Text

2009 Point Beach Initial License Examination Proposed Dynamic Simulator Scenarios
	ML100920278
Person / Time
Site:	Point Beach
Issue date:	05/11/2009
From:	Bielby M; NRC/RGN-III/DRS/OLB
To:	; Florida Power & Light Energy Point Beach
References
	NRC 2009-0022
	Download: ML100920278 (142)
	v • d • e

Appendix 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months was entered 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago. The goal of the shift is to maintain current plant conditions.

Event Malf. Event Event No. No. Type* Description 1 C-BOP C-SRO 1P-11A CCW pump trip with failure of 1P-11B auto start TS-SRO 2 I-RO VCT level transmitter 112 fails low I-SRO 3 C-BOP Trip of Accident Fan W1B1 TS-SRO 4 R-RO N-BOP B SGFP high bearing temp and associated power reduction N-SRO 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)

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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Validated by: Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Guide Requirements To have the crew successfully respond to a failure of a CCW pump, Goal of VCT level transmitter failure, Accident Fan trip, Loss of a SG Feed Training: Pump, feed line rupture in containment, 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 None Objectives:

1. Simulator available Prerequisites: 2. Students enrolled in Initial License Program

1. Floor Instructor as Shift Manager Training 2. Floor Instructor as Shift Technical Advisor Resources: 3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

1. OP 1C Startup to Power Operation Unit 1

References:

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 System Malfunction Unit 1

7. EOP 0 Reactor Trip or Safety Injection

8. EOP 2 Faulted Steam Generator 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 Simulator performance will be evaluated by NRC Examiners IAW Evaluation NUREG-1021 Method:

Operating None Experience:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Initiating Event with Core Damage Frequency:

Related PRA Feedline Rupture in Containment CDF 9.8E-07 Information:

Important Components:

Important Operator Actions with Task Number:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Loss of 1P11A CCW Pump with 1P11B failure to auto start

2. VCT Level transmitter LT-112 fails LOW

3. Loss of 1W1B Accident Fan

4. High bearing temperature on SGFP P-28B

5. B Feed line rupture 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 containment 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the 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 Pumps are protected equipment

1W-45A Bus Duct Cooling Fan is protected equipment SEQUENCE OF EVENTS:

Event 1: Failure of 1P11A CCW Pump with 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

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 containment pressure nearing 2 psig

Crew enters EOP 0 and performs immediate actions

Transition is made to CSP-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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, 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 EXPECTED STUDENT RESPONSES POS 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

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

1. SIMULATOR SET UP (perform set up per the 1W-45B Bus Duct Cooling Fan Simulator Setup Checklist, including entering action 1P-29 TDAFW Pump (OOS tag) items per the Simulator Input Summary.)

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

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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Failure of 1P11A CCW Pump with 1P-11B BOP/SRO BOP identifies the A CCW Pump failure with the B CCW failure to auto start Pump not auto starting. BOP requests from the SRO to start B CCW Pump manually.

BOP or RO address ARBs as applicable.

Communications: If asked, the PAB AO reports the A CCW Pump inboard motor bearing is hot to the touch. Crew Enter AOP 9B CCW malfunction to address the lost CCW Pump. BOP will verify adequate tank level and start 1P-11B CCW Pump.

If asked, the PAB AO will report nothing unusual with the B CCW Pump discharge pressure indicator, it Crew will address surge tank level which will require no reads 125 psig locally. action.

Crew will address system leakage requiring no action.

If asked, the TH AO will report the A CCW Pump breaker has tripped on overcurrent. SRO Chemistry will be requested to analyze CCW.

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

NOTE: Crew may elect to place 1P-11A in pullout to clear Motor Breaker Trip alarm. Send AOs out locally to the pump/breaker and discharge BOP/RO pressure indicator to find any problems.

End of evolution: Proceed to next event at Lead Examiner discretion.

SRO Address LCO 3.7.7 CCW and enter 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TSAC 3.7.7.A Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: Failure of 1LT-112 VCT Level Transmitter RO/SRO RO identifies LT-112 failed low due to auto make up LOW occurring and not required. Requests from the SRO to take make up to off.

NOTE: Crew may go to AOP-24 to address instrument Crew Crew enters AOP-1D CVCS Malfunction to address the failure. If AOP-24 is used go to next page of the SEG. level transmitter failure.

RO RO determines no RCS leak in progress SRO Determines malfunction to be LT-112 and goes to step 58 Communications: If asked, the APB AO reports nothing abnormal locally with LT-112. RO VCT Divert valve to VCT.

Make up controls to STOP.

Communications: If SM is contacted regarding DCS and I&C reply the notifications are taking place. SRO/RO VCT level control in manual should be discussed.

SRO SRO addresses Technical Requirements Manual for the failed transmitter. There are no implications due to LT-141 still being operable.

End of evolution: Proceed to next event at Lead OS1 will ask the SM to Inform DCS and I&C Duty and Examiner discretion. Call.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Failure of 1LT-112 VCT Level Transmitter LOW SRO Crew enters AOP-24 for instrument failure.

(contd)

RO Identify failed instrument.

RO 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 SRO 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 End of evolution: Proceed to next event at Lead Check for TS or TRM applicability. Address Technical Examiner discretion. Requirements Manual for the failed transmitter. There are no implications due to LT-141 still being operable.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Trip of Accident Fan 1W1B BOP BOP responds to board alarms for Low Air Flow associated with the 1W1B Accident Fan and Motor Breaker Trip.

NOTE: Have an OI-72 marked up and available if crew BOP references ARP(s) for Low Air Flow and/or Motor elects to start 1W-1A1. Breaker Trip to validate alarm(s).

SRO may elect to start 1W-1A1 to maintain a normal SRO alignment with 3 Accident Fans running. At a minimum, they should discuss monitoring RCP and Containment conditions if two fans are left operating.

NOTE: Next event takes several minutes to bring in an alarm. SRO addresses TS 3.6.6 and enters TSAC 3.6.6.C for the B Accident Fan, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

End of evolution: Proceed to next event at Lead Examiner discretion.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: 1P-28B Main Feed Pump high bearing RO RO acknowledges the 1TR-2000B Recorder alarm.

temperature RO/BOP address ARBs as applicable.

BOP Goes behind the boards to determine affected component.

Communication: If asked reply with the following as Send out an AO to investigate 1P-28B status.

requested by the control room. The U1 TH AO reports the 1P-28B SGFP inboard motor bearing is hot to the SRO Crew enters AOP-2B Feedwater System Malfunction touch and the paint is slightly discolored. Oil temperature was 95F at the start of watch and is now RO (CA STEP) maintain power <100%

105F. There is lower than normal oil flow since BOP Check FRV response normal rounds were taken. Normal service water flow, oil reservoir level normal, oil pressure is normal, seal Check S/G level <78%

water flow/temperature normal and no smoke.

Check MFPs running Check Condensate pumps running SRO Check MFPs normal, crew should determine the RNO column is applicable. Crew ramps Unit to <60% load per AOP 17A.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS 1P-28B Main Feed Pump high bearing temperature SRO Determine power level to be met. Crew determines ramp (contd) to <60% turbine load.

OS1 asks the SM to notify PSS of load ramp.

RO Check control rod system in AUTO.

NOTE: Acknowledge SRO request to have SM SRO Select ramp reduction method and rate.

notify PSS. RO (CA STEP) Borate to keep rods above insertion limits.

(CA STEP) Check PZR Pressure normal.

(CA STEP) Check PZR Level normal.

BOP (CA STEP) Check S/G level controlling in AUTO.

End of evolution: Proceed to next event at Lead RO (CA STEP) Maintain RCS Tave.

Examiner discretion.

BOP Check SGFP Seal Water pumps operating.

Event 5: B feed line ruptures inside containment Crew Diagnose a secondary leak with containment humidity rising, Sump A level rising, containment pressure rising and no RMS alerts or alarms.

RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to 5 psig in SRO Enter AOP 2A and will eventually trip reactor based on containment approaching 2 psig inside containment. SRO will direct a plant trip and enter EOP 0.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: Reactor trip buttons fail to operate in RO When the Unit trip is called for, the RO recognizes the RX Control Room 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.

CREW (CA STEP) Monitor folder page criteria

- Should identify adverse containment conditions

- Should isolate feed flow to the B S/G BOP Verify Automatic Actions per Attachment A RO/BOP Verify Secondary Heat Sink Available CREW 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: P-38A and P-38B fail to operate as BOP determined the A and B MDAFW Pumps are not BOP designed. operating as designed.

BOP and SRO may elect to attempt 1 restart of P-38A Communication: If asked, the TH AO reports nothing MDAFW Pump.

abnormal with P38B MDAFW Pump, Motor or associated breaker. SRO should determine entry into CSP-H.1 Loss of Heat Sink is required.

Communication: If asked, the TH AO reports P-38A SRO MDAFW Pump motor is very hot to the touch and if BOP should stop performing actions in EOP 0 Attachment asked the breaker tripped on overcurrent. A after transition to CSP-H.1.

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS P-38A and P-38B fail to operate as designed CREW (CA STEP) Monitor folder page criteria (contd)

BOP SRO should direct completion of Attachment C RO 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 Ts in the RCS loops.

RO Verify S/G sample and Blowdown valves shut Check control room indications for cause of loss of AFW Communication: AO will be contacted to locally align SRO Check total feed flow greater than 200 GPM. SRO should AFW per Attachment B of CSP H.1. Acknowledge assign an AO to perform Attachment B for local valve the request; however, valve lineups do not affect the alignments.

scenario and do not need to be performed Stop Both RCPs RO RO Check Condensate Pumps - AT LEAST ONE RUNNING NOTE: Crew may or may not have to start a RO/BOP (CA STEP) Maintain hotwell level greater than 5 inches condensate pump based on their actions from the previous failure. Check condensate and feedwater piping intact

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS P-38A and P-38B fail to operate as designed RO/BOP Establish feedwater flow path. Crew will reset SI and verify (contd) 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.

FR-H.1 A Restore feedwater flow into at least one Check SGFP Discharge MOV open.

steam generator before RCS bleed and feed is required. Establish S/G levels. Crew will feed the A S/G to restore level.

SRO Return to procedure step in effect. SRO directs return to EOP-0 step 6.

RO Verify RCP Seal cooling NOTE: EOP 0 Attachment A should be recommenced after exiting CSP-H.1. (CA STEP) Verify RCS Temperature Control Check PZR PORVs shut Check PZR Sprays shut Check if RCPs should remain running SRO Start monitoring Critical Safety Function Status Trees RO/BOP (CA STEP) Verify Containment Sump Recirculation not Required Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS P-38A and P-38B fail to operate as designed BOP Check if Secondary System is intact - NO (contd)

SRO Transition to EOP-2 RO Check RCS Hot Leg wide range temperatures stable BOP Isolate both MSIVs NOTE: Lead Evaluator can terminate scenario at Check if any S/G is not faulted any point after entry into EOP-2.

CSP H.1 Attachment C actions Verify Safeguards busses energized.

BOP 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 MSIVs can remain open.

Verify Containment Spray is not required.

Check 4160 VAC safeguards busses energized by offsite.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A 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 Communication: When contacted the PAB AO should contact the PAB to check 2 local valves and isolate loads report that SW-LW-61 and 62 radwaste SW isolation per Event 8 below.

valves are both shut.

Verify containment accident cooling.

Check CR ventilation in accident mode.

Check if main steam lines can remain open.

Verify proper SI valve alignment.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A (contd) BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the (CA STEP) Check AFW Area temperature.

Computer Room is 72F. Wait 2 more minutes and report CWPH temperature at 65F. (CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

SUMMARY

EVENT 1: Failure of 1P11A CCW Pump with 1P-11B failure to auto start Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload MGA MAL MAL1MGA005B - 1W-45B Bus Duct Fan OOS Preload SGN VLV VLV1SGN015 1-Fail CP 1P-29 TDAFW Pump OOS Fuse (1MS-2019)

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

Preload CVC BKR BKR1CVC006 6- Fail CP 1P-2B Charging Pump OOS Fuse Preload AFW VLV VLVAFW031 1- Fail CP 1AF-4000 OOS Fuse Preload AFW VLV VLVAFW032 1- Fail CP 1AF-4001 OOS Fuse PLE CCW PMP PMP1CCW001 2-shaft 1 1P-11A CCW Pump seizure CCW BKR BKR1CCW002 4-fail to Preload 1P-11B CCW Pump auto close Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

SUMMARY

Expected Communications

If asked, wait one minute and have the PAB AO reports the A CCW Pump inboard motor bearing 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 report the A CCW Pump breaker has tripped on overcurrent Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

SUMMARY

EVENT 2: Failure of 1LT-112 VCT Level Transmitter LOW Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description CVC XMT XMT1CVC019A 0 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 EVENT 3: Loss of 1W-1B1 Accident Fan Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 EVENT 4: 1P-28B Main Feed Pump high bearing temperature Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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 95F at the start of watch and is now 105F. 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 EVENT 5: B feed line ruptures inside containment Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload PPL BST BST1PPL056 1-fail as 1PC945A SI Cont Pres is bistable Preload PPL BST BST1PPL060 1-fail as 1PC947A SI Cont Pres is bistable PLE CFW FLX FLX1CFW031 5000 9 900 sec B feedline break inside containment Expected Communications None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 EVENT 6: Reactor trip buttons fail to operate in Control Room Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload PPL OVR OVR1PPL033 Off Reactor trip Button 1C04 Preload PPL OVR OVR1PPL034 Off Reactor trip Button 1C04 Expected Communications None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 EVENT 7: P38A and P38B MDAFW pumps fail to operate as designed Relative System Or Order Panel Severity Drawing Type Code 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 P-38B MDAFW Pump fails to is start Expected Communications

If asked, the TH AO reports P38A MDAFW Pump, Motor hot to the touch and associated 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 report room temperatures for the Computer Room is 72F. Wait 2 more minutes and report CWPH temperature at 65F.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, 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 workstation, if required after initial Scenario specific props (tags, protected equipment magnets, startup of MST 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.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 Post Scenario Simulator Restoration P&Ids cleaned and restored Marked up procedures replaced Marked up ARBs/ARPs cleaned Simulator restored to appropriate IC (default is IC2)

Scenario specific props (tags, protected equipment signs, etc.) removed

Mimic bus magnets restored to appropriate IC IF last session of the day, THEN

Depost access doors

Replace burned out lights

Replace spent charts

Shutdown MST Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life 14200 4500 (MWD/MTU):

Reactor power (%): 75% 26%

Boron concentration 88 ppm 1109 ppm (ppm):

Rod height (CBD @): CBD @ 181 CBD @ 158 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Reason One turbine driven AFW pump system inoperable in MODE 1, 2 or 3 for reasons 1P-29 TDAFW Pump was placed OOS 4 other than Condition A. hours ago for bearing replacement on the 3.7.5.B turbine.

Restore turbine driven AFW pump system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3.0 EQUIPMENT OUT OF SERVICE:

1P-29 TDAFW pump OOS for bearing replacement.

1AF-4000 and 1AF-4001 TDAFW Discharge MOVs 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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SHIFT TURNOVER INFORMATION 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

1. The scenario contains objectives for the desired tasks and relevant human Yes No performance tools. X

2. The scenario identifies key parameter response, expected alarms, and Yes No N/A automatic actions associated with the induced perturbations. (This action X applies to all SEGs 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.)

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

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

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Yes No N/A Assessment. X

6. The scenario contains procedurally driven success paths. Procedural Yes No discrepancies are identified and corrected before training is given. X

7. The scenario guide includes responses for all anticipated communications to Yes No N/A simulated personnel outside the Control Room, based on procedural X guidance and standard operating practices.

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

9. Training elements and specific human performance elements are addressed Yes No N/A in the scenario critique guide to be used by the critique facilitator. The X critique guide includes standards for expected performance.

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

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 001E, 2009 NRC EXAM SCENARIO 1, Rev. 0 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 No X

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

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

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

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

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

7. Evaluation: The simulator is capable of being used to satisfy learning Yes No N/A or examination objectives without exceptions, significant performance X discrepancies, or deviation from the approved scenario sequence.

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

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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Appendix 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months was entered 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago. The goal of the shift is to maintain current plant conditions.

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

SITE: POINT BEACH SEG # PBN-LOI-NRC-002E SEG TITLE: 2009 NRC EXAM SCENARIO #2 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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Validated by: Tom Larson Operations Department Representative Date Approved by: Randy Amundson Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Guide Requirements To have the crew successfully respond to a failure of a CV-135, B SI Goal of pump control power failure, loss of bus duct cooling resulting in a Training: downpower, small RCS leak, LOCA, failure 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 None Objectives:

1. Simulator available Prerequisites: 2. Students enrolled in Initial License Program

1. Floor Instructor as Shift Manager Training 2. Floor Instructor as Shift Technical Advisor Resources: 3. Simulator Booth Operator

4. Communicator

5. NRC Examiners

1. AOP 1D CVCS Malfunction Unit 1

References:

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 Recirculation - Low Head Unit 1

7. Technical Specifications None Commitments:

Simulator performance will be evaluated by NRC Examiners IAW Evaluation NUREG-1021 Method:

None Operating Experience:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Initiating Event with Core Damage Frequency:

Related PRA Large LOCA CDF 3.4E-08 Information:

Important Components:

Important Operator Actions with Task Number:

Operator fails to align for LHR Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 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, initiate a manual reactor trip prior to pressurizer level reaching 10%

2. E0-I Manually start 1P-15A prior to exiting EOP 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the 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 Pumps are protected equipment

1P-2A and 1P-2C Charging Pumps 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0

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, Transfer 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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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 EXPECTED STUDENT RESPONSES POS 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.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

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

1. SIMULATOR SET UP (perform set up per the 1W-45B Bus Duct Cooling Fan Simulator Setup Checklist, including entering action 1P-29 TDAFW Pump (OOS tag) items per the Simulator Input Summary.)

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

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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Failure of CV-135 Letdown Backpressure RO/SRO RO identifies CV-135 pressure controller malfunction and Controller takes controller to manual to control back pressure.

Addresses ARB for Letdown High Pressure.

SRO Enter AOP 1D to address the malfunction and verify actions taken.

RO Check RCS leak not in progress.

SRO Reviews foldout page criteria Communications:

If asked, the PAB AO reports there is nothing abnormal Determine CVCS malfunction - CV-135 pressure control with CV-135. RO which directs transition to step 36.

SRO Establish manual control of CV-135 NOTE: AOP-24 may be utilized in addition to AOP-1D. Request SM to notify DCS and I&C Duty and Call (see next page for AOP-24 actions)

The crew will have to keep CV-135 in manual control and discuss how this will be done. (may review step 36 RNO)

BOP May send out the PAB AO to look at CV-135 locally.

End of evolution: Proceed to next event at Lead Examiner discretion.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Failure of CV-135 Letdown Backpressure SRO Crew enters AOP-24 for instrument failure.

Controller (contd)

RO Identify failed instrument/controller.

RO 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.

End of evolution: Proceed to next event at Lead Examiner discretion. SRO Return controls to automatic, which cannot be done.

Letdown pressure control in manual should be discussed Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP Responds to critical control power relay with ARB. Sends Event 2: Failure of 1P-15B SI Pump control power AOs in the field to determine cause of alarm.

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

Communications:

If AOs are sent to electrical busses or specific Informs the SRO which component is affected, 1P-15B.

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 SRO Determines LCO 3.5.2 is not met and TSAC 3.5.2.A is (Relay 1-74/A85FM located on 1A52-85) entered with 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the pump to operable.

If Maintenance is notified inform the SRO an Electrician is OS1 should ask the SM to notify Maintenance to on the way to investigate.

determine cause of failure and repair.

Crew may ask the relay to be pulled to clear the critical NOTE: If the relay is to be removed, then clear the control power relay to allow other potential alarms process malfunction and report relay 1-74/A85FM is removed. through.

Crew may elect to place 1P-15B control switch to pullout.

End of evolution: Proceed to next event at Lead Examiner discretion.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CREW Identifies RMS trends, lowering VCT level and Sump A Event 3: 10 gpm RCS leak B RTD manifold rising which indicates an RCS leak.

Enter AOP 1A RCS leak to stabilize plant parameters.

The OS must differentiate between a primary and RO RO controls charging as needed to determine an RCS secondary leak. With this small of an RC leak, it will leak rate.

take about 4-5 minutes before an RMS alert is received.

(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 SRO entered with 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to reduce leakage.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS 10 gpm RCS leak B RTD manifold (contd) RO Check make up controls set at desired value SRO OS1 should ask the SM to notify DCS and implement Emergency plan BOP Check S/G tubes intact Communications: Shift Manager will be asked to notify RO DCS and implement E-Plan Check RCP seal leakoff normal 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP Address ARB and direct the TH1 AO to investigate alarm.

Event 4: Failure of 1W-45A Bus Duct Cooling Fan Informs the SRO of equipment status and the need for unit NOTE: Bus Duct Cooling Air Temp High alarm is ramp received about 3 minutes after initial fan failure.

Enter AOP-17A and perform approximately a 5%/min SRO 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.

Communications: TH1 AO reports back that the fan 1W-45A has thrown its belts due to the motor pulley falling off. OS1 should inform the SM to notify PSS of load reduction.

PAB and TH AOs will be notified to monitor the Check rod control in auto. RO should inform the SRO rods changing plant conditions due to the downpower. are already in auto.

RO Select rate reduction method and reduce load.

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

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Failure of 1W-45A Bus Duct Cooling Fan (contd) RO (CA STEP) Check Pressurizer Level Stable at OR trending to program level.

(CA STEP) Check Steam Generator Level controlling - IN Communications: Unit 1 TH AO will be requested to BOP AUTO start 1P-99A and B and will report back when complete. RO (CA STEP) Maintain RCS Tavg BOP Check Main Feed Pump Seal Water Pump - RUNNING.

BOP will have AO start 1P-99A and 99B.

Determine Desired end point - LESS THAN 50%

SRO TURBINE LOAD. SRO will determine this is NO.

RO (CA STEP) Check if boration can be stopped.

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

End of evolution: Proceed to next event after an appropriate load reduction per Lead Examiner discretion.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS RO Determines RCS leak has gotten worse and plant trip is Event 5: Large LOCA, Rx trip, Transfer to sump required.

recirculation Recommend trip of the unit with manual SI/CI per RO/SRO 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 CRITICAL TASK: RT-7, When a reactor trip is IAs with no SI pumps running. - perform manual SI and procedurally called for, initiate a manual reactor CI trip prior to pressurizer level reaching 10%

When reviewing foldout page criteria the crew should CREW determine RCPs need to be tripped and adverse containment conditions exist. - SI pump should be manually started with injection verified prior to RCP securing SRO/BOP Direct EOP 0 Attachment A to be completed RO Verify secondary heat sink Verify RCP Lab seal D/P Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large LOCA, Rx trip, Transfer to sump RO (CA STEP) Verify RCS temperature control.

recirculation (contd)

Check PORVs shut.

Check Spray valves shut.

Check if RCPs should remain running. RCPs should have been secured per foldout page criteria, if not they Communications: STA will be asked to commence should be secured here.

monitoring Status Trees, acknowledge request.

Start monitoring CSFSTs. SRO should direct the STA to SRO perform this function.

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 RO (CA STEP) Verify containment sump recirc not required.

CSP-P.1. If they do transition prior to transition to EOP 1.3, step 1 of CSP-P.1 sends them back to SRO Transition to EOP 1.3 containment sump recirc.

procedure step in effect.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large LOCA, Rx trip, Transfer to sump BOP Reset SI recirculation (contd)

RO Check RCS break size.

BOP Check if containment sump pH should be adjusted.

BOP Check if train A SI flow should be stopped. - stop train A ECCS system BOP Check if Train B should be stopped - go to step 6 Communication: AO will be contacted to complete RO (CA STEP) Monitor Core Cooling Attachment A of EOP 1.3 Transfer to Containment Sump Recirc. Acknowledge request and then insert BOP Direct PAB operator to perform Attachment A trigger 13. No follow up report is required because the attachment will not be complete prior to the end of the RO/BOP Direct unnecessary personnel to evacuate the PAB scenario.

BOP Check Control Room fans armed RO/BOP Isolate CCW to containment Isolate CCW to NRHX Check SW Pumps 6 running Check SW header a continuous flowpath Establish CCW to RHR HXs Ensure Core Deluge valves are open Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large LOCA, Rx trip, Transfer to sump RO/BOP Align SI test lines for recirc recirculation (contd)

Align RHR pump suction valves Communication: AO will be contacted to complete Check Train A ready for recirculation - yes step 16.b in EOP 1.3 to locally shut both SI test line return isolation valves. Acknowledge report and then Check Train B ready for recirculation - no insert trigger 15. Report when valves are shut.

Check at least 1 train ready for recirculation - yes train A SRO Note reference for other procedures are now applicable that do not interfere with EOP 1.3 BOP 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.

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%.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

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

CRITICAL TASK: E0-I Manually start 1P-15A prior Check SI pumps running. If not previously started 1P-15A to exiting EOP 0 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.

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW isolation Verify containment accident cooling.

valves are both shut.

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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A (contd) BOP (CA STEP) Verify containment spray not required.

Verify SI flow.

(CA STEP) Check CSR temperature.

Communication: When contacted, wait 2 minutes and have the AO report room temperatures for the (CA STEP) Check AFW Area temperature.

Computer Room is 72F. Wait 2 more minutes and report CWPH temperature at 65F. (CA STEP) Check Computer Room temperature.

(CA STEP) Check CWPH temperature.

Event 6: Failure of 1P-15A SI Pump to auto start BOP 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.

SRO This pump can be started per OM 3.7 which allows taking Communication: If an AO is requested to locally check the pump or breaker report there is nothing abnormal action if auto actions have failed or attachment A of EOP 0 from the field. will check this equipment.

This pump should be started when the crew has to trip the RCPs due to loss of subcooling on foldout page criteria CRITICAL TASK: E0-I Manually start 1P-15A prior EOP 0.

to exiting EOP 0 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: Failure of 1SI-852A Core Deluge to auto BOP Determine that 1SI-852A core deluge did not auto open.

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

Communication: If an AO is requested to locally check This valve can be opened per OM 3.7 which allows taking the valve breaker report there is nothing abnormal action if auto actions have failed or attachment A of EOP 0 from the field. will check this valve in the proper position.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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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 System Or Severity Or Event Order Panel Drawing Type Code Value Trigger Timing Description Preload MAL1MGA005B - 1W-45B Bus Duct Fan OOS Preload SGN VLV VLV1SGN015 1-Fail CP 1P-29 TDAFW Pump OOS Fuse (1MS-2019)

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

Preload CVC BKR BKR1CVC006 6- Fail CP 1P-2B Charging Pump OOS Fuse Preload AFW VLV VLVAFW031 1- Fail CP 1AF-4000 OOS Fuse Preload AFW VLV VLVAFW032 1- Fail CP 1AF-4001 OOS Fuse 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.

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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 System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE SIS BKR BKR1SIS002 6-fail cntrl 3 1P-15B control power fuse pwr fuse faiure PLE ANN C02 ANN-C02D-D06 OFF 20 Clear control power failure alarm window Expected Communications

If AOs 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.

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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 System Or Severity Event Order Panel Drawing Type Code Or Value 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.

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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 System Or Order Panel Severity Event Drawing Type Code Or Value Trigger Timing Description PLE MGA BKR BKR1MGA008 6-fail CP 7 1W-45A failure fuse As CFW LOA LOA1CFW083 ON 9 Start 1P-99A SGFP Seal Water requested Injection Pump As CFW LOA LOA1CFW084 ON 9 30 sec delay Start 1P-99B SGFP Seal Water requested 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 AOs 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.

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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, Transfer to sump recirculation Relative System Or Order Panel Severity Event Drawing Type Code Or Value Trigger Timing Description PLE RCS MAL MAL1RCS002F 80 11 360 sec ramp LOCA B RCS INT Loop As LOA LOA1CCW016 0 13 60 sec Ramp 1 CC740A requested As LOA LOA1CCW021 0 13 120 sec Delay 1 CC750A requested 60 sec Ramp As LOA LOA1SIS030 0 15 60 sec Ramp 1 SI 897A requested As LOA LOA1SIS031 0 15 60 sec Delay 1 SI 897B requested 60 sec Ramp Expected Communications

When the PAB AO is contacted, the PAB 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 report room temperatures for the Computer Room is 72F. Wait 2 more minutes and report CWPH temperature at 65F.

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.

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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 System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload SIS BKR BKR1SIS001 4-fails to 1P-15A fails to auto start auto close Expected Communications

If an AO is requested to locally check 1P-15A pump or breaker 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.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 Event 7: Failure of 1SI-852A Core Deluge to auto open Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload SIS VLV VLV1SIS027 4-fails to 1SI-852 core deluge auto open Expected Communications

If PAB AO sent to look at breaker locally, nothing abnormal should be reported to control room.

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.

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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 workstation, if required after initial Scenario specific props (tags, protected equipment magnets, startup of MST 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.

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SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life 7800 320 (MWD/MTU):

Reactor power (%): 100% 100%

Boron concentration 735 ppm 1322 ppm (ppm):

Rod height (CBD @): CBD @ 220 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Reason One turbine driven AFW pump system 3.7.5.B inoperable in MODE 1, 2 or 3 for reasons 1P-29 TDAFW Pump was placed OOS 4 other than Condition A. hours ago for bearing replacement on the turbine.

Restore turbine driven AFW pump system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3.0 EQUIPMENT OUT OF SERVICE:

1P-29 TDAFW pump OOS for bearing replacement

1AF4000 and 1AF-4001 TDAFW Discharge MOVs 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.

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SHIFT TURNOVER INFORMATION 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 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.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

PBN LOI NRC 002E, 2009 NRC EXAM SCENARIO 2, Rev. 0 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.