ML13028A070
ML13028A070 | |
Person / Time | |
---|---|
Site: | Point Beach ![]() |
Issue date: | 12/17/2012 |
From: | NRC/RGN-II |
To: | |
Zoia, Charles | |
Shared Package | |
ML11354A219 | List: |
References | |
Download: ML13028A070 (104) | |
Text
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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Reference:
FP-T-SAT-75
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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, 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
- 9. EOP-0 Reactor Trip or Safety Injection Unit 1
- 10. EOP-1 Loss of Reactor or Secondary Coolant 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 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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Reference:
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Reference:
FP-T-SAT-75
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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. MFIVs fail to close Abnormal Events:
- 1. 1LT-427 Pressurizer Level Instrument transmitter fails low
- 3. Rapid Power Reduction Major Transients:
- 1. Small Break LOCA Critical Tasks:
- 1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to Pressurizer level reaching 10%
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:
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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-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-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)
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
- Crew should swap PZR controlling channel per ARB and restore Letdown and Charging to normal per AOP.
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.
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)
- 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
- 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
- BOP recognizes MFIV failure to close
- SRO concurs with BOP closing MFIVs 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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: 8100 MWD/MTU
- Power: 73.9%
- Boron: 125ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 187 steps
- Generator: 475 MWe Unit 2
- Mode: 1
- Burnup: 1400 MWD/MTU
- Power: 26.9%
- Boron: 1170 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 143steps
- Generator: 165 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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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 SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the Simulator Input Summary.)
- Line 111 disconnects magnets open
- Guarded equipment tag for 1W-3A
- Extra AO name tags
- Marked-up copy of AOP-31 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.
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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-24 may be utilized in addition to SRO Directs entry into AOP-1D, CVCS Malfunction or AOP-1D. (See next page for AOP-24 actions) 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 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.
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:
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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 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.
SRO References step regarding performance of AOP-21.
In order to save scenario time, the package for removing the channel from service will be prepared by the exam Addresses caution regarding currently tripped team before the scenario and will be provided to the bistables - this does not apply as no other bistables Crew when they ask for it to be prepared. are tripped.
NOTE: IF asked for references, the Shift Technical Directs removal of failed instrument IAW Advisor will provide the following logic diagrams 0-SOP-IC-001 WHITE.
as referenced in 0-SOP-IC-001-WHITE page 19.
Sheets #175, #180 and #181 and Crew Restore Charging to Automatic 0-SOP-IC-002 in its entirety. 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.
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 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- SRO Enters AOP-1A, Reactor Coolant Leak.
211/212 radiation monitors in alarm, rising Check SI not required (CA): Adequate PZR Level and containment humidity, Sump A rising, VCT level RO Subcooling.
lowering and the automatic charging pump speeding up. 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 SRO may address Technical Specifications at PZR level and RCP Lab Seals.
this time due to RCS leakage. If TS not addressed here, a scenario follow-up question Check Pressurizer Pressure: Stable or trending to will be needed. LCO 3.4.13 is not met due to program.
unidentified leakage exceeding 1 GPM.
Check Rx Makeup Controls: Set for proper blend, armed and in auto.
SRO Request SM notify DCS and implement E-Plan.
Continue to next event per Lead Evaluator or SRO may Address Tech Specs.
determination of leak rate. Ensure charging/letdown SRO Directs performance of steps 7 through 18. These is recovered, if it was isolated, prior to downpower. steps include directions to isolate letdown and charging and various other leakage possibilities.
If requested, inform OS1 that the 4th License will perform the OI-55 calculation.
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:
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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: 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 it will take several hours to troubleshoot the problem. Using guidance in ARB 1C04 1C 2-9, directs rapid 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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Reference:
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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 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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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 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 when the team is prepared to make the leak larger and booth operator will increase the leak to 500 GPM over 10 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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Reference:
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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 5: Small Break LOCA (500 GPM) Crew Recognizes increased leak rate and uses continuous 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.
-Trip RCPs if 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.
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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 Small Break LOCA (500 GPM) contd BOP Performs Attachment A. (actions listed later)
RO Verifies Secondary Heat Sink Verify RCP Seal Cooling (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 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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 Check RHR Pump Room High alarms clear Check if RCS cooldown and depressurization required SRO Transition to EOP 1.2 Small Break LOCA BOP (CA STEP) Check all AC Busses energized by Offsite Ensure Miscellaneous Loads are energized RO Check if RHR Pumps should be stopped Verify Charging flow BOP (CA STEP) Stabilize intact S/G levels RO Check SI signal status BOP Reset SI 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 Small Break LOCA (500 GPM) contd Initiate RCS cooldown to cold shutdown Check RCS subcooling Once action has been taken to start the cooldown, the scenario can be terminated at Lead Evaluators 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 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.
isolation valves are both shut.
Check if main steam lines can remain open.
Verify proper SI valve alignment.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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.
(CA STEP) Check Computer Room ventilation operating.
(CA STEP) Ensure Aux Building filter/exhaust fans operating.
(CA STEP) Check AFW Area ventilation operating.
Communication: When contacted, wait 2 minutes and (CA STEP) Energize façade Freeze protection at the have the AO report CWPH temperature at 65 F and discretion of Operations Shift Management.
stable.
(CA STEP) Check CWPH temperature.
Communication: When contacted, wait 2 minutes and have the PAB AO report SFP temperature at 75F and (CA STEP) Periodically check the status of SFP stable with level at 63 feet and stable. 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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 guidance will be to start 1P-15B manually.
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: Manually start at least one SI pump prior to transition out of EOP-0 (This task should have been completed during performance of Att. A for EOP-0)
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.
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)
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 Cntl 1W-3B Shroud Fan Breaker 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.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SIMULATOR INPUT
SUMMARY
EVENT 1: Shift Accident Fans per OI-72 Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Expected Communications 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)
SIMULATOR INPUT
SUMMARY
EVENT 2: 1LT-427 Pressurizer Level fails LOW Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE RCS XMT XMT1RCS008A 0 1 20 sec ramp 1LT-427 PZR Level Transmitter Expected Communications 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)
SIMULATOR INPUT
SUMMARY
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 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)
SIMULATOR INPUT
SUMMARY
EVENT 4: 1W-3B Shroud Fan trip Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE CNM BKR BRK1CNM017 1-Trip 5 1W-3A Shroud Fan Breaker PLE CFW LOA LOA1CFW083 ON 12 1P-99A SGFP Seal Water Pump PLE CFW LOA LOA1CFW084 ON 12 30 sec delay 1P-99B SGFP Seal Water Pump 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 Trigger 12 for 1P-99A/B Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SIMULATOR INPUT
SUMMARY
EVENT 5: Small Break LOCA (500 gpm)
Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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 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 6: 1P-15A SI Pump trip and 1P-15B SI Pump fails to AUTO start Relative System Or Severity Or Event Order Panel Drawing Type Code Value Trigger Timing Description Preload SIS PMP PMP1SIS001 2-Shaft 60 sec delay 1P-15A SI Pump Shaft Seizure Seizure Preload SIS BKR BKR1SIS002 4-Fail to 1P-15B SI Pump fail to auto start Auto Close 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 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 7: MFIVs fail to AUTO close Relative System Or Severity Or Event Order Panel Drawing Type Code Value Trigger Timing Description Preload CFW VLV VLV1CFW030A 1-Fail to CF-3124 MFIV fails to auto Auto Close close Preload CFW VLV VLV1CFW031A 1-Fail to CF-3125 MFIV fails to auto Auto Close close Expected Communications:
If contacted, PAB AO reports actual position of valve with no other abnormal indications.
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)
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:
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) 1.0 PLANT CONDITIONS:
UNIT 1 UNIT 2 Time in core life 400 14960 (MWD/MTU):
Reactor power (%): 73.9% 26.9%
Boron concentration 125 ppm 1170 ppm (ppm):
Rod height (CBD @): CBD @ 187 CBD @ 143 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.
- 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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Reference:
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Reference:
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Point Beach Nuclear Plant PROCEDURE / WORK INSTRUCTION RECORD AND FIELD COPY TRACKING Record/Field Copy Identification Field Copy Number RECORD RED - Record Copy; BLACK - Field Copy Procedure / Work Instruction No. OI-72 Unit PB1 Revision Number 15 Procedure / Work Instruction Title Containment Air Recirculation System Revision Date July 5, 2012 Procedure / Work Instruction Revision Checked and Current; Tracking Checked for Temporary Changes:
By Andrew Zommers Date Today Record Copy Holder/Location CO/Control Room FIELD COPY DISTRIBUTION Copy No. Holder/Location Issue Date Return Date 1
2 3
4 5
6 7
8 9
10 NOTE 1: ANY TEMPORARY CHANGES MADE TO THIS PROCEDURE OR WORK INSTRUCTION SHALL BE MADE TO THE RECORD COPY AND ALL OTHER FIELD COPIES THAT HAVE BEEN ISSUED.
NOTE 2: RETURN ALL FIELD COPIES TO THE HOLDER OF THE RECORD COPY UPON PROCEDURE OR WORK INSTRUCTION COMPLETION.
PBF-0026i Revision 3 05/15/12
Reference:
NP 1.1.4
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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Reference:
FP-T-SAT-75
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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
- 9. AOP-31 Solar Magnetic Disturbance Unit 1
- 10. AOP 6C Uncontrolled Rod Motion Unit 1
- 11. EOP-0 Reactor Trip or Safety Injection Unit 1
- 12. EOP-0.1 Reactor Trip Response Unit 1
- 14. Alarm Response Books
- 15. Technical Specifications and associated 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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Reference:
FP-T-SAT-75
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Evaluation Simulator performance will be evaluated IAW NUREG 1021.
Method:
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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Reference:
FP-T-SAT-75
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)
Malfunctions:
Before EOP Entry:
- 2. Failure of CV-135 Letdown Backpressure Controller
- 3. G02 EDG alarm, low starting air pressure
- 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. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to 25% Pressurizer Level.
- 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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Reference:
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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-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)
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 Addresses Technical Specifications Event 2: Failure of CV-135 Letdown Backpressure Controller
- RO takes manual control and stabilizes system parameters
- Crew responds per ARB C02 F 2-1, G-02 Emergency Diesel alarm
- SRO addresses Technical Specifications Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Event 4: Solar Magnetic Disturbance AOP-31/Rapid Power Reduction
- Crew responds to call from AO that neutral current is 65 amps
- 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.
- 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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: 100%
- Boron: 947 ppm (MOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 619 Mwe Unit 2
- Mode: 1
- Burnup: 14960 MWD/MTU
- Power: 100%
- Boron: 1461 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 619 Mwe Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the Simulator Input Summary.)
- Line 111 disconnects magnets open
- Guarded equipment tag for 1W-3A
- Extra AO name tags
- Marked-up copy of AOP-31 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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)
Communications: If asked, the PAB AO reports the A BOP or RO address ARBs as applicable.
CCW Pump inboard motor bearing is hot to the touch.
Enter AOP 9B CCW malfunction to address the lost SRO CCW Pump. BOP will verify adequate tank level and Communications: If asked, the PAB AO will report start 1P-11B CCW Pump.
nothing unusual with the B CCW Pump discharge pressure indicator, it reads 125 psig locally. Crew Crew will address surge tank level which will require no action.
Communications: If asked, the TH AO will report the Crew will address system leakage requiring no action.
A CCW Pump breaker has tripped on overcurrent.
SRO Chemistry will be requested to analyze CCW.
OS1 will ask the SM to call DCS and implement NOTE: Crew may elect to place 1P-11A in pullout to Emergency Plan.
clear Motor Breaker Trip alarm.
BOP/RO Send AOs out locally to the pump/breaker and discharge pressure indicator to find any problems.
End of evolution: Proceed to next event at Lead Examiner discretion. 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 SRO 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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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 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 36 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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Reference:
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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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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. 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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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 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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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 (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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Reference:
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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 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 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 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 25%
Pressurizer Level. 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 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.
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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 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.
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Reference:
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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 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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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 (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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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 and C are SHUT and OPEN, respectively 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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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.
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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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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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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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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
- 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 14 for 1P-99A/B Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SIMULATOR INPUT
SUMMARY
EVENT 5 1PT-485 First Stage Pressure fails LOW with Rod Motion Failure requiring plant trip Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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 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)
SIMULATOR INPUT
SUMMARY
EVENT 6: Failure of BS-2, H52-31, G01, G02, G03 requiring entry into ECA 0.0 Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload DSG MAL MAL1DSG002B G03 overspeed during startup Preload DSG BKR BKR1DSG001 5-fail as is G01 Output Breaker fail as is 1A52-60 Preload SWD BKR BKR1SWD008 1-trip 9 JCRFTR, 30 H52-31 breaker sec delay Preload DSG BKR BKR1DSG004 6-fail 9 G04 Output Breaker fail to close close fuse PLE SWD MAL MAL1SWD004B 9 JCRFTR, 30 345 Bus Section 2 Lockout sec delay PLE DSG MAL MAL2DSG001A G-02 EDG Failure to Start 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)
SIMULATOR INPUT
SUMMARY
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.
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)
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 9 Stuck Rod - B6 B6 Trip PLE CRF MAL MAL1CRF001- 1-Non 9 Stuck Rod - D10 D10 Trip PLE CRF MAL MAL1CRF001- 1-Non 9 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.
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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 400 14960 (MWD/MTU):
Reactor power (%): 99.7% 99.4%
Boron concentration 947 ppm 1461 ppm (ppm):
Rod height (CBD @): CBD @ 220 CBD @ 220 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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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.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SITE: POINT BEACH SEG # PBN LOI NRC SEG TITLE: 2012 ILT NRC SCENARIO #3 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 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Guide Requirements To have the crew successfully perform/respond to Starting a second train of Goal of feedwater, normal up power from 45%, Pressurizer Pressure Controller fails Training: low, PT-468 fails high, B Steam Line leak inside containment, failure of A Accident Fan to start, and B MSIV fails to close. 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. OP-1C, Startup to Power Operation Unit 1
References:
- 2. 0-SOP-IC-001 - White, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - White Channels
- 3. 0-SOP-IC-002, Technical Specifications LCO-Instrument Cross Reference
- 4. AOP-24 Response to Instrument Malfunction
- 6. AOP-2A Secondary Coolant Leak Unit 1
- 7. AOP-2B Secondary Malfunction Unit 1
- 8. EOP-0 Reactor Trip or Safety Injection Unit 1
- 9. EOP-2 Faulted Steam Generator Unit 1
- 10. Technical Specifications
- 11. Technical Specifications 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Operating N/A Experience:
Initiating Event with Core Damage Frequency:
Related PRA SLB/FB in Containment 9.8E-7 Information:
Important Components:
Main Steam 1.2% CDF 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)
Malfunctions:
Before EOP Entry:
- 1. 1W-1A Accident Fan fails to start
- 2. 1PT-468 A S/G Pressure Transmitter fa1ls HIGH
- 4. B Steam Line leak inside containment After EOP Entry:
- 1. Both MSIV fail to auto close Abnormal Events:
- 1. 1PT-468 A S/G Pressure Transmitter fails HIGH
- 3. B Steam Line leak inside containment Major Transients:
- 1. B Steam Line Break inside containment Critical Tasks:
- 1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to exceeding 5 psig in containment.
- 2. E-2 A: Isolate the faulted steam generator before transition out of EOP-2.
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-163, created from IC-04
- 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-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)
SEQUENCE OF EVENTS:
Event 1: Start a Second Feed Train
- Crew starts a second feed train per OP-1C Event 2: Perform a Normal Up Power from 45%
- RO recognizes spray valve controller failure
- Crew recognizes transmitter failure
- BOP takes manual control of A S/G Atmospheric Steam Dump and A MRFV
- SRO addresses Technical Specifications Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Event 5: B Steam Line Leak in containment requiring plant trip
- Crew identifies secondary leak in containment
- Crew recognizes failure of 1W-1A to start
- BOP recognizes MSIVs failed to shut when required Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS:
Standard IC-163 from IC-04 Unit 1
- Mode: 1
- Burnup: 8100 MWD/MTU
- Power: 45.6%
- Boron: 1737 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 129 steps
- Generator: 283 MWe Unit 2
- Mode: 1
- Burnup: 14960 MWD/MTU
- Power: 99.6%
- Boron: 857 ppm (MOL)
- 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the Simulator Input Summary.)
- Line 111 disconnects magnets open
- Guarded equipment tag for 1W-3A
- Extra AO name tags
- Marked-up copy of AOP-31 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Start Second Feed Train per OP-1C SRO Crew will brief the evolution prior to entering the simulator.
Communication: If asked, the TH AO will report that 1CS-182B, 1P-25B-M Cond Pump motor bearing BOP BOP will start second feed train per OP-1C cooling Condensate return to suction, was adjusted for 30 GPM to motor bearing cooler. (Step 5.39.6)
Communication: If asked, the TH AO will report that 1CS-50 and IA-434 are OPEN. (Step 5.39.9)
Communication: If asked, the TH AO will report that the supply breaker for the 1P-28B SGFP is RACKED IN with the 125 VDC Trip and Close fuse blocks on. (Step 5.39.9)
Communication: If asked, the TH AO will report that the Top Case Temp of 305F, Bottom Case Temp of 305F and SGFP Discharge Temp of 305F and all stable for 1P-28B. (Step 5.39.10)
Communication: If asked, the TH AO will report that the 1P-73A control switch is positioned in AUTO, prior to placing switch to TEST. (Step 5.39.16.b.1)
Communication: If asked, the TH AO will report that 1P-73A has not restarted and oil pressure is NORMAL at 18 psig and 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 EVENT 1: (Contd)
Communication: If asked, the TH AO will report that no moisture is dripping from or steam leaving either bracket and the seal outlet temperatures is at 165°F.
(Step 5.39.17 a & b)
Communication: If asked, the TH AO will report that 1TI-3642B indicates 115°F and you will continue to monitor. (Step 5.39.18.b)
End of evolution: Proceed to next event at Lead Examiner discretion.
EVENT 2: Normal Up Power from 45%. Per Crew Briefing on power ascension may be performed in OP-1C classroom prior to beginning of the scenario.
NOTE: Once step 5.39.18.b communication is complete, RO Withdraws rods and/or Dilute in addition to adjusting inform crew that one (1) hour has elapsed with stable steam demand as needed to establish power SGFP oil temperatures and that they are to proceed with increase.
power ascension starting at step 5.39.18.d of OP-1C.
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 3: 1HC-431K Pressurizer Pressure Crew The crew may go to hold on the load ramp.
Controller fails LOW RO Take manual control of 1HC-431K. Ensure controller responds to manual control.
SRO Direct entry into AOP-24, Response to Instrument Malfunctions.
RO Identify Failed Instrument: - RNO go to Step 3 Establish Manual Control: Verify 1HC-431K in manual End of evolution: Proceed to next event at Lead and turn heaters off.
Examiner discretion.
Return Affected Parameter(s) to desired value(s):
Crew may restore pressure if not already done 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: 1PT-468 A S/G Pressure Transmitter BOP/SRO Acknowledge and respond to receipt of annunciators.
fails HIGH Realize feed control issues and S/G Atmospheric opening are due to instrument failure and place Communications: SM may be requested to contact I&C to troubleshoot and repair PT-468.
affected controllers in Manual.
Communications: If requested by OS1, SM agrees to The crew may go to hold on the load ramp.
let Crew take A FRV to auto per ARB guidance by shifting controlling feed flow channels (1C03 1E2 2-2 or Crew enters AOP-2B.
3-2).
RO (CA Step) Maintain Power <100%
NOTE: Crew may initially enter either AOP-2B or AOP-24 BOP Determine Secondary malfunction - FRV response Communications: If requested by OS1 inform them Check Feed Regulating Valve Response OS2 will be preparing the 0-SOP-IC-001 RED to remove 1PT-468 from service. Place affected controller in manual if desires In order to save scenario time, the package for removing Stabilize S/G level the channel from service will be prepared by the exam team before the scenario and will be provided to the SRO If transient due to instrument failure go to AOP-24 Crew when they ask for it to be prepared.
Crew enters AOP-24 NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic BOP Identify Failed Instrument:
diagrams as referenced in 0-SOP-IC-001-RED page 29. Sheets #169, #172 and #179 Check if failed instrument is a controlling channel:
and 0-SOP-IC-002 in its entirety.
Establish Manual Control 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 1PT-468 A S/G Pressure Transmitter fails HIGH Return Affected Parameter(s) to desired value(s):
BOP (contd) MFRV may be placed back in auto if ARB guidance is used to swap controlling feed flow channels. Alarm will NOTE: Intent is to NOT take the instrument out of service per 0-SOP-IC 001 RED not be in due to the low power but guidance could still be used NOTE: Add logic sheet (#176) for 1FT-464 being OOS concurrent with 1PT-468 Use Attachment A to determine if RTO is affected -
RTO not affected NOTE: IF SRO determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager Remove failed instrument from service per 0-SOP-IC-should inform OS1 that OS2 will review 001 - RED AOP-21 and take any necessary actions. SRO Return controls to automatic if desired Review 0-SOP-IC-002 Technical Specification LCO-Instruments Cross Reference.
- Table 3.3.1-1 item 14-2 SF/FF Mismatch
- Table 3.3.2-1 item 1e SI-Steam Line Pressure-Low
- Table 3.3.2-1 item 3c CI-Safety Injection (no action)
- Table 3.3.2-1 item 5c FI-Safety Injection (no action)
- Table 3.3.2-1 item 6c AFW-Safety Injection (no action)
- Table 3.3.3-1 item 17 SG Pressure (no action)
- Table 3.3.5-1 item 2 CREFS Cont. Isolation (no action)
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: (Contd) 1FT-464 End of evolution: Proceed to next event at Lead
- Table 3.3.1-1 item 14-2 SF/FF Mismatch Examiner discretion.
- Table 3.3.2-1 item 4d-1 SLI-High Steam Flow
- Table 3.3.2-1 item 4e-1 SLI-High High Steam Flow NOTE: Upon initiation of next event, takes about 7 minutes before first PPCS alarm comes in.
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 5: B Steam Line Break inside Crew Containment humidity will rise, Sump A level will rise, no Containment RMS alarms and reactor power rise. Crew should diagnose a secondary fault inside containment and trip the reactor CRITICAL TASK: RT-7, When a reactor trip is prior to reaching 5 psig in containment.
procedurally called for, initiate a manual reactor trip prior to exceeding 5 psig in containment. SRO Enter AOP-2A RO/BOP (CA STEP) Determine Secondary Leakage NOT Hazardous to Personnel or Equipment (CA STEP) Maintain Plant within limits (CA STEP) Maintain RCS Tavg BOP Check Containment Conditions Normal - NO RNO - Start All Containment Accident Fans - NO, Fails to start NOTE: Once the crew attempts to start the A Containment Accident Fan or per Lead Make determination that SLB is getting worse, Trip Unit Evaluator, raise the severity of the SLB to Crew based on CA STEP 1, SRO may direct manual SI and 2E005 lbm/hr. manual CI SRO Enter EOP-0 after reactor trip RO Verify Reactor Tripped Verify Turbine Tripped Verify Safeguards Busses 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Steam Line breaks (contd)
RO Check if SI is actuated BOP Isolate Feed Flow to B S/G per Foldout Page Perform Attachment A RO Verify Secondary Heat Sink Verify RCP Seal cooling (CA STEP) Verify RCS Temperature Control Check PZR PORVs shut Check PZR Spray Valves shut Check if RCPs should remain running Start monitoring critical safety function status trees (CA STEP) Verify containment sump recirc not required Check if Secondary System is intact - No SRO Transition to EOP-2 RO Check RCS wide range hot leg temperatures stable BOP Isolate both main steam lines Check if any S/G not faulted Identify Faulted S/G Reset Loss of Feedwater Turbine Trip 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 Steam Line breaks (contd) Isolate Feed to the Faulted S/G BOP Isolate Flow from the Faulted S/G Check CST Level - Greater than 4 ft RO Check Secondary System Radiation Normal End of evaluation: Lead evaluator can end scenario SRO Transition to EOP-1.
any time after the Transition to EOP-1.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: 1W-1A1 Accident Fan fails to start Recognize 1W-1A1 failure to start during performance BOP of AOP-2A.
NOTE: If the movement of the scenario is such that the SRO does not verbalize the LCO is not Declare 1W-1A OOS and address Technical SRO met for the failed Accident Fan, a follow up Specifications.
question after the scenario ends may be required.
LCO 3.6.6 NOT MET and TSAC 3.6.6.C entered Event 7: Both MSIVs fail to auto close BOP After immediate actions the Crew may notice both MSIVs are still open. If the Crew does not notice either Attachment A of EOP-0 or EOP-2 actions will try to shut the MSIVs.
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 EOP-0 Attachment A BOP Verify Feedwater isolation.
Verify Containment isolation.
Verify AFW actuation.
Check SI pumps running.
Check RHR pumps running.
Check only 1 CCW pump running.
Unit 2 will enter TSAC 3.7.8.F when SW-2907 and 2908 Verify Service Water System alignment. BOP should are opened. contact the PAB to check 2 local valves.
Communication: When contacted the PAB AO should Verify Containment Accident Cooling.
report that SW-LW-61 and 62 Radwaste SW isolation valves are both shut. Check CR Ventilation in mode 5.
Check if Main Steam lines can remain open. NO Verify proper SI valve alignment.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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.
(CA STEP) Check Computer Room ventilation operating.
(CA STEP) Ensure Aux Building filter/exhaust fans operating.
(CA STEP) Check AFW Area ventilation operating.
Communication: When contacted, wait 2 minutes and (CA STEP) Energize façade Freeze protection at the have the AO report CWPH temperature at 70F and discretion of Operations Shift Management.
stable.
(CA STEP) Check CWPH temperature.
Communication: When contacted, wait 2 minutes and have the PAB AO report SFP temperature at 75F and (CA STEP) Periodically check the status of SFP stable with level at 63 feet and stable. 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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
- 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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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 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)
SIMULATOR INPUT
SUMMARY
EVENT 1: Start Second Feed Train per OP-1C Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 1P-73A AC Lube oil pump for PLE CFW LOA LOA1CFW079 OFF 12 SGFP B Also need to place back to auto after using trigger 12 Expected Communications
- If asked, the TH AO will report that 1CS-182B, 1P-25B-M Cond Pump motor bearing cooling Condensate return to suction, was adjusted for 30 GPM to motor bearing cooler. (Step 5.39.6)
- If asked, the TH AO will report that the supply breaker for the 1P-28B SGFP is RACKED IN with the 125 VDC Trip and Close fuse blocks on. (Step 5.39.9)
- If asked, the TH AO will report that the Top Case Temp of 83F, Bottom Case Temp of 85F and SGFP Discharge Temp of 92F and all stable for 1P-28B. (Step 5.39.10)
- If asked, the TH AO will report that the 1P-73A control switch is positioned in AUTO, prior to placing switch to TEST. (Step 5.39.16.b.1)
- If asked, the TH AO will report that 1P-73A has not restarted and oil pressure is NORMAL at 18 psig and stable.
- If asked, the TH AO will report that no moisture is dripping from or steam leaving either bracket and the seal outlet temperatures is at 165°F.
(Step 5.39.17 a & b)
- If asked, the TH AO will report that 1TI-3642B indicates 115°F and you will continue to monitor. (Step 5.39.18.b)
LOAs used
- When order to place 1P-73A test switch to TEST, initiate Trigger 12 then return switch position back to AUTO.
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)
SIMULATOR INPUT
SUMMARY
EVENT 2: Raise power per OP-1C from 45%
Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 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)
SIMULATOR INPUT
SUMMARY
EVENT 3: 1HC-431K Pressurizer Pressure Controller fails LOW Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE PCS CNH CNH1PCS009E 0 1 15 sec ramp 431K PZR Pressure Controller failure 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)
SIMULATOR INPUT
SUMMARY
EVENT 4: 1PT-468 A S/G Pressure Transmitter fails HIGH Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE SGN MAL MAL1SGN015A 1400 3 15 sec ramp PT-468 fails HIGH 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)
SIMULATOR INPUT
SUMMARY
EVENT 5 B Steam Line leak inside Containment Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description PLE SGN MAL MAL1SGN003B 3000 5 60 sec ramp B steam leak inside containment (6.5 min to humidity alarm)
PLE SGN MAL MAL1SGN003B 2E005 240 sec ramp Change B steam leak inside containment PLE PLE SGN LOA LOA1SGN025 0 14 1MS-237 AFP/ Radwaste Steam Expected Communications
- If actions are directed for the AO to go near the steam lines near containment, inform control room you cannot gain access.
Monitor B S/G status, when the S/G is blown down, then actions can be performed, report only residual steam.
- 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 at 70F and stable.
- When contacted, wait 2 minutes and have the PAB AO report SFP temperature at 75 F and stable with level at 63 feet and stable.
LOA used Trigger 14 to shut 1MS-237. 1MS-238 is not modeled.
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)
SIMULATOR INPUT
SUMMARY
EVENT 6: 1W-1A Accident Fan fails to start Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload CNM BKR BKR1CNM001 5-Fail as 1W-1A Accident Fan breaker is fail as is Expected Communications:
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SIMULATOR INPUT
SUMMARY
EVENT 7: Both MSIVs fail to auto close Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Preload PPL BST BST1PPL068 1-fail as is TC401A fails as is Preload PPL BST BST1PPL069 1-fail as is TC402D fails as is Preload PPL BST BST1PPL070 1-fail as is TC403D fails as is Preload PPL BST BST1PPL058 1-fail as is Cont High Pressure fails as is Cont High Pressure fails as is Preload PPL BST BST1PPL062 1-fail as is Cont High Pressure fails as is Preload PPL BST BST1PPL014 1-fail as is Cont High Pressure fails as is Preload PPL BST BST1PPL016 1-fail as is 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 400 14960 (MWD/MTU):
Reactor power (%): 45.6% 99.6%
Boron concentration 1737 ppm 857 ppm (ppm):
Rod height (CBD @): CBD @ 129 CBD @ 220 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 a second train of feedwater per OP-1C Startup to Power Operation Step 5.39.4.
Once the second feed train is started raise power at 15% per hour up to 75% power.
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.
- 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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
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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Reference:
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