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2012 Point Beach Nuclear Plant Initial License Examination Administered Scenarios with ES-D-1 Forms
	ML13028A093
Person / Time
Site:	Point Beach
Issue date:	12/17/2012
From:	; NRC/RGN-III
To:	;
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ML11354A210	List: ML13016A280; ML13028A085; ML13028A088; ML13028A091; ML13028A093;
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Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: ___1____ Op-Test No.: _2012301___

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Line 111, Point Beach to Sheboygan Energy Center, is OOS for tower repairs, B MFRV controlling channel is shifted to YELLOW, 1W-3B CRDM shroud fan is OOS for bearing failure, Solar Magnetic Disturbance alert for GIC readings greater than 30 amps, IRPI in alternate for 1Y-06-21 breaker replacement, 1PI-2198 Condenser B Pressure Indicator is OOS for I&C calibration, Turnover Unit 1 is stable at 75% power. Following turnover, per OI-72, Containment Air Recirculation System, start Unit 1 A Accident Recirc and Cooling Fans then secure B Accident Recirc and Cooling fans in preparation for upcoming vibration data collection.

Event Malf. Event Event No. No. Type* Description 1 N-BOP Shift Containment Accident Recirc and Cooling Fans N-SRO I-RO 2 I-SRO 1LT-427 Pressurizer Level (White) fails low TS-SRO C-RO 3 C-SRO Loop B RTD Bypass Line leak (20 gpm)

TS-SRO R-RO 4 N-BOP 1W-3A CRDM Shroud Fan trips/Rapid Power Reduction N-SRO 5 M-All Small Break LOCA (500 gpm) 6 C-RO 1P-15A Safety Injection Pump trips 1P-15B Safety Injection Pump fails to auto start 7 C-BOP Main Feed Isolation Valves fail to AUTO close 8 C-BOP RCS Hot Leg Containment Isolation failures with 1 gpm leak

(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 SEG TITLE: 2012 ILT NRC SCENARIO #1 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Additional signatures may be added as desired.

Developed by: Andrew Zommers 7/27/12 Instructor Reviewed by: Joey Trudeau Instructor (Simulator Scenario Development Checklist.)

Validated by: Andrew Zommers Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Approved by: Randy Amundson Training Supervision Approved by: Tom Larson Training Program Owner 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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Guide Requirements To have the crew successfully perform/respond to shifting Accident Fans, Goal of Pressurizer Level Transmitter failure, RCS leak, Rapid Power Reduction, Training: SBLOCA, failure of RCS Hot Leg CI valves with leak and a failure of a Safety Injection Pump. 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/Shift Technical Advisor Training 2. Simulator Booth Operator Resources: 3. Communicator

4. Evaluators

1. OI-72, Containment Air Recirculation System

References:

2. AOP-1D, Chemical and Volume Control System Malfunction

3. AOP-1A, Reactor Coolant Leak Unit 1

4. 0-SOP-IC-001 - White, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - White Channels

5. 0-SOP-IC-002, Technical Specifications LCO-Instrument Cross Reference

6. AOP-17A Rapid Power Reduction Unit 1

7. AOP-24 Response to Instrument Malfunction

8. AOP-21 PPCS Malfunction

9. EOP-0 Reactor Trip or Safety Injection Unit 1

10. EOP-1 Loss of Reactor or Secondary Coolant Unit 1

11. EOP-1.2 Small Break LOCA Unit 1

12. ARB 1C04 1C 2-9, Containment or Aux Bldg Vent System Air Flow Low

13. Alarm Response Books

14. Technical Specifications and Technical Specifications Bases Commitments: 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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Evaluation Simulator performance will be evaluated IAW NUREG 1021.

Method:

Operating N/A Experience:

Initiating Event with Core Damage Frequency:

Related PRA Small LOCA 1.2E-07 Information:

Important Components:

Reactor Protection 0.3%

ESFAS 0.2%

Important Operator Actions with Task Number:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.

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QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. 1LT-427 Pressurizer Level Instrument transmitter fails low

2. Loop B RTD Bypass Line leak

3. 1W-3A CRDM Shroud Fan Trips/Rapid downpower After EOP Entry:

1. 1P-15A SI Pump seized shaft

2. 1P-15B SI Pump failure to auto start

3. MFIVs fail to close

4. RCS Hot Leg Containment Isolation failures with 1 gpm leak Abnormal Events:

1. 1LT-427 Pressurizer Level Instrument transmitter fails low

2. 20 gpm RCS leak on B RTD loop manifold

3. Rapid Power Reduction Major Transients:

1. Small Break LOCA Critical Tasks:

1. E O: Close Containment Isolation valves such that at least one valve is closed on each critical penetration before the end of the scenario.

2. E I: Manually start at least one SI pump prior to transition out of 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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SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Specific IC set:

IC-162, created from IC-03

2. The following equipment is OOS:

Line-111 Point Beach to Sheboygan Energy Center is OOS with disconnects open

B Main Feedwater Regulating Valve controlling channels shifted to YELLOW

1W-3B, B CRDM Shroud Fan (need OOS tag on Control Board)

1W-3A ACRDM Shroud Fan is Guarded Equipment

Red Barrier Tape set up around 1(2) X01 Transformers per AOP-31(Document on White Board behind SM desk)

1PI-2198 Condenser B Pressure Indicator is OOS for I&C calibration SEQUENCE OF EVENTS:

Event 1: Shift Accident Fans

Crew starts A Accident Recirc and Cooling Fans and secures B Accident Recirc and Cooling Fans per OI-72 Event 2: 1LT-427, PZR Level Channel Fails Low

RO recognizes failure of 1LT-427, PZR Level Channel.

Crew enters AOP-1D and determines 1LT-427 has failed.

SRO refers to LCO 3.3.1, LCO 3.3.3, and if applicable LCO 3.4.9.

Crew should swap PZR controlling channel per ARB and restore Letdown and Charging to normal per AOP.

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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Event 3: Loop B RTD Bypass Line Leak at 20 GPM RCS Leak

Loop B RTD bypass line develops a 20 GPM leak

SRO enters AOP-1A, Reactor Coolant Leak.

Crew determines that neither SI nor Rx Trip is required and RO raises charging speed to maintain Pressurizer Level.

Crew enters diagnostic phase of AOP-1A and begins to determine leak location. Crew will possibly isolate Letdown and Charging as part of the diagnostic steps.

Event 4: 1W-3A CRDM Shroud Fan Trips/Rapid Power Reduction

RO responds to annunciator 1C04 1C 2-9, Containment Vent System Air Flow Low, using ARB

ARB directs rapid power reduction using AOP-17A, Rapid Power Reduction

Crew coordinates to lower unit power at 1% per minute with an RCS leak Event 5: Small Break LOCA (500 gpm)

Crew recognizes RCS leak has gotten worse

SRO refers back to continuous action steps and ensures reactor trip and manual SI/CI

SRO enters EOP network Event 6: 1P-15A SI Pump Shaft Seizure and 1P-15B SI Pump Fails to Auto Start

RO recognizes SI pump trip and failure to start

SRO concurs with RO starting 1P-15B 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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Event 7: MFIVs fail to Auto close

BOP recognizes MFIV failure to close

SRO concurs with BOP closing MFIVs manually Event 8: Failure of RCS Hot Leg sample CI valves to shut with 1 gpm leak

BOP recognizes CI valves fail to close

SRO concurs with BOP closing CI valves manually 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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SCENARIO TIME-LINE:

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

Standard IC-162 from IC-03 Unit 1

Mode: 1

Burnup: 16000 MWD/MTU

Power: 73.9%

Boron: 125 ppm (EOL)

Temperature: NOT

Pressure: NOP

Xenon: Equilibrium

Rods: Bank D @ 187 steps

Generator: 475 MWe Unit 2

Mode: 1

Burnup: 6500 MWD/MTU

Power: 26.9%

Boron: 1170 ppm (MOL)

Temperature: NOT

Pressure: NOP

Xenon: Equilibrium

Rods: Bank D @ 143steps

Generator: 175 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator

Line 111 and 1W-3B (OOS tag)

Setup Checklist, including entering action items per the Simulator Input Summary.)

Line 111 disconnects magnets open

Guarded equipment tag for 1W-3A

Red Barrier Tape listed behind SM desk for AOP-31, around 1(2) X01 Transformers

Extra AO name tags

Marked-up copy of AOP-31

1PI-2198 Condenser B PI is OOS for I&C calibration Simulator Pre-brief:

COMPLETE TURNOVER:

Review applicable current Unit Status Review relevant At-Power Risk status Review current LCOs not met and Action Requirements Verify crew performs walk down of control boards and reviews turnover checklists.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Shift Containment Fans per OI-72 SRO Crew will brief the shifting of containment fans prior to assuming the watch.

BOP BOP will start 1W-1A and secure 1W-1B Containment Fans per OI-72.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2: 1LT-427, PZR Level Transmitter Fails RO Acknowledges PZR High/Lo Level alarm and informs Low. Crew. RO recognizes loss of Letdown and recommends going to minimum charging.

RO/BOP RO/BOP address the ARBs for alarms associated with the PZR Level failure NOTE: AOP-1D actions are on this page, see next SRO SRO recognizes entry conditions for AOP-1D, CVCS page for AOP-24 actions. Malfunction and AOP-24 Instrument Failure.

RO Verifies no RCS leak in progress.

SRO Addresses notes prior to step 2 and determines LCO 3.4.9 addressed by the SRO if TS value 1LT-427 failure section of AOP should be performed.

reached. Continues to step 48.

RO recognizes if PZR Level exceeds TS value of 52%

RO and informs the SRO. (May occur depending on timing of actions, though not likely when starting at 75%

If asked by the SRO, Shift Manager directs defeating power) the failed PZR level channel per the ARB.

Crew Crew should swap to different controlling PZR level per ARB 1C04 1C 1-3 Pressurizer Level High or Low BOP Place White PZR level to defeat Crew Restore Letdown and Charging to normal per AOP-1D along with PZR Heaters.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS 1LT-427, PZR Level Transmitter Fails Low. Crew may enter AOP-24 Response to Instrument SRO (contd) Malfunction prior to swapping controlling channels.

RO Identifies 1LT-427 PZR Level as failed instrument.

Checks that instrument is controlling channel for PZR Level Program.

Ensures that Charging is in manual and minimum.

SM should inform SRO that the 4th license will Return affected parameter to desired value - ensures reference AOP-21. that PZR level is returning to program value as well as SRO resetting pressurizer heaters.

References step regarding performance of AOP-21.

NOTE: IF asked for references, the Shift Technical Addresses caution regarding currently tripped Advisor will provide the following logic diagrams bistables - this does not apply as no other bistables as referenced in 0-SOP-IC-001-WHITE page 19. are tripped.

Sheets #175, #180 and #181 and 0-SOP-IC-002 in its entirety. Directs removal of failed instrument IAW 0-SOP-IC-001 WHITE.

Crew Restore Charging to Automatic SRO LCO 3.3.1 and LCO 3.3.3 addressed by the SRO.

3.3.1-1 item 8 PZR water level high Per Lead Examiner, once Letdown is restored with

3.3.3-1 item 14 PZR level is MET charging in manual or auto, proceed to next event.

TSAC 3.3.1.A and 3.3.1.K are entered.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Loop A RTD Bypass Line Leak at 20 Crew Recognizes indications of leakage inside containment:

GPM Rising humidity, Sump A alarm and RMS alarms.

Indications of an RCS leak would be 1RE-211/212 SRO Enters AOP-1A, Reactor Coolant Leak.

radiation monitors in alarm, rising containment Check SI not required (CA): Adequate PZR Level and humidity, Sump A rising, VCT level lowering and the RO Subcooling.

automatic charging pump speeding up.

Check Rx Trip not required (CA): Charging Aligned to VCT.

SRO may address Technical Specifications at this Check Pressurizer Level (CA): stable or trending to time due to RCS leakage. If TS not addressed here, program, Adjusts Charging as needed to maintain a scenario follow-up question will be needed. LCO PZR level and RCP Lab Seals.

3.4.13 is not met due to unidentified leakage exceeding 1 GPM. (TSAC 3.4.13.A) Check Pressurizer Pressure: Stable or trending to program.

Communication: If sent to locally check Charging Check Rx Makeup Controls: Set for proper blend, Pump Relief valves, report reliefs are not lifting.

armed and in auto.

Continue to next event per Lead Evaluator or SRO Request SM notify DCS and implement E-Plan.

determination of leak rate. Ensure charging/letdown is recovered, if it was isolated, prior to downpower. SRO may Address Tech Specs.

SRO Directs performance of steps 7 through 18. These If requested, inform OS1 that the 4th License will steps include directions to isolate letdown and perform the OI-55 calculation. charging and various other leakage possibilities.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4: Loss of 1W-3A, Running CRDM RO Announce failure and refers to Alarm Response Book Shroud Fan trips / Rapid Power Reduction for Motor Breaker Trip and Containment or Aux Bldg Vent System Air Flow Low.

Communication: When sent to local breaker for Inspects PAB/Containment ventilation control station shroud fan, report that the breaker has tripped. If on rear of 1C04 and determines only available CRDM requested to close breaker, report that breaker will BOP shroud fan has tripped. May attempt restart with SRO not stay closed. concurrence. Should contact AO to look at local breaker for fan.

1W3-A control switch might be placed in pullout to Communication: If Electrical Maintenance was clear control board alarms.

contacted to look at the breaker, report back with damage to the breaker cubicle will take several Using guidance in ARB 1C04 1C 2-9, directs rapid hours to troubleshoot. SRO power reduction IAW AOP-17A.

Announces entry into AOP-17A, Rapid Power SRO Reduction.

Determines desired power level and ramp rate and announces to CR - SRO determines that unit be ramped at 1% per minute as directed by ARB.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Rapid power reduction continued SRO SRO also determines that the unit needs to be taken off line and could direct BOP to set the endpoint at 0%

on the turbine.

Requests SM to notify PSS.

RO Checks Rod control in Auto.

BOP Selects Rate Reduction method, likely Operator Auto

- 1st Stage IN per the note prior to step 4.

RO (CA STEP) Commences boration, should refer to ROD 1.3 for power reduction boration and rod bank requirements (CA STEP) Check PZR Pressure - Stable or trending to program (CA STEP) Check PZR Level - Stable at or trending to program 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS (cont): Rapid Power Reduction Unit 1 BOP (CA STEP) Check SG levels - controlling in Auto RO (CA STEP) Maintain T avg - Checks T avg within limits Communication: When requested, TH AO start BOP Check MFW Seal Water Pumps Running - Contacts 1P-99A and B SGFP Seal Water Pumps U1 Turbine Operator to Start 1P-99A and B.

SRO Determines endpoint is MODE 3.

BOP May transfer auxiliary loads.

Per Lead Evaluator, As the leak is unisolable, the Lead Examiner will direct (after approximately a 5% power reduction) when the team is prepared to make the leak larger and booth operator will increase the leak to 500 GPM over 4 minutes.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: Small Break LOCA (500 GPM) Recognizes increased leak rate and uses continuous Crew action guidance from AOP-1A to trip the reactor.

Inserts Manual Trip to trip the reactor.

RO RO inserts manual SI and CI also and carries out Immediate Actions of EOP-0.

Verify Reactor Trip Verify Turbine Trip Verify Safeguards Buses - At least one 4160 and one 480 V Bus energized.

Check if SI is Actuated Verifies Immediate Action steps.

Addresses Fold Out Page.

SRO -Trip RCPs if conditions are met BOP Performs Attachment A. (actions listed later)

RO Verifies Secondary Heat Sink

- Checks S/G levels

- Verifies proper AFW flow for heat sink

- Maintains S/G levels 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Small Break LOCA (500 GPM) contd RO Verify RCP Seal Cooling

- Checks CCW pump operating

- Checks Lab Seal DP (CA STEP) Verify RCS Temp Control Ensure MSIVs are shut.

Check PZR PORVs both shut.

Check Normal spray valves both shut.

Check Aux spray valve shut.

Check if RCPs should remain running SRO Start Monitoring CSFSTs (CA STEP) Verify Sump Recirc not required Check if Secondary System intact Check if S/G Tubes intact Check if RCS is intact inside containment - NO 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Small Break LOCA (500 GPM) contd SRO Transition to EOP-1 RO Check if RCPs should remain running BOP Check if Secondary System is intact (CA STEP) Stabilize intact S/G levels Check Secondary System Radiation Normal RO (CA STEP) Check PORV and PORV Block Valves BOP Reset SI Reset Containment Isolation Reset 1B03 and 1B04 lockouts Check 4160 Safeguards busses powered Re-establish Instrument Air to Containment RO Verify Charging Flow Check if SI flow should be terminated (CA STEP) Check if Spray should be stopped 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Small Break LOCA (500 GPM) contd BOP Check if RHR pumps should be stopped RO Check RCS and S/G pressures BOP Check if EDGs should be stopped The 4th License will secure the running EDGs.

Crew Initiate evaluation of plant status Check if RCS is intact outside containment - might answer NO and transition to ECA-1.2 LOCA Outside Lead Evaluator can terminate the scenario once Containment Step 16 of EOP-1 is addressed if all critical tasks are met. If the flowpath out of containment via Check RHR Pump Room High alarms clear the RCS Hot Leg Sample line is not isolated then SRO Check if RCS cooldown and depressurization required the crew should be allowed to transition to ECA-1.2 to address the penetration leak prior to Transition to EOP 1.2 Small Break LOCA terminating the scenario.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A BOP Verify feedwater isolation - NO, manually shut MFIVs.

Verify containment isolation.

Verify AFW actuation.

Check SI pumps running.

Unit 2 will enter TSAC 3.7.8.F when SW-2907 and Check RHR pumps running.

2908 are opened.

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.

Communication: When contacted the PAB AO should report that SW-LW-61 and 62 radwaste SW Check CR ventilation in mode 5. - CUE PURPLE isolation valves are both shut. LIGHT IS LIT 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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SCENARIO TIME-LINE:

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

Verify SI flow.

Stop any boration via the blender in progress (CA STEP) Check CSR ventilation operating. - CUE W-13A1 RED LIGHT IS LIT.

(CA STEP) Check Computer Room ventilation operating.

(CA STEP) Ensure Aux Building filter/exhaust fans operating.

Communication: When contacted, wait 2 minutes and have the AO report CWPH temperature at 65 F and (CA STEP) Check AFW Area ventilation operating.

stable.

(CA STEP) Energize façade Freeze protection at the discretion of Operations Shift Management.

Communication: When contacted, wait 2 minutes and (CA STEP) Check CWPH temperature.

have the PAB AO report SFP temperature at 75F and stable with level at 63 feet and stable. (CA STEP) Periodically check the status of SFP cooling.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: 1P-15A SI Pump trip and 1P-15B SI Pump BOP RO notices 1P-15A pump trip and failure of 1P-15B to fails to AUTO start start. After immediate actions 1P-15B can be manually started or during EOP-0 Attachment A Communications: If contacted, PAB AO reports guidance will be to start 1P-15B manually.

seized shaft on 1P-15A SI Pump.

Communications: If contacted TH AO reports breaker for 1P-15A is tripped on overcurrent.

Communications: If contacted TH AO reports breaker for 1P-15B is normal and state current position.

CRITICAL TASK: E I: Manually start at least one SI pump prior to transition out of EOP-0.

Event 7: MFIV's fail to AUTO close BOP During performance of EOP-0 Attachment A step A1, the BOP should recognize the MFIV's did not close as required and take manual action to shut these valves.

Event 8: RCS Hot Leg Sample Line fails to isolate BOP During performance of EOP-0 Attachment A step A2, with 1 gpm leak the BOP should recognize the RCS Hot Leg Sample Line did not isolate as required. Procedurally the BOP CRITICAL TASK: E O: Close Containment Isolation valves such that at least one valve is should initiate a manual CI and take 1SC-966C to closed on each critical penetration before the end of closed and inform the SRO.

the scenario.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS End the scenario by placing the simulator in freeze Crew:

Inform Examinees they are to remain at their stations and

No debrief or critique due to this being an cannot discuss the scenario. They are to wait for any evaluated scenario.

follow up questions the examiners may have.

EVENT 3: 20 GPM RCS leak B Loop RTD manifold Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE RCS MAL MAL1RCS003F 20 3 120 ramp Loop B RTD Manifold Leak Expected Communications PAB AO: If sent to locally check Charging Pump Relief valves, report reliefs are not lifting.

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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

EVENT 8: RCS Hot Leg Sample Line fails to isolate with 1 gpm leak Relative System Or Severity Or Event Order Panel Drawing Type Code Value Trigger Timing Description Preload NSS VLV VLV1NSS005D 0.5 7 (JCRFTR) 1SC-955 RCS Hot Leg fails partially open Preload NSS VLV VLV1NSS009D 1.0 1SC-966C RCS Hot Leg Sample valve fails open Preload NSS FLX FLX1NSS001 1 gpm 7 (JCRFTR) HTX 14C Shell Tube Leak at 1 gpm Preload X01I121C.eq.1 Conditional for taking 1SC-966C to shut on Panel C01, will override the failed open malfunction so valve can shut manually.

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)

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: This SEG was developed for the 2012 NRC ILT Examination.

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) 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life 16000 6500 (MWD/MTU):

Reactor power (%): 73.9% 26.9%

Boron concentration 125 ppm 1170 ppm (ppm):

Rod height (CBD @): CBD @ 187 CBD @ 143 Target AFD 1.5 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Reason None None None 3.0 EQUIPMENT OUT OF SERVICE:

Line 111, Point Beach to Sheboygan Energy Center, is Out of Service for emergent tower repairs.

1W-3B Shroud Fan is Out of Service for bearing failure.

4.0 PLANNED EVOLUTIONS:

After shift turnover, start 1W-1A Containment Fans and secure 1W-1B Containment Fans per OI-72.

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) 5.0 TURNOVER INFORMATION:

Safety Monitor is Green.

Line 111, Point Beach to Sheboygan Energy Center is OOS for emergent tower repairs.

Unit 1 is at 75% power with Xenon stable per ATC for grid stability.

AOP-31, Solar Magnetic Disturbance Alert Response, is in effect for both units due to a Kp6 SMD Alert. ATC has notified PBNP that 1X-01 DC Neutral Current (GIC) readings are 32 amps and continuous monitoring is in effect per step 5 and Attachment B. The 4th license is providing the Auxiliary Operators with control room data for Attachment B. ATC is continuing to monitor 2X-01 DC Neutral Current (GIC) readings. Red barrier tape is put up around 1(2) X01 Transformers.

1W-3B, Containment Control Rod Shroud Fan, is Out of Service due to bearing failure.

1-43/RPI, Rod Position Indication Power Transfer Switch is in Alternate (1Y-02-15) for 1Y-06-21 breaker replacement.

SG B Feedwater Flow Control and SG B Steam Flow Control Transfer Switches have been selected to Yellow after performance of 1 ICP 02.001 BL, Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test.

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.

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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.

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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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.

Discrepancies noted (Check none or list items found) None SMAR = Simulator Action Request SMAR: SMAR: SMAR: SMAR:

Comments:

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in 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.: _2012301___

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Line 111, Point Beach to Sheboygan Energy Center, is OOS for tower repairs, B MFRV controlling channel is shifted to YELLOW, 1W-3B CRDM shroud fan is OOS for bearing failure, Solar Magnetic Disturbance alert for GIC readings greater than 30 amps, IRPI in alternate for 1Y-06-21 breaker replacement, 1PI-2198 Condenser B Pressure Indicator is OOS for I&C calibration, Turnover: Unit 1 is at 100% power. Normal shift routine is anticipated per the plant schedule.

Event Malf. Event Event No. No. Type* Description C-BOP 1 C-SRO 1P-11A CCW Pump trip and 1P-11B CCW Pump fails to auto start TS-SRO 2 C-RO 1CV-135 Letdown Line Backpressure Controller oscillations C-SRO (controller works in manual) 3 TS-SRO G02 Emergency Diesel Generator Low Starting Air Pressure alarm R-RO 4 N-BOP Solar Magnetic Disturbance AOP-31 1%/hr ramp per AOP-17A, N-SRO Rapid Power Reduction 5 I-SRO 1PT-485 Turbine First Stage Pressure fails low with rod motion I-RO failure requiring plant trip 6 Failure of BS-2 345 KV Bus Section, H52-31, 13.8 KV cross-tie M-ALL breaker, G01 and G03 Emergency Diesel Generators (ECA 0.0 entry) 7 C-RO 3 stuck rods post trip

(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 SEG TITLE: 2012 ILT NRC SCENARIO #2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Additional signatures may be added as desired.

Developed by: Andrew Zommers 7/27/12 Instructor Date Reviewed by: Joey Trudeau Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Andrew Zommers Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by: Randy Amundson Training Supervision Date Approved by: Tom Larson Training Program Owner 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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Guide Requirements To have the crew successfully perform/respond to loss of CCW Pump, Goal of CV-135 oscillations, G01 EDG low air pressure, Solar Magnetic Training: Disturbance requiring rapid downpower, 1PT-485 failure with Rod Motion failure requiring trip, ECA-0.0 and stuck rods. 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/Shift Technical Advisor Training 2. Simulator Booth Operator Resources: 3. Communicator

4. Evaluators

1. AOP-9B Component Cooling Water Malfunction Unit 1

References:

2. AOP-1D, Chemical and Volume Control System Malfunction Unit 1

3. 0-SOP-IC-001 - White, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - White Channels

4. 0-SOP-IC-002, Technical Specifications LCO-Instrument Cross Reference

5. AOP-6C Uncontrolled Rod Motion Unit 1

6. AOP-17A Rapid Power Reduction Unit 1

7. AOP-24 Response to Instrument Malfunction

8. AOP-21 PPCS Malfunction

9. AOP-31 Solar Magnetic Disturbance Unit 1

10. EOP-0 Reactor Trip or Safety Injection Unit 1

11. EOP-0.1 Reactor Trip Response Unit 1

12. ECA 0.0 Loss of All AC Unit 1

13. Alarm Response Books

14. Technical Specifications and associated Bases Commitments: None Evaluation Simulator performance will be evaluated IAW NUREG 1021.

Method:

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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Operating N/A Experience:

Initiating Event with Core Damage Frequency:

Related PRA Information: Transient w/o PCS 7.3E-07 Station Blackout 5.2E-07 Important Components:

Component Cooling Water 2.1% CDF Important Operator Actions with Task Number:

Operator Fails to Start CCW Pumps Operator fails to align G04 to 1A06 per ECA 0.0 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)

QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Running CCW Pump trips with no Auto start of standby CCW Pump

2. Failure of CV-135 Letdown Backpressure Controller

3. G02 EDG alarm, low starting air pressure

4. 1PT-485 Turbine First Stage Pressure fails low After EOP Entry:

1. Bus section 2 lockout with H52-31 H01 to H02 tie breaker failure

2. G01 and G03 EDG failures

3. 3 stuck control rods Abnormal Events:

1. A CCW Pump Trip

2. 1CV-135 letdown Backpressure controller failure

3. G02 Starting Air Low Pressure

4. Solar Magnetic Disturbance

5. 1PT-485 failure with Rod Control failure Major Transients:

1. ECA 0.0 Loss of All AC Critical Tasks:

1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to automatic rod motion stopping with AFD in 'UNACCEPTABLE OPERATION' region of TRM Figure 6.

2. E C: SRO/BOP must energize at least one AC emergency bus before placing safeguards equipment in pullout per ECA 0.0.

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)

SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Specific IC set:

IC-161, created from IC-02

2. The following equipment is OOS:

Line-111 Point Beach to Sheboygan Energy Center is OOS with disconnects open

B Main Feedwater Regulating Valve controlling channels shifted to YELLOW

1W-3B, B CRDM Shroud Fan (need OOS tag on Control Board)

1W-3A ACRDM Shroud Fan is Guarded Equipment

Red Barrier Tape set up around 1(2) X01 Transformers per AOP-31 (Document on White Board behind the SM desk)

1PI-2198 Condenser B Pressure Indicator is OOS for I&C calibration SEQUENCE OF EVENTS:

Event 1: Running CCW Pump Shaft Seizure with failure of Standby CCW Pump to Auto start.

Crew recognizes failure and manually starts Standby CCW Pump

SRO Enters AOP-9B Component Cooling Water System Malfunction

SRO Addresses Technical Specifications Event 2: Failure of CV-135 Letdown Backpressure Controller

RO takes manual control and stabilizes system parameters

SRO directs crew response with AOP-1D CVCS Malfunction Event 3: G02 EDG alarm, low starting air pressure

Crew responds per ARB C02 F 2-1, G-02 Emergency Diesel alarm

SRO declares G02 OOS

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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Event 4: Solar Magnetic Disturbance AOP-31/Rapid Power Reduction

Crew responds to call from AO that neutral current is 65 amps

AOP-31 directs rapid power reduction using AOP-17A, Rapid Power Reduction

Crew coordinates to lower unit power at 1% per minute Event 5: Turbine First Stage Pressure Transmitter PT-485 fails Low

Crew recognizes failure and takes manual control of rods.

SRO Enters AOP-6C Uncontrolled Rod Motion

RO recognizes rod control failure requiring plant trip Event 6: Failure of BS-2, H52-31, G01, G02, G03 requiring entry into ECA 0.0

Crew recognizes failures require entry into ECA-0.0

Crew aligns a safeguards bus via G04 Event 7: 3 stuck rods

RO recognizes stuck rods during immediate actions

Attempts another manual trip of reactor

SRO later determines boration required for stuck rods 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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SCENARIO TIME-LINE:

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

Standard IC from IC-02 (IC-161)

Unit 1

Mode: 1

Burnup: 8100 MWD/MTU

Power: 99.7%

Boron: 947 ppm (MOL)

Temperature: NOT

Pressure: NOP

Xenon: Equilibrium

Rods: Bank D @ 220 steps

Generator: 619 Mwe Unit 2

Mode: 1

Burnup: 950 MWD/MTU

Power: 99.4%

Boron: 1461 ppm (BOL)

Temperature: NOT

Pressure: NOP

Xenon: Equilibrium

Rods: Bank D @ 220 steps

Generator: 623 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator

Line 111 and 1W-3B (OOS tag)

Setup Checklist, including entering action items per the Simulator Input Summary.)

Line 111 disconnects magnets open

Guarded equipment tag for 1W-3A

Red Barrier Tape listed behind SM desk for AOP-31, around 1(2) X01 Transformers

Extra AO name tags

Marked-up copy of AOP-31

1PI-2198 Condenser B PI is OOS for I&C calibration Simulator Pre-brief:

COMPLETE TURNOVER:

Review applicable current Unit Status Review relevant At-Power Risk status Review current LCOs not met and Action Requirements Verify crew performs walk down of control boards and reviews turnover checklists.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Running CCW Pump Shaft Seizure BOP BOP identifies the A CCW Pump failure with the B with failure of Standby CCW Pump to CCW Pump not auto starting. BOP requests from the Auto start. SRO to start B CCW Pump manually. (1C03 1D 2-6 and 1C03 1D 3-7)

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

start 1P-11B CCW Pump.

Crew will address surge tank level which will require Communications: If asked, the PAB AO will report Crew nothing unusual with the B CCW Pump discharge no action.

pressure indicator, it reads 125 psig locally. Crew will address system leakage requiring no action.

Check Reactor Trip Communications: If asked, the TH AO will report the A CCW Pump breaker has tripped on overcurrent. Check RHR Status SRO Chemistry will be requested to analyze CCW.

NOTE: Crew may elect to place 1P-11A in pullout to OS1 will ask the SM to call DCS and implement clear Motor Breaker Trip alarm. Emergency Plan.

Send AOs out locally to the pump/breaker and BOP/RO discharge pressure indicator to find any problems.

End of evolution: Proceed to next event at Lead SRO 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 Examiner discretion. 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: Failure of CV-135 Letdown RO/SRO RO identifies CV-135 pressure controller malfunction Backpressure Controller and takes controller to manual to control back pressure.

Addresses ARB for Letdown High Pressure (1C04 1C 4-6).

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

RO Check RCS leak not in progress.

Communications:

If asked, the PAB AO reports there is nothing SRO Reviews foldout page criteria abnormal with CV-135.

Determine CVCS malfunction - CV-135 pressure RO control which directs transition to step 36.

NOTE: AOP-24 may be utilized in addition to Establish manual control of CV-135 - 250#

AOP-1D. (see next page for AOP-24 actions)

SRO 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 37 RNO)

End of evolution: Proceed to next event at Lead Examiner discretion. May send out the PAB AO to look at CV-135 locally.

BOP 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)

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Failure of CV-135 Letdown Backpressure SRO Crew may also enter AOP-24 Response to Instrument Controller (contd) Malfunction.

RO CV-135 pressure controller malfunction Checks that instrument is controlling channel for PZR Level Program and takes controller to manual to control back pressure.

Return affected parameter to desired value - ensures that pressure is returning to normal.

References step regarding performance of AOP-21.

SRO Addresses caution regarding currently tripped bistables - this does not apply as no other bistables are tripped.

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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP Address G02 alarm on panel C02. Dispatches AO to Event 3: G02 EDG alarm, low starting air determine local alarm that is in.

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

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 LCO 3.8.3 not met, enter TSAC 3.8.3.D immediately bank 160 psig and slowly lowering. The north and declare G02 OOS for both units.

bank air compressor is running with one of the bank relief valves leaking by. (ARB C65A C35 P7)

LCO 3.8.1 not met, enter TSAC 3.8.1.E for required standby emergency power sources inoperable for both NOTE: IF asked by the OS1, the Shift Manager units.

will state OS2 will prepare the required paperwork per OI-35A to align G01to 2A05.

May ask for Diesel Air Start PID, M-209 Determine the need to align G01 to both 1A05 and Sheet 12 (#134). 2A05.

Call in Maintenance to troubleshoot and fix.

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)

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4: SMD AOP-31 / Rapid Power SRO Crew is receives a call from AO on Unit 1.

Reduction Determine that GSU DC Neutral Amps are 65 amps Crew determines rapid downpower per AOP-31 is required.

SRO directs rapid power reduction IAW AOP-17A.

Communication: AO at 1X01 Transformers reports that the GSU Neutral Amps are sustained 65 amps for the last 5 minutes.

Communication: If asked, AO at Unit 2 X01 Transformers reports conditions remain stable.

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)

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS (cont): Rapid Power Reduction Unit 1 Determines desired power level and ramp rate and announces to CR - SRO determines that unit be ramped at 1% per minute as directed by AOP.

SRO SRO will direct BOP to set the endpoint at 78% on the turbine.

Requests SM to notify PSS.

Checks Rod control in Auto.

RO Selects Rate Reduction method, likely Operator Auto BOP - 1st Stage IN per the note prior to step 4.

(CA STEP) Commences boration, should refer to RO ROD 1.3 or the reactivity management sheets for power reduction boration and rod bank requirements (CA STEP) Check PZR Pressure - Stable or trending to program (CA STEP) Check PZR Level - Stable at or trending to program 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS (cont): Rapid Power Reduction Unit 1 BOP (CA STEP) Check SG levels - controlling in Auto RO (CA STEP) Maintain T avg - Checks T avg within limits Communication: When requested, TH AO start BOP Check MFW Seal Water Pumps Running - Contacts 1P-99A and B SGFP Seal Water Pumps U1 Turbine Operator to Start 1P-99A and B.

SRO Determines endpoint is <50% - NO.

End of evolution: Proceed to next event at approximately a 5% power reduction or 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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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: Turbine First Stage Pressure RO Identifies inward rod motion, recommends placing rod Transmitter PT-485 fails Low and rod control in Manual motion fails requiring plant trip SRO Concurs with recommendation, directs placing rods in Manual RO Rod Motion not responding, recommends reactor trip RT-7, When a reactor trip is procedurally called for, Inserts Manual Trip to trip the reactor.

initiate a manual reactor trip prior to automatic rod motion stopping with AFD in 'UNACCEPTABLE Verify Reactor Trip OPERATION' region of TRM Figure 6.

Verify Turbine Trip Verify Safeguards Buses Determine no 4160 and 480 safeguards busses are energized for Unit 1.

Try to fast start any EDGs Try to load any running EDGs If power cannot be restored, have the STA start monitoring Unit 1 CSFSTs and transition to ECA 0.0.

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 4 11/18/09 Page 16 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: Bus Section 2 H52-31, G-01, G-02 and G-03 EDG failures causing entry in ECA 0.0 SRO Enter ECA 0.0 RO Verify Reactor tripped Communication: If asked, wait 2 minutes and the TH AO reports G03 has indications and alarms locally that Verify Turbine tripped it oversped.

SRO Monitor foldout page items Communication: If asked, wait 2 minutes and the TH AO reports G01 output breaker is open and nothing Ensure both RCPs - Stopped appears abnormal.

RO/BOP Maintain RCS inventory - RO and BOP will check Communication: If asked, wait 2 minutes and the TH various vent valves, sample valves, letdown and AO reports G02 EDG is not running and everything PORVs shut.

looks normal.

BOP Verify TDAFW Pump operating Communication: If asked, wait 3 minutes and the TH Check cooling to AFW Pump bearings AO can report that H52-31 tie breaker is tripped and there are no other abnormal indications. Check both 4160 VAC busses not energized 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.

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 4 11/18/09 Page 17 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SCENARIO TIME-LINE:

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

BOP Check Diesels - All Running NOTE: Additional SW Pumps may be started per ARB to ensure adequate SW header pressure. Check Diesel Status Communication: If the SM is asked, direct OS1 that SRO Check H-01 not energized - Start G05 and continue the 3rd RO will start G05.

BOP Check 1A-05 not energized Communication: SM will concur with OS1 recommendations concerning EDG operation (Starting BOP/SRO Check 1A-05 energized from G01 - breaker wont or securing.) close go to step 14 BOP Energize 1A-05 from G02 - G02 did not start Check 1A-06 not energized Energize 1A-06 from G03 - cannot be done due to BOP/SRO G03 overspeed condition. - Go to step 17.

BOP Energize 1A-06 from G04 - Manually shut alternate breaker.

SRO Check 480 Vac busses at least one energized - Yes 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)

SCENARIO TIME-LINE:

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

BOP Verify SW System operation SRO Return to procedure step in effect, which was EOP 0 E-0 C, SRO/BOP must energize at least one AC step 3 RNO emergency bus before placing safeguards equipment in pullout per ECA 0.0 SRO Verify safeguards power is available for at least one(1) 4160 and 480 VAC bus RO/BOP Check if SI is actuated - NO go to EOP-0.1 SRO Transition to EOP-0.1 RO (CA STEP) Verify RCS Temperature Control using Atmospheric Steam Dumps Communication: If asked, OS2/4th License will take BOP Verify Feedwater Isolation step 7 RNO action.

Transfer Feedwater Control to the Bypasses - NO (CA STEP) Stabilize S/G Levels Verify Generator Trip Ensure Miscellaneous Electrical Loads are Energized 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)

SCENARIO TIME-LINE:

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

BOP Check All AC Busses Energized by Offsite Power th Communication: If asked, OS2/4 License will take step 7 RNO action. RO Verify Charging Pump Suction Alignment Communication: If asked, the PAB AO verifies that Verify Charging Flow 1CV-112 B is SHUT and 1CV-112C is OPEN.

Check ALL Control Rods Fully Inserted - NO The scenario can be terminated at Lead Evaluators discretion or once action has been Check Pressurizer Level >12%

taken to start the boration.

Event 7: 3 stuck rods RO Recognizes 3 control rod stuck after reactor trip.

May attempt another trip with second set of trip buttons.

While in EOP-0.1 recall there are 3 stuck control rods Crew and take actions per the RNO to borate.

Take action to borate for 3 stuck rods by adding 2825 gallons of acid for each stuck rod.

End the scenario by placing the simulator in freeze Crew:

Inform Examinees they are to remain at their stations

No debrief or critique due to this being an and cannot discuss the scenario. They are to wait for evaluated scenario.

any follow up questions the examiners may have.

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)

SIMULATOR INPUT

SUMMARY

Scenario preloads Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload SWD LOA LOA1SWD001 OPEN SWYD Line 111 breaker Preload SWD LOA LOA1SWD002 OPEN SWYD Line 111 disconnects Preload CNM BKR BRK1CNM018 6-Fail 1W-3B Shroud Fan Breaker Cntl Fuse Preload Preload 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 4 11/18/09 Page 21 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

EVENT 1: Loss of 1P-11A and failure of 1P-11B to auto start Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload CCW BKR BKR1CCW002 4-Fail to 1P-11B CCW Pump fails to auto Auto start Close PLE CCW PMP PMP1CCW001 2-Shaft 1 1P-11A CCW Pump shaft seizure Seizure Expected 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.

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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Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

EVENT 2: 1CV-135 Letdown Backpressure Controller failure Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE CVC CNH CNH1CVC014F 50 3 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 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)

SIMULATOR INPUT

SUMMARY

EVENT 3: G02 EDG alarm, low starting air pressure Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE G02 ANN ANN-C02F-B01 0-ON 5 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 valves is 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.

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Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

EVENT 4: Solar Magnetic Disturbance requiring rapid plant downpower Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE CFW LOA LOA1CFW083 ON 14 1P-99A SGFP Seal Water Pump PLE CFW LOA LOA1CFW084 ON 14 30 sec delay 1P-99B SGFP Seal Water Pump Expected Communications

When requested, TH AO starts 1P-99A and B SGFP Seal Water Pumps (Trigger 14)

AO at 1X01 Transformers reports that the GSU Neutral Amps are sustained 65 amps for the last 5 minutes.

If asked, AO at Unit 2 X01 Transformers reports nothing has changed.

Expected Communications:

If asked, wait 2 minutes and the TH AO reports G01 appears normal

If asked, wait 2 minutes and the TH AO reports G03 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 H52-31 has tripped 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 CWPH temperature is at 65F and stable.

When asked PAB AO will be directed to locally shut 1SI-896 and 1SI-856 MOVs.

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 4 11/18/09 Page 28 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

EVENT 7: 3 stuck rods Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE CRF MAL MAL1CRF001- 1-Non 7 Stuck Rod - B6 B6 Trip PLE CRF MAL MAL1CRF001- 1-Non 7 Stuck Rod - D10 D10 Trip PLE CRF MAL MAL1CRF001- 1-Non 7 Stuck Rod - F12 F12 Trip 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 4 11/18/09 Page 29 of 34

Reference:

FP-T-SAT-75

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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: This SEG was developed for the 2012 NRC ILT Examination.

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) 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life 8100 950 (MWD/MTU):

Reactor power (%): 99.7% 99.4%

Boron concentration 947 ppm 1461 ppm (ppm):

Rod height (CBD @): CBD @ 220 CBD @ 220 Target AFD -4.6 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Reason None None None 3.0 EQUIPMENT OUT OF SERVICE:

Line 111, Point Beach to Sheboygan Energy Center, is Out of Service for emergent tower repairs.

1W-3B Shroud Fan is Out of Service for bearing failure.

4.0 PLANNED EVOLUTIONS:

Normal Shift Routine 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) 5.0 TURNOVER INFORMATION:

Safety Monitor is Green

Line 111, Point Beach to Sheboygan Energy Center is OOS for emergent tower repairs.

AOP-31, Solar Magnetic Disturbance Alert Response, is in effect for both units due to a Kp6 SMD Alert. ATC has notified PBNP that 1X-01 DC Neutral Current (GIC) readings are 32 amps and continuous monitoring is in effect per step 5 and Attachment B. The 4th license is providing the Auxiliary Operators with control room data for Attachment B. ATC is continuing to monitor 2X-01 DC Neutral Current (GIC) readings. Red barrier tape is put up around 1(2) X01 Transformers.

1W-3B, Containment Control Rod Shroud Fan, is Out of Service due to bearing failure.

1-43/RPI, Rod Position Indication Power Transfer Switch is in Alternate (1Y-02-15) for 1Y-06-21 breaker replacement.

SG B Feedwater Flow Control and SG B Steam Flow Control Transfer Switches have been selected to Yellow after performance of 1 ICP 02.001 BL, Reactor Protection and Engineered Safety Features Blue Channel Analog 92 Day Surveillance Test.

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 4 11/18/09 Page 32 of 34