yes No N/A 10. Scenario requires an Emergency Preparedness NARS to be completed. (If YES, a NARS answer key validated by EP personnel is attached to the SEG.) Reference CAP 01021167 - 02.

X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the

cover page. Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 33 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 003E, 2009 NRC EXAM SCENARIO 3, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 34 of 34

Reference:

FP-T-SAT-75 Simulator Scenario Validation Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include an explanation after the item.

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

Yes X No 2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes X No 3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X No 4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes X No 5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes X No 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 Yes X No 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 N/A 8. NARS form is accurate for the classification and release conditions presented during the scenario. (MET data is variable based on instrument noise) Reference CAP 01021167 - 02.

Yes No N/A X Discrepancies noted (Check "none" or list items found)

None SMAR = Simulator Action Request

SMAR: SMAR: SMAR: SMAR: Comments: No was selected for several training items on the development checklist. These items will remain 'NO' due this SEG being developed IAW NUREG 1021 for an Initial NRC license exam. No was selected for step 2 of the development checklist due to this being N/A for our plant.

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

A ppendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.:

___4____ Op-Test No.: _2009-01 Examiners: ____________________________ Operators: _____________________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions: Unit 1 is at 100% power MOL. G01 EDG is OOS for a maintenance overhaul with G02 EDG aligned to 1A05 and 2A05 safeguards busses. 1P-2B Charging Pump is OOS due to repairs on the variable frequency drive system. A severe thunderstorm watch is in effect for the day.

Turnover: Protected equipment includes 1P-2A Charging Pump, 1P-2C Charging Pump. You are to lower Unit 1 to 94% power per OP-2A, "Normal Power Operation" in preparation for Atmospheric Steam Dump testing.

Event No. Malf. No. Event Type* Event Description 1 R-RO N-BOP N-SRO Normal downpower to 94% per OP-2A 2 I-RO I-SRO TS-SRO RCS Tcold 401B failed high 3 TS-SRO 1X03 transformer lockout 4 C-ALL Lowering of Condenser Vacuum 5 M-ALL 1P-30A Circulating Water Pump bearing failure requiring plant trip 6 C-BOP C-SRO Main Turbine Fails to AUTO & MANUALLY Trip 7 C-ALL Post trip 1X04 fails along with G02 and G03 requiring entry into ECA 0.0

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

Retention: Life of Plant SITE: POINT BEACH SEG # PBN-LOI-NRC-004E SEG TITLE: 2009 NRC EXAM SCENARIO #4 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING

1. PB-ILT COURSE: #: TOTAL TIME:

2.0 Additional signatures may be added as desired.

Developed by: Andrew Zommers Instructor Date Reviewed by: Sam Hall Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Validated by:

Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 1 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Guide Requirements Goal of Training:

To have the crew successfully lower reactor power, respond to a

failure of a temperature channel, fa ilure of 1X03, lowering condenser vacuum, failure of a Circulating Water pump requiring plant trip, failure of manual and auto turbine tr ip and post trip malfunctions that require entry into ECA 0.0. Embedded within these events is the expectation to properly utilize Technical Specifications.

Learning Objectives:

None Prerequisites:

1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

2. Floor Instructor as Shift Technical Advisor

3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

References:

1. OP 2A Normal Power Operations

2. AOP 5A Loss of Condenser Vacuum Unit 1

3. AOP 6C Uncontrolled Rod Motion Unit 1

4. AOP 24 Instrument Failure or Malfunction

5. EOP 0 Reactor Trip or Safety Injection Unit 1

6. EOP 1.1 SI Termination Unit 1

7. ECA 0.0 Loss of All AC Unit 1

8. Alarm Response Books

9. Technical Specifications Commitments:

None Evaluation

Method:

Simulator performance will be evaluated by NRC Examiners IAW

NUREG-1021 Operating Experience:

None Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 2 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Related PRA Information: Initiating Event with Core Damage Frequency:

Transient w/o PCS 1.8E-06

Station Blackout 5.2E-07

Important Components:

Important Operator Actions with Task Number:

Operator fails to align G04 to 1A06 per ECA 0.0 Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 3 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Lower power from 100% to ~94%

IAW OP-2A, Normal Power Operations

2. Failure of 401B Red channel Tcold high

3. Failure of 1X03 transformer After EOP Entry:

1. Main turbine fails to auto and manual trip

2. 1X04 failure

3. G02 and G03 EDG failures

Abnormal Events:

1. Lowering Main Condenser Vacuum

2. Loss of a Circulating Wate r Pump requiring plant trip

Major Transients:

1. ECA 0.0 Critical Tasks:

1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to Main Condenser Vacuum reaching 8 in Hg Abs.

2. E-0 C, SRO/BOP must energize at least one AC emergency bus before placing safeguards equipment in pullout per ECA 0.0 Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 4 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from t he following Standard (Specific) IC sets: IC-111, created from IC-02

2. The following equipment is OOS: G01 EDG 1P-2B Charging Pump 1P-2A and 1P-2C Charging Pu mps are protected equipment G02 EDG is protected equipment SEQUENCE OF EVENTS:

Event 1: Normal downpower Crew performs downpower for Atmospheric Steam Dump testing to 94% per OP-2A Event 2: Failure of 401B Red T cold high Red T cold channel fails high Crew responds per AOP-6C SRO addresses Technical Specifications Event 3: Failure of 1X03 Crew diagnosis and response per ARB's Crew reviews OP-2A fo r operating restrictions SRO addresses Technical Specifications Event 4: Lowering Condenser Vacuum Crew responds to lowering vacuum per AOP 5A Crew determines downpower required per AOP 17A Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 5 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 6 of 33

Reference:

FP-T-SAT-75 Event 5: Loss of Circulating Water Pump BOP responds to 1P-30A high bearing temperature After pump trip SRO determines to trip the plant

Event 6: Main turbine fails to auto and manual trip RO performs RNO actions step 2 EOP 0

Event 7: 1X04, G02 and G03 fail post trip Electrical failures require entry into ECA 0.0 Safeguards busses are recovered via G04 EDG

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES INITIAL CONDITIONS:

Standard IC-111 from IC-02

Unit 1 Mode: 1 Burnup: 7800 MWD/MTU Power: 100% Boron: 735 ppm (MOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 220 steps Generator: 533 Mwe Unit 2 Mode: 1 Burnup: 320 MWD/MTU Power: 100% Boron: 1322 ppm (BOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @ 220 steps Generator: 535 Mwe Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 7 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ CREW POS EXPECTED STUDENT RESPONSES SEQUENCE OF EVENTS / INSTRUCTOR NOTES

1. SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

1P-2B Charging Pump (OOS tag) G01 EDG (OOS tag)

Protected equipment tags on 1P-2A and 1P-2C.

Protected equipment tag for G02 EDG

2. Simulator Pre-brief:

a. Inform the crew that this session will be performed in the evaluation mode per NUREG 10201.

b. If required, inform the crew of differences between the simulator and actual plant equipment.

c. Crew positions

3. COMPLETE TURNOVER:

a. Review applicable current Unit Status.

b. Review relevant At-Power Risk status.

c. Review current LCOs not met and Action Requirements.

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

e. Crew takes the shift.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 8 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1: Normal downpower to 94% per OP-2A

Communication: When notified, System Control Power System Supervisor acknowledges report of downpower.

Communication: When notified, the Auxiliary Operators Acknowledge the downpower and the PAB AO understands the requirement to monitor S/G blowdown.

Communication: When notified, the Unit 1 TH Auxiliary Operator acknowledges the request to start 1P-99A and B, then 2 minutes later reports the pumps are started.

End of evolution:

Proceed to next event at Lead Examiner discretion.

SRO RO/BOP BOP CREW Crew will brief the down power and reactivity control

requirements prior to taking any actions. Record pre-load reduction information in OP 2A Attachment A. An additional letdown orifice may be placed in service. Crew may elect to start 1P-99A and B SGFP Seal Water Injection Pumps.

Lower plant load per OP-2A Attachment A and the pre-job briefing. Monitor the plant during the down power and subsequent stabilization.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 9 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2: T-401B, Red Tcold Fails High

Communication: If asked, I&C is notified and will work on sending in support as requested.

Communication: If asked, the Shift Manager will have OS2 prepare the 0-SOP-IC-001 RED procedure to

remove the failed instrument from service.

RO SRO SRO RO RO BOP RO Recognizes instrument failure for the Red channel Tcold. Recommends placing rods to MANUAL. SRO acknowledged recommendation and alarms.

Enter AOP 6C for uncontrolled rod motion.

Check rod motion required - take rods to manual (CA STEP) Maintain RCS Tave Check RCS Tave at or trending to program - Crew should discuss current temperature and a plan on how to restore

it. Charging may be taken to manual. With the unit at a reduced power program level will be raised to the full power setting based on the circuit selecting auctioneered

high Tave. Condenser Steam Dumps will be shifted to manual pressure control mode per Alarm Response Procedure

actions. Check control rods above insertion limits (CA STEP) Verify AFD within limits Check rod motion due to instrument failure Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 10 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES T-401A, Red Tcold Fails High (cont'd)

NOTE: The intent is to NOT remove the channel from

service.

End of evolution:

Proceed to next event at Lead Examiner discretion.

SRO RO SRO Enter AOP-24 Response to Instrument Malfunction.

Identify failed instrument Check if failed instrument is controlling channel Establish manual control as required Return affected parameters to desired values Using Attachment A verify failed instrument does not affect PPCS RTO Remove failed instrument from service per 0-SOP-IC-001-RED Review Technical Specifications. SRO should review LCO 3.3.1 Instrumentation Table 3.3.1-1 items 5 and 6. LCO 3.3.2 ESFAS Instrumentation Table 3.3.2-1 item 4d-

3. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 11 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3: Lockout of 1X03 HV Station transformer Communication: If asked, the reports for 1X03 are no smoke, fire, or anything abnormal from outside the switchyard. There is a bad thunderstorm with lots of lightning over the plant. If sent into the switchyard the AO confirms or provides

the previous information and that there is a 1X03

sudden pressure trip actuation.

Communication: If asked, SM will inform OS1 that OS2 will work on getting an OI-110 together for starting the Gas Turbine.

Communication:

If asked, the Kewaunee Nuclear Power Generating Station is currently on line at full power. Communication: If asked, the Power System Stabilizers are enabled for PBNP and Kewaunee.

Communication: If asked, the SM will ask OS1 to disable a U2 4160 fast bus transfer along with U1.

NOTE: Next event takes approximately 5-7 minutes to bring in an alarm.

End of evolution:

Proceed to next event at Lead Examiner discretion.

BOP SRO/BOP BOP SRO BOP SRO Identify the loss of 1X03 HV transformer and validate plant conditions are correct. Reviews C02 alarms and verifies they are consistent with the plant conditions: 345 breaker trip, 13.8 breaker trip and 1X03 lockout. ARB for loss of a 345 breaker directs looking in OP-2A for possible power restrictions with less than a fully operable switchyard. There are no power restrictions for Unit 1 and Unit 2 per OP-2A Attachment O. OP-2A Attachment O section 3.0 will require the disabling of one(1) 4160 fast bus transfer for each unit in Mode 1. Typically this is done by going to pullout on the breaker.

LCO 3.8.1 AC Sources - Operating should be reviewed. TSAC 3.8.1.A is entered with direction to start the Gas Turbine within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 12 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4: Lowering Main Condenser Vacuum

Communication:

If asked, local air ejector air flow electronic and manometer are both reading at their high limit of 25 SCFM.

Communication:

If asked to perform Attachment A, wait 3 minutes and have the TH AO report second set of air ejectors are lined up.

NOTE: Vacuum malfunction can be slowed or lessoned to show vacuum is stable or recovering after the second set of air ejectors is lined up.

Communication: If asked, the Shift manager will not place the priming air ejectors in service.

Communication:

If asked, Shift manager can report he will contact the DCS, PSS, NRC Resident and the Duty Regulatory Services Person.

BOP SRO RO CREW BOP SRO CREW Identify that vacuum is lowering in the Main Condenser. Address Low Vacuum alarm when it comes in. Enter AOP 5A for lowering Vacuum.

Maintain RCS Tave.

Check condenser pressure within limits. - Crew should determine if continued plant operation is allowed and set a limit for when the plant should be taken off line. Check for excessive air in-leakage. - AO should be dispatched to get the local readings. Place all available air ejectors in service. - AO should be dispatched to align second set of air ejectors. Check if Priming Air ejector should be used. - SRO should determine this is not required. Notify DCS, PSS, Regulatory Service Duty Person, and NRC Resident.

Reduce Load as necessary per AOP-17A. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 13 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5: Loss of Circulating Water Pump requiring plant trip Communication:

If asked, TH AO reports normal oil level and Service Water cooling to 1P-30A Circulating Water Pump. The Upper motor bearing oil is discolored and the top motor area is very hot to the

touch

RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to Main Condenser Vacuum reaching 8 in Hg Abs BOP SRO Respond to temperature alarm for 1P-30A. BOP will go behind boards to determine which component is alarming.

When the pump trip occurs, the SRO should determine condenser vacuum will not be maintained and direct a unit

trip. Event 6: Failure of Auto and Manual Turbine Trip

RO Determines the Turbine did not trip. Depress the manual trip button Manually runback the turbine Place the EH Pumps to pullout If turbine still not tripped, then shut both MSIV's

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 14 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7: 1X04, G02 and G03 EDG failures causing entry in ECA 0.0

Communication: If asked, wait 2 minutes and the TH AO reportsG03 has indications and alarms locally that

it oversped.

If asked, wait 2 minutes and the TH AO reports G02

output breaker is open and nothing appears abnormal.

Communication: If asked, wait 3 minutes and the TH AO can report that 1X04 LV transformer has tripped due to sudden pressure trip and there are no other

abnormal indications.

NOTE: Crew may elect to go right to ECA 0.0 without taking any actions per EOP 0 Step 3 RNO. Entry

conditions are met.

RO SRO RO RO CREW RO/BOP BOP Determine no 4160 and 480 safeguards busses are energized for Unit 1. Try to fast start any EDG's Try to Exercise start any EDG's If power cannot be restored, have the STA start monitoring Unit 1 CSFST's and transition to ECA 0.0. Enter ECA 0.0

Verify Reactor tripped Verify Turbine tripped. - Will either take action listed in event 6 or verify them taken previously. Monitor foldout page items Maintain RCS inventory - RO and BOP will check various vent valves, sample valves, letdown and PORV's shut. Verify TDAFW Pump operating

Check cooling to AFW Pump bearings Check both 4160 VAC busses not energized Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 15 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES ECA 0.0 (cont'd)

E-0 C, SRO/BOP must energize at least one AC emergency bus before placing safeguards equipment

in pullout per ECA 0.0 BOP SRO BOP BOP/SRO BOP BOP/SRO BOP SRO BOP SRO Check Diesels - All Running Check Diesel Status Check H01 not energized - RNO go to step 11

Check 1A05 not energized Check 1A05 energized from G01 - go to step 13 Energize 1A05 from G02 - G02 output breaker will not close Check 1A06 not energized Energize 1A06 from G03 - cannot be done due to G03 overspeed condition. - Go to step 16. Energize 1A06 from G04 - This will be successful and the crew should energize 1A06 from G04 EDG. Utilize foldout page criteria to transition to step 28.

Verify SW operation Return to procedure step in effect, which was EOP 0 step 3 RNO Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 16 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES ECA 0.0 (cont'd)

RO/BOP RO BOP RO SRO RO Verify safeguards power is available for at least one(1) 4160 and 480 VAC bus.

Check if SI is actuated.

Perform Attachment A Verify Secondary Heat Sink Verify RCP Seal Cooling (CA STEP) Verify RCS Temperature Control Check PZR PORV's shut Check PZR Spray's shut Check if RCP's should remain running Start monitoring Critical Safety Function Status Trees (CA STEP) Verify Containment Sump recirc not required Check if Secondary System is intact Check if Steam Generator tubes are intact Check if RCS is intact inside Containment Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 17 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES ECA 0.0 (cont'd)

NOTE: Lead Evaluator can terminate scenario at any point after transition to EOP 1.1 SI Termination.

RO/BOP SRO BOP RO BOP (CA STEP) Check if SI should be terminated Transition to EOP 1.1 Reset Safety Injection Reset Containment Isolation Reset 1B03 and 1B04 Non-Safeguards Lockouts Check 4160 VAC Safeguards Busses Powered by Offsite Reestablish Instrument Air to Containment Verify Charging Flow

Stop both SI Pumps Stop both RHR Pumps Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 18 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation

valves are both shut.

BOP Verify feedwater isolation.

Verify containment isolation

Verify AFW actuation.

Check SI pumps running.

Check RHR pumps running.

Check only 1 CCW pump running.

Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves.

Verify containment accident cooling.

Check CR ventilation in accident mode.

Check if main steam lines can remain open.

Verify proper SI valve alignment.

Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 19 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 20 of 33

Reference:

FP-T-SAT-75 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EOP 0 Attachment A (cont'd)

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the Computer Room is at 72

ûF. Wait 2 more minutes and report CWPH temperature is at 65

ûF.

BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

(CA STEP) Check AFW Area temperature.

(CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 1: Normal downpower to 94%

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload DSG MAL MAL1DSG001A G01 failure to start Preload CVC BKR BKR1CVC006 6-fail cont pwr fuse 1P-2B OOS for Maint PLE CFW LOA LOA1CFW083 on 1 1P-99A SGFP Seal Water Pump PLE CFW LOA LOA1CFW084 on 1 30 sec delay 1P-99B SGFP Seal Water Pump Expected Communications When notified, the Auxiliary Operators acknowledge the downpower and the PAB AO understands the requirement to monitor S/G blowdown.

When notified, the Unit 1 TH Auxiliary Operator acknowledges the request to start 1P-99A and B, then 2 minutes later reports the pumps are started.

LOAs used Trigger 1 is used to start 1P-99A/B 1 minute after getting the request. Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 21 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 22 of 33

Reference:

FP-T-SAT-75 EVENT 2: 401 Red Tcold failing high Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS XMT XMT1RCS024A 650 3 20 sec ramp 1TE401 Tcold fail high Expected Communications None LOAs used

None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 3: Lockout of 1X03 HV Station Transformer Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE SWD MAL MAL1SWD001A 5 1X03 Lockout Expected Communications If asked, the reports for 1X03 are no smoke, fire, or anything abnormal from outside the switchyard.

There is a bad thunderstorm with lots of lighting over the plant.

If sent into the switchyard the AO confirms or provides the previous information and that there is a 1X03 sudden pressure trip actuation.

LOAs used

None Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 23 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 4: Lowering Ma in Condenser vacuum Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE CFW MAL MAL1CFW005A 550 7 900 sec ramp Loss of Cond A Vacuum PLE CFW MAL MAL1CFW005B 550 7 900 sec ramp Loss of Cond B Vacuum PLE MSS VLV LOA1MSS001 1 15 60 sec ramp 1MS-101 1 st stage AE stm supply PLE MSS VLV LOA1MSS004 1 15 60 sec ramp 1MS-104 1 st stage AE stm supply PLE MSS VLV LOA1MSS018 1 15 60 sec ramp 1MS-98 2nd stage AE stm supply PLE CFW VLV LOA1CFW010 1 15 80 sec delay 1AR-5 AE Air Inlet PLE CFW VLV LOA1CFW013 1 15 80 sec delay 1AR-8 AE Air Inlet PLE CFW VLV LOA1CFW003 1 15 80 sec delay 1AR-14 AE Air Inlet Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 24 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 25 of 33

Reference:

FP-T-SAT-75 Expected Communications If asked, local air ejector air flow electronic and manometer are both reading at their high limit of 25 SCFM.

If asked to perform Attachment A, insert trigger 15, wait 3 mi nutes and have the TH AO report second set of air ejectors are lined up.

NOTE: Vacuum malfunction can be slowed or lessoned to show vacuum is stable or recovering after the second set of air ejectors is lined up. Changing the rate of lowering vacuum takes several minutes to see an effect. The booth operator will have to slow the leak down or st op it several inches of mercury prior to 5" hg ab

s. At the same time as the CW pump trip malfunction, re-insert the original vacuum leak size.

LOAs used

Insert trigger 15 for aligning second set of air ejectors.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 5 Loss of Circulating Wa ter Pump requiring plant trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE CWS XMT XMT1CWS018A 300 20 180 sec ramp 1P-30A CW Pump upper motor bearing high temp PLE CWS PMP PMP1CWS003 2-shaft siezure 20 180 sec delay 1P-30A CW Pump shaft seizure Expected Communications If asked, TH AO reports normal oil level and Service Water cooling to 1P-30A Circulating Water Pump. The Upper motor bearing oil is discolored and the top motor area is very hot to the touch.

LOAs used None Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 26 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 6: Auto and Manual fa ilure of the Turbine Trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload EHC MAL MAL1EHC007A Manual Turbine Trip failure Preload EHC MAL MAL1EHC007B Auto Turbine Trip failure Expected Communications None

LOAs used

None Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 27 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 SIMULATOR INPUT

SUMMARY

Retention: Life of Plant Retain in: Training Program File EVENT 7: 1X04, G02 and G03 EDG failures post trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload DSG MAL MAL1DSG002B G03 overspeed during startup Preload DSG BKR BKR1DSG002 5-fail as is G02 Output Breaker fail as is 1A52-66 Preload EPS MAL MAL1EPS002 9 JCRFTR 1X04 LV Transformer lockout Expected Communications If asked, wait 2 minutes and the TH AO reportsG03 has indications and alarms locally that it oversped. If asked, wait 2 minutes and the TH AO reports G02 output breaker is open and nothing appears abnormal If asked, wait 3 minutes and the TH AO can report that 1X04 LV transformer has tripped due to sudden pressure trip and there are no other abnormal indications. When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation valves are both shut. When contacted, wait 2 minutes and have the AO report room temperatures for the Computer Room is at 72

ûF. Wait 2 more minutes and report CWPH temperature is at 65

ûF. LOAs used None Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 28 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 VERIFY the simulator setup for training mode scenario (for evaluated scenarios use PBF-6801):

Rod counters reset

Training signs installed Watchstation nametags assigned

Horns on All CO station books in proper places Instrument noise on Digital Displays set appropriately

STA CSFST Sheets available All mimic bus magnets in proper positions

MCB / instrument rack doors shut, lights off Sim 20 lighting breakers closed

Radios available and operable

TR-2000 series recorders in Data (auto) /

Scan (auto) SPDS computers restarted Startup Fireworks PC at 1C20 workst ation, if required after initial startup of MST Scenario specific props (tags, protected equipment magnets, etc.) installed: None Ensure the Simulator Base Station is set to Simulator

Talk Group 1. (Clear screen saver by moving mouse. Simulator Group 1 should be outlined in green)

[Ref. CAP 01039821, Item 4]

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 29 of 33

Reference:

FP-T-SAT-75

SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

7500 1500 Reactor power (%):

100% 100% Boron concentration (ppm): 736 ppm 1498 ppm Rod height (CBD @): CBD @ 220 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC Description Reason None 3.0 EQUIPMENT OUT OF SERVICE

G01 EDG is OOS for a scheduled overhaul. 1P-2B Charging Pump is OOS for VFD maintenance.

4.0 PLANNED EVOLUTIONS

Reduce power to 94% for Atmospheric Steam Dump testing.

5.0 TURNOVER INFORMATION

Safety Monitor is Green. G02 EDG is aligned to 1A05 and 2A05 4160 Safeguards busses. G02 EDG is protected equipment. 1P-2A and 1P-2C Charging Pumps are protected equipment. There is a severe thunderstorm watch for the area. Clock time is real time and you have the normal shift complement.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 30 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Attach the following information as necessary: Simulator Set-up Checklist (before and after training) Pre-evaluation Brief Guide (for evaluations only) Post-evaluation Critique (for evaluations only) Turnover Log Historical Record:

(Optional)

Rev 0: This scenario is being developed for the ILT 2009 NRC

Exam.

Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 31 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Simulator Scenario Development Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include justification for the answer or the corrective action needed to correct the discrepancy after the item. Yes No 1. The scenario contains objectives for the desired tasks and relevant human performance tools.

X Yes No N/A 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEG's new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

X Yes No 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

X Yes No 4. Plant PRA initiating events, important equipment, and important tasks are identified.

X Yes No N/A 5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment. X Yes No 6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

X Yes No N/A 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. X Yes No N/A 8. The scenario includes related industry experience.

X Yes No N/A 9. 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.

X Yes No N/A 10. Scenario requires an Emergency Preparedness NARS to be completed. (If YES, a NARS answer key validated by EP personnel is attached to the SEG.) Reference CAP 01021167 - 02.

X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the

cover page. Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 32 of 33

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) PBN LOI NRC 004E, 2009 NRC EXAM SCENARIO 4, Rev. 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1. QF-1075-02 Revision 3 10/08/08 Page 33 of 33

Reference:

FP-T-SAT-75 Simulator Scenario Validation Checklist Mark with an X Yes, No or N/A for any of the following. If the answer is No or N/A, include an explanation after the item.

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

Yes X No 2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes X No 3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes X No 4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes X No 5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes X No 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 Yes X No 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 N/A 8. NARS form is accurate for the classification and release conditions presented during the scenario. (MET data is variable based on instrument noise) Reference CAP 01021167 - 02.

Yes No N/A X Discrepancies noted (Check "none" or list items found)

None SMAR = Simulator Action Request

SMAR: SMAR: SMAR: SMAR: Comments: No was selected for several training items on the development checklist. These items will remain 'NO' due this SEG being developed IAW NUREG 1021 for an Initial NRC license exam. No was selected for step 2 of the development checklist due to this being N/A for our plant.

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