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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 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 No. Malf. No. Event Type* Event Description 1 N-BOP N-SRO Shift Containment Accident Recirc and Cooling Fans 2 I-RO I-SRO TS-SRO 1LT-427 Pressurizer Level (White) fails low 3 C-RO C-SRO TS-SRO Loop 'B' RTD Bypass Line leak (20 gpm) 4 R-RO N-BOP N-SRO 1W-3A CRDM Shroud Fan trips/Rapid Power Reduction 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)

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 1 of 38

Reference:

FP-T-SAT-75 SITE: POINT BEACH SEG # PBN LOI NRC SEG TITLE:

201 2 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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 2 of 38

Reference:

FP-T-SAT-75 Guide Requirements Goal of Training: To have the crew successfully perform/respond to shifting Accident Fans , Pressurizer Level Transmitter failure, RCS leak, Rapid Power Reduction, 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 Objectives:

None Prerequisites: 1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

/Shift Technical Advisor

2. Simulator Booth Operator

3. Communicator

4. Evaluator s

References:

1. OI-72, Containment Air Recirculation System 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 Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 3 of 38

Reference:

FP-T-SAT-75 Evaluation Method: Simulator performance will be evaluated IAW NUREG 1021.

Operating Experience:

N/A Related PRA Information:

Small LOCA 1.2E

-07 Initiating Event with Core Damage Frequency:

Reactor Protection 0.3%

Important Components:

ESFAS 0.2%

None Important Operator Actions with Task Number:

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 4 of 38

Reference:

FP-T-SAT-75 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Before EOP Entry:

Malfunctions:

1. 1 L T-4 27 Pressurizer Level Instrument transmitter fails low 2. Loop 'B' RTD Bypass Line leak

3. 1W-3 A 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. MFIV's fail to close

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

1. 1LT-427 Pressurizer Level Instrument transmitter fails low Abnormal Events:

2. 20 gpm RCS leak on 'B' RTD loop manifold

3. Rapid Power Reduction

1. Small Break LOCA Major Transients:

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.

Critical Tasks:

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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 5 of 38

Reference:

FP-T-SAT-75 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-3 B , 'B' CRDM Shroud Fan (need OOS tag on Control Board) 1 W-3 A 'A'CRDM 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 Fan s and secures 'B' Accident Recirc and Cooling Fan s per OI-72 Event 2 RO recognizes failure of 1LT-427, PZR Level Channel

. : 1LT-427, PZR Level Channel Fails Low 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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 6 of 38

Reference:

FP-T-SAT-75 Event 3 : Loop 'B' RTD Bypass Line Leak at 2 0 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 RO responds to annunciator 1C04 1C 2

-9, Containment Vent System Air Flow Low , using ARB : 1W-3 A CRDM Shroud Fan Trips/Rapid Power Reduction 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: Crew recognizes RCS leak has gotten worse Small Break LOCA (500 gpm) SRO refers back to continuous action steps and ensures reactor trip and manual SI/CI SRO enters EOP network Event 6: RO recognizes SI pump trip and failure to start 1P-15A SI Pump Shaft Seizure and 1P-15B SI Pump Fails to Auto Start SRO concur s with RO starting 1P-15B

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 7 of 38

Reference:

FP-T-SAT-75 Event 7: BOP recognizes MFIV failure to close MFIV's fail to Auto close SRO concur s with BOP closing MFIV's manually Event 8: BOP recognizes CI valves fail to close Failure of RCS Hot Leg sample CI valves to shut with 1 gpm leak SRO concurs with BOP closing CI valves manually

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 8 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

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

Standard IC

-162 from IC-03 Unit 1 Mode: 1 Burnup: 16000 MWD/MTU Power: 7 3.9% Boron: 125 ppm (EOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @

187 steps Generator: 475 M W e Unit 2 Mode: 1 Burnup: 6500 MWD/MTU Power: 2 6.9% Boron: 1 170 ppm (MOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @

143steps Generator: 1 75 M W e Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 9 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

Line 111 and 1W

-3 B (OOS tag) Line 111 disconnects magnets open Guarded equipment tag for 1W-3 A Red Barrier Tape listed behind SM desk for AOP

-3 1 , around 1(2) X01 Transformers Extra AO name tags Marked-up copy of AOP

-31 1PI-2198 Condenser B P I 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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 10 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1 : Shift Containment Fans per OI-72 End of evolution: Proceed to next event at Lead Examiner discretion.

SRO BOP Crew will brief the shifting of containment fans prior to assuming the watch

. BOP will start 1W-1A and secur e 1W-1B Containment Fans per OI

-72.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 11 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 2 : 1LT-427, PZR Level Transmitter Fails Low.

NOTE : AOP-1D actions are on this page, see next page for AOP

-24 actions

.

LCO 3.4.9 addressed by the SRO if TS value reached.

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

RO RO/BOP SRO RO SRO RO Crew BOP Crew Acknowledges PZR High/Lo Level alarm and informs Crew. RO recognizes loss of Letdown and recommends going to minimum charging.

RO/BOP address the ARB's for alarms associated with the PZR Level failure SRO recognizes entry conditions for AOP-1D, CVCS Malfunction and AOP-24 Instrument Failure.

Verifies no RCS leak in progress.

Addresses notes prior to step 2 and determines 1LT-427 failure section of AOP should be performed. Continues to step 48.

RO recognizes if PZR Level exceeds TS value of 52% and informs the SRO. (May occur depending on timing of actions, though not likely when starting at 75% power) Crew should swap to different controlling PZR level per ARB 1C04 1C 1

-3 Pressurizer Level High or Low Place White PZR level to defeat Restore Letdown and Charging to normal per

AOP-1D along with PZR Heaters

.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 12 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 1LT-427, PZR Level Transmitter Fails Low. (cont'd)

SM should inform SRO that the 4 th license will reference AOP

-21. NOTE: IF asked for referenc e s, the Shift Technical Advisor will provide the following logic diagrams as referenced in 0

-SOP-IC-001-WHITE page

19. Sheets #17 5, #180 and #1 81 and 0-SOP-IC-002 in its entirety

.

Per Lead Examiner, once Letdown is restored with charging in manual or auto, proceed to next event.

SRO RO SRO Crew SRO Crew may enter AOP

-24 Response to Instrument Malfunction prior to swapping controlling channels.

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.

Return affected parameter to desired value

- ensures that PZR level is returning to program value as well as resetting pressurizer heaters

. References step regarding performance of AOP

-21. Addresses caution regarding currently tripped bistables

- this does not apply as no other bistables are tripped.

Directs removal of failed instrument IAW 0-SOP-IC-001 WHITE.

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

3.3.1-1 item 8 PZR water level high 3.3.3-1 item 14 PZR level is TSAC 3.3.1.A and 3.3.1.K are entered.

MET Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 13 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3 : Loop 'A' RTD Bypass Line Leak at 2 0 GPM Indications of an RCS leak would be 1RE-211/212 radiation monitors in alarm, rising containment humidity, Sump A rising, VCT level lowering and the automatic charging pump speeding up.

SRO may address Technical Specifications at this time due to RCS leakage. If TS not addressed here, a scenario follow

-up question will be needed. LCO 3.4.13 is not met due to unidentified leakage exceeding 1 GPM.

(TSAC 3.4.13.A)

Communication:

If sent to locally check Charging Pump Relief valves, report reliefs are not lifting.

Continue to next event per Lead Evaluator or determination of leak rate.

Ensure charging/letdown is recovered

, if it was isolated

, prior to downpower.

If requested, inform OS1 that t he 4 thCrew License will perform the OI

-55 calculation.

SRO RO

SRO SRO Recognizes indications of leakage inside containment: Rising humidity, Sump 'A' alarm and RMS alarms.

Enters AOP

-1A, Reactor Coolant Leak.

Check SI not required (CA): Adequate PZR Level and Subcooling.

Check Rx Trip not required (CA): Charging Aligned to VCT. Check Pressurizer Level (CA): stable or trending to program, Adjusts Charging as needed to maintain PZR level and RCP Lab Seals.

Check Pressurizer Pressure: Stable or trending to program. Check Rx Makeup Controls: Set for proper blend, armed and in auto.

Request SM notify DCS and implement E

-Plan. SRO may Address Tech Specs.

Directs performance of steps 7 through 18. These steps include directions to isolate letdown and charging and various other leakage possibilities.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 14 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 4 : Loss of 1W

-3 A, Running CRDM Shroud Fan trips / Rapid Power Reduction Communication:

When sent to local breaker for shroud fan, report that the breaker has tripped. If requested to close breaker, report that breaker will not stay closed.

Communication:

If Electrical Maintenance was contacted to look at the breaker, report back with damage to the breaker cubicle will take several hours to troubleshoot.

RO BOP

SRO SRO

Announce failure and refers to Alarm Response Book for Motor Breaker Trip and Containment or Aux Bldg Vent System Air Flow Low.

Inspects PAB/Containment ventilation control station on rear of 1C04 and determines only available CRDM shroud fan has tripped. May attempt restart with SRO concurrence. Should contact AO to look at local breaker for fan.

1W3-A control switch might be placed in pullout to clear control board alarms.

Using guidance in ARB 1C04 1C 2

-9, directs rapid power reduction IAW AOP

-17A. Announces entry into AOP

-17A, Rapid Power 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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 15 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Rapid power reduction continued

SRO RO BOP RO 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.

Checks Rod control in Auto.

Selects Rate Reduction method, likely Operator Auto

- 1st(CA STEP) Commences boration, should refer to ROD 1.3 for power reduction boration and rod bank requirements Stage IN per the note prior to step 4.

(CA STEP) Check PZR Pressure

- Stable or trending to program (CA STEP) Check PZR Level

- Stable at or trending to program

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 16 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES (cont) : Rapid Power Reduction Unit 1 Communication:

When requested, TH AO start 1P-99A and B SGFP Seal Water Pumps 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. BOP RO BOP SRO BOP (CA STEP) Check SG levels

- controlling in Auto (CA STEP) Maintain Tavg - Checks TavgCheck MFW Seal Water Pumps Running

- Contacts U1 Turbine Operator to Start 1P

-99A and B.

within limits Determines endpoint is MODE 3.

May transfer auxiliary loads.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 17 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5Crew : Small Break LOCA (500 GPM)

RO

SRO BOP RO Recognizes increased leak rate and uses continuous action guidance from AOP

-1A to trip the reactor.

Inserts Manual Trip to trip the reactor.

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.

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

Verifies Secondary Heat Sink

- Checks S/G levels

- Verifies proper AFW flow for heat sink

- Maintains S/G levels

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 18 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Small Break LOCA (500 GPM) cont'd RO

SRO 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

Start Monitoring CSFST's (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 Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 19 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Small Break LOCA (500 GPM) cont'd SRO RO BOP RO BOP

RO Transition to EOP

-1 Check if RCP's should remain running Check if Secondary System is intact (CA STEP) Stabilize intact S/G levels Check Secondary System Radiation Normal (CA STEP) Check PORV and PORV Block Valves Reset SI Reset Containment Isolati on Reset 1B03 and 1B04 lockouts Check 4160 Safeguards busses powered Re-establish Instrument Air to Containment Verify Charging Flow Check if SI flow should be terminated (CA STEP) Check if Spray should be stopped

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 20 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Small Break LOCA (500 GPM) cont'd The 4 th License will secure the running EDG

's.

Lead Evaluator can terminate the scenario once Step 16 of EOP

-1 is addressed if all critical tasks are met. If the flowpath out of containment via the RCS Hot Leg Sample line is not isolated then the crew should be allowed to transition to ECA

-1.2 to address the penetration leak prior to terminating the scenario.

BOP RO BOP Crew SRO Check if RHR pumps should be stopped Check RCS and S/G pressures Check if EDG's should be stopped Initiate evaluation of plant status Check if RCS is intact outside containment

- might answer NO and transition to ECA

-1.2 LOCA Outside Containment Check RHR Pump Room High alarms clear Check if RCS cooldown and depressurization required

Transition to EOP 1.2 Small Break LOCA

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 21 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

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

Unit 2 will enter TSAC 3.7.8.F when SW

-2907 and 2908 are opened.

Communication:

When contacted the PAB AO should report that SW

-LW-61 and 62 radwaste SW isolation valves are both shut.

BOP Verify feedwater isolation

- NO, manually shut MFIV's

. Verify containment isolation.

Verify AFW actuation.

Check SI pumps running.

Check RHR pumps running.

Check only 1 CCW pump running.

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

Verify containment accident cooling.

Check CR ventilation in mode

5. - CUE PURPLE LIGHT IS LIT Check if main steam lines can remain open.

Verify proper SI valve alignment.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 22 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

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

Communication

When contacted, wait 2 minutes and have the AO report CWPH temperature at 65stable. Communication

When contacted, wait 2 minutes and have the PAB AO report SFP temperature at 75stable with level at 63 feet and stable.

BOP (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. (CA STEP) Check AFW Area ventilation operating.

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

. (CA STEP) Check CWPH temperature.

(CA STEP) Periodically check the status of SFP cooling.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 23 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6 : 1P-15A SI Pump trip and 1P-15B SI Pump fails to AUTO start Communications:

If contacted, PAB AO reports 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. BOP RO notices 1P

-15A pump trip and failure of 1P

-15B to start. After immediate actions 1P

-15B can be manually started or during EOP

-0 Attachment A guidance will be to start 1P

-15B manually.

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 with 1 gpm leak CRITICAL TASK:

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

. B OP During performance of EOP

-0 Attachment A step A2, the BOP should recognize the RCS Hot Leg Sample Line did not isolate as required. Procedurally the BOP should initiate a manual CI and take 1SC

-966C to closed and inform the SRO.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 24 of 38

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES End the scenario by placing the simulator in freeze Inform Examinees they are to remain at their stations and cannot discuss the scenario. They are to wait for any follow up questions the examiners may have.

Crew: No debrief or critique due to this being an evaluated scenario

.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 25 of 38

Reference:

FP-T-SAT-75 Scenario preloads Relative Order System Or Panel Drawing Type Code Severity Or Value Event 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 Cntl Fuse 1W-3B Shroud Fan Breaker

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 26 of 38

Reference:

FP-T-SAT-75 EVENT 1: Shift Accident Fans per OI

-72 Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Expected Communications None LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 27 of 38

Reference:

FP-T-SAT-75 EVENT 2: 1LT-427 Pressurizer Level fails LOW Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS XMT XMT1RCS008A 0 1 20 sec ramp 1LT-427 PZR Level Transmitter Expected Communications None LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 28 of 38

Reference:

FP-T-SAT-75 EVENT 3: 20 GPM RCS leak 'B' Loop RTD manifold Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS MAL MAL1RCS003F 2 0 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. LOAs used None.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 29 of 38

Reference:

FP-T-SAT-75 EVENT 4: 1W-3B Shroud Fan trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE CNM BKR BRK1CNM017 1-Trip 5 1W-3A Shroud Fan Breaker Expected Communications If contacted, the TH AO reports breaker for 1W

-3A is tripped and cannot be reset if asked to do so.

LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 30 of 38

Reference:

FP-T-SAT-75 EVENT 5: Small Break LOCA (500 gpm)

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE RCS MAL MAL1RCS003F 500 240 ramp Loop 'B' RTD Manifold Leak Change value of the RCS Leak to 500 GPM Expected Communications None LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 31 of 38

Reference:

FP-T-SAT-75 EVENT 6: 1P-15A SI Pump trip and 1P

-15B SI Pump fails to AUTO start Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload SIS PMP PMP1SIS001 2-Shaft Seizure 1P-15A SI Pump Shaft Seizure Preload SIS BKR BKR1SIS002 4-Fail to Auto Close 1P-15B SI Pump fail to auto start Expected Communications

If contacted, PAB AO reports seized shaft on 1P

-15A SI Pump.

If contacted TH AO reports breaker for 1P

-15A is tripped on overcurrent.

If contacted TH AO reports breaker for 1P

-15B is normal and state current position.

LOAs used: None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 32 of 38

Reference:

FP-T-SAT-75 EVENT 7: MFIV's fail to AUTO close Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload CFW VLV VLV1CFW030A 1-Fail to Auto Close CF-3124 MFIV fails to auto close Preload CFW VLV VLV1CFW031A 1-Fail to Auto Close CF-3125 MFIV fails to auto close Expected Communications:

If contacted, PAB AO reports actual position of valve with no other abnormal indications.

LOAs used:

None

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 33 of 38

Reference:

FP-T-SAT-75 EVENT 8: RCS Hot Leg Sample Line fails to isolate with 1 gpm leak Relative Order System Or Panel Drawing Type Code Severity Or Value Event 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 Preloa d 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 Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 34 of 38

Reference:

FP-T-SAT-75 Attach the following information as necessary:

Simulator Set-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log Historical Record:

This SEG was developed for the 2012 NRC ILT Examination.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 35 of 38

Reference:

FP-T-SAT-75 1.0 PLANT CONDITIONS

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

16000 6500 Reactor power (%):

73.9% 26.9% Boron concentration (ppm): 125 ppm 1 170 ppm Rod height (CBD @):

CBD @ 187 CBD @ 143 Target AFD 1.5 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC None Description None Reason None 3.0 EQUIPMENT OUT OF SERVICE

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

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

. 4.0 PLANNED EVOLUTIONS

After shift turnover, start 1W-1A Containment Fan s and secure 1W

-1B Containment Fan s per OI-72.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 36 of 38

Reference:

FP-T-SAT-75 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 4 th 1W-3B, Containment Control Rod Shroud Fan

, is Out of Service due to bearing failure

. license is providing the Auxiliary Operator s 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.

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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 37 of 38

Reference:

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

Yes No X 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

(This action applies to all SEG's new or revised for those on the ANS/ANSI

-3.5-1998 standard.

This action is NOT applicable for those on the ANS/ANSI

-3.5-1985 standard.)

Yes No N/A X 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor

-led training freezes, or both.

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

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

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

Yes No X 7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Yes No N/A X 8. The scenario includes related industry experience.

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

Yes No N/A X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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Reference:

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

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

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

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

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

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

Yes X No 6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Yes X No 7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

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

None S MAR = Simulator Action Request S MAR: S MAR: S MAR: S MAR: Comments: Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

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 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 No. Malf. No. Event Type* Event Description 1 C-BOP C-SRO TS-SRO 1P-11A CCW Pump trip and 1P

-11B CCW Pump fails to auto start 2 C-RO C-SRO 1CV-135 Letdown Line Backpressure Controller oscillations (controller works in manual) 3 TS-SRO G0 2 Emergency Diesel Generator Low Starting Air Pressure alarm 4 R-RO N-BOP N-SRO Solar Magnetic Disturbance AOP-31 1%/hr ramp per AOP

-17A , Rapid Power Reduction 5 I-SRO I-RO 1P T-485 Turbine First Stage Pressure fails low with rod motion failure requiring plant trip 6 M-ALL Failure of BS-2 345 KV Bus Section, H52-31, 13.8 KV cross

-tie 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)

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 1 of 34

Reference:

FP-T-SAT-75 SITE: POINT BEACH SEG # PBN LOI NRC SEG TITLE:

201 2 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Andrew Zommers Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Randy Amundson Training Supervision Date Approved by:

Tom Larson Training Program Owner Date Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 2 of 34

Reference:

FP-T-SAT-75 Guide Requirements Goal of Training: To have the crew successfully perform/respond to loss of CCW Pump , CV-135 oscillations, G01 EDG low air pressure, Solar Magnetic 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 Objectives:

None Prerequisites:

1. Simulator available

2. Students enrolled in Initial License Program Training Resources:

1. Floor Instructor as Shift Manager

/Shift Technical Advisor

2. Simulator Booth Operator

3. Communicator

4. Evaluator s

References:

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

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-6 C 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. E OP-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 Method: Simulator performance will be evaluated IAW NUREG 1021.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 3 of 34

Reference:

FP-T-SAT-75 Operating Experience:

N/A Related PRA Information:

Initiating Event with Core Damage Frequency:

Transient w/o PCS 7.3E-0 7 Station Blackout 5

.2E-07 Component Cooling Water 2.1% CDF Important Components:

Important Operator Actions with Task Number:

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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 4 of 34

Reference:

FP-T-SAT-75 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Before EOP Entry:

Malfunctions:

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

2. Failure of CV

-135 Letdown Backpressure Controller

3. G0 2 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

1. 'A' CCW Pump Trip Abnormal Events: 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

1. ECA 0.0 Loss of All AC Major Transients:

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 OPERATI ON' region of TRM Figure 6.

Critical Tasks:

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

.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 5 of 34

Reference:

FP-T-SAT-75 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 'A'CRDM 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 Crew recognizes failure and manually starts Standby CCW Pump

Running CCW Pump Shaft Seizure with failure of Standby CCW Pump to Auto start. SRO Enters AOP

-9B Component Cooling Water System Malfunction SRO Addresses Technical Specifications Event 2 RO takes manual control and stabilizes system parameters

Failure of CV-135 Letdown Backpressure Controller SRO directs crew response with AOP

-1D CVCS Malfunction Event 3 : G0 2 EDG alarm, low starting air pressure Crew responds per ARB C02 F 2-1 , G-0 2 Emergency Diesel alarm SRO declares G0 2 OOS SRO addresses Technical Specifications

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 6 of 34

Reference:

FP-T-SAT-75 Event 4 Crew responds to call from A O that neutral current is 65 amps

Solar Magnetic Disturbance AOP-31/Rapid Power Reduction AOP-31 directs rapid power reduction using AOP

-17A, Rapid Power Reduction Crew coordinates to lower unit power at 1% per minute Event 5: Crew recognizes failure and takes manual control of rods.

Turbine First Stage Pressure Transmitter PT

-485 fails Low SRO Enters AOP-6C Uncontrolled Rod Motion RO recognizes rod control failure requiring plant trip Event 6: Crew recognizes failures require entry into ECA

-0.0 Failure of BS

-2, H52-31, G01, G02, G03 requiring entry into ECA 0.0 Crew aligns a safeguards bus via G04 Event 7: RO recognizes stuck rods during immediate actions 3 stuck rods Attempts another manual trip of reactor SRO later determines boration required for stuck rods Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 7 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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: 1 4 6 1 ppm (BOL) Temperature: NOT Pressure: NOP Xenon: Equilibrium Rods: Bank D @

220 steps Generator: 623 Mwe Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 8 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SIMULATOR SET UP (perform set up per the "Simulator Setup Checklist", including entering action items per the "Simulator Input Summary.")

Line 111 and 1W

-3B (OOS tag)

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 P I 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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 9 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1: Running CCW Pump Shaft Seizure with failure of Standby CCW Pump to Auto start.

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

Communications:

If asked, the PAB AO will report nothing unusual with the 'B' CCW Pump discharge pressure indicator, it reads 125 psig locally.

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

NOTE: Crew may elect to place 1P

-11A in pullout to clear 'Motor Breaker Trip' alarm.

End of evolution

Proceed to next event at Lead Examiner discretion

. BOP SRO Crew

SRO BOP/RO SRO BOP identifies the 'A' CCW Pump failure with the 'B' CCW Pump not auto starting. BOP requests from the SRO to start 'B' CCW Pump manually.

(1C03 1D 2

-6 and 1C03 1D 3

-7) Enter AOP 9B CCW malfunction to address the lost CCW Pump. BOP will verify adequate tank level and start 1P-11B CCW Pump.

Crew will address surge tank level which will require no action.

Crew will address system leakage requiring no action.

Check Reactor Trip Check RHR Status Chemistry will be requested to analyze CCW.

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

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

Address LCO 3.7.7 CCW and enter 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSAC 3.7.7.A Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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 10 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2: Failure of CV

-135 Letdown Backpressure Controller

Communications:If asked, the PAB AO reports there is nothing abnormal with CV

-135.

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

-24 actions)

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

RO/SRO SRO RO SRO RO SRO BOP RO identifies CV

-135 pressure controller malfunction and takes controller to manual to control back pressure. Addresses ARB for Letdown High Pressure (1C04 1C 4

-6). Enter AOP 1D to address the malfunction and verify actions taken.

Check RCS leak not in progress.

Reviews foldout page criteria Determine CVCS malfunction

- CV-135 pressure control which directs transition to step 36.

Establish manual control of CV

-135 - 250# 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 3 7 RNO) May send out the PAB AO to look at CV

-135 locally.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 11 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Failure of CV

-135 Letdown Backpressure Controller (cont'd)

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

SRO RO SRO Crew may also enter AOP-24 Response to Instrument Malfunction

. 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. Addresses caution regarding currently tripped bistables

- this does not apply as no other bistables are tripped.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 12 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3: G0 2 EDG alarm, low starting air pressure Communication

When sent out, have the TH1 AO wait 2 minutes and report that G0 2 south bank air pressure is 190 psig and stable with the north bank 160 psig and slowly lowering. The north bank air compressor is running with one of the bank relief valve s leaking by. (ARB C6 5A C3 5 P7) NOTE: IF asked by the OS1, the Shift Manager will state OS2 will prepare the required paperwork per OI-35A to align G0 1to 2A05. May ask for Diesel Air Start PID, M

-209 Sheet 12 (#134).

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

BOP SRO

Address G0 2 alarm on panel C02. Dispatches AO to determine local alarm that is in.

When the report comes back to Control the SRO should determine that G0 2 EDG is OOS.

LCO 3.8.3 not met, enter TSAC 3.8.3.D immediately and declare G0 2 OOS for both units. LCO 3.8.1 not met, enter TSAC 3.8.1.E for required standby emergency power sources inoperable for both units. Determine the need to align G0 1 to both 1A05 and 2A05.

Call in Maintenance to troubleshoot and fix.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 13 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES EVENT 4 : SMD AOP-31 / Rapid Power Reduction

Communication:

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

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

. Crew is receives a call from AO on Unit 1.

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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 14 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES (cont) : Rapid Power Reduction Unit 1

SRO RO BOP RO Determines desired power level and ramp rate and announces to C R - SRO determines that unit be ramped at 1% per minute as directed by A OP. SRO will direct BOP to set the endpoint at 78% on the turbine. Requests SM to notify PSS.

Checks Rod control in Auto.

Selects Rate Reduction method, likely Operator Auto

- 1st(CA STEP) Commences boration, should refer to ROD 1.3 or the reactivity management sheets for power reduction boration and rod bank requirements Stage IN per the note prior to step 4.

(CA STEP) Check PZR Pressure

- Stable or trending to program (CA STEP) Check PZR Level

- Stable at or trending to program

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 15 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES (cont) : Rapid Power Reduction Unit 1 Communication:

When requested, TH AO start 1P-99A and B SGFP Seal Water Pumps

End of evolution: Proceed to next event at approximately a 5% power reduction or Lead Examiner discretion.

BOP RO BOP SR O (CA STEP) Check SG levels

- controlling in Auto (CA STEP) Maintain Tavg - Checks TavgCheck MFW Seal Water Pumps Running

- Contacts U1 Turbine Operator to Start 1P

-99A and B.

within limits Determines endpoint is <50%

- NO.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 16 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5 : Turbine First Stage Pressure Transmitter PT

-485 fails Low and rod motion fails requiring plant trip

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.

RO SRO RO Identifies inward rod motion, recommends placing rod control in Manual Concurs with recommendation, directs placing rods in Manual Rod Motion not responding, recommends reactor trip Inserts Manual Trip to trip the reactor. Verify Reactor Trip Verify Turbine Trip Verify Safeguards Buses Determine no 4160 and 480 safeguards busses are energized for Unit 1.

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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 17 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6 : Bus Section 2 H52-31 , G-01, G-02 and G-03 EDG failures causing entry in ECA 0.0 Communication

If asked, wait 2 minutes and the TH AO reports G03 has indications and alarms locally that it overspe

d. Communication

If asked, wait 2 minutes and the TH AO reports G0 1 output breaker is open and nothing appears abnormal.

Communication

If asked, wait 2 minutes and the TH AO reports G0 2 EDG is not running and everything looks normal

. Communication

If asked, wait 3 minutes and the TH AO can report that H52-31 tie breaker is tripped and there are no other abnormal indications.

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

S RO RO SRO RO/BOP B O P

Enter ECA 0.0 Verify Reactor tripped Verify Turbine tripped Monitor foldout page items Ensure both RCP's

- Stopped Maintain RCS inventory

- RO and BOP will check various vent valves, sample valves, letdown and PORV's shut.

Verify TDAFW Pump operating Check cooling to AFW Pump bearings Check both 4160 VAC busses not energized

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 18 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

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

NOTE : Additional SW Pumps may be started per ARB to ensure adequate SW header pressure.

Communication

If the SM is asked, direct OS1 that the 3rd RO will start G05.

Communication

SM will concur with OS1 recommendations concerning EDG operation (Starting or securing.)

BOP SRO BOP BOP/SRO BOP BOP/SRO BOP SRO Check Diesels

- All Running Check Diesel Status Check H-01 not energized - Start G05 and continue Check 1A-05 not energized Check 1A-05 energized from G01

- breaker won't close go to step 1 4 Energize 1A

-05 from G02

- G02 did not start Check 1A-06 not energized Energize 1A

-06 from G03

- cannot be done due to G03 overspeed condition.

- Go to step 1

7. Energize 1A

-06 from G04

- Manually shut alternate breaker. Check 480 Vac busses at least one energized

- Yes Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 19 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

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

E-0 C, SRO/BOP must energize at least one AC emergency bus before placing safeguards equipment in pullout per ECA 0.0

Communication: If asked, OS2/4 thBOP License will take step 7 RNO action.

SRO SRO RO/BOP SRO RO BOP Verify SW System operation Return to procedure step in effect, which was EOP 0 step 3 RNO Verify safeguards power is available for at least one(1) 4160 and 480 VAC bus Check if SI is actuated

- NO go to EOP

-0.1 Transition to EOP

-0.1 (CA STEP) Verify RCS Temperature Control using Atmospheric Steam Dumps Verify Feedwater Isolation Transfer Feedwater Control to the Bypasses

- NO (CA STEP) Stabilize S/G Levels Verify Generator Trip Ensure Miscellaneous Electrical Loads are Energized

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 20 of 34

Reference:

FP-T-SAT-75 SCENARIO TIME

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

Communication: If asked, OS2/4 th License will take step 7 RNO action.

Communication

If asked, the PAB AO verifies that 1CV-112 B is SHUT and 1CV-112C is OPEN. The scenario can be terminated at Lead Evaluators discretion or once action has been taken to start the boration

. BOP RO Check All AC Busses Energized by Offsite Power Verify Charging Pump Suction Alignment Verify Charging Flow Check ALL Control Rods Fully Inserted

- NO Check Pressurizer Level >12%

Event 7: 3 stuck rods RO Crew 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 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 Inform Examinees they are to remain at their stations and cannot discuss the scenario. They are to wait for any follow up questions the examiners may have.

Crew: No debrief or critique due to this being an evaluated scenario.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 Scenario preloads Relative Order System Or Panel Drawing Type Code Severity Or Value Event 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 Cntl Fuse 1W-3B Shroud Fan Breaker Preload Preload Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 22 of 34

Reference:

FP-T-SAT-75 EVENT 1: Loss of 1P

-11A and failure of 1P

-11B to auto start Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload CCW BKR BKR1CCW002 4-Fail to Auto Close 1P-11B CCW Pump fails to auto start PLE CCW PMP PMP1CCW001 2-Shaft Seizure 1 1P-11A CCW Pump shaft 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 Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT SUMMA RY 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 23 of 34

Reference:

FP-T-SAT-75 EVENT 2: 1 CV-135 Letdown Backpressure Controller failure Relative Order System Or Panel Drawing Type Code Severity Or Value Event 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 Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 24 of 34

Reference:

FP-T-SAT-75 EVENT 3: G0 2 EDG alarm, low starting air pressure Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE G0 2 ANN ANN-C02 F-B0 1 0-ON 5 G0 2 EDG alarm Expected Communications When sent out, have the TH1 AO wait 2 minutes and report that G0 2 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.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 25 of 34

Reference:

FP-T-SAT-75 EVENT 4: Solar Magnetic Disturbance requiring rapid plant downpower Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE CFW LOA LOA1CFW083 ON 1 4 1P-99A SGFP Seal Water Pump PLE CFW LOA LOA1CFW084 ON 1 4 30 sec delay 1P-99B SGFP Seal Water Pump Expected Communications When requested, TH AO start s 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.

LOA used Trigger 1 4 for 1P-99A/B Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 26 of 34

Reference:

FP-T-SAT-75 EVENT 5 1PT-485 First Stage Pressure fails LOW with Rod Motion Failure requiring plant trip Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE MSS XMT XMT1MSS008A 0 7 30 sec ramp 1PT-485 First Stage Pressure fails low PLE CRF OVR OVR-CRF009D ON 7 Rod Control Selector Switch in AUTO PLE CRF OVR OVR-CRF009D OFF 7 Rod Control Selector Switch in MAN Expected Communications None LOAs used None Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 27 of 34

Reference:

FP-T-SAT-75 EVENT 6: Failure of BS

-2, H52-31, G01, G02, G03 requiring entry into ECA 0.0 Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Preload DSG MAL MAL1DSG002B G03 overspeed during startup Preload DSG BKR BKR1DSG00 1 5-fail as is G0 1 Output Breaker fail as is 1A52-6 0 Preload SWD BKR BKR1SWD008 1-trip 9 JCRF TR , 30 sec delay H52-31 breaker Preload DSG BKR BKR1DSG004 6-fail close fuse 9 G04 Output Breaker fail to close PLE SWD MAL MAL1SWD004B 9 JCRFTR , 30 sec delay 345 Bus Section 2 Lockout PLE DSG MAL MAL 2DSG001A G-0 2 EDG Failure to Start

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 28 of 34

Reference:

FP-T-SAT-75 Expected Communications

If asked, wait 2 minutes and the TH AO reports G0 1 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 MOV's.

LOAs used: None.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

SIMULATOR INPUT

SUMMARY

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

QF-1075-02 Revision 4 11/18/09 Page 29 of 34

Reference:

FP-T-SAT-75 EVENT 7: 3 stuck rods Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description PLE CRF MAL MAL1CRF001

-B6 1-Non Trip 7 Stuck Rod

- B6 PLE CRF MAL MAL1CRF001

-D10 1-Non Trip 7 Stuck Rod

- D10 PLE CRF MAL MAL1CRF001

-F12 1-Non Trip 7 Stuck Rod

- F12 Expected Communications None LOAs used None

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 30 of 34

Reference:

FP-T-SAT-75 Attach the following information as necessary: Simulator Set

-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log Historical Record:

This SEG was developed for the 201 2 NRC ILT Examination.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 31 of 34

Reference:

FP-T-SAT-75 1.0 PLANT CONDITIONS

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

8100 950 Reactor power (%):

99.7% 99.4% Boron concentration (ppm): 9 47 ppm 1461 ppm Rod height (CBD @):

CBD @ 220 CBD @ 220 Target AF D -4.6 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT

TSAC None Description None Reason 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

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QF-1075-02 Revision 4 11/18/09 Page 32 of 34

Reference:

FP-T-SAT-75 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 4 th 1W-3B, Containment Control Rod Shroud Fan

, is Out of Service due to bearing failure

. license is providing the Auxiliary Operator s 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.

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

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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

QF-1075-02 Revision 4 11/18/09 Page 33 of 34

Reference:

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

Yes No X 2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

(This action applies to all SEG's new or revised for those on the ANS/ANSI

-3.5-1998 standard.

This action is NOT applicable for those on the ANS/ANSI

-3.5-1985 standard.)

Yes No N/A X 3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor

-led training freezes, or both.

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

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

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

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

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

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

Yes No N/A X Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

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QF-1075-02 Revision 4 11/18/09 Page 34 of 34