Text

2016 LaSalle County Station Initial License Examination Administered Scenarios
	ML17095A922
Person / Time
Site:	LaSalle
Issue date:	11/16/2016
From:	Chuck Zoia; NRC/RGN-III/DRS/OLB
To:	; Exelon Generation Co
Shared Package
ML15274A405	List: ML17095A759; ML17095A914; ML17095A922;
References
	Download: ML17095A922 (241)
	v • d • e

Facility NRC EXAM Scenario __

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 1 Op-Test No.: 2016301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 is at 7%4% power during a Startup.

Turnover: Secure the RWCU drain to the Main Condenser. Continue control rod withdrawal in preparation for taking the Mode Switch to RUN.

Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Secure RT Reject IAW LOP-RT-09 2 none R (ATC) Control Rod Withdrawals 3 none T (SRO) Damage to Fire Hose Station 109 Reported (TRM) 4 mni018 I (ATC) A IRM INOPfails UPSCALE, Half SCRAM 5 g8c75g14 C (BOP) TBCCW Header Pressure Low 6 B EHC Pump TRIP, Standby Pumps Fails to meh002 C (BOP)

Auto-Start 7 R0601 T (SRO) Low ADS Bottle Bank Nitrogen Pressure (TS) 8 mrd279 C (ATC) CRD FCV Fails CLOSED 9 RWCU Leak in RT Pump Room, RWCU Fails to mrw010 M (ALL)

Isolate 10 Two Areas Above Max Safe, Emergency RPV none M (ALL)

Blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification

LaSalle County Station ILT DYNAMIC SIMULATOR SCENARIO GUIDE ESG NRC 15-1-1 Rev. 0 07/20/2016 DEVELOPED BY: Colin Betken 8/15/2016 Instructor Date VALIDATED BY: Draper / Messina / Gallick / Jozwiak 8/1/2016 SME/Instructor Date REVIEWED BY: Mark Smith 8/17/2016 Operations Manager Date APPROVED BY: Dan Moren 8/17/2016 Exam Author Date

NRC 15-1-1 Revision 00 Facility: LaSalle County Station Scenario No.: NRC 15-1-1 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Secure RT Reject IAW LOP-RT-09 As a continuation of the unit startup the crew will secure RT Reject per LGP-1-1

2. Control Rods Withdrawals The crew is expected to withdraw Control Rods per LGP-1-1 to continue the Unit Startup.

3. Damage to Fire Hose Station 109 Reported (TRM)

Unit 1 Rounds Operator will report damage to a fire station and the Unit Supervisor will determine TRM requirements.

4. A IRM fails INOP, Half SCRAM The crew will determine A IRM is INOP and Bypass it A IRM, then reset the half scram

5. TBCCW Header Pressure Low The crew will respond by starting the standby pump and pressures will return to normal.

6. B EHC Pump TRIP, Standby Pumps Fails to Auto-Start The crew will respond by manually starting the standby EHC Pump.

7. Accumulator Trouble Alarm (TS)

8. CRD FCV Fails CLOSED The crew will have to transfer to the standby FCV when the online FCV fails.

9. RWCU Leak in RT Pump Room RT will experience a steam supply leak and the isolation valves will fail to automatically and manually isolate. The crew will manually scram the reactor per LGA-002

10. RWCU Fails to Isolate When the crew attempts to manually isolate RT due to the automatic isolations failure, RT will fail to isolate.

11. Two Areas Above Max Safe, Emergency RPV Blowdown The crew may anticipate Blowdown. When a second area parameter exceeds a Max Safe value, The LGA-004 Blowdown will be performed.

Critical Tasks

1. With a primary system discharging into the secondary containment, and discharge cannot be isolated or isolation attempt failed, scram the reactor, before any area exceeds the maximum safe operating levels..

2. With a primary system discharging into the secondary containment, and temperatures/radiation levels exceeding maximum safe values in more than one area, INITIATE emergency depressurization. (or anticipates Blowdown and depressurizes rapidly via the main turbine bypass valves.)

Page 2 of 38

NRC 15-1-1 Revision 00 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

2. None Operator Fundamentals

1. Monitoring plant indications and conditions closely

2. Controlling plant evolutions precisely

3. Operating the plant with a conservative bias

4. Working effectively as a team

5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2

1. Oversight ensures proper focus

2. Equipment restoration risk evaluation

3. Preparation for high risk evolution

4. Control Room resources adequate for EOP response

5. Sufficient engagement of others in decision making Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 15-1 NRC Exam Page 3 of 38

NRC 15-1-1 Revision 00 INITIAL SIMULATOR SETUP/REQUIRED DOCUMENTATION

1. Recall IC 3322 Password 3323

2. Place simulator in RUN.

3. Load and run the Smart Scenario: NRC15-1-1.ssf

4. Place Protected Equipment rings and/or robust barriers on the following components: None

5. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A

6. Perform the following panel manipulations:

Place B EHC Pump in RUN

Place A EHC Pump in STBY

Place A WT Pump in RUN

Place B WT Pump in STBY

Verify IRMs between 19 and 75

Verify RCMS prompting is set to RAISE

Verify the Main Condenser Low Vacuum Isolation Logic Bypass Switches are in NORM with Keys removed.

7. Place the following Tags: none

8. Have a copy of the following procedures:

LGP-1-1, completed up to Step E.6.4, IRM/APRM overlap completed per E.6.5 through E.6.8, and E.6.10 complete

LOP-RM-01, completed up to Step E.2

LOP-NR-02, completed up to Step E.2.1.8

LOP-RT-09, completed up to Step E.3. (Note: Step E.2 is N/A)

One copy of LOP-RT-09, (blank) for Unit Supervisor

Mark up Rod sheet to current rod per RCMS

9. Perform the pre-scenario checklist. (TQ-LA-150-0308)

Page 4 of 38

NRC 15-1-1 Revision 00 Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 1 Op-Test No.: 2016301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 is at 7% power during a Startup.

Turnover: Secure the RWCU drain to the Main Condenser. Continue control rod withdrawal in preparation for taking the Mode Switch to RUN.

Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Secure RT Reject IAW LOP-RT-09 2 none R (ATC) Control Rod Withdrawals 3 none T (SRO) Damage to Fire Hose Station 109 Reported (TRM) 4 mni018 I (ATC) A IRM fails INOP, Half SCRAM 5 g8c75g14 C (BOP) TBCCW Header Pressure Low B EHC Pump TRIP, Standby Pumps Fails to 6 meh002 C (BOP)

Auto-Start 7 R0601 T (SRO) Low ADS Bottle Bank Nitrogen Pressure (TS) 8 mrd279 C (ATC) CRD FCV Fails CLOSED RWCU Leak in RT Pump Room, RWCU Fails to 9 mrw010 M (ALL)

Isolate Two Areas Above Max Safe, Emergency RPV 101 none M (ALL)

Blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification Formatted Table Formatted: Indent: Left: 0", First line: 0" ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal: 1 Malfunction(s) after EOP (1-2): 1 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 4 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 2 ATC I/C (4 / set): 2 EOPs (1-2): 2 SRO-I I/C (4 / set inc 2 as ATC): 5 EOP Contingencies (0-2): 1 SRO Tech Spec (2 per set): 2 Critical Tasks (2-3): 2 ALL Major Transients (2 per set): 2 Formatted: Indent: Left: 0", Hanging: 0.62", Space Before: 7.2 pt Formatted: Line spacing: single, Tab stops: Not at 0.5" APPROXIMATE SCENARIO RUN TIME 90 Minutes Page 5 of 38

NRC 15-1-1 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)

During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

TASKS RO - ATC Provided initial indications, respond to a CRD failures from the Main Control 25.048 Room IAW station procedures.

Provided initial conditions, perform Control Room actions for a loss of 42.003 SRM/IRM indication IAW station procedures.

Given Unit Supervisor authorization, perform a Notch Withdrawal of a Control 47.001 Rod IAW station procedures.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given Unit Supervisor authorization, perform a normal unit startup from Mode 300.020 Switch in START-HOT STBY through RR pump upshift IAW station procedures.

Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 RO - BOP/ASSIST Maintain Reactor Vessel Water Level By Rejecting Water Via the Reactor 27.009 Water Cleanup System to either the Main Condenser or to Radwaste.

Perform Control Room actions to EVALUATE a breach of Secondary 70.021 Containment.

73.005 Perform the in plant actions to shift EHC pumps.

Perform the Main Control Room Actions for an Instrument Nitrogen System 97.016 Trouble Alarm.

Perform the Main Control Room actions for a Turbine Building Closed Cooling 113.016 Water (TBCCW) Pump Discharge Pressure Low Alarm Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given Unit Supervisor authorization, perform a normal unit startup from Mode 300.020 Switch in START-HOT STBY through RR pump upshift IAW station procedures.

Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given LGA-02, Secondary Containment Control, in progress, evaluate plant 417.000 conditions and control temperature in secondary containment by operation of ventilation, IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Given entry in LGA-4/06, RPV Blowdown, evaluate plant conditions and 428.000 rapidly depressurize the RPV using SRVs via the ADS system IAW station procedures.

Page 6 of 38

NRC 15-1-1 Revision 00 SRO - UNIT SUPERVISOR Provided initial indications, respond to a CRD failures from the Main Control 25.048 Room IAW station procedures.

Maintain Reactor Vessel Water Level By Rejecting Water Via the Reactor 27.009 Water Cleanup (RWCU) System to either the Main Condenser or to Radwaste.

Provided initial conditions, perform Control Room actions for a loss of 42.003 SRM/IRM indication IAW station procedures.

Given Unit Supervisor authorization, perform a Notch Withdrawal of a Control 47.001 Rod IAW station procedures.

Perform Control Room actions to EVALUATE a breach of Secondary 70.021 Containment.

73.005 Perform the in plant actions to shift EHC pumps.

Perform the Main Control Room Actions for an Instrument Nitrogen System 97.016 Trouble Alarm.

Perform the Main Control Room actions for a Turbine Building Closed Cooling 113.016 Water (TBCCW) Pump Discharge Pressure Low Alarm Given a set of plant conditions, identify and prepare the Technical 201.011 Specification required actions IAW Tech Specs.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given Unit Supervisor authorization, perform a normal unit startup from Mode 300.020 Switch in START-HOT STBY through RR pump upshift IAW station procedures.

Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given LGA-03, Primary Containment Control, in progress, cool the 421.000 Suppression Pool IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Given entry in LGA-4/06, RPV Blowdown, evaluate plant conditions and 428.000 rapidly depressurize the RPV using SRVs via the ADS system IAW station procedures.

Page 7 of 38

NRC 15-1-1 Revision 00 Event-1

==

Description:==

Secure RT Reject per LOP-RT-09 Initiation: TurnoverOn direction of Lead Evaluator Cues: LGP-1-1 Objective Position EXPECTED OPERATOR RESPONSE Per LOP-RT-09

Slowly DECREASE 1G33-R606, RWCU Reject Flow Controller to ZERO

VERIFY CLOSED 1G33-F031, RWCU Reject Header Orificea Bypass Valve o If required, THROTTLE 1G33-F042, RWCU Return Upstream Isolation Valve, to establish desired RWCU System Flow (360 gpm max) 27.009 BOP

VERIFY CLOSED the following:

1G33-F034, RWCU Discharge to Main Cond Stop Valve

1G33-F035, RWCU Blowdown Header Radwaste Drain Valve

From Control Room Panel 1H13-P602 VERIFY:

o RWCU Reject Flow Indicator 1G33-R602 shows no flow (expected) o Reactor level is stable at desired level ATC

Monitor Reactor Level and inform Unit Supervisor of any changes 27.009 US

Direct above actions Page 8 of 38

NRC 15-1-1 Revision 00 Event - 1

==

Description:==

Secure RT Reject per LOP-RT-09 Simulator Operator Actions With the concurrence of the Lead Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs none Terminus: When RT Reject is secured.

Page 9 of 38

NRC 15-1-1 Revision 00 Event-2

==

Description:==

Withdraw Control Rods to raise power Initiation: TurnoverFollowing crew assuming shift, on direction of Lead Evaluator Cues: LGP-1-1 Objective Position EXPECTED OPERATOR RESPONSE

Monitors control room panels and notify the CRS of any unusual or unexpected Formatted: Font: 10 pt 300.020 BOP conditions. Formatted: Font: 10 pt

Peer checks movements.

Per LGP-1-1 Formatted: Font: 10 pt, Bold

Continue to increase CTP with control rod withdrawal Formatted: Font: 10 pt o Monitor IRM and APRM recorders o Verify Main Turbine BPVs open as reactor power increases o Formatted: Indent: Hanging: 0.01", Bulleted + Level: 1 +

Per LOP-RM-01: Aligned at: 0" + Indent at: 0.25"

Verify Rod desired to be positioned is selected on the Rod Select Display Formatted: Font: 10 pt, Bold

Verify rod position information is correct on the Rod Select display/Status Formatted: Font: 10 pt Display/Core Map Display

Verify no insert or withdraw block indications on the Rod Select Display

Verify CRD Drive Flow Trip Circuit Bypass Switch is in the BYPASS position

CRD Drive Flow Trip Circuit Test Switch is in the NORMAL position.

Simultaneously DEPRESS and HOLD both CONTINUOUS WITHDRAW and WITHDRAW push-button. Selected rod will Formatted: Indent: Left: 0.25", No bullets or numbering

continuously withdraw until one (1) push-button is released.

Rod Withdraw Sequence begins:

o Rod INSERT indication appears on the ROD SELECT Display or Formatted: Bulleted + Level: 1 + Aligned at: 0.25" +

STATUS Display. Indent at: 0.5", Tab stops: Not at 0.49" o Rod WITHDRAW indication appears on the ROD SELECT Formatted: Font: (Default) Arial 300.020 Display or STATUS Display. Formatted: List Paragraph, No bullets or numbering ATC 47.001 DEPRESS rod WITHDRAW push-button and CHECK control rod withdrawal Formatted: Font: 10 pt sequence begins:

Formatted: Indent: Hanging: 0.01", Bulleted + Level: 1 +

Rod insert indication appears on the Rod Select or Status Display Aligned at: 0" + Indent at: 0.25", Tab stops: Not at 0.49" Rod withdraw indication appears on the Rod Select or Status Display Formatted: Indent: Left: 0.48", Hanging: 0.01", No bullets Control Rod motion is indicated on the Rod Select or Status Display or numbering, Tab stops: 0.49", List tab RELEASE rod WITHDRAW pushbutton and CHECK: Formatted: Font: 10 pt Rod position indication on Rod Select Display, Status Display or Core Map shows new rod position Observe changes in nuclear instrumentation indications Rod settle light is lit for ~2 seconds Repeat for each Control Rod movement o Control Rod continuous motion is indicated on the ROD SELECT Formatted: Font: (Default) Arial Display or STATUS Display. Formatted: Font: 10 pt

OBSERVE changes in nuclear instrumentation indications. Formatted: List Paragraph, Indent: Left: 0.25", Space

When either push-button is released, Rod SETTLE indication is lit for Before: 0 pt, After: 0 pt, No bullets or numbering, approximately 2 seconds. Widow/Orphan control, Adjust space between Latin and Asian text, Adjust space between Asian text and numbers

New rod position will be indicated on the ROD SELECT Display, STATUS Display and CORE MAP Display. Formatted: List Paragraph, Indent: Left: 0.25", Space o If control rod is withdrawn to position 48, PERFORM Rod Coupling Before: 0 pt, After: 0 pt, No bullets or numbering, Widow/Orphan control, Adjust space between Latin and Asian Check per Step E.7, as applicable.

text, Adjust space between Asian text and numbers Page 10 of 38

NRC 15-1-1 Revision 00

SIMULTANEOUSLY DEPRESS both CONTINUOUS WITHDRAW and WITHDRAW push-buttons. Formatted: Font: (Default) Arial

CHECK to ensure that the control rod does NOT go to the withdrawn Formatted: Font: 10 pt Overtravel position using as many of the following indications as are available Formatted: List Paragraph, Indent: Left: 0.49", Space Before: 0 pt, After: 0 pt, No bullets or numbering, o OBSERVE that the "+ +" position indication goes blank then returns to Widow/Orphan control, Adjust space between Latin and Asian the "+ +" position on the ROD SELECT Display or STATUS Display. text, Adjust space between Asian text and numbers, Tab o OBSERVE that drive flow drops from normal flow to stall flow. stops: 0.49", List tab o OBSERVE that CRD OVERTRAVEL does NOT alarm. Formatted: Font: (Default) Arial

Repeat for each Control Rod movement Formatted: Font: 10 pt

Upon completion of Control Rod moves, verify CRD Drive Flow Circuit BYPASS Switch is in the ACTIVE position Formatted: Font: (Default) Arial 300.020 Formatted: Font: 10 pt US

Direct above action 47.001 Formatted: Font: (Default) Arial Formatted: Font: 10 pt Formatted: Font: 10 pt Formatted: Left Page 11 of 38

NRC 15-1-1 Revision 00 Event - 2

==

Description:==

Withdraw Control Rods to raise power Simulator Operator Actions none Simulator Operator Role Play None Floor Instructor Notes/OPEX/TRs None Terminus: When indicated APRM power has risen by 2% or at the discretion of the Lead Evaluator Page 12 of 38

NRC 15-1-1 Revision 00 Event-3

==

Description:==

Damage to Fire Hose Station F109 Initiation: On direction of Lead Evaluator Cues: Phone call Objective Position EXPECTED OPERATOR RESPONSE

Receives call from field and updates the crew on the status of Fire Hose BOP Station 109 ATC

Monitor Plant conditions and update crew as required

Declare the Fire Hose Station INOP

Enter TRM 3.7.m Action A.1, place additional fire hose from operable hose station to protect the affected area in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Required Action A.3.1, restore the inoperable station to an operable 201.011 US status in 14 days OR Required Action A.3.2, prepare the corrective action report in 14 days

Direct Field Supervisor to make preparations to support TRM requirements

Inform Fire Marshall Page 13 of 38

NRC 15-1-1 Revision 00 Event - 3

==

Description:==

Damage to Fire Hose Station F109 Simulator Operator Actions With the concurrence of the Call the 2307 and follow role play below.

Lead Evaluator Simulator Operator Role Play With the concurrence of the Lead Evaluator:

Call as MMD and report, While performing TRM Fire Hose Station inspections, per LMS-FP-15, I you discovered Fire Hose Station F109 on Reactor Building 820, Location F9, the hose reel is benthas a bent hose reel and will not allow unwinding of the hose.

Role Play in plant operators as necessary if asked to confirm the report of hose station damage.

Floor Instructor Notes/OPEX/TRs none Terminus: Following phone call to Shift Manager for TRM requirements.

Page 14 of 38

NRC 15-1-1 Revision 00 Event-4

==

Description:==

A IRM Fails INOP, Half SCRAM Initiation: On direction of Lead Evaluator, release Event 4 Cues:

Automatic Actions: Half Scram Expected Annunciators:

1H13-P603-A308, ROD OUT BLOCK 1H13-P603-B304, CHANNEL A IRM HI-HI/INOP 1H13-P603-B206, CHANNEL A1 AND B1 NEUTRON MONITOR TRIP Key Parameter Response: A RPS solenoids de-energize Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitor plant parameters and update the crew as required Per LOR-1H13-P603-B304

Verify Automatic Actions

VERIFY A IRM Range Switch in the correct position

If one IRM in Channel A has failed High or is Inop, BYPASS that IRM and INITIATE corrective action to restore operability.

RESET RPS Channel A 42.003 ATC Formatted: Indent: Left: 0.24" OR Per LOA-NR-101

Stop all Control Rod motion / Power changes Formatted: Indent: Left: 0.24", No bullets or numbering

Check IRM indications

If IRM is INOP, BYPASS the IRM

Direct above actions 42.003 US

REFER to Tech Spec 3.3.1.1 and TRM 3.3.c (No timeclocks applicable)

Inform Shift Manager Page 15 of 38

NRC 15-1-1 Revision 00 Event - 4

==

Description:==

A IRM Fails INOP, Half SCRAM Simulator Operator Actions With the concurrence of the Release Event 4 Lead Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs None Terminus: When Half Scram Reset Page 16 of 38

NRC 15-1-1 Revision 00 Event-5

==

Description:==

TBCCW Header Pressure Low Initiation: On direction of Lead Evaluator, release Event 5 Cues:

Automatic Actions: none Expected Annunciators: LOR-1PM10J-A304, Turbine Building Closed Cooling Water Pump Discharge Header Pressure Low Key Parameter Response: Lowering TBCCW Header Pressure Objective Position EXPECTED OPERATOR RESPONSE 113.016 Per LOR-1PM10J-A304

CHECK Turbine Building Closed Cooling Water Pump Discharge Header pressure is less than or equal to Alarm setpoint

START a standby Turbine Building Closed Cooling Water Pump

DISPATCH operator to TB 735 to INSPECT Turbine Building Closed Cooling Water Pump for proper operation per LOP-WT-02, Startup and Operation of Turbine Building Closed Cooling Water System BOP

INITIATE appropriate corrective action as required OR Per LOA-WT-101

CHECK TBCCW Discharge Header pressure - GREATER THAN 50 psig.

START standby TBCCW pump (B). Formatted: Font: Not Bold Formatted: Indent: Left: 0.24", No bullets or numbering

Secure A WT Pump ATC

Observe and report plant parameters 113.016

Direct above actions US

Set WT temperature pressure as critical parameter

Set SCRAM criteria - loss of all WT Page 17 of 38

NRC 15-1-1 Revision 00 Event - 5

==

Description:==

TBCCW Header Pressure Low Simulator Operator Actions With the concurrence of the Release Event 5 Lead Evaluator Simulator Operator Role Play When dispatched to 1A WT Pump while it is still running, wait 2 minutes and report, there is rumbling noise coming from 1A TBCCW pump.

Floor Instructor Notes/OPEX/TRs Terminus: When the 1B TBCCW Pump has been started and the 1A TBCCW Pump has been secured.

Page 18 of 38

NRC 15-1-1 Revision 00 Event-6

==

Description:==

B EHC Pump TRIP, Standby Pumps Fails to Auto-Start Initiation: On direction of Lead Evaluator, release Event 6 Cues:

Automatic Actions: none (Auto Start Fails)

Expected Annunciators:

1PM02J-B401, EHC HYDRAULIC FLUID PUMP AUTO TRIP Key Parameter Response: EHC Pressure lowering and EHC Pump Auto Trip Light illuminated Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM02J-B401

VERIFY Standby EHC hydraulic Fluid Pump has STARTED

Monitor EHC Pump and system parameters return to normal, refer to LOP-EH-04 as necessary

DISPATCH operator to perform post start checks on the running EHC 73.005 BOP Pump

DISPATCH operator to Bus 132A to INSPECT EHC Hydraulic Fluid Pumps breaker for abnormalities

At EHC Reservoir at Turbine Building Elevation 710 INSPECT EHC Hydraulic Fluid Pump which tripped

Monitor Reactor Power, level and pressure and update the crew as ATC necessary

Dispatch Equipment Operator to investigate Tripped EHC Pump

Direct above actions 73.005 US

Notify Shift Manager Page 19 of 38

NRC 15-1-1 Revision 00 Event - 6

==

Description:==

B EHC Pump TRIP, Standby Pumps Fails to Auto-Start Simulator Operator Actions With the concurrence of the Release Event 6 Lead Evaluator Simulator Operator Role Play If sent to investigate B EHC Pump report that the motor is hot to the touch.

Floor Instructor Notes/OPEX/TRs If the standby EHC Pump is not started by 1100 psig EHC pressure (~2 minutes) the Main Turbine will trip and the Reactor will scram.

Terminus: When A EHC Pump is running and parameters have returned to normal and/or at the discretion of the Lead Evaluator.

Page 20 of 38

NRC 15-1-1 Revision 00 Event-7

==

Description:==

Low ADS Bottle Bank Nitrogen Pressure Initiation: On direction of Lead Evaluator, release Event 7 Cues:

Automatic Actions: none Expected Annunciators:

LOR-1PM13J-A404, INSTRUMENT NITROGEN SYSTEM TROUBLE Key Parameter Response: none Objective Position EXPECTED OPERATOR RESPONSE ATC

Assists BOP Operator as directed Per 1PM13J-A404 Report and take actions per annunciator 1PM13J-A404, INSTRUMENT 97.016 NITROGEN SYS TROUBLE:

If alarm is due to R0601, refer to LOP-IN-05 (yes-R0601)

BOP Per LOP-IN-05:

Direct bottles replaced when pressure is less than 800 psig.

NOTE that 4 bottles should be replaced when 1PM13J-A404 alarms

Direct above Actions

Make call to Shift Manager, enter T.S. 3.5.1, required Action G.1, be in 97.016 US mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Required Action G.2, reduce reactor Steam 201.011 Dome Pressure to < 150 psig in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Page 21 of 38

NRC 15-1-1 Revision 00 Event - 7

==

Description:==

Low ADS Bottle Bank Nitrogen Pressure Simulator Operator Actions With the concurrence of the Release Event 7 Lead Evaluator Wait until the Tech Spec From the Summary Screen, delete Malfunction r0601 and then call has been made and at perform the Role Play #2 below least 3 minutes after being directed to restore N2 Simulator Operator Role Play Role-Play #1: As the EO, wait 1 minute and report that the South Bottle Bank pressure is 490 psig.

You will restore the bottle bank immediately.

- - If asked, the Reserve Bottle Pressure is 1000 psig and as the EO, you will replace the reserve bottle also.

- - If asked, the area has been inspected and there is no indication of a leak. The nitrogen bottle pressures are stable.

When annunciator 1PM13J-A404 has reset, Role-Play #2: As the EO, and report that the bottle bank is restored and pressure reads 1580psig.

- - If asked, the reserve bottle is restored and pressure reads 2040 psig.

Floor Instructor Notes/OPEX/TRs none Terminus: After Tech Spec call.

Page 22 of 38

NRC 15-1-1 Revision 00 Event-8

==

Description:==

CRD FCV Fails Closed Initiation: On direction of Lead Evaluator, release Event 8 Cues:

Automatic Actions: PPC alarm CRD low flow Expected Annunciators:

1H13-P603-A403, CRD HYD TEMP HI Key Parameter Response: CRD Flow Controller Position Demand downscale; CRD System Flow, Cooling Water Pressure, and CRD Cooling Flow indications lowering, inability to withdraw control rods Objective Position EXPECTED OPERATOR RESPONSE

Provide peer checks as required

Monitor CRD temperatures BOP Per LOR-1H13-P603-A403

At 1H22-P007, on CRD/RX Vessel Temperature Recorder, determine which of the CRDs initiated the alarm Per LOA-RD-101

Check no control rods drifting

Check CRD parameters normal:

CRD system flow approximately 63 gpm

Cooling header differential pressure <30 psid

Drive water header differential pressure <600 psid Determine CRD parameters are not normal

Transfer flow controller, 1C11-R600, to Manual

ManuallyAttempt to adjust flow controller output using open/close pushbuttons to return parameters to normal (WILL NOT WORK)

Determine flow controller output will not adjust, and then locally Formatted: Indent: Left: 0.25", No bullets or numbering 25.048 ATC verify instrument air is lined up to and is available to CRD manual/auto station (YES)

Throttle drive water PCV 1C11-F003 as required to restore parameters to normal

Determine Flow Control valve is still not controlling CRD system flow at approximately 63 gpm

Direct EO to place FCV in Local Manual operation at CRD Manual/Auto station (RB 761)

Determine CRDFCV is not controlling at approximately 63 gpm , and direct EO to transfer to standby FCV per Attachment B

Coordinate with EO in local control to restore system parameter to normal

Direct above actions 25.048 US

Establish CRD temperatures as critical parameter Page 23 of 38

NRC 15-1-1 Revision 00 Event - 8

==

Description:==

CRD FCV Fails Closed Simulator Operator Actions With the concurrence of the Release Event 8 Lead Evaluator Simulator Operator Role Play As EO, when requested, wait 1 minute and report that instrument air is lined up and available to the CRD M/A station (step 2.1.2)Acknowledge reports as required.

When directed to place A FCV in Local Manual (step 4.1), follow above Sim Op action, wait 2 minutes and report that the FCV will not open in local manual.

If asked, 1C11-F601A and 1C11-F602A are open.

When ordered to perform Attachment B, coordinate to perform the following (if the crew does not attempt to coordinate with the EO for Attachment B then perform the following actions an report Attachment B complete):

When ordered to open 1C11-F046B (B.1.1.1), wait 10 seconds and report 1C11-F046B is open.

When ordered to open 1C11-F047B (B.1.1.2), follow above Sim Op action and report 1C11-F047B is open.

When ordered to open 1C11-F602B (B.1.1.3), follow the above Sim Op action to delete malfunction; and report 1C11-F602B is open.

When ordered raise flow in local manual using 1C11-F600B, use above Sim Op action and report when complete (B.1.1.4).

- - if asked, 1C11-R301B is reading the same as 1C11-R301A (B.1.1.4).

When ordered to close 1C11-F602A (B.1.1.5), wait 10 seconds and report it is closed.

When ordered to close 1C11-F046A (B.1.1.6), wait 10 seconds and report it is closed.

When ordered to close 1C11-F047A (B.1.1.7), perform above Sim Op action and report that it is closed.

Adjust 1C11-F600B as requested using Sim Op action above Floor Instructor Notes/OPEX/TRs Terminus: AB CRD FCV operating in RemoteLocal Manual mode.

Page 24 of 38

NRC 15-1-1 Revision 00 Event-9

==

Description:==

RWCU Leak in RT Pump Room, RT Fails to isolate Initiation: On direction of Lead Evaluator, release Event 9 Cues:

Automatic Actions: (automatic isolation valves have been failed)

Expected Annunciators:

1H13-P601-B408, C511, C411, & B507, RT system High Flow and High Flow 1H13-P601-E&F204, RB and RB Vent Rad levels high Key Parameter Response: RT system Flow and Flow indications Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1H13-P601-C411

Attempt to identify and correct cause of high diff flow

If this cannot be cleared in 45 seconds and system trips, perform the 70.021 BOP following:

Verify auto action occurs

Verify RT Pump, 1G33-C001A/B trips

Dispatch an operator to investigate for leaks and abnormalities

Refer to LOA-RT-101 Page 25 of 38

NRC 15-1-1 Revision 00

Formatted: Indent: Left: 0.25", No bullets or numbering, Tab stops: Not at 0.55" Per LOA-RT-101

Check RWCU - Isolated o 1G33-F001, RWCU Suct Inbd Isol Vlv - CLOSED o G33-F004, RWCU Suct Otbd Isol Vlv - CLOSED 70.021 BOP Response not obtained

Close valves as necessary

Check RWCU pump TRIPPED Response not obtained

Trip running RWCU pump

Formatted: Indent: Left: 0.25", No bullets or numbering Per LOA-AR-101

Notify and evacuate personnel from affected areas

Restrict access to affected areas

Dispatch RP Technician to survey and sample the affected areas

Refer to LGA-002 ATC

Check cause of high radiation Formatted: Bulleted + Level: 1 + Aligned at: 0" + Tab after: 0.25" + Indent at: 0.25", Tab stops: 0.55", List tab +

4.03", Left

Dispatch EO to isolate if possible Formatted: Indent: Left: 0.25", No bullets or numbering

Check area Formatted: No bullets or numbering controlled by RP personnel Formatted: No bullets or numbering, Tab stops: Not at

Have RP determine exposure of personnel 0.55" Per LGA-002 Formatted: No bullets or numbering, Tab stops: 0.55", List

Operate area coolers, if possible and Reactor Building Vent, if permitted tab + 4.03", Left

Report to the Unit Supervisor the RT System failed to isolate and Formatted: Font: 11 pt 304.010 manual isolation attempts failed 417.000 BOP

Before any area temperature, radiation, or water level reaches max safe Formatted: Font: 11 pt 413.000 value the scram and enter LGA-001 Formatted: No widow/orphan control

Monitor area temperature, radiation levels and trends and reports trends Formatted: Font: 11 pt to Unit Supervisor Formatted: Font: 11 pt Formatted: Indent: Left: 0.25", No bullets or numbering, Performs Reactor Scram and LGP 3-2 on US direction. (CT) No widow/orphan control

ARM and DEPRESS Scram Pushbuttons

PLACE Reactor Mode Switch in SHUTDOWN

INSERT SRMs

CHECK Control Rods INSERTED and Power Decreasing

INFORM Unit Supervisor of Control Rod Status and Reactor Power 304.010

Operate Feedwater and/or ECCS as necessary to maintain RPV Water ATC Level 20" to 50" or as specified by Unit Supervisor 413.000

Place LFFRV in AUTO o Verify FRV closed in MANUAL

REPORT to the Unit Supervisor the status of RPV Level and Pressure

If needed for level control:

o Place the FRV in AUTO o Reset the Scram o Dispatch an EO to close 1C11-F034, Charging Water Supply Valve Page 26 of 38

NRC 15-1-1 Revision 00

STABILIZE Reactor Pressure <1020 psig o If Main Condenser is available, open Bypass Valves

Maintains RPV water level as directed

Maintains RPV pressure as directed

Direct above actions

Directs Reactor Scram (CT) 304.010 US

Directs isolation of RWCU 413.000

When two areas are above Max Safe of the same parameter enter LGA-004 Page 27 of 38

NRC 15-1-1 Revision 00 Event - 9

==

Description:==

RWCU Leak in RT Pump Room Simulator Operator Actions With the concurrence of the Release Event 9 Lead Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs none Terminus: continued Page 28 of 38

NRC 15-1-1 Revision 00 Event-10

==

Description:==

RWCU Fails to Isolate Initiation: continued Objective Position EXPECTED OPERATOR RESPONSE Per LGA-002

Operate area coolers, if possible and Reactor Building Vent, if permitted 304.010

If any area temperature or radiation above max normal or any floor drain sump is overflowing then isolate all discharges into affected areas 417.000 BOP except the systems needed for Damage Control or LGA actions 413.000

If any area temperature, radiation, or water level reaches max safe value the scram and enter LGA-001

Wait until two or more areas above max safe value in the same parameter and enter LGA-004 Performs Reactor Scram and LGP 3-2 on US direction. (CT)

ARM and DEPRESS Scram Pushbuttons

PLACE Reactor Mode Switch in SHUTDOWN

INSERT SRMs

CHECK Control Rods INSERTED and Power Decreasing

INFORM Unit Supervisor of Control Rod Status and Reactor Power

Operate Feedwater and/or ECCS as necessary to maintain RPV Water Level 20" to 50" or as specified by Unit Supervisor 304.010

Place LFFRV in AUTO ATC 413.000 o Verify FRV closed in MANUAL

REPORT to the Unit Supervisor the status of RPV Level and Pressure

If needed for level control:

o Place the FRV in AUTO o Reset the Scram o Dispatch an EO to close 1C11-F034, Charging Water Supply Valve

STABILIZE Reactor Pressure <1020 psig o If Main Condenser is available, open Bypass Valves

Maintains RPV water level as directed Maintains RPV pressure as directed 304.010

Direct above actions US 413.000

Directs isolation of RWCU Page 29 of 38

NRC 15-1-1 Revision 00 Event - 10

==

Description:==

RWCU Fails to Isolate Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs none Terminus: continued Formatted: Left Page 30 of 38

NRC 15-1-1 Revision 00 Event-101

==

Description:==

Two Areas Above Max Safe, Emergency RPV Blowdown Initiation: continued Objective Position EXPECTED OPERATOR RESPONSE ATC

Maintains RPV water level as directed during Blowdown Formatted: Font: 10 pt

Monitors Reactor Building areas for rising Temperature and/or rad levels

Notifies Unit Supervisor of two area radiations are above Max Safe (CT)

Per LGA-004 428.000 Formatted: Font: 10 pt BOP

When directed, performs a manual initiation of ADS (CT) 421.000

Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons

Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons

Verifies 7 ADS valves open. (CT)

o If directed, opens Turbine Bypass Valves Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25"

Per LGA-003

When directed, starts all available Pool Cooling per LGA-RH-103

Startup RHR Service Water as follows:

OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B

At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, START first RHR Service Water Pump:

1A or 1B/C or D

When indicated flow reaches 3000 gpm, START second RHR Service Water 421.000 Pump Formatted: Font: 10 pt BOP 421.010

Startup RHR

Start 1A/1B RHR Pump

Throttle 1E12-F024A/B (Test Valve) OPEN to establish RHR flow of 1500 to Formatted: Font: 10 pt 7450 gpm

Close 1E12-F048A/B (HX Bypass) o Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B or o Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B

o May anticipates Blowdown and direct actions to rapidly depressurize via turbine Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent bypass valves at: 0.25"

Directs LGA-004, RPV Blowdown, when 2 areas above Max Safe Radiation 428.000 and unable to isolate leak. enters and directs LGA-004 (CT) Formatted: Font: 10 pt 421.000 US

Verifies Suppression Pool level is greater thanabove -18 ft.

421.010

Directs a manual initiation of ADS

Verifies 7 ADS valves open (CT)

o If Suppression Pool Water Temperature exceeds 105°F or Suppression Pool Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent Level exceeds +3, enters and directs LGA-003 at: 0.25" Page 31 of 38

NRC 15-1-1 Revision 00 Event - 101

==

Description:==

Two Areas Above Max Safe, Emergency RPV Blowdown Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs none Terminus: When Blowdown has been performed and/or at the discretion of the Lead Evaluator Page 32 of 38

NRC 15-1-1 Revision 00 REFERENCES Procedure Title Revision

1. LGA-001 RPV CONTROL 017

2. LGA-002 SECONDARY CONTAINMENT CONTROL 009

3. LGA-003 PRIMARY CONTAINMENT CONTROL 016

4. LGA-004 RPV BLOWDOWN 009

5. LGP-1-1 NORMAL UNIT STARTUP 115

6. LGP-3-2 REACTOR SCRAM 072 REACTOR WATER CLEAN-UP SYSTEM (RWCU) -

7. LOP-RT-09 017 COOLANT REJECTION

8. LOP-NR-02 INTERMEDIATE RANGE MONITOR OPERATION 019

9. LOR-1H13-P603-B304 CHANNEL A IRM HI-HI INOP 003 TURBINE BUILDING CLOSED COOLING WATER

10. LOR-1PM10J-A304 002 PUMP DISCHARGE HEADER PRESSURE LOW

11. LOR-1PM02J-B401 EHC HYDRAULIC FLUID PUMP A OR B AUTO TRIP 001

12. LOR-1PM13J-A404 INSTRUMENT NITROGEN SYSTEM TROUBLE 008 LEAK DETECTION REACTOR WATER CLEANUP

13. LOR-1H13-P601-C411 007 FLOW HIGH LEAK DETECTION REACTOR WATER CLEANUP

14. LOR-1H13-P601-B507 005 FLOW HIGH CONTROL ROD DRIVE HYDRAULIC TEMPERATURE

15. LOR-1H13-P603-A403 006 HIGH

16. LOA-RD-101 CONTROL ROD DRIVE ABNORMAL 020

17. LOA-RT-101 LOSS OF REACTOR WATER CLEANUP SYSTEM 019 UNIT 1 AREA RADIATION MONIYORING SYSTEM

18. LOA-AR-101 004 ABNORMAL Unit 1 A and B RHR Operations in the LGAs and 012

19. LGA-RH-103 SAMGs

20. LOP-RM-01 ROD CONTROL MANAGEMENT SYSTEM 043 TECHNICAL REQUIREMENTS MANUAL FIRE HOSE 024

21. LMS-FP-15 STATION INSPECTION

22. LOA-NR-101 NEUTRON MONITORING TROUBLE 019 LOSS OF TURBINE BUILDING CLOSED COOLING 004

23. LOA-WT-101 WATER (TBCCW)

REPLACING NITROGEN BOTTLES ON INSTRUMENT 025

24. LOP-IN-05 NITROGEN SYSTEM SHIFTING PUMPS AND PRESSURE ADJUSTMENT IN 017

25. LOP-EH-04 THE ELECTRO HYDRAULIC CONTROL SYSTEM Page 33 of 38

NRC 15-1-1 Revision 00 COMPUTER AIDED EXERCISE PROGRAM (CAEP)

ESG NRC 15-1-1 Revision: 00 Revision Date: 6/30/16 Developed By: C. Betken Page 34 of 38

NRC 15-1-1 Revision 00 Page 35 of 38

NRC 15-1-1 Revision 00 Page 36 of 38

NRC 15-1-1 Revision 00 THIS PAGE INTENTIONALLY LEFT BLANK Page 37 of 38

NRC 15-1-1 Revision 00 U1 SUPERVISOR TURNOVER Shift: 2 Date: Today Mode: 2 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level

7 % Power

100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions

Startup in progress following

None maintenance outage per LGP-1-1 Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance

None

None LOSs in progress or major maintenance LOSs in progress or major maintenance

None

None Equipment removed from service or currently unavailable

None

None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.

1. Next step is to secure RT Reject per

Non-Div workweek LGP-1-1 step E.6.9 and LOP-RT-09

OLR is Green

2. Followed by withdrawing Control Rods to 10% per LGP-1-1 step E.6.4

IRM to APRM overlap has been completed

Non-Div workweek

OLR is Green Page 38 of 38

Facility NRC EXAM Scenario __

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 2 Op-Test No.: _2016301_______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% power Turnover: SPE Blower swap IAW LOP-GS-05 Event Malf. No. Event Event No. Type* Description 1 none N (BOP) SPE Blower SWAP IAW LOP-GS-05 2 none T (SRO) U-2 Reports DIV 2 DG INOPERABLE 3 mcw014 C (BOP) 1A WR Pump TRIP 4 r0342 R (ATC) 1E MPT Transformer Hot Spot 5 r0742 T (SRO) SBLC Squib Valve Continuity Lost 6 none C (BOP) B VR SupplyExhaust Fan TRIP mcw015 C (ALL) Complete Loss of RBCCW 7

mcw013 8 mrp017 M (ALL) Electrical ATWS 9 none C (ATC) ARI Fails (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

LaSalle County Station ILT DYNAMIC SIMULATOR SCENARIO GUIDE ESG NRC 15-1-2 Rev. 0 07/29/2016 DEVELOPED BY: Colin Betken 8/15/2016 Instructor Date VALIDATED BY: J. Martin / Hawkins / Jozwiak / Clark 7/31/2016 SME/Instructor Date REVIEWED BY: Mark Smith 8/17/2016 Operations Manager Date APPROVED BY: Dan Moren 8/17/2016 Exam Author Date

NRC 15-1-2 Revision 00 Facility: LaSalle County Station Scenario No.: NRC 15-1-2 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. SPE Blower SWAP IAW LOP-GS-05

2. U-2 Reports DIV 2 DG INOP The crew will enter Tech Specs.

3. 1A WR Pump TRIP The crew will Start one of the standby WR Pumps.

4. 1E MPT Transformer Hot Spot The crew will lower Reactor Power to lower transformer temperature.

5. SBLC Squib Valve Continuity Lost The crew will enter Tech Specs.

6. B VR Supply Fan TRIP The crew will start the standby VR Supply Fan

7. Complete Loss of RBCCW The crew will scram the Reactor.

8. Electrical ATWS The crew will take action to insert Control Rods and shutdown the core.

9. ARI Fails Critical Tasks

1. With a reactor scram required and insufficient control rod worth inserted to maintain the reactor shutdown under all conditions without boron; take action to insert control rods, and if reactor power is above 3% or unknown following recirculation flow reduction, inject boron.

2. With a reactor scram required and insufficient control rod worth inserted to maintain the reactor shutdown under all conditions without boron, inhibit ADS and prevent ECCS.

3. During an ATWS with reactor power above 3% or unknown, rapidly lower RPV water level to at least -60 inches.

3.4. During an ATWS with reactor power above 3% or unknown, and RPV water level lowered to less than -60 inches, use Preferred ATWS Systems to hold RPV water level between -60 inches and -150 inches on Wide Range.

Page 2 of 30

NRC 15-1-2 Revision 00 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

2. None Operator Fundamentals

1. Monitoring plant indications and conditions closely

2. Controlling plant evolutions precisely

3. Operating the plant with a conservative bias

4. Working effectively as a team

5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2

1. Oversight ensures proper focus

2. Equipment restoration risk evaluation

3. Preparation for high risk evolution

4. Control Room resources adequate for EOP response

5. Sufficient engagement of others in decision making Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 15-1 NRC Exam Page 3 of 30

NRC 15-1-2 Revision 00 INITIAL SIMULATOR SETUP/REQUIRED DOCUMENTATION

1. Recall a full power IC 151.

2. Place simulator in RUN.

3. Load and run the Smart Scenario: NRC 15-1-2.ssf

4. Place Protected Equipment rings and/or robust barriers on the following components: None

5. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A

6. Perform the following panel manipulations:

Verify A WR Pump is Running

Verify 0 and B WR Pumps are in Standby

Verify A and B VR trains are running

Verify an edge rod is selected

7. Place the following Tags: None

8. Update the Tech Spec Timeclock Sheet as follows:

9. Have a copy of LOP-GS-05

10. Verify keys 85 and 87 are in the proper location in the key storage locker Formatted: Font: (Default) Arial, 11 pt 10.11. Verify Thermal Power is less than 3546 MWth, lower using RR ganged flow. Formatted: Indent: Left: 0.5", No bullets or numbering 11.12. Perform the pre-scenario checklist. TQ-LA-150-0308 Page 4 of 30

NRC 15-1-2 Revision 00 Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 2 Op-Test No.: __2016301______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% power Turnover: SPE Blower swap IAW LOP-GS-05 Event Malf. No. Event Event No. Type* Description 1 none N (BOP) SPE Blower SWAP IAW LOP-GS-05 2 none T (SRO) U-2 Reports DIV 2 DG INOPERABLE 3 mcw014 C (BOP) 1A WR Pump TRIP 4 r0342 R (ATC) 1E MPT Transformer Hot Spot 5 r0742 T (SRO) SBLC Squib Valve Continuity Lost 6 none C (BOP) B VR Supply Fan TRIP mcw015 C Formatted: Centered 7 Complete Loss of RBCCW mcw013 (ALLTC) 8 mrp017 M (ALL) Electrical ATWS 8 none C (ATC) ARI Fails (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Formatted: Indent: Left: 0", First line: 0" ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal: 1 Malfunction(s) after EOP (1-2): 1 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 3 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 1 ATC I/C (4 / set): 2 EOPs (1-2): 1 SRO-I I/C (4 / set inc 2 as ATC): 4 EOP Contingencies (0-2): 1 SRO Tech Spec (2 per set): 2 Critical Tasks (2-3): 3 ALL Major Transients (2 per set): 1 Formatted: Indent: Left: 0", Hanging: 0.62", Space Before: 7.2 pt APPROXIMATE SCENARIO RUN TIME 90 Minutes Page 5 of 30

NRC 15-1-2 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)

During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

TASKS RO - ATC Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.000 shutdown the reactor IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert 431.010 control rods IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.020 perform SBLC injection, IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 432.000 maintain a Heat Sink, IAW station procedures.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 433.000 maintain RPV water level IAW LGA-010.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control 434.000 reactor power by maintaining RPV water level IAW station procedures.

RO - BOP/ASSIST Respond to a Transformer Trouble and take the appropriate actions to 2.010 restore.

Perform Control Room actions to startup and shutdown Gland Seal Steam 71.033 System, Perform the Main Control Room actions for a Trip of a Reactor Building 114.019 Closed Cooling Water (RBCCW) Pump.

Perform the Main Control Room actions for a Reactor Building Closed Cooling 114.027 Water (RBCCW) Pump Discharge Pressure Low Alarm 114.029 Perform Control Room actions for a loss of RBCCW.

119.014 Start-up the Turbine Building Ventilation System (VT).

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 432.000 maintain a Heat Sink, IAW station procedures.

Page 6 of 30

NRC 15-1-2 Revision 00 SRO - UNIT SUPERVISOR Respond to a Transformer Trouble and take the appropriate actions to 2.010 restore.

Perform Control Room actions to startup and shutdown Gland Seal Steam 71.033 System, Perform the Main Control Room actions for a Trip of a Reactor Building 114.019 Closed Cooling Water (RBCCW) Pump.

Perform the Main Control Room actions for a Reactor Building Closed Cooling 114.027 Water (RBCCW) Pump Discharge Pressure Low Alarm 114.029 Perform Control Room actions for a loss of RBCCW.

119.014 Start-up the Turbine Building Ventilation System (VT).

Given a set of plant conditions, identify and prepare the Technical 201.011 Specification required actions IAW Tech Specs.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.000 shutdown the reactor IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert 431.010 control rods IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.020 perform SBLC injection, IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 432.000 maintain a Heat Sink, IAW station procedures.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 433.000 maintain RPV water level IAW LGA-010.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control 434.000 reactor power by maintaining RPV water level IAW station procedures.

Page 7 of 30

NRC 15-1-2 Revision 00 Event-1

==

Description:==

SPE Blower swap IAW LOP-GS-05 Initiation: TurnoverFollowing crew assuming shift, on direction of Lead Evaluator Cues: Turnover Objective Position EXPECTED OPERATOR RESPONSE Per LOP-GS-05

Start the idle Blower associated with the operating Steam Packing Exhauster 1CD01SAB

While maintaining Steam Packing Exhauster Inlet Header A/B at between 5-12 W.C. on 1PI-GS032, perform the following:

Partially throttles open the suction valve for the idle Blower until the SPE Steam Inlet Header vacuum increases to 12 W.C.

Partially throttle shut the suction valve for the Blower that was initially in the operation until the SPE Steam Inlet Header vacuum decreases 71.033 BOP to 5 W.C. or until the suction valve for the blower that was initially operating is closed

Alternately repeat steps 1 and 2 above until the suction valve for the Blower that was initially in operation indicates closed

Adjust the position of the Blower suction valve for the on-line Blower, as necessary, to maintain an SPE Steam Inlet Header vacuum of 8-12 W.C.

Close the Steam Packing Exhauster Blower Suction Valve that was initially open, 1N62-MOV-D1/2 or 1N62-MOV-D3/4

Stop the A/B Steam Packing Exhauster Blower that was initially in operation ATC

Monitor Plant parameters and update crew as required.

US

Direct above actions.

Page 8 of 30

NRC 15-1-2 Revision 00 Event - 1

==

Description:==

SPE Blower swap IAW LOP-GS-05 Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs None Terminus: When SPE Blowers have been swapped.

Page 9 of 30

NRC 15-1-2 Revision 00 Event-2

==

Description:==

U-2 Reports DIV 2 DG INOPERABLE Initiation: On direction of Lead Evaluator Cues: Call from the Booth Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitor Plant conditions and update the crew as required.

ATC

Monitor Plant conditions and update the crew as required.

Call Shift Manager

Enter Tech Spec 3.8.1

Condition B - Required opposite unit division 2 DG inoperable

Required Action

B.1 - perform SR 3.8.1.1 for operable required offsite circuits in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 201.011 US AND

B.2 - Declare features supported by DG INOP in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR

B.3.2 - perform SR 3.8.1.2 AND

B.4 - Restore required DG to operable in 14 days Page 10 of 30

NRC 15-1-2 Revision 00 Event - 2

==

Description:==

U-2 Reports DIV 2 DG INOPERABLE Simulator Operator Actions With the concurrence of the Make call to crew with role play below.

Lead Evaluator Simulator Operator Role Play Call 2300 to the Unit Supervisor and report, Unit 2 A Diesel Generator has been declared INOP due to LOS-DG-M2 Floor Instructor Notes/OPEX/TRs If the crew attempts to perform offsite power lineup, inform the Unit Supervisor that the Unit 2 Assist NSO is performing the offsite power lineup.

Terminus: After Tech Spec call.

Page 11 of 30

NRC 15-1-2 Revision 00 Event-3

==

Description:==

1A WR Pump TRIP Initiation: On direction of Lead Evaluator, release Event 3 Cues:

Automatic Actions: A WR Pump Trip Expected Annunciators:

1PM10J-A101, REACTOR BUILDING CLOSED COOLING WATER PUMP AUTOMATIC TRIP 1PM10J-A201, RBCCW PMP DSCH HDR PRESS LO (if RT isolates the following annunciators are expected) 1H13-P602-A106, REACTOR WATER CLEANUP RECIRCULATION PUMP AUTO TRIP 1H13-P602-A203, REACTOR WATER CLEANUP FILTER INLET TEMPERATURE HIGH 1H13-P602-A206, REACTOR WATER CLEANUP RECIRCULATION PUMPS FLOW LOW 1H13-P602-A303, RWCU FILTER INLET TEMP HI-HI 1H13-P602-B103, REACTOR WATER CLEANUP FILETER DEMIN TROUBLE Key Parameter Response: Lowering WR pressure and rising WR temperature Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM10J-A101

Verify automatic action occurs

Start standby Reactor Building Closed Cooling Water Pump

Dispatch operator to Bus 133 for Pump 1A to inspect breaker for 114.019 Reactor Building Closed Cooling Water Pump for abnormalities BOP 114.027

Dispatch operator to El 786 in Reactor Building to inspect Reactor Building Closed Cooling Water Pump for abnormalities

Refer to LOA-WR-101, Loss of Reactor Building Closed Cooling Water o Refer to LOP-WR-02, Startup and Operation of the Reactor Building Closed Cooling Water System Per LOA-WR-101 114.019

Check RBBCW header discharge pressure - greater than 50 psig 114.027 BOP Response not obtained 114.029

Start standby RBCCW pump

Monitor Plant parameters and update the crew as required.

ATC o Refer to LOA-RT-101 114.019

Direct above actions 114.027 US 114.029 Page 12 of 30

NRC 15-1-2 Revision 00 Event - 3

==

Description:==

1A WR Pump TRIP Simulator Operator Actions With the concurrence of the release Event 3 Lead Evaluator Simulator Operator Role Play If sent to investigate the A WR Pump as the Operator in the field, wait 2 minutes and report, A WR Pump tripped on Overcurrent If asked, as Unit 2 inform the Unit 1 that the Common WR Pump is aligned to Unit 1.

Floor Instructor Notes/OPEX/TRs RT may isolate due to WR Pump trip. RT recovery will not be performed.

Terminus: When a standby WR Pump is running.

Page 13 of 30

NRC 15-1-2 Revision 00 Event-4

==

Description:==

1E MPT Transformer Hot Spot Initiation: On direction of Lead Evaluator, release Event 4 Cues:

Key Parameter Response: none Expected Annunciators:

1PM01J-A204, MAIN TRANSFORMER 1 EAST TROUBLE Automatic Actions: none Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM01J-A204

DISPATCH an operator to 1E Transformer 2.010 BOP

Verify alarm

Toggle local alarm switch to determine status of alram Per LOA-TRAN-101 section B.5

Check power available to fans and pumps

Check all fan and pump banks - operating

Refer to attachment C and attachment E for MPT 1E/1W operating parameters/limits 2.010 BOP

Check MPT Hot Spot Temperature below 160C (YES)

Check MPT Hot Spot Temperature below 120C (NO)

Response not obtained

Reduce transformer load to reduce MPT Hot Spot temperature

<120C

Record time transformer temperature exceeded 120C

Contact system engineering and EMD for transformer repairs

Lower Reactor Power to reduce MPT Temperature to below 120C 2.010 ATC o Reduce RR Flow Formatted: Justified, Bulleted + Level: 1 + Aligned at: 0" +

Indent at: 0.25"

o Insert Cram Rods

Direct above actions US

Inform TSO Page 14 of 30

NRC 15-1-2 Revision 00 Event - 4

==

Description:==

1E MPT Transformer Hot Spot Simulator Operator Actions With the concurrence of the Release Event 4 Lead Evaluator When asked to take alarm toggle switch to From Smart Summary place r0342 in OFF RESET/OFF When asked to take alarm From Smart Summary place r0342 in ON toggle switch to ON When asked to take alarm toggle switch to From Smart Summary place r0342 in OFF RESET/OFF When Reactor Power has been reduced 100 MWeWith concurrence from DELETE from smart summary r0342 the Lead Evaluator (Satisfactory Reactivity Manipulation)

Simulator Operator Role Play when dispatched to the 1E transformer, wait 2 minutes and report that 1E Transformer has a Hot spot and Temperature is 125 degrees Celsius and rising one degree every 2 minutes and the oil temperature alarm is in.

If asked, inform the crew all fan banks and pumps are running and power is available.

If asked, 6 coolers are running and ambient temperature is 23 degrees Celsius.

If asked to take the oil temperature toggle Switch follow the above Sim Op Actions After initial down power, if the crew stops lowering power prior to 100 MWe inform them temperature is at 125 degrees Celsius and stable.

When power has been lowered by 100 MWe and with concurrence of the Lead Evaluator, call and Formatted: Underline inform the crew, transformer oil temperature is 115 degrees Celsius and lowering Acknowledge reports as required Floor Instructor Notes/OPEX/TRs none Terminus: When power is lowered 100 MWe or at the discretion of the Lead Evaluator.

Page 15 of 30

NRC 15-1-2 Revision 00 Event-5

==

Description:==

SBLC Squib Valve Continuity Lost Initiation: On direction of Lead Evaluator, release Event 5 Cues:

Key Parameter Response: none Expected Annunciators:

1H13-P603-A105, SBLC SQUIB VALVE CONTINUITY LOSS Automatic Actions: none Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitor Plant conditions and update the crew as necessary Per LOR-1H13-P603-A105

At back panel 1H13-P603:

If M1 Meter Relay 1C41-M600A/B milliamp reading is < 0.2 ma, declare Squib Valve INOP

Check fuse F1, 2, 3/F4, 5, 6 (1/4 amp feed to M1 Relay)

ATC

Verify circuit breakers ON at MCC 135X-1 Compt D1, Ckt Bkr 19 for A pump or MCC 136X-2 Compt E1, Ckt Bkr 14 for B pump

Refer to Tech Spec 3.1.7

Initiate Action Request to have M1 Meter Relay 1C41-M600A/B circuit repaired

Direct above actions

Enter Tech Spec 3.1.7, inform Shift Manager 201.011 US

Condition A, One SLC subsystem inoperable

Required Action A.1 Restore SLC subsystem to OPERABLE STATUS in 7 days Page 16 of 30

NRC 15-1-2 Revision 00 Event - 5

==

Description:==

SBLC Squib Valve Continuity Lost Simulator Operator Actions With the concurrence of the Release Event 5 Lead Evaluator Simulator Operator Role Play Role Play EO dispatched to a SBLC Pump breaker at MCC 135X-1, Compartment D1, Breaker 19:

Wait 2 minutes and then report that:

The Breaker is still closed and there are no obvious signs of damage.

Role Play EMD as necessary if contacted to investigate this failure.

Floor Instructor Notes/OPEX/TRs If clarification of indications is required, inform the Crew member who checks the SBLC M1 Meter Relay fuses (in 1H13-P603 interior) that fuses F1, F2, and F3 are sat..

Terminus: Ttech Spec call is made or at the discretion of the Lead Evaluator.

Page 17 of 30

NRC 15-1-2 Revision 00 Event-6

==

Description:==

B VR Supply Fan TRIP Initiation: On direction of Lead Evaluator, release Event 6 Cues:

Key Parameter Response: Reactor Building D/P Expected Annunciators:

1PM06J-A406, REACTOR BUILDING VENTILATION SUPPLY FAN AUTO TRIP Automatic Actions: B VR Supply Fan Trip Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM06J-A406

CHECK automatic action occurs

MONITOR temperature as needed

IF less than 2 supply fans are running, PERFORM following to bypass Group 1 Main Steam Isolation valve logic before restarting fans:

INSTALL MSL Pipe Tunnel Diff. Temperature Bypass Keys (Control key Number 85 and 87) at Panel 1H13-P642 for control switches. MSL 119.014 BOP PIPE TUNNEL DIFF TEMP BYPASS DIV 2 SIG B/D.

PLACE keylock switches at Panel 1H13-P642 to bypass

Start appropriate time clock

PLACE MSL PIPE TUNNEL DIFF TEMP BYPASS DIV 2 SIG B/D keylock switches at panel 1H13-P642 to NORMAL

DISPATCH operator to investigate cause of alarm at SWGR 132X, Cub 503B

START standby Reactor Building Ventilation Supply Fan ATC

Monitor Plant parameters and update the crew as necessary

Direct above actions

Enter Tech Spec 3.3.6.1 for MSL Pipe Tunnel Diff Temp bypass

Condition A - one or more channels INOP

Required Action A.1- to place channel in trip in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when Formatted: Indent: Left: 0.49", Tab stops: 0.74", List tab 119.014 US key lock switches are in bypass + Not at 0.25" + 0.49"

Condition B - one or more automatic function with isolation capability not maintained

Required Action B.1- restore isolation capability in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Formatted: Indent: Left: 0.49", Tab stops: 0.74", List tab

+ Not at 0.25" + 0.49" Formatted: Indent: Left: 0.25", No bullets or numbering Page 18 of 30

NRC 15-1-2 Revision 00 Event - 6

==

Description:==

B VR Supply Fan TRIP Simulator Operator Actions With the concurrence of the Release Event 6 Lead Evaluator Simulator Operator Role Play As the operator in the field, if told to investigate VR Fan trip, wait 3 minutes and report, B Supply Fan tripped on Overcurrent Floor Instructor Notes/OPEX/TRs none Terminus: Standby VR Supply Fan started and parameters return to normal.

Page 19 of 30

NRC 15-1-2 Revision 00 Event-7

==

Description:==

Complete Loss of RBCCW Initiation: On direction of Lead Evaluator, release Event 7 Cues:

Key Parameter Response: Lowering RBBCW Header Pressure and rising RBCCW temperatures Expected Annunciators:

1PM10J-A101, RBCCW PMP AUTO TRIP 1PM10J-A201, RBCCW PMP DSCH HDR PRESS LO Automatic Actions: RBCCW Pump Auto Trip Objective Position EXPECTED OPERATOR RESPONSE Per LOA-WR-101

Check RBBCW header discharge pressure - greater than 50 psig Response not obtained

Start standby RBCCW pump 114.019

If NO RBBCW Pump can be started go to Section B.2 114.027 BOP

Monitor RR pump temperatures per LOR-1H13-P602-B507 114.029

Check open 1WR029, 1WR040, 1WR179, and 1WR180

Check RR Pumps running in slow speed Response not obtained

Manually SCRAM Reactor

Performs Reactor Scram and LGP 3-2 on US direction.

ARM and DEPRESS Scram Pushbuttons

PLACE Reactor Mode Switch in SHUTDOWN 304.010 ATC

INSERT IRMs and SRMs

CHECK Control Rods INSERTED and Power Decreasing

INFORM Unit Supervisor of Control Rod Status and Reactor Power 114.019 114.027 US

Direct above actions 114.029 Page 20 of 30

NRC 15-1-2 Revision 00 Event - 7

==

Description:==

Complete Loss of RBCCW Simulator Operator Actions With the concurrence of the Release Event 7 Lead Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Crew will Scram on Loss of RBCCW Terminus: continued Page 21 of 30

NRC 15-1-2 Revision 00 Event-8

==

Description:==

Electrical ATWS Initiation: On direction of Lead Evaluator Cues:

Key Parameter Response: Rod position and Reactor Power Expected Annunciators: multiple Automatic Actions: none Objective Position EXPECTED OPERATOR RESPONSE Per LGA-010

Inhibit ADS (CT) Formatted: Font: 9.5 pt

Prevent injection from HPCS, LPCS and LPCI (CT)

Per the PRESSURE Leg BOP

STABILIZE pressure <1059 psig using main turbine bypass valves Formatted: Font: 9.5 pt

VERIFY required automatic actions occur o May request LGA-RH-101 jumper installation Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent

RUNBACK Reactor Recirculation flow to minimum at: 0.25"

If power is >3% then TRIP RR Pumps Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent

Recognize that all rods did not insert and notify US (Electrical ATWS) at: 0.25" Per the POWER Leg, if Control Rod remains out Formatted: Indent: Left: 0.24", Bulleted + Level: 1 +

If control rods remain out: Aligned at: 0" + Indent at: 0.25"

Initiate ARI

If power is above 3%, initiate SBLC (CT)

Insert Control rods per LGA-NB-01 (CT) 431.000 Formatted: Font: 9.5 pt

Method 3 Single Rod Insert 431.010

Bypass RWM 431.020

Place CRD Drive Flow Trip Circuit in BYPASS 432.000 ATC

Insert control rods using Continuous Insert or Insert Button 433.000 434.000

WAIT until rods full in except one OR all rods in to at least 02 OR Reactor will stay shutdown under all conditions without boron per QNE.

WAIT until Reactor is Shutdown or Cold Shutdown Boron is injected (<3050 gal in SBLC Tank)

Per the Level Leg

If reactor power > 3% or unknown then Rapidly LOWER Level to at least -60 inches (minimizes Feedwater injection) (CT) and use only preferred systems to hold level between -100 and -60 inches. (CT)

When directed, stops SBLC pump

VERIFY Main Turbine and Generator Trip 304.010 Formatted: Font: 9.5 pt ATC

STABILIZE Reactor Pressure <1020 psig 433.000

Monitors and reports RPV water level throughout

Controls injection from Condensate and Feed system

Method 4 Reset Scram/Drain SDV/Re-Scram 431.010 Formatted: Font: 9.5 pt

Direct Unit 2 Assist to deenergize ARI 433.000 ATC

Direct Unit 2 Assist to Install jumpers for resetting the scram

Reset Scram/Drain SDV/Re-Scram

If all rods are not in to at least 02 and the reactor will not stay shutdown without Formatted: Font: 9.5 pt 431.000 Boron then EXIT LGA-001 and ENTER LGA-010 431.010 US

Directs Inhibit ADS (CT) Formatted: Font: 9.5 pt 431.020

Directs rapidly lowering vessel level to -60.(CT) (PRA) 432.000

Directs controlling level -100 to -60.(CT)

Page 22 of 30

NRC 15-1-2 Revision 00 433.000

Directs start of SBLC and/or insert control rods.(CT) (PRA) 434.000

Directs method of control rod insertion per LGA-NB-01 Method 1 (CT)

Direct Method 1 Remove Scram/Discharge fuses Formatted: Bulleted + Level: 1 + Aligned at: 0.25" + Tab o May direct Method 3 Single Rod Insert after: 0.5" + Indent at: 0.5" o May direct Method 4 Reset Scram/Drain SDV/Re-Scram

Directs bypassing MSIV low level isolation per LGA-MS-01 Event - 8

==

Description:==

Electrical ATWS Simulator Operator Actions With the concurrence of the Lead Evaluator when Release Method 1 requested to remove A RPS fuses (Attachment

Removes A RPS fuses and SDV Vent and Drain fuses 1B/1E) for Method 1 LGA-NB-01 With the concurrence of the

From the RNI display - JMP Screen - click on LGA-NB-01 (2 Lead Evaluator when LGA-jumpers)

NB-01 Method 4 is called

Select INSTALLED then INSERT for

De-energize ARI using iaaride1 and iaaride2 LGA-RH-101 With the concurrence of the

From the RNI display - JMP Screen - click on LGA-RH-101 (1 Lead Evaluator when LGA-jumper)

RH-101 is called for

Select INSTALLED then INSERT LGA-MS-01 With the concurrence of the

From the RNI display - JMP Screen - click on LGA-MS-01 Lead Evaluator when LGA- jumpers (5 jumpers)

MS-01 is called for

Install only jumper #4

Select INSTALLED then INSERT When requested to reinstall From Smart Summary Select isdvf18a and isdv18b, install and insert SDV Vent and Drain Fuses Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs The Failure of ARI is intended for the ATC and is part of their normal ATWS choreography.none Terminus: When all Control Rods are full in, SBLC is secured, and at the discretion of the Lead Evaluator.continued Page 23 of 30

NRC 15-1-2 Revision 00 Event-8 (Continued)

Objective Position EXPECTED OPERATOR RESPONSE

As directed perform LGA-NB-01 Method 3 431.010

Method 4 Reset Scram/Drain SDV/Re-Scram 433.000 ATC

Direct Unit 2 Assist to deenergize ARI

Direct Unit 2 Assist to Install jumpers for resetting the scram

Reset Scram/Drain SDV/Re-Scram

RUNBACK Reactor Recirculation flow to minimum BOP

If power is >3% then TRIP RR Pumps Page 24 of 30

NRC 15-1-2 Revision 00 Event-8 (Continued) Formatted: Centered

==

Description:==

ATWS, After Control rods inserted Objective Position EXPECTED OPERATOR RESPONSE

When directed, stops SBLC pump

VERIFY Main Turbine and Generator Trip 304.010 ATC

STABILIZE Reactor Pressure <1020 psig 433.000

Monitors and reports RPV water level throughout

Controls injection from Condensate and Feed system

Monitors reactor to ensure operations remain within established bands BOP

Monitors control room panels and notifies the SRO of any unusual or unexpected conditions

When rods inserted, direct securing SBLC injection

When rods inserted, exits LGA-010 and re-enters LGA-001

Enters and directs actions of LGA-001 LEVEL LEG 433.000 US

Directs water level band of +11" to +59.5" (+20" to +50" preferred)

Enters and directs actions of LGA-001 PRESSURE LEG

STABILIZE Reactor Pressure below 1059 psig Page 25 of 30

NRC 15-1-2 Revision 00 Floor Instructor Notes/OPEX/TRs None Terminus: When all Control Rods are full in, SBLC is secured, or when sufficient Control Rods have been inserted at the discretion of the Lead Evaluator.

Page 26 of 30

NRC 15-1-2 Revision 00 Formatted: Left REFERENCES Procedure Title Revision

1. LGA-001 RPV CONTROL 017

2. LGA-010 FAILURE TO SCRAM 015 UNIT 1 A AND B RHR OPERATIONS IN THE LGAS

3. LGA-RH-103 012 AND SAMGS

4. LGA-SC-101 INITIATION OF SBLC UNIT 1 002

5. LGA-NB-01 ALTERNATE ROD INSERTION 018

6. LGP-3-1 POWER CHANGES 062

7. LGP-3-2 REACTOR SCRAM 072 REACTOR BUILDONG CLOSED COOLING WATER

8. LOR-1PM10J-A101 002 PUMP AUTOMATIC TRIP

9. LOR-1H13-P603-A105 SBLC SQUIB VALVE CONTINUITY 004 REACTOR BUILDING VENTILATION SUPPLY FAN

10. LOR-1PM06J-B406 001 1RT01CB AUTOMATIC TRIP LOSS OF REACTOR BUILDING CLOSED COOLING

11. LOA-WR-101 014 WATER (RBCCW)

REACTOR WATER CLEANUP RECIRCULATION

12. LOR-1H13-P602-A106 004 PUMP AUTO TRIP REACTOR WATER CLEANUP FILTER INLET

13. LOR-1H13-P602-A203 001 TEMPERATURE HIGH REACTOR WATER CLEANUP RECIRCULATION

14. LOR-1H13-P602-A206 003 PUMPS FLOW LOW

15. LOR-1H13-P602-A303 RWCU FILTER INLET TEMP HI-HI 002 REACTOR WATER CLEANUP FILETER DEMIN

16. LOR-1H13-P602-B103 001 TROUBLE

17. LOR-1PM10J-A201 RBCCW PMP DSCH HDR PRESS LO 002

18. LOA-TRAN-101 TRANSFORMER TROUBLE 025 CHANGE OVER OF GLAND SEAL STEAM

19. LOP-GS-05 003 PACKING EXHAUSTER BLOWERS

20. LOA-RT-101 LOSS OF REATOR WATER CLEANUP SYSTEM 019

21. LOR-1PM01J-A204 MAIN TRANSFORMER 1E TROUBLE 004 PLANT PROCESS COMPUTER MISCELLANEOUS

22. LOP-CX-07 016 FUNCTIONS Page 27 of 30

NRC 15-1-2 Revision 00 SMART SCENARIO ESG NRC 15-1-2 Revision: 00 Revision Date: 7/29/15 Developed By: C. M. Betken Page 28 of 30

NRC 15-1-2 Revision 00 THIS PAGE INTENTIONALLY LEFT BLANK Page 29 of 30

NRC 15-1-2 Revision 00 U1 SUPERVISOR TURNOVER Shift: 2 Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level

100 % Power

100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions

None

None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance

None

None LOSs in progress or major maintenance LOSs in progress or major maintenance

None

None Equipment removed from service or currently unavailable

None

None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.

Will be swapping SPE blowers IAW

Non-Div workweek LOP-GS-05 from 1A SPE Blower A to

OLR is Green 1A SPE Blower B

Non-Div workweek

OLR is Green Page 30 of 30

Facility NRC EXAM Scenario __

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 3 Op-Test No.: __2016301______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Reactor power, RCIC is OOS ready to be returned to Standby.

Turnover: Warm RCIC Steam Line and return to Standby IAW LOP-RI-05 step E.9 Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Warm RCIC Steam Lines and Return to Standby (Optional) 2 mrw001 C (BOP) RT Pump TRIP 3 r0414 C (BOP) OG Building Exhaust Fan TRIP 4 mcn017 R (ATC) Earthquake Below OBE/SSE Limit, Small Condenser Air Leak 4 none T (SRO) Seismic Event 5 k3k02p1y C (ATC) Failure of the RR Ganged Controller in AUTO 6 mca014 M (ALL) Scram, Suppression Pool Leak 7 mrd040 C (ATC) Five Control Rods Remain Out 8 none M (ALL) Blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification

LaSalle County Station ILT DYNAMIC SIMULATOR SCENARIO GUIDE ESG NRC 15-1-3 Rev. 0 07/13/2016 DEVELOPED BY: Colin Betken 8/15//2016 Instructor Date VALIDATED BY: Tutich / Reyes / Nicoll / Dejewski 7/16/2016 SME/Instructor Date REVIEWED BY: Mark Smith 8/17/2016 Operations Manager Date APPROVED BY: Dan Moren 8/17/2016 Exam Author Date

NRC 15-1-3 Revision 00 Facility: LaSalle County Station Scenario No.: NRC 15-1-3 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Warm RCIC Steam Lines and Return to Standby. The crew will return RCIC following maintenance performed on it.

2. RT Pump TRIP. The crew will respond to the Reactor Water Cleanup Pump Trip and Restart the RT System.

3. OG Building Exhaust Fan TRIP. The crew will respond to the Off Gas Building Exhaust fan Trip by securing the on service train of ventilation and starting the standby train.

4. Earthquake Below OBE/SSE Limit, Suppression Pool Leak. Following the validation of the Earthquake, the crew will see a lowering Suppression Pool Level and send operators to investigate and will notice a leak in the Suppression Pool. The crew will respond by Scramming the Reactor.

5. Small Condenser Air Leak. The crew will see the rising Backpressure and will attempt to lower Reactor Power using Reactor Recirculation flow or Control Rods to alter the trend of backpressure

6. Failure of the RR Ganged Controller in AUTO. When attempting to lower Reactor Power using Reactor Recirculation flow, they will attempt to use the lower pushbutton on ganged RR flow control. With this being unsuccessful the crew should attempt to take manual control of the Reactor Recirculation Flow Control Valves and lower flow.

7. Five Control Rods Remain Out. Following the Reactor Scram, five Control Rods will remain out, placing the Reactor in an ATWS (Anticipated Transient Without Scram) condition. This will force the crew to use alternate means of inserting Control Rods.

8. Blowdown. The crew will Blowdown the Reactor Vessel using ADS (Automatic Depressurization System) due to Suppression Pool level approaching -12 feet.

Critical Tasks

1. With a reactor scram required and insufficient control rod worth inserted to maintain the reactor shutdown under all conditions without boron; take action to insert control rods, and if reactor power is above 3% or unknown following recirculation flow reduction, inject boron.

2. When suppression pool level cannot be maintained > -12 feet, initiate emergency depressurization.

(Or anticipate Blowdown and depressurize rapidly via the main turbine bypass valves.)

3. During an ATWS with emergency depressurization required and Suppression Pool Level above -18 feet, the crew will terminate and prevent all injection except Boron, CRD, RCIC. (If the crew exits LGA-010 prior to blowing down, this Critical Task will not be applicable)

Page 2 of 34

NRC 15-1-3 Revision 00 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

2. None Operator Fundamentals

1. Monitoring plant indications and conditions closely

2. Controlling plant evolutions precisely

3. Operating the plant with a conservative bias

4. Working effectively as a team

5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2

1. Oversight ensures proper focus

2. Equipment restoration risk evaluation

3. Preparation for high risk evolution

4. Control Room resources adequate for EOP response

5. Sufficient engagement of others in decision making Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 15-1 NRC Exam Page 3 of 34

NRC 15-1-3 Revision 00 INITIAL SIMULATOR SETUP/REQUIRED DOCUMENTATION

1. Recall a full power IC 151342 Password 3423. (if not performing Event 1 then use IC 151)

2. Place simulator in RUN.

3. Load and run the Smart Scenario: NRC 15-1-3.ssf Formatted: Font: Not Bold 3.4. If intending to perform event 1: complete 5 through 9, otherwise they are N/A 4.5. Place Protected Equipment rings and/or robust barriers on the following components for RCIC Inoperable:

HPCS Pump C/S HPCS DG C/S 1E22-F004 C/S 1E22-F015 C/S HPCS WLP C/S HPCS DGCWP C/S 1E22-F012 C/S 1E22-F023 C/S 5.6. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time T.S. 3.5.3 RCIC A.1 Verify HPCS is operable Immediately Completed T.S. 3.5.3 RCIC A.2 Restore to OPERABLE 14 Days 12 Days from status now 6.7. Perform the following panel manipulations:

Isolate the RCIC Steam Lines as follows:

Close the following RCIC Steam Supply Valves:

1E51-F076, RCIC Steam Supply Inbd Isol Bypass/Warmup Valve

1E51-F063, RCIC Steam Supply Inbd Isol Valve

1E51-F008, RCIC Steam Supply Otbd Isol Valve

1E51-F045, RCIC Turb Steam Inlet Isol Vlv.

Open the Steam Supply Drain Trap Bypass valve; 1E51-F054

Allow approximately 15 minutes for RCIC Steam Supply Pressure to decay to 0 psig on PI 1E51-R602

Close 1E51-F054 7.8. Verify the following:

The 1B RWCU Pump is running

The 0A Offgas Building Supply and Exhaust fans are running

RCIC PI 1E51-R602 reading approximately 0 psig

9. Have a copy of LOP-RI-05 marked up, with E.8 the next step to be completed.

10. Verify Power is less than 3546 MWth 8.11. Following the Scenario: check paper copies of LOP-RT-02 and LOP-VO-01 for marks and replace as required.

9.12. Perform the pre-scenario checklist. (TQ-LA-150-0308)

Page 4 of 34

NRC 15-1-3 Revision 00 Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 3 Op-Test No.: __2016301______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Reactor power, RCIC is OOS ready to be returned to Standby.

Turnover: Warm RCIC Steam Line and return to Standby IAW LOP-RI-05 step E.9 Event Malf. No. Event Event No. Type* Description 1 none Warm RCIC Steam Lines and Return to Standby N (BOP)

(Optional) 2 mrw001 C (BOP) RT Pump TRIP 3 r0414 C (BOP) OG Building Exhaust Fan TRIP 4 mcn017 Earthquake Below OBE/SSE Limit, Small R (ATC)

Condenser Air Leak 4 none T (SRO) Seismic Event 5 k3k02p1y C (ATC) Failure of the RR Ganged Controller in AUTO 6 mca014 M (ALL) Scram, Suppression Pool Leak 7 mrd040 C (ATC) Five Control Rods Remain Out 8 none M (ALL) Blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal: 1 Malfunction(s) after EOP (1-2): 1 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 4 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 2 ATC I/C (4 / set): 2 EOPs (1-2): 2 SRO-I I/C (4 / set inc 2 as ATC): 4 EOP Contingencies (0-2): 2 SRO Tech Spec (2 per set): 0 Critical Tasks (2-3): 3 ALL Major Transients (2 per set): 2 Formatted: Indent: Left: 0", Hanging: 0.62" APPROXIMATE SCENARIO RUN TIME 90 Minutes Page 5 of 34

NRC 15-1-3 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)

During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

TASKS RO - ATC Given various plant conditions, predict how the RR System will respond to 22.00.21 various system component failures while operating the system or on an exam in accordance with station procedures.

Given Unit Supervisor authorization, respond to a Loss of Condenser Vacuum 111.002 IAW station procedures.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.000 shutdown the reactor IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert 431.010 control rods IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 432.000 maintain a Heat Sink, IAW station procedures.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 433.000 maintain RPV water level IAW LGA-010.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control 434.000 reactor power by maintaining RPV water level IAW station procedures.

RO - BOP/ASSIST Perform the Main Control Room actions to Warm Up, Flush and Startup the 27.001 Reactor Water Cleanup (RWCU) System.

Perform Control Room actions to reset a RCIC System isolation or Turbine 32.006 trip.

Given Unit Supervisor authorization, respond to a Loss of Condenser Vacuum 111.002 IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Evaluate plant conditions and control and maintain Suppression Pool Level 422.000 below the SRVTPL Limit.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 423.000 conditions and control and maintain Suppression Pool Level above -12 feet IAW station procedures.

Given entry in LGA-4/06, RPV Blowdown, evaluate plant conditions and 428.000 rapidly depressurize the RPV using SRVs via the ADS system IAW station procedures.

Page 6 of 34

NRC 15-1-3 Revision 00 SRO - UNIT SUPERVISOR Perform the Main Control Room actions to Warm Up, Flush and Startup the 27.001 Reactor Water Cleanup (RWCU) System.

Perform Control Room actions to reset a RCIC System isolation or Turbine 32.006 trip.

Given a set of plant conditions, identify and prepare the Technical 201.011 Specification required actions IAW Tech Specs.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Evaluate plant conditions and control and maintain Suppression Pool Level 422.000 below the SRVTPL Limit.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 423.000 conditions and control and maintain Suppression Pool Level above -12 feet IAW station procedures.

Given entry in LGA-4/06, RPV Blowdown, evaluate plant conditions and 428.000 rapidly depressurize the RPV using SRVs via the ADS system IAW station procedures.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.000 shutdown the reactor IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert 431.010 control rods IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 432.000 maintain a Heat Sink, IAW station procedures.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 433.000 maintain RPV water level IAW LGA-010.

Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control 434.000 reactor power by maintaining RPV water level IAW station procedures.

Page 7 of 34

NRC 15-1-3 Revision 00 Event-1

==

Description:==

Warm RCIC Steam Lines and Return to Standby Initiation: Following crew assuming shift, on direction of Lead Evaluator Cues: Turnover Objective Position EXPECTED OPERATOR RESPONSE Per LOP-RI-05

Perform the following to warm up the RCIC Steam Line

Reset the RCIC Turbine Trip as follows:

Verify 1E51-F045, RCIC Turb Steam Inlet Isol Vlv is closed

If an Isolation caused turbine trip, RESET isolation signal on division that was tripped

Close 1E51-F360, RCIC Turb Trip & Throttle Vlv. This will reset the valve

Slowly throttle open 1E51-F008

Slowly throttle open 1E51-F076

Verify RCIC steam line pressure reaches reactor supply pressure by observing the pressure indicated on 1E51-R602 on Control Room Panel 1H13-P601

Verify water in the section of pipe downstream of 1E51-F063, RCIC Steam Supply Inbd Isol Valve, has been forced out of the piping.

When Reactor pressure and RCIC pressure match, as indicated on 32.006 BOP the 1E51-R602, open 1E51-F063, RCIC Steam supply Inbd Isol Valve

Close 1E51-F076, RCIC Steam Supply Inbd Isol Bypass/Warmup Valve

Open 1E51-F360, RCIC Turb Trip & Throttle Vlv. Verify both sets of RCIC Turb Trip & Throttle Vlv Red/Green lights indicate open

Perform the following to properly align RCIC:

Verify RCIC governor valve is open

Verify 1E51-F360, RCIC Turb Trip & Throttle Vlv is open

Verify 1E51-R600, RCIC Pmp Dsch Flow Controller, is in AUTO and the flow rate is set to 600 gpm

Close 1E51-F004, Baro Cndsr Pmp Upstm Stop

Open 1E51-F004, Baro Cndsr Pmp Upstm Stop

Open 1E51-F005, Baro Cndsr Pmp Dwnst Stop

Close 1E51-F005, Baro Cndsr Pmp Dwnst Stop

Cycle open and close the RCIC Steam Drain Pot isolation valves

Verify the RCIC pushbutton collars and logic is RESET

Verify ESF panel light is not lit ATC

Monitor Plant parameters and update the crew as required

Direct above actions 32.006 US

Refer to Tech Spec 3.3.6.1 Page 8 of 34

NRC 15-1-3 Revision 00 Event - 1

==

Description:==

Warm RCIC Steam Lines and Return to Standby Simulator Operator Actions When requested to perform Attachment A to bypass the Release Event 1 High Steam Line Flow switches When requested to restore the High Steam Flow From the Summary Page, DELETE Remote Function: iarihisf switches per Steps 19-24 Simulator Operator Role Play Role Play as the EO/IMD directed to bypass Flow switches per Steps 2-9:

(Time Compression) Wait 1 minute then perform the SIMOP action above and report that Attachment A Steps 2-9 are complete.

Role Play as the EO/IMD directed to bypass Flow switches per Steps 10-16:

(Time Compression) Wait 1 minute then report that Attachment A Steps 10-16 are complete.

Role Play as the EO/IMD directed to restore the High Steam Flow switches per Steps 19-24:

(Time Compression) Wait 1 minute then perform the SIMOP action above and report that Attachment A Steps 19-24 are complete.

Floor Instructor Notes/OPEX/TRs None Terminus: When RCIC Turbine Trip & Throttle Valve, 1E51-F360 has been opened per Step E.9.7 Page 9 of 34

NRC 15-1-3 Revision 00 Event-2

==

Description:==

RT Pump TRIP Initiation: On direction of Lead Evaluator, release Event 2 Cues:

Key Parameter Response: 1B RWCU Pump indications, RT System flow, Expected Annunciators: 1H13-P602-A107, 1B RWCU RECIRC PUMP AUTO TRIP Automatic Action: RWCU Filter Demineralizers isolate Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1H13-P602-A107 - Refer to LOA-RT-101:

Check RWCU Not Isolated: Verify 1G33-F001 and F004 Open

Directs EO to place RT F/D control switches to ISOLATE and check F/D inlet and outlet valves closed

Start Standby RWCU pump per LOP-RT-02 Per LOP-RT-02

Direct an EO to verify RBCCW is valved in to 1A RWCU Pump Heat Exchanger: 1WR007A open and 1WR008A throttled for 35-45 gpm

Direct an EO to verify 1A suction and Discharge valves are open:

1G33-F043A, Pump Suction Header Upstream Stop

1G33-F005A, Pump Suction Header Downstream Stop 27.001 BOP

1G33-F013A, Pump Discharge Valve

Direct an EO to verify Purge flow at 0.5 to 1.0 gpm for 1A RWCU Pump

Direct an EO to report 1A RWCU Pump local casing temperature

Determine Reactor Vessel Water Temperature/RR Pump suction Temp

Verify difference between Pump casing temp and RPV water temp is less than 100ºF

Direct an EO to close the A Pump discharge Check Bypass Valve, 1G33-F373

Start the 1A RWCU Pump

Adjust system flow by throttling open the filter Demin Bypass valve, 1G33-F354 (Nominal 270 - 300 gpm, Maximum 360 gpm)

Direct an EO to backwash the filters that were in service (Per LOA-RT-101)

Monitor Plant conditions and update the crew as required.

ATC

Dispatch an Equipment Operator to investigate RT Pump TRIP

Direct above actions 27.001 US

Inform Shift Manager and EMD of RT Pump TRIP Page 10 of 34

NRC 15-1-3 Revision 00 Event - 2

==

Description:==

RT Pump TRIP Simulator Operator Actions With the concurrence of the Release Event 2 Lead Evaluator When directed by the crew to PLACE the A/B/C Vessel Release RT F/D Isolation Control Switch to ISOLATE Simulator Operator Role Play NOTE: Time compress as necessary with Lead Evaluator concurrence.

As an EO, if requested to investigate the 1B RT Pump trip, report the breaker is tripped As an EO, when directed to place RWCU F/D control switches in ISOLATE; perform the SIMOP actions above and then report that the F/Ds are isolated.

As an EO, when directed to verify 1A RWCU Pump Suction and Discharge valves are open; report that 1G33-F043A, F005A and F013A are open.

As an EO, when directed to verify RBCCW is valved in to 1A RWCU Pump Heat Exchanger; report that 1WR007A is open and 1WR008A is throttled for 35-45 gpm.

As an EO, when directed to verify 1A RWCU Pump Suction and Discharge valves are open; report that 1G33-F043A, F005A and F013A are open.

As an EO, when directed to verify CRD purge flow; report that 1A RWCU Pump purge flow is 1.0 gpm.

As an EO, when directed to 1A RWCU Pump local casing temperature; report 1A RWCU Pump casing temperature at 480ºF.

As an EO, when directed to close the 1A Pump discharge Check Bypass Valve; report that the 1A Pump discharge Check Bypass Valve is closed.

As an EO, when directed to backwash the filters that were in service; acknowledge this directive. (No further action is necessary)

If asked to report cause of Demin Trouble Alarm (1H13-P602-B103) report the is caused by Filter Demin Low Flow Floor Instructor Notes/OPEX/TRs none Terminus: RWCU System returned to service on the 1A RWCU Pump Page 11 of 34

NRC 15-1-3 Revision 00 Event-3

==

Description:==

OG Building Exhaust Fan TRIP Initiation: On direction of Lead Evaluator, release Event 3 Cues:

Key Parameter Response: Offgas Building Exhaust Fan 0VO03CA indicating lights Expected Annunciators: 1PM06J-A106, OFFGAS BLDG 0A EXH FAN AUTO TRIP Automatic Action: Off Gas Building HVAC Exhaust Fan 0VO03CA trips Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM06J-A106

Verify automatic actions occurred

Start the standby Off Gas Building HVAC Train per LOP-VO-01

DISPATCH operator to 480V MCC 134Y-2 to investigate cause of alarm BOP

Direct an EO to INSPECT Off Gas Building HVAC Exhaust Fan for abnormalities

o INITIATE action request if applicable Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25"

Direct an EO to Verify OGFB (Off Gas Filter Building) is at negative pressure. If OGFB is at a positive pressure notify Reactor Protection to sample for the presence of Noble Gas Per LOP- VO-02 o PLACE OV001CA, Off Gas Supply fan in the STOP position Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent o PLACE OV003CA, Off Gas Exhaust fan in the STOP position at: 0.25" Formatted: Font: (Default) Arial, 11 pt Per LOP- VO-01 Formatted: Space Before: 0 pt, After: 0 pt, Bulleted +

PLACE the oncoming OV003CB, Off Gas Exhaust fan in the AUTO Level: 1 + Aligned at: 0" + Indent at: 0.25", Widow/Orphan control, Adjust space between Latin and Asian text, Adjust BOP position space between Asian text and numbers, Tab stops: Not at

PLACE the oncomingOV001CB, Off Gas Supply fan in the START 4.03" position for 10 seconds and RELEASE

VERIFY the Supply fan starts

VERIFY the oncoming Exhaust fan starts

Direct an EO to START the oncoming B Train Heaters ATC

Monitor Plant conditions and update the crew as required

Direct above actions

Notify EMD of failed OG Building Exhaust Fan

Enter ODCM 12.4.5 US

Condition A, one or more VENTILATION EXHAUST TREATMENT SYSTEMS inoperable

Required Action A.1, restore system to OPERABLE status within 31 days Page 12 of 34

NRC 15-1-3 Revision 00 Event - 3

==

Description:==

OG Building Exhaust Fan TRIP Simulator Operator Actions With the concurrence of the Release Event 3 Lead Evaluator Simulator Operator Role Play Role Play as EO dispatched to Off Gas Building:

When asked to investigate at 480V MCC 134Y-2:

Wait 2 minutes, then report that the 0A Off Gas Exhaust Fan breaker is tripped.

During shutdown of A Train (LOP-VP-02, if ordered)

(Step E.2) When asked, the Off Gas Bldg Supply Dampers and Exhaust Dampers are CLOSED

(Step E.3) When asked, the A HVAC Heating Train is secured

(Step E.4) When asked, the Off Gas Refrigeration Unit is shutdown During startup of B Train (LOP-VO-01)

(Step E.3.1) When asked, the B Off Gas Bldg Supply Dampers are open.

(Step E.3.2) When asked, all five LOW FLOW Alarms have cleared.

(Step E.3.3) When asked, the B Off Gas Bldg Exhaust Dampers are open.

(Step E.5) When asked, B Train differential pressures are normal.

(Step E.8) When directed, report the B Train heaters have been started.

IF asked, wait 12 minutes and report, The Off Gas Filter Building is at a negative pressure.

Floor Instructor Notes/OPEX/TRs none Terminus: When the 0B Off Gas Bldg Supply and Exhaust Fans have been started.

Page 13 of 34

NRC 15-1-3 Revision 00 Event-4

==

Description:==

Earthquake Below OBE/SSE Limit, Small Condenser Air Leak Initiation: On direction of Lead Evaluator, release Event 4 Expected Annunciators: 1PM10J-B504 STRONG MOTION SEIS INSTR SYSTEM INITIATED (In Formatted: Font: 10 pt approximately 7 minutes) 1N62-P600-B506, OFF GAS CHARCOAL ADSORBER TRAIN HI DP (In approximately 7 minutes) 1N62-P600-B204 OFF GAS OUTLET FLOW ABNORMAL (In approximately 9.5 minutes) 1PM03J-B511, CONDENSER VACUUM LOW (In approximately 7 minutes) 1N62-P600-B506, OFF GAS CHARCOAL ADSORBER TRAIN HI DP (In approximately 7 minutes) 1N62-P600-B204 OFF GAS OUTLET FLOW ABNORMAL (In approximately 9.5 minutes) 1PM03J-B511, CONDENSER VACUUM LOW Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM10J-B504:

Determine if an actual seismic event can be confirmed:

CALL several people at different locations of the plant, (RW Control Room, MAF ) and ASK if ground motion was felt.

Dispatch EO to panel 0PA11J, (AEER) check seismic system triggered light ON.

If additional confirmation of seismic activity is required to confirm a Seismic event, CALL the National Earthquake Information Center (Emergency Response Facilities Telephone Directory) and request conformation of seismic activity.

If a Confirmed Seismic event occurred:

BOP

Inform shift management of the need to review EALs and implement the Formatted: Font: 11 pt Emergency Plan as appropriate

NOTIFY System Engineering to evaluate data collected from seismic event.

MONITOR Primary Containment and continued operability of instrumentation in T.S. Table 3.3.3.1-1 and TRM Table T3.3.d-1.

REFER to LOA-DIKE-001; dispatch personnel to inspect the cooling lake dike for leaks

Direct an EO to inspect Hi-Storm Fuel casks for damage or blocked vents

Contact CMO to perform thermography on switchyard components

Obtain accelerometer data

Formatted: Font: 11 pt Per LOR-1PM03J-B511 Formatted: Indent: Left: 0.11", No bullets or numbering

Monitor Condenser Vacuum indication. DO NOT operate with sustained condenser vacuum less than:

23.5 HG (6.5 backpressure) with Reactor Power greater than 75%

VERIFY SJAE are operating properly per LOP-OG 07, startup of Off Gas 111.002 BOP System Formatted: Font: 11 pt

VERIFY Circulating Water System is operating properly per LOP-CW-03, startup of Circulating Water System Formatted: Font: 11 pt

If condenser Formatted: Indent: Left: 0.11", No bullets or numbering vacuum decreases to point of turbine trip point (21.6) refer to:

Page 14 of 34

NRC 15-1-3 Revision 00

LOA-TG-101, Unit 1 Turbine Generator

Initiate appropriate corrective action as required Per LOR-1PM03J-B511

If condenser vacuum continues to decrease, REDUCE Reactor Power per LGP-3-1 as necessary (lowering RR flow), to a point at which condenser vacuum has stabilized. If vacuum cannot be stabilized and Turbine Trip is 111.002 ATC Formatted: Font: 11 pt imminent, MANUALLY scram reactor(Event 6) per LGP-3-2 (When the crew attempts to lower Reactor Power using RR ganged flow (Event 5) it will not work)

Formatted: Font: 11 pt

Directs actions above. Formatted: Indent: Left: 0.11", No bullets or numbering

Notifies Shift Manager.

References TRM 3.3.o, Condition C for a valid seismic eventfor Seismic Monitoring Instrumentation

Condition A - one or more Seismic Monitoring Instruments INOP

Required Action A.1 - restore instrument to operable status in 30 days Formatted: Indent: Left: 0.11", Hanging: 0.19"

Condition C - one or more Seismic Instruments actuated during a valid Seismic event > 0.01g 201.011 US

Required Action C.1 - restore actuated instrument to operable in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Formatted: Indent: Left: 0.11", Hanging: 0.19"

Required Action C.2 - perform TSR 3.3.o.3 for each actuated instrument in 5 days

Required Action C.3 - analyze data retrieved from instruments in 10 days Formatted: Font: 10 pt

Required Action C.4 - prepare a corrective action report describing the event and effect on facility features important to safety in 10 days

C.1, return instruments to operable in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Formatted: No bullets or numbering

C.2 perform TSR 3.3.o.3 for each activate instrument in 5 days Event - 4

==

Description:==

Earthquake Below OBE/SSE Limit, Small Condenser Air Leak Simulator Operator Actions With the concurrence of the Release Event 4 (Earthquake)

Lead Evaluator Following Tech Spec Call and wWith the concurrence Release Event 4 (Condenser Air leak initial) of the Lead Evaluator Simulator Operator Role Play As EO, if sent to seismic system, report the seismic SYSTEM TRIGGERED light is ON, but no OBE or SSE light lit. Report a seismic monitor reading of 0.015 g.

As System Engineer, role play as necessary and acknowledge the directive to evaluate the datae collected from the seismic event.

As personnel in plant, If requested, report you did feel movement.

If requested to obtain peak acceleration data from the OPA11J panel, report that when you lifted the Page 15 of 34

NRC 15-1-3 Revision 00 laptop screen, nothing displayed (procedures states to notify IMs).

If requested to check SBLC and Suppression Pool levels, verify the commands have been deleted have been deleted and then report that SBLC and Suppression Pool levels are normal.

Floor Instructor Notes/OPEX/TRs Two separate triggers to allow Crew time to calm down following the Earthquake.

Terminus: continued Formatted: Left Page 16 of 34

NRC 15-1-3 Revision 00 Event-5

==

Description:==

Failure of the RR Ganged Controller in AUTO Initiation: continued Cues:

Key Parameter Response: RR Master controller does not respond; flow in the Recirc Loops does not lower; Reactor power does not lower when using Ganged Controller Expected Annunciators: None Automatic Actions: None Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitor Plant conditions and update the crew as necessary Per OP-LA-101-111-1002

Take Manual Control of a failed AUTO controller to maintain a process parameter

Lower Reactor Power using RR flow in MANUAL Formatted: List Paragraph, Space Before: 0 pt, After: 0 pt, Widow/Orphan control, Adjust space between Latin and Asian

On the A & B Recirc Loop Flow Controller M/A Stations text, Adjust space between Asian text and numbers

VERIFY manual light on Recirc Flow Control M/A Station A & B is on Formatted: Font: (Default) Arial, 11 pt 22.00.21 ATC

Press LOWER pushbutton(s) and observe flow indications (two Formatted: Indent: Left: 0.3", Hanging: 0.19", Bulleted +

handed operation is authorized) Level: 1 + Aligned at: 0" + Indent at: 0.25"

Lower Reactor Power using RR flow in MANUALMaintain Recirculation Loop Flow Mismatch as read from 1B21-R611A and 1B21-R611B within:

o 5.425 Mlbm/hr if core flow is > 79.95 Mlbm/hr o 10.85 Mlbm/hr if core flow is < 79.95 Mlbm/hr o Lower Reactor power Using Control Rods

Direct above actions 304.010 US

Inform EMD of failed ganged RR Flow controller Page 17 of 34

NRC 15-1-3 Revision 00 Event - 5

==

Description:==

Failure of the RR Ganged Controller in AUTO Simulator Operator Actions none Simulator Operator Role Play Acknowledge reports as required.

Floor Instructor Notes/OPEX/TRs After Reactor Power is lowered by taking Reactor Recirc to manual , Condenser Vacuum will continue to lower and conditions will dictate a manual Scram due to High Condenser Backpressure.

Terminus: continued Page 18 of 34

NRC 15-1-3 Revision 00 Event-6

==

Description:==

Scram (from Condenser Air Leak), Suppression Pool Leak Initiation: On direction of Lead Evaluator Cues:

Key Parameter Response: Lowering Suppression Pool Level Expected Annunciators: Multiple Automatic Actions: None Objective Position EXPECTED OPERATOR RESPONSE

Monitor Condenser Backpressure and report when backpressure Formatted: List Paragraph, Indent: Left: 0", Hanging:

reaches or exceeds 6.5 backpressure 0.24", Bulleted + Level: 1 + Aligned at: 0.5" + Indent at:

0.75"

Refer to LOA-TG-101 Formatted: Font: (Default) Arial, 11 pt Per LOR-1PM13J-B203 Formatted: List Paragraph, Indent: Left: 0.24"

Check Suppression Pool water level is less than or equal to alarm 422.000 BOP setpoint as indicated from computer analog point number L124

DISPATCH operator into Reactor Building to confirm Suppression Pool low level at local sight glass

MONITOR major plant systems that take suction on Suppression Pool, for possible reason of water level decrease

ENTER LGA-003 at -4.5 Suppression Pool Level

Verify RCIC operable Per LGA-003

Hold Suppression Pool Level above -4.5 (No)

Cannot hold level above -4.5 go to block 20 421.000

Evaluate continued RCIC pump use if cannot hold pool level above -10 feet 421.010 BOP

Hold Suppression Pool level above -12 feet 423.000

Before Suppression Pool level reaches -12 feet SCRAM and enter LGA-001

IF cannot restore level above -12 feet (downcomers) and hold it there BLOWDOWN Performs Reactor Scram and LGP 3-2 on US direction

ARM and DEPRESS Scram Pushbuttons 304.010

PLACE Reactor Mode Switch in SHUTDOWN ATC 413.000

INSERT IRMs and SRMs

CHECK Control Rods INSERTED and Power Decreasing (5 Rods Out)

INFORM Unit Supervisor of Control Rod Status and Reactor Power

Direst above actions 421.000

Inform Shift Manager 421.010 *o May Direct Closing MSIVs and control pressure using SRVs Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent US at: 0.25" 422.000

Set Suppression Pool Level as Critical parameter 423.000

REFER to Tech Spec 3.5.2 and 3.6.2.2

Enter LGA-003 Page 19 of 34

NRC 15-1-3 Revision 00 Event - 6

==

Description:==

Scram (from Condenser Air leak), Suppression Pool Leak Simulator Operator Actions Following the crew lowering Reactor Power and with concurrence from the Lead Release Event 4 (Condenser Air leak that leads to Scram)Release evaluatorWith the Event 6 concurrence of the Lead Evaluator Simulator Operator Role Play As the operator sent to investigate a Suppression Pool Leak, wait 2 minutes and report, Report that water is flowing out of what appears to be a crack 8 feet below the grating on 694. Its coming out pretty quick and filling the bottom of the raceway.

As the operator for any safety precautions (such as entering from 694 elevation). [Entering from 673 may not be possible depending on how much water is in the raceway, and it could jeopardize the corner room you enter from.]

Floor Instructor Notes/OPEX/TRs The leak in the Suppression Pool is at -12 feet.

Terminus: continued Page 20 of 34

NRC 15-1-3 Revision 00 Event-7 Formatted Table

==

Description:==

Five Control Rods Remain Out, ATWS Initiation: continuedOn direction of Lead Evaluator Cues:

Key Parameter Response: Rod position indication for stuck rods Expected Annunciators: None Automatic Actions: None Objective Position EXPECTED OPERATOR RESPONSE Per LGA-010

Inhibit ADS

Prevent injection from HPCS, LPCS and LPCI (CT)

Per the PRESSURE Leg BOP o STABILIZE pressure <1059 psig using main turbine bypass valves Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent

o STABILIZE pressure <1059 psig using SRVs at: 0.25"

VERIFY required automatic actions occur (See event 6)

o May request LGA-RH-101 jumper installation Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25" LGA-010

Recognize that all rods did not insert and notify US (Hydraulic ATWS)

Per the POWER Leg if control rods remain out:

If control rods remain out:

Initiate ARI 432.000

If power is above 3%, initiate SBLC (No) 433.000

Insert Control rods per LGA-NB-01 (CT) 434.000 ATC

Method 3 Single Rod Insert 431.000

Bypass RWM 431.010

Place CRD Drive Flow Trip Circuit in BYPASS

Insert control rods using Continuous Insert or Insert Button o May request LGA-NB-01 Method 4 Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent

WAIT until rods full in except one OR all rods in to at least 02 OR at: 0.25" Reactor will stay shutdown under all conditions without boron per QNE.

Formatted: Indent: Left: 0.25", No bullets or numbering

Directs LGA-001 and LGA-010 actions

Directs Inhibit ADS

Formatted: Indent: Left: 0", Hanging: 0.5" 432.000

When only one Rod remaining out, transition back to LGA-001 433.000

Directs Inhibit ADS 434.000 US

Set Reactor Level and Pressure Bands 431.000

Directs LGA-NB-01 (CT) Formatted: Indent: Left: 0", Hanging: 0.5" 431.010

Directs method of Control Rod insertion per LGA-NB-01

Direct Method 3, Single Rod Insertion Formatted: Indent: Left: 0.3", Hanging: 0.25", Tab stops:

0.55", List tab + Not at 0.25"

o May direct Method 4, Reset Scram/Drain SDV/Re-ScramMay direct Method 3 Single Rod Insert Formatted: Indent: First line: 0.05", Bulleted + Level: 1 +

Aligned at: 0" + Indent at: 0.25", Tab stops: Not at 0.43" Page 21 of 34

NRC 15-1-3 Revision 00 Event - 7

Description:

Five Control Rods Remain Out, ATWS Simulator Operator Actions Immediately after Scram, From the Summary Page, MODIFY the Rod Friction Malfunctions reduce the friction on the (mrd046, 042, 209, 215, & 033) to 20% Severity to allow the stuck stuck rods control rods to be driven in.

LGA-MS-01

From the RNI display - JMP Screen - click on LGA-MS-01 jumpers (5 jumpers)

Install only jumper #4

Select INSTALLED then INSERT When directed by the crew, insert ATWS Jumpers and LGA-NB-01 Method 4 pull fuses. These actions

From the RNI display - JMP Screen - click on LGA-NB-01 jumpers should take approximately 5 (1 set) minutes - or- as directed by

Select INSTALLED then INSERT the Lead Examiner/Floor Instructor. Actions may be

From the CRD Screen (RD1), close CRD 34 when directed: irf delayed to allow completion vhrd034d 0 of actions.

From the Action List Remote Function (RD), deenergize ARI Logic when directed:

irf iaaride1 de-energize and irf iaaride2 de-energize LGA-RH-101

From the RNI display - JMP Screen - click on LGA-RH-101 (1 jumper)

Select INSTALLED then INSERT Simulator Operator Role Play Role Play Unit 2 operators as necessary to support the Remote Functions above Floor Instructor Notes/OPEX/TRs Per LGA-NB-01 Step C.2.b, the method of rod insertion per LGA-NB-01 should be Method 3 for Single Rod insertion. Formatted: Font: Bold Terminus: When all control rods are fully inserted Page 22 of 34

NRC 15-1-3 Revision 00 Event - 7

==

Description:==

Five Control Rods Remain Out, ATWS Simulator Operator Actions Immediately after Scram, From the Summary Page, MODIFY the Rod Friction Malfunctions reduce the friction on the (mrd046, 042, 209, 215, & 033) to 20% Severity to allow the stuck stuck rods control rods to be driven in.

LGA-MS-01

From the RNI display - JMP Screen - click on LGA-MS-01 jumpers (5 jumpers)

Install only jumper #4

Select INSTALLED then INSERT When directed by the crew, insert ATWS Jumpers and LGA-NB-01 Method 4 pull fuses. These actions

From the RNI display - JMP Screen - click on LGA-NB-01 jumpers should take approximately 5 (1 set) minutes - or- as directed by

Select INSTALLED then INSERT the Lead Examiner/Floor Instructor. Actions may be

From the CRD Screen (RD1), close CRD 34 when directed: irf delayed to allow completion vhrd034d 0 of actions.

From the Action List Remote Function (RD), deenergize ARI Logic when directed:

irf iaaride1 de-energize and irf iaaride2 de-energize LGA-RH-101

From the RNI display - JMP Screen - click on LGA-RH-101 (1 jumper)

Select INSTALLED then INSERT Simulator Operator Role Play Role Play Unit 2 operators as necessary to support the Remote Functions above Floor Instructor Notes/OPEX/TRs Per LGA-NB-01 Step C.2.b, the method of rod insertion per LGA-NB-01 should be Method 3 for Single Rod insertion. This event is intended for the ATC.

Terminus: When all control rods are fully inserted Page 23 of 34

NRC 15-1-3 Revision 00 Event-8

==

Description:==

RPV Blowdown Initiation: Suppression Pool Level cannot be maintained above -12 feetOn direction of Lead Evaluator Cues:

Key Parameter Response: Suppression Pool Water Level Expected Annunciators: 1PM13J-B203, SUP POOL WTR LVL LO Automatic Actions: None Formatted: Space Before: 6 pt, After: 6 pt Objective Position EXPECTED OPERATOR RESPONSE Per LGA-006

IF all rods in to at least 02 or all rods full in except one or Reactor will stay shutdown under all conditions without boron per QNE

Stop injecting boron unless needed for RPV level control

Exit this procedure and enter LGA-004

Terminate and prevent all RPV Injection except: (CT)

RCIC, CRD, and Boron

CRD 423.000

Boron Formatted: Font: 9.5 pt BOP 428.000

Initiate ADS - ok to exceed 100 F/hr cool down (CT) Formatted: Font: Not Bold

Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons

Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons Formatted: Indent: Hanging: 0.01", Space Before: 0 pt,

Verify all 7 ADS valves open (Yes) After: 0 pt, Widow/Orphan control, Adjust space between Latin and Asian text, Adjust space between Asian text and

Return to ATWS level numbers, Tab stops: Not at 4.03"

Leave SRVs open. Allow RPV to depressurize.

Formatted: Font: 10 pt

Wait until Shutdown Cooling pressure Interlock clears (143 psig)

Formatted: Font: 9.5 pt

Cool down to cold shutdown using Shutdown Cooling (LOP-RH-07)

Formatted: Bulleted + Level: 1 + Aligned at: 0" + Tab after: 0.25" + Indent at: 0.25" Per LGA-004

Prevent LPCS and LPCI not needed for core cooling

Initiate ADS - ok to exceed 100 F/hr cool down (CT) Formatted: Font: Not Bold 423.000

Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons Formatted: Font: 9.5 pt BOP 428.000

Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons

Verify 7 SRVs are open (Yes) Formatted: Indent: Left: 0.25"

Leave SRVs open. Allow RPV to depressurize. Formatted: Font: 9.5 pt

Wait until Shutdown Cooling pressure Interlock clears (143 psig) Formatted: Font: 9.5 pt

Cool down to cold shutdown using Shutdown Cooling (LOP-RH-07)

Per LGA-003 Formatted: Indent: Left: 0.25", No bullets or numbering

When directed, starts all available Pool Cooling per LGA-RH-103

Startup RHR Service Water as follows:

OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B

At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, BOP START first RHR Service Water Pump Formatted: Font: 9.5 pt

When indicated flow reaches 3000 gpm, START second RHR SW Pump

Startup RHR

Start 1A/1B RHR Pump

Throttle 1E12-F024A/B OPEN to establish RHR flow of 1500 to 7450 gpm

Close 1E12-F048A/B (HX Bypass)

Page 24 of 34

NRC 15-1-3 Revision 00 Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/BPer LGA-003

Start Suppression Pool Cooling ATC

Maintain RPV level as directed by Unit Supervisor per LGA-001 and LGA-010 Formatted: Font: 9.5 pt

If cannot restore level above -12 feet and hold it there per LGA-003 then blowdown per LGA-004/006 (CT) 423.000

Direct actions per LGA-0046/0064 and LGA-001/010 Formatted: Font: 9.5 pt US 428.000

Performs emergency blowdown (CT)

Inform Shift Manager Page 25 of 34

NRC 15-1-3 Revision 00 Event - 8

==

Description:==

RPV Blowdown Simulator Operator Actions None Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs none Terminus: RPV Blow down complete. RPV level restored and being maintained in normal operating range with containment parameters stable or improving.

Page 26 of 34

NRC 15-1-3 Revision 00 REFERENCES Procedure Title Revision

1. LGA-001 RPV CONTROL 017

2. LGA-003 PRIMARY CONTAINMENT CONTROL 016

3. LGA-004 RPV BLOWDOWN 009

4. LGA-006 ATWS BLOWDOWN 009

5. LGA-010 FAILURE TO SCRAM 015

6. LGA-NB-01 ALTERNATE ROD INSERTION 018 USING MAIN CONDENSER AS A HEAT SINK IN AN

7. LGA-MS-01 014 ATWS ALTERNATE VESSEL INJECTION USING SHUTDOWN

8. LGA-RH-101 004 COOLING RETURN UNIT 1 A AND B RHR OPERATIONS IN THE LGAS AND 012

9. LGA-RH-103 SAMGS

10. LGP-3-1 POWER CHANGES 062

11. LGP-3-2 REACTOR SCRAM 072 PREPARATION FOR STANDBY OPERATION OF THE

12. LOP-RI-05 033 REACTOR CORE ISOLATION COOLING SYSTEM STARTUP AND OPERATION OF THE OFF GAS

13. LOP-VO-01 013 BUILDING HVAC SYSTEM

14. LOP-VO-02 SHUTDOWN OF AN OFF GAS BUILDING HVAC TRAIN 012 REACTOR WATER CLEANUP SYSTEM STARTUP AND

15. LOP-RT-02 048 PUMP TRANSFER

16. LOA-DIKE-001 LAKE DIKE DAMAGE FAILURE 011

17. LOR-1PM03J-B511 CONDENSER VACUUM LOW 006 OFF GAS BUILDING HVAC EXHAUST FAN 0VO03CA

18. LOR-1PM06J-A106 003 AUTO TRIP STRONG MOTION SEISMIC INSTRUMENT SYSTEM

19. LOR-1PM10J-B504 024 IMITATED

20. LOR-1PM13J-B203 SUPPRESSION POOL WATER LEVEL LOW 004

21. OP-LA-101-111-LASALLE OPERATIONS PHILOSOPHY HANDBOOK 066 1002

22. LOR-1H13-P602- REACTOR WATER CLEANUP RECIRC PUMP 1B 004 A107 AUTOMATIC TRIP

23. LOA-RT-101 LOSS OF REACTOR WATER CLEANUP SYSTEM 019 Page 27 of 34

NRC 15-1-3 Revision 00 COMPUTER AIDED EXERCISE PROGRAM (CAEP)

ESG NRC 15-1-3 Revision: 00 Revision Date: 7/5/16 Developed By: C. M. Betken Page 28 of 34

NRC 15-1-3 Revision 00 Page 29 of 34

NRC 15-1-3 Revision 00 Page 30 of 34

NRC 15-1-3 Revision 00 THIS PAGE INTENTIONALLY LEFT BLANK Page 31 of 34

NRC 15-1-3 Revision 00 U1 SUPERVISOR TURNOVER Shift: 2 Date: Today Mode: 1 OLR: Yellow Work Week: RCIC Unit 1 power level Unit 2 power level

100 % Power

100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions

None

None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance

RCIC, ready to be returned to standby readiness. Warm RCIC Steam Lines per LOP-RI-05 Step E.8

None

RCIC, 12 days left, T.S. 3.5.3

IMD is standing by to perform Attachment A of LOP-RI-05 LOSs in progress or major maintenance LOSs in progress or major maintenance

None

None Equipment removed from service or currently unavailable

None

None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.

Online Risk - YELLOW

Div 2 workweek

PROTECTED: HPCS

OLR is Green

RCIC Workweek Page 32 of 34

NRC 15-1-3 Revision 00 Page 33 of 34

NRC 15-1-3 Revision 00 U1 SUPERVISOR TURNOVER (Alternate)

Shift: 2 Date: Today Mode: 1 OLR: Green Work Week: RCIC Unit 1 power level Unit 2 power level

100 % Power

100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions

None

None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance

None

None LOSs in progress or major maintenance LOSs in progress or major maintenance

None

None Equipment removed from service or currently unavailable

None

None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.

None

Div 2 workweek

OLR is Green

OLR is Green

RCIC Workweek Page 34 of 34

Facility NRC EXAM Scenario __

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 4 Op-Test No.: __NRC 15-12016301______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Reactor power, C CD/CB OOS Turnover: Swap VR Supply/Exhaust Fans IAW LOP-VR-01 Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Swap VR Supply/Exhaust Fans IAW LOP-VR-01 2 mms056 R (ATC) Abnormal Turbine Generator Vibrations mai006 Station Air Compressor TRIP, Standby Fails to 3 C (BOP) Auto Start mai007 4 mni073 I (ATC) LPRM Fails Downscale 5 mrd353 I (ATC) Loss of RPIS 56 mrd353 T (SRO) Loss of RPIS Abnormal Turbine Generator Vibrations, Manual 67 mms056 M (ALL)

SCRAM 78 mcf034 M (ALL) Feedwater Rupture Inside Primary Containment C HPCS Fails to Auto-Start 89 mes032 (BOPALL

)

9 none M (ALL) RPV Blowdown (Contingency)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 7 BOP Normal: 1 Malfunction(s) after EOP (1-2): 2 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 4 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 2 ATC I/C (4 / set): 2 EOPs (1-2): 2 SRO-I I/C (4 / set inc 2 as ATC): 4 EOP Contingencies (0-2): 0 SRO Tech Spec (2 per set): 1 Critical Tasks (2-3): 2 ALL Major Transients (2 per set): 2 Formatted: Indent: Left: 0", Hanging: 0.62"

LaSalle County Station ILT DYNAMIC SIMULATOR SCENARIO GUIDE ESG NRC 15-1-4 Rev. 0 07/20/2016 DEVELOPED BY: Colin Betken 8/15/2016 Instructor Date VALIDATED BY: Murphy / Hawkins / Nicoll / Adams 7/23/2016 SME/Instructor Date REVIEWED BY: Mark Smith 8/17/2016 Operations Manager Date APPROVED BY: Dan Moren 8/17/2016 Exam Author Date

NRC 15-1-4 Revision 00 Facility: LaSalle County Station Scenario No.: NRC 15-1-4 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Swap VR Supply/Exhaust Fans IAW LOP-VR-01.

Following turnover the crew will place the standby VR Supply and Exhaust Fan on service and secure a running VR Supply and Exhaust Fan

2. Abnormal Turbine Generator Vibrations.

Following the VR swap, vibes will slowly increase until the crew takes action and lowers Reactor Power. After Reactor Power is lowered vibes will slowly return to normal.

3. Station Air Compressor TRIP, Standby Fails to Auto Start.

The crew will take action to start the 0 Station Air Compressor following the TRIP of the Unit 1 Station Air compressor and Service/Instrument header pressures will return to normal.

4. LPRM Fails Downscale.

The crew will respond to the failed Local Power Range Monitor and Bypass that LPRM.

5. Loss of RPIS.

Rod 38-19 will loss position indication and the rod will have to fully inserted and electrically disarmed.

6. Abnormal Turbine Generator Vibrations, Manual SCRAM Turbine Generator Vibes will return and continue to increase forcing the crew to SCRAM and TRIP the Main Turbine.

7. Feedwater Rupture Inside Primary Containment.

Following the SCRAM the Feedwater System will develop a leak inside the Drywell. The crew should take action to attempt to isolate the leak by isolating the Feedwater System and commence cooling the Containment.

8. HPCS Fails to Auto-Start.

9. HPCS will fail to automatically start on a high drywell signal from the LOCA. The crew should Formatted: Indent: Left: 0.25", No bullets or numbering take action to manually start HPCS to maintain RPV level.

9. RPV Blowdown (Contingency)

If the crew is unable to maintain level >-150 they will blowdown per LGA-004 Formatted: Indent: Left: 0.25", No bullets or numbering

10. HPCS Fails to Auto-Start.

HPCS will fail to automatically start on a high drywell signal from the LOCA. The crew should take action to manually start HPCS to maintain RPV level.

Critical Tasks

1. Identify failures of automatic system response, and where such response is needed to maintain adequate core cooling, take manual action to place the system in operation.

Page 2 of 35

NRC 15-1-4 Revision 00

2. With suppression chamber pressure above 12 psig, containment flood level below 722 feet, and Formatted: Font: 11 pt drywell parameters below the Drywell Spray Initiation Limit; trip all recirculation pumps and start drywell sprays using RHR pumps not needed for adequate core cooling.

3. With available injection systems unable to hold RPV water level above -150 inches on Wide Range, INITIATE emergency depressurization when RPV water level drops to -150 inches on Wide Range. (N/A if the crew is able to maintain RPV Level >-150)

4. Place the Residual Heat Removal (RHR) heat exchangers in service to establish containment cooling. (N/A if the crew is able to maintain RPV Level >-150)

1. Start drywell spray before exceeding the PSP curve.

2. With primary containment pressure above 1.93 psig, containment flood level below 723 feet, and pumps not needed for core cooling available; start suppression chamber spray.

Page 3 of 35

NRC 15-1-4 Revision 00 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

2. None Operator Fundamentals

1. Monitoring plant indications and conditions closely

2. Controlling plant evolutions precisely

3. Operating the plant with a conservative bias

4. Working effectively as a team

5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2

1. Oversight ensures proper focus

2. Equipment restoration risk evaluation

3. Preparation for high risk evolution

4. Control Room resources adequate for EOP response

5. Sufficient engagement of others in decision making Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 15-1 NRC Exam Page 4 of 35

NRC 15-1-4 Revision 00 INITIAL SIMULATOR SETUP/REQUIRED DOCUMENTATION

1. Recall a full power IC.

2. Place simulator in RUN.

3. Load and run the smart scenario: NRC 15-1-4

4. Place Protected Equipment rings and/or robust barriers on the following components:

Place protected path rings on A, B, and D CD/CB Pumps

5. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A

6. Perform the following panel manipulations:

Place C CD/CB Pump in PTL

7. Place the following Tags:

Hang OOS on C CD/CB Pump

8. Verify the following:

Unit 1 SAC is Running

0 SAC is in STBY

9. Have a copy of LOP-VR-01 and LOP-PR-04

10. Verify a stopwatch is available 9.11. Perform the pre-scenario checklist. (TQ-LA-150-0308)

Page 5 of 35

NRC 15-1-4 Revision 00 Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 4 Op-Test No.: ____2016301____

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Reactor power, C CD/CB OOS Turnover: Perform LOP-VR-01 to swap VR Supply/Exhaust Fans Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Swap VR Supply/Exhaust Fans IAW LOP-VR-01 2 mms056 R (ATC) Abnormal Turbine Generator Vibrations mai006 Station Air Compressor TRIP, Standby Fails to 3 C (BOP) Auto Start mai007 4 mni073 I (ATC) LPRM Fails Downscale 5 mrd353 I (ATC) Loss of RPIS 56 mrd353 T (SRO) Loss of RPIS 67 Abnormal Turbine Generator Vibrations, Manual mms056 M (ALL)

SCRAM 78 mcf034 M (ALL) Feedwater Rupture Inside Primary Containment C HPCS Fails to Auto-Start Formatted: Centered 89 mes032 (ALLBOP

)

9 none M (ALL) RPV Blowdown (Contingency) Formatted: Centered (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes: Formatted: Indent: Left: 0", First line: 0" Total Malfunctions (5-8): 7 BOP Normal: 1 Malfunction(s) after EOP (1-2): 2 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 4 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 2 ATC I/C (4 / set): 2 EOPs (1-2): 2 SRO-I I/C (4 / set inc 2 as ATC): 4 EOP Contingencies (0-2): 0 SRO Tech Spec (2 per set): 1 Critical Tasks (2-3): 2 ALL Major Transients (2 per set): 2 Formatted: Indent: Left: 0", Hanging: 0.62" APPROXIMATE SCENARIO RUN TIME 90 Minutes Page 6 of 35

NRC 15-1-4 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)

During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

TASKS RO - ATC 43.001 Perform Control Room actions for a Local Power Range Monitor Failure, Perform the Main Control Room actions for a Loss of Control Rod Position 47.012 Information System.

Perform Control Room actions for Main Turbine Generator high vibration or 71.030 noise.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 413.010 Evaluate plant conditions and control RPV water level using CRD RO - BOP/ASSIST 71.029 Perform Control Room actions for Main Turbine Generator trip (load > 25%),

Perform Control Room actions for Main Turbine Generator high vibration or 71.030 noise.

97.025 Perform Control Room actions for a loss of Instrument Air/Service Air, Evaluate plant conditions and control secondary containment by operation of the following ventilation systems, 415.000 (a) VR (b) VG (c) VQ Given LGA-03, Primary Containment Control, in progress, evaluate plant 419.000 conditions and control and maintain Primary Containment pressure less than 1.93 psig IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, spray the 419.020 Suppression Pool IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, spray the Drywell 419.030 IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 420.000 conditions and control and maintain Drywell Temperature less than 340F IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Page 7 of 35

NRC 15-1-4 Revision 00 SRO - UNIT SUPERVISOR Perform the Main Control Room actions for a Loss of Control Rod Position 47.012 Information System.

71.029 Perform Control Room actions for Main Turbine Generator trip (load > 25%),

Perform Control Room actions for Main Turbine Generator high vibration or 71.030 noise.

97.025 Perform Control Room actions for a loss of Instrument Air/Service Air, Given a set of plant conditions, identify and prepare the Technical 201.011 Specification required actions IAW Tech Specs.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 413.010 Evaluate plant conditions and control RPV water level using CRD Evaluate plant conditions and control secondary containment by operation of the following ventilation systems, 415.000 (a) VR (b) VG (c) VQ Given LGA-03, Primary Containment Control, in progress, evaluate plant 419.000 conditions and control and maintain Primary Containment pressure less than 1.93 psig IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, spray the 419.020 Suppression Pool IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, spray the Drywell 419.030 IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 420.000 conditions and control and maintain Drywell Temperature less than 340F IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, cool the 421.010 Suppression Pool IAW station procedures.

Page 8 of 35

NRC 15-1-4 Revision 00 Event-1

==

Description:==

Swap VR Supply/Exhaust Fans IAW LOP-VR-01 Initiation: Following crew assuming shift, on direction of Lead Evaluator Cues: Turnover Objective Position EXPECTED OPERATOR RESPONSE Per LOP-VR-01 o If desired, maintain CRD room Fan 1VR03CA/B running by quickly placing the C/S in START

Direct EO aAt 1PL27J VERIFY VR discharge check damper of fans to be started are closed

STOP one running VR supply fan 1VR01CA by placing the control switch in the STOP position

IMMEDIATELY STOP one VR Exhaust Fan 1VR02A by placing the control switch in the STOP position 415.000 BOP

Direct EO aAt 1PL27J, CHECK corresponding fan discharge check dampers 1VR01YA, and 1VR02YA CLOSED

START on standby VR Exhaust Fan 1VR02CC

IMMEDIATELY start one VR Supply Fan 1VR01CC

Direct EO aAt 1PL27J, CHECK corresponding fan discharge check dampers 1VR01YC and 1VR02YC OPEN

o VERIFY Station Vent Stack WRGM sample flow is isokinetic Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25" o If a CRD room Fan 1VR03CA/B was placed in START quickly place the C/S in AUTO ATC

Monitor plant parameters and update the crew as required 415.000 US

Direct above actions Page 9 of 35

NRC 15-1-4 Revision 00 Event - 1

==

Description:==

Swap VR Supply/Exhaust Fans IAW LOP-VR-01 Simulator Operator Actions none Simulator Operator Role Play As the operator in the field, when ordered to check the status of dampers in the field at the 1PL27J, wait 1 minute and report, 1VR01YA and 1VR02YA are CLOSED following the securing of the off going supply and exhaust fan.

As the operator in the field, when ordered to check the status of dampers in the field at the 1PL27J, wait 1 minute and report, 1VR01YC and 1VR02YC are OPEN following the starting of the oncoming supply and exhaust fan.

Floor Instructor Notes/OPEX/TRs None Terminus: VR Supply and Exhaust Fans swapped.

Page 10 of 35

NRC 15-1-4 Revision 00 Event-2

==

Description:==

Abnormal Turbine Generator Vibrations Initiation: On direction of Lead Evaluator, release Event 2 Cues:

Key Parameter Response: Rising Turbine Generator Vibrations Expected Annunciators: 1PM02J-B405, U1 TUBINE VIBRATIONS HI HI Automatic Action: none Objective Position EXPECTED OPERATOR RESPONSE Per 1PM02J-B405 Formatted: Font: Bold

Refer to LOA-TG-101 Formatted: List Paragraph, Indent: Left: 0", Hanging:

0.24", Bulleted + Level: 1 + Aligned at: 0.5" + Indent at:

0.75" Per LOA-TG-101 Formatted: Font: (Default) Arial, 11 pt

CHECK vibration level - REFER to the limits identified in Attachment A Formatted: List Paragraph, Indent: Left: 0.24"

Request EMD to take Shaft Voltage per LEP-TG-101

CHECK Turbine Lube Oil temp within the following limits:

Turbine Oil is being maintained at 110F to 120F

CHECK Temperature rise across bearings 71.030 BOP

COMPARE Turb Bearing Metal Temp

DISPATCH an Operator to the Turbine Generator area to listen around Turbine Generator - NO abnormal noise

CHECK Turbine Lube Oil System - OPERATINGOPEARTING NORMALLY

CHECK Steam Seal system - pressure greater than 4 psig

CHECK Turbine hood temperature less - than 175F

CHECK Main Generator Bearings 9 and 10 - Not affected Per LOA-TG-101 71.030 ATC

At direction of Unit Supervisor REDUCE Reactor Power using Reactor Recirculation Flow or Control Rods

Direct above actions

Set Critical Parameter Turbine Vibes

Designate Scram Criteria 71.030 US

Inform Shift Manager

Contact IMD & EMD as necessary

Contact Generation Dispatch of MWe reduction Page 11 of 35

NRC 15-1-4 Revision 00 Event - 2

==

Description:==

Abnormal Turbine Generator Vibrations Simulator Operator Actions With the concurrence of the Release Event 2 Lead Evaluator When the Crew lowers From smart summary change mms056, change the initial value to the Reactor Power and at the current value of vibes and change the final value to 0 and ramp over 2 discretion of the Lead minutes Evaluator Simulator Operator Role Play As the equipment operator sent to the TSI panel, wait 4 minutes and report to the Main Control Room requested information using RNI Panel view at 1PM02J-03 for bearing vibrations (mils)

As the operator sent to the turbine deck, wait 3 minutes and report, There are NO abnormal sounds from the Turbine Generator on the Turbine Deck.

Floor Instructor Notes/OPEX/TRs Turbine Vibration Limits per Attachment A of LOA-TG-101:

Bearings 1 through 10 - 12 mils or 10 mils for 15 minutes

Bearings 11 and 12 - 10 mils (must indicate greater than value on both X and Y TSI panel indicators to meet the criteria for a manual turbine trip.

Terminus: Reactor Power lowered and Turbine Vibrations trend turned.

Page 12 of 35

NRC 15-1-4 Revision 00 Event-3

==

Description:==

Station Air Compressor TRIP, Standby Fails to Auto Start Initiation: On direction of Lead Evaluator, release Event 3 Cues:

Key Parameter Response: Lowering Air Pressures Expected Annunciators: 1PM10J-B104, UNIT 1 STATION AIR COMPRESSOR AUTO TRIP Automatic Action: Unit 1 Station Air Compressor Automatic Trip Objective Position EXPECTED OPERATOR RESPONSE Per LOR-1PM10J-B104

Verify auto actions occur

If air pressure is dropping, START standby air compressor per LOP-SA-01/02

DISPATCH operator to Local Control Panel to CHECK for cause of 97.025 BOP TRIP

If low oil pressure is indicated at Local Control Panel:

VERIFY lube oil reservoir level is proper

CHANGE lube oil filters as necessary o If Station Air pressure drops below 100 psig and the standby air Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent compressor has not started, start 0SA01C at: 0.25" Per LOP-SA-02

Dispatch an operator to perform post start checks on the Unit 0 Station BOP Air Compressor

Verify system parameters return to normal, and adjust as necessary ATC

Monitor plant parameters and update the crew as required

Direct above actions 97.025 US

Inform Shift Manager

Contact EMD Page 13 of 35

NRC 15-1-4 Revision 00 Event - 3

==

Description:==

Station Air Compressor TRIP, Standby Fails to Auto Start Simulator Operator Actions With the concurrence of the Release Event 3 Lead Evaluator Simulator Operator Role Play As the equipment operator sent to investigate the Unit 1 Station Air Compressor, wait 4 minutes and report, Unit 1 Station Air Compressor tripped on low oil pressure.

Floor Instructor Notes/OPEX/TRs Low lube oil pressure trip setpoint is 8 psig for Unit 1 Station Air Compressor. Station Air Compressor will Auto start set point is 100 psig header pressure.

Terminus: Startup of 0 Station Air Compressor and parameters return to normal.

Page 14 of 35

NRC 15-1-4 Revision 00 Event-4

==

Description:==

LPRM Fails Downscale Initiation: On direction of Lead Evaluator, release Event 4 Formatted: Font: Bold Cues:

Key Parameter Response: LPRM Downscale and lowering D APRM Power Expected Annunciators:

1H13-P603-A407, LOCAL POWER RANGE MONITOR DOWNSCALE 1H13-P603-B507, OPRM / INOP TROUBLE Automatic Action: none Objective Position EXPECTED OPERATOR RESPONSE

Monitor Plant parameters and update the crew as required BOP

BYPASS failed LPRM detector Per LOR-1H13-P603-A407 43.001 ATC

REFER to LOA-NR-101, Neutron Monitor Trouble

Verify core power and flow.

Per LOA-NR-101

STOP all control rod motion/power changes

SELECT a control rod that will display suspect LPRM on the 1H13-P603 display of four LPRM strings

If required, REVIEW LPRM Diagnostics Screen on PPC to aid in determining LPRM operability

EVALUATE LPRM indication - NORMAL for plant conditions.

NOT Upscale/Downscale Response not obtained

BYPASS the APRM fed by the failed LPRM 43.001 ATC

REFER to Attachment B to assist in determining the operability of associated APRM

SELECT control rod that displays affected LPRM detector and VERIFY downscale reading on the meter

BYPASS the failed LPRM Detector

VERIFY APRM gains prior to restoring APRM

o If desired, UNBYPASS the APRM Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25"

NOTIFY QNE

VERIFY, using the Process Computer and the core mentoring software system, that LPRM inputs are zero

o Initiate an IR Formatted: Bulleted + Level: 1 + Aligned at: 0" + Indent at: 0.25"

Direct above actions

Contact QNE US

Contact Shift Manager

Refer to Tech Spec 3.3.2.1 and 3.3.1.3 Page 15 of 35

NRC 15-1-4 Revision 00 Event - 4

==

Description:==

LPRM Fails Downscale Simulator Operator Actions With the concurrence of the ReleaseELEASE Event 4 Lead Evaluator Simulator Operator Role Play Respond as QNE and Shift Manager.

Floor Instructor Notes/OPEX/TRsLPRM 08-33A is in input to D APRM per Attachment B of LOA-NR-101 The downscale light for the LPRM is not modeled on the back panel of the simulator, if questioned, inform the examinee that the downscale light is illuminated.

Terminus: D APRM Bypassed / 08-33A LPRM Bypassed Page 16 of 35

NRC 15-1-4 Revision 00 Event-5

==

Description:==

Loss of RPIS for Control Rod 38-19 Initiation: On direction of Lead Evaluator, release Event 5 Cues:

Key Parameter Response: Data Fault On Rod Display Expected Annunciators: none Automatic Actions: none Objective Position EXPECTED OPERATOR RESPONSE

Monitor plant parameters and update the crew as required BOP

Formatted: Font: 10 pt

Provide peer checksProvides peer checks as required Formatted: Font: 10 pt Formatted: Font: 10 pt Per LOA-RM-101 Formatted: Font: 10 pt

CHECK Control Rod Position indicates XX

CHECK Control Rod NOT at position 00/Full InOut prior to indication loss. Formatted: Font: 10 pt

CHECK Control Rod NOT at position 48/Full Out prior to indication loss. (NO) Formatted: Font: 10 pt

Apply 2 second withdraw jog:

Formatted: List Paragraph

Place CRD Drive Flow Trip Circuit Bypass Switch to BYPASS

Bypass RWM

Navigate to Withdraw Jog under SURVEILLANCE with RCMS

Apply 1 to 2 second duration Withdraw Jog command using withdraw and Formatted: Indent: Left: 0.24", Tab stops: 0.49", List tab continuous withdraw pushbuttons and observe withdraw drive flow and + Not at 0.25" withdraw and continuous withdraw indicators

Check rod indicates valid position (NO)INSERT withdraw Jog

INSERT control rod one notch:

º SET RWM Blocks to LPSP

º VERIFY RWM Bypass Switch in BYPASSBypass the Rod within RCMS per Formatted: Font: 10 pt LOP-RM-02 47.012 ATC

APPLY one single notch insert command only, Formatted: Font: 10 pt

OBSERVE Drive Flow and INSERT/SETTLE indicators

CHECK Control Rod - INDICATES new, valid position. (no)

Fully insert rod per attachment A

Fill out Attachment A table/check list Formatted: Font: (Default) Arial, 10 pt

REVIEW and PRINT PPC LPRM Status Display for LPRM power readings Formatted: Font: (Default) Arial, 10 pt, Font color: Black before inserting any control rod Formatted: Font: 10 pt

NOTIFY IMD to be prepared to manually read the RPIS probe after the rod is inserted.

INSERT control rod, by depressing and holding the INSERT Pushbutton while Formatted: Font: 10 pt timing and observing the following: Formatted: Font: 10 pt

Expected LPRM power decay.

Expected DECREASE in Reactor Power. Formatted: Indent: Hanging: 0.01"

Control rod full in should be indicated by:

Stall Flow is observed Formatted: Font color: Black

IMD verification of full in reed switch actuation Formatted: Normal, Indent: Left: 0.24", Space Before: 0 pt, After: 0 pt, Bulleted + Level: 1 + Aligned at: 0.75" +

Control rod insertion time is approximately equal to the previous LOS-RD- Indent at: 1", Widow/Orphan control, Adjust space between SR5 value from the time the insert PB was initially depressed Latin and Asian text, Adjust space between Asian text and numbers, Tab stops: 0.49", List tab Page 17 of 35

NRC 15-1-4 Revision 00

Release the Control Rod INSERT Pushbutton

Restore RWM to RUN o Rod may be placed OOS in RCMS

Electrically Disarm Control Rod Formatted: Font: 10 pt

Direct above actions Formatted: Normal, Space Before: 0 pt, After: 0 pt,

Contact QNE Widow/Orphan control, Adjust space between Latin and Asian text, Adjust space between Asian text and numbers 47.012

Enter Tech Spec 3.1.3 Condition C US Formatted: Font: 10 pt 201.011

Required action C.1 fully insert inop control rod in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND C.2 disarm the associated CRD in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Formatted: Indent: Left: 0.24", Bulleted + Level: 1 +

Aligned at: 0" + Tab after: 0.25" + Indent at: 0.25", Tab stops: 0.49", List tab + Not at 0.25" Formatted: Left Page 18 of 35

NRC 15-1-4 Revision 00 Event - 5

==

Description:==

Loss of RPIS for Control Rod 38-19 Simulator Operator Actions With the concurrence of the Release Event 5 Lead Evaluator Simulator Operator Role Play As QNE, is asked the previous stroke time was 56.3 seconds and the previous recorded stall flow was 1.9 gpm when last pperformedperformed.

As IMD, when asked inform the crew, standing by to read RPIS probe locally As IMD, when the rod is fully inserted, inform the crew the rod indicates fully inserted by local reading.

Floor Instructor Notes/OPEX/TRs none Terminus: when Rod is electrically disabled disarmed and Tech Spec call is made Page 19 of 35

NRC 15-1-4 Revision 00 Event-6

==

Description:==

Abnormal Turbine Generator Vibrations, Manual SCRAM Initiation: On direction of Lead Evaluator, release Event 6 Cues:

Key Parameter Response: Rising Turbine Generator Vibrations Expected Annunciators: 1PM02J-B405, U1 TUBINE VIBRATIONS HI HI Automatic Action: none Objective Position EXPECTED OPERATOR RESPONSE Per LOA-TG-101

CHECK vibration level - REFER to the limits identified in Attachment A

Determine turbine vibration levels exceed limits and inform the Unit Supervisor

TRIP and PERFORM Subsection B.1 of this procedure

CHECK Reactor Power - below 25% and stable Response not obtained

SCRAM Reactor

CHECK Turbine Bypass Valves - controlling Reactor Pressure

CHECK Turbine TRIPPED

CHECK at least one of the following - CLOSED o All MSVs (Yes) 71.029 Formatted: Font: 10 pt BOP o All CVs (Yes) 71.030

VERIFY Load Limiter at 2.0%

CHECK Generator OCBs 9-10 and 10 OPEN

CHECK Generator field breaker - OPEN

CHECK Voltage Regulator in - MANUAL

CHECK In-house loads transferred to SAT

CHECK Heater Valve alignment

MONITOR Turbine parameters throughout coastdown:

Speed (decreasing)

Bearing Vibrations (<10 mils)

Bearing Metal Temperatures (<190F)

Turbine Lube Oil Temperatures Per LOA-TG-101

If directed by Unit Supervisor REDUCE Reactor Power using Reactor 71.030 ATC Formatted: Font: 10 pt Recirculation Flow or Control Rods

Scram Reactor

Direct above actions

Set Critical Parameter Turbine Vibes Formatted: Font: 10 pt 71.029 US

Designate Scram Criteria 413.000

Inform Shift Manager

Contact Generation Dispatch of MWe reduction Page 20 of 35

NRC 15-1-4 Revision 00 Event - 6

==

Description:==

Abnormal Turbine Generator Vibrations, Manual SCRAM Simulator Operator Actions With the concurrence of the Formatted Table Release Event 6 Lead Evaluator Following the Turbine Trip Ramp mns056 to 0 over 2 minutes Simulator Operator Role Play As the equipment operator sent to the TSI panel, wait 4 minutes and report to the Main Control Room requested information using RNI Panel view at 1PM02J-03 for bearing vibrations (mils)

As the operator sent to the turbine deck, wait 3 minutes and report, There is NO abnormal sounds from the Turbine Generator on the Turbine Deck.

Formatted: Left Page 21 of 35

NRC 15-1-4 Revision 00 Event contd

==

Description:==

Abnormal Turbine Generator Vibrations, Manual SCRAM Objective Position EXPECTED OPERATOR RESPONSE

Manually TRIP the Main Turbine 71.029 BOP

Monitor Plant parameters and update the crew as required.

Performs Reactor Scram and LGP 3-2 on US direction.

ARM and DEPRESS Scram Pushbuttons

PLACE Reactor Mode Switch in SHUTDOWN

INSERT IRMs and SRMs

CHECK Control Rods INSERTED and Power Decreasing

INFORM Unit Supervisor of Control Rod Status and Reactor Power

Operate Feedwater and/or ECCS as necessary to maintain RPV Water Level 20" to 50" or as specified by Unit Supervisor

Place LFFRV in AUTO o Verify FRV closed in MANUAL 304.010

If MDRFP can maintain level, trip the running TDRFP and close its 413.000 ATC discharge valve

REPORT to the Unit Supervisor the status of RPV Level and Pressure

If needed for level control:

o Place the FRV in AUTO o Reset the Scram o Dispatch an EO to close 1C11-F034, Charging Water Supply Valve

VERIFY Reactor Recirculation Pumps have downshifted

VERIFY Main Turbine and Generator Trip

STABILIZE Reactor Pressure <1020 psig o If Main Condenser is available, open Bypass Valves

Maintains RPV water level as directed

Maintains RPV pressure as directed

Direct above actions 413.000 SRO

Order Reactor Scram and Turbine TRIP

Direct actions of LGA-001 Formatted: Left Page 22 of 35

NRC 15-1-4 Revision 00 Floor Instructor Notes/OPEX/TRs Turbine Vibration Limits per Attachment A of LOA-TG-101:

Bearings 1 through 10 - 12 mils or 10 mils for 15 minutes

Bearings 11 and 12 - 10 mils (must indicate greater than value on both X and Y TSI panel indicators to meet the criteria for a manual turbine trip.

Terminus: Turbine tripped and speed lowering.

THIS PAGE INTENTIONALLY LEFT BLANK Page 23 of 35

NRC 15-1-4 Revision 00 Event-7

==

Description:==

Feedwater Rupture Inside Primary Containment Initiation: Automatic Cues:

Key Parameter Response: Rising DW Pressure Expected Annunciators: Multiple Automatic Action: none Objective Position EXPECTED OPERATOR RESPONSE

When directed places Suppression Pool Cooling in service: (CT) Formatted: Font: Bold

Startup RHR Service Water as follows:

OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B

At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, START first RHR Service Water Pump:

1A or 1B/C or D

When indicated flow reaches 3000 gpm, START second RHR Service Water Pump.

Startup RHR 419.000

Start 1A/1B RHR Pump 419.020

Establish RHR flow of 1500 to 7450 gpm:

419.030

Throttle 1E12-F024A/B (Test Valve) OPEN.

420.000 BOP

Close 1E12-F048A/B (HX Bypass) 421.000 o Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE 421.010 and THROTTLE CLOSED 1E12-F048A/B.

o Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B

When directed establish Suppression Chamber Spray: (CT)

VERIFY 1A/1B RHR Pump is running

OPEN 1E12-F027A/B

When directed establish Drywell Spray: (CT)

VERIFY 1A/1B RHR Pump is running

THROTTLE 1E12-F024A/B CLOSED

OPEN:1E12-F016A/B and 1E12-F017A/B 413.000 ATC

Monitors and reports trends in RPV level and pressure

When Drywell Pressure exceeds 1.93 psig, enters and directs LGA-003

Before Suppression Chamber Pressure exceeds 12 psig

Verifies Containment Flood level below 723 ft.

419.000

Directs start of Suppression Chamber Sprays 419.020

When Suppression Chamber Pressure exceeds 12 psig, direct initiation of 419.030 Drywell sprays (CT) 420.000 US

Verifies Containment Flood level below 722 ft.

421.000

Verifies Drywell Pressure and Temperature permit Drywell Sprays per 421.010 Figure D

Verifies both Recirc Pumps are tripped

Direct initiation of Drywell sprays

When Suppression Pool temperature exceeds 105ºF initiation of Ddirect initiation of Suppression Pool Cooling (CT)

Page 24 of 35

NRC 15-1-4 Revision 00 Event contd

Description:

Feedwater Rupture Inside Primary Containment Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitors plant parameters and updates the crew as required.

Isolate the source of the leak

Prevent Injection from Feedwater or Condensate/Condensate Booster:

o CLOSE 1B21-F065A and B Feedwater Stops o CLOSE 1FW010A and B, TDRFP Discharge Valves, and 1FW003, Feed ATC Reg Valve Isolation and 1FW145, LFCV Upstream Stop o CLOSE 1FW015A and B, High Pressure Heater Outlets, and 1FW013, High Pressure Heater Bypass Stop.

Report if the source of the leak is isolated using RPV level and pressure trends

Direct actions of LGA-001 US

Direct actions of LGA-003

May direct isolation of the Feedwater System Event - 7

==

Description:==

Feedwater Rupture Inside Primary Containment Simulator Operator Actions Auto event Released when the Reactor Mode Switch is in Shutdown Simulator Operator Role Play Role play as required.

Floor Instructor Notes/OPEX/TRs The ATC should notice RPV trends as well as the deviation between FW header flows to determine the leak is in the Feedwater System.

Terminus: continued Page 25 of 35

NRC 15-1-4 Revision 00 Formatted: Left Formatted: Left Event contd

==

Description:==

Feedwater Rupture Inside Primary Containment Objective Position EXPECTED OPERATOR RESPONSE BOP

Monitors plant parameters and updates the crew as required.

Isolate the source of the leak

Prevent Injection from Feedwater or Condensate/Condensate Booster:

o CLOSE 1B21-F065A and B Feedwater Stops o CLOSE 1FW010A and B, TDRFP Discharge Valves, and 1FW003, Feed ATC Reg Valve Isolation and 1FW145, LFCV Upstream Stop o CLOSE 1FW015A and B, High Pressure Heater Outlets, and 1FW013, High Pressure Heater Bypass Stop.

Report if the source of the leak is isolated using RPV level and pressure trends

Direct actions of LGA-001 US

Direct actions of LGA-003

May direct isolation of the Feedwater System Page 26 of 35

NRC 15-1-4 Revision 00 THIS PAGE INTENTIONALLY LEFT BLANK Page 27 of 35

NRC 15-1-4 Revision 00 Event-8

==

Description:==

HPCS Fails to Auto-Start Initiation: Automatic Cues:

Key Parameter Response: HPCS Pump Discharge Pressure and Run Lights Expected Annunciators: Multiple Automatic Action: none (HPCS Fails to Auto Start)

Objective Position EXPECTED OPERATOR RESPONSE

Recognizes that HPCS did not AUTO initiate at 1.93 psig Drywell pressure 413.000 BOP

Manually takes action to initiate HPCS and control RPV level in band (CT)

If directed, starts a second CRD pump per LGA-RD-01

Directs an EO to perform in-plant actions for starting a second CRD Pump

Align 2 Drive Water Filters and 2 Suction Filters

Open Minimum flow valves

Close 1C11-F434 in CRD Pump Recirculation Line

Defeat the CRD Low Suction Pressure trips

Starts the second CRD Pump

Places BOTH CRD Pump switches in START and holds for 413.010 ATC 5 seconds before releasing

Opens 1C11-F003, CRD Drive Pressure Control Valve

If directed, starts SBLC per LGA-SC-102

Starts only one SBLC pump

Place A SBLC Pump in Sys A

Place B SBLC Pump in Sys B

Check that the Storage tank Outlet valve opens on the selected pump

Check that the selected SBLC Pump starts

Check that SBLC Discharge Pressure rises above RPV pressure

When RPV water level cannot be maintained above 11 inches, directs actions to maintain level above -150 inches

Directs use of Alternate Injection systems 413.010 US

Starting both CRD pumps

Injecting with SBLC

Direct actions of LGA-001 and LGA-003 Page 28 of 35

NRC 15-1-4 Revision 00 Event - 8

==

Description:==

HPCS Fails to Auto-Start Simulator Operator Actions Event it is Auto released Align the off service CRD Pump using RNI RD1 drawing (wait one minute between valve operations)

When requested to perform

OPEN 1C11-F021A and B LGA-RD-01 field actions to

OPEN 1C11-F114 and 116 start the standby CRD

CLOSE 1C11-F014A or B for the Standby Pump Pump

ISOLATE the low suction pressure trip for both CRD Pumps (iardalst and iarbalst)

Using RNI RD1 Following the Standby CRD Pump Start

OPEN 1C11-F014A/B

Restore both low suction pressure trip switches to normal Simulator Operator Role Play As the operator sent to perform LGA-RD-01, perform actions above and report to the crew when they are complete using LGA-RD-01 as a reference.

Floor Instructor Notes/OPEX/TRs The crew should notice that HPCS does not start due to a Hi Drywell initiation signal (1.93 psig)

Terminus: RPV level is stable in band and at the direction of the Lead Evaluator Page 29 of 35

NRC 15-1-4 Revision 00 Event-9

==

Description:==

RPV Blowdown Initiation: if unable to restore and maintain RPV level greater than -150 Cues:

Key Parameter Response: LOWERING RPV PRESSURE Expected Annunciators: NONE Automatic Actions: 7 SRVs OPEN Objective Position EXPECTED OPERATOR RESPONSE 413.000 ATC

Maintains RPV water level as directed

If directed, opens Turbine Bypass Valves o If directed, prevents LPCS, LPCI, and HPCS not needed for core cooling.

Performs a manual initiation of ADS.(CT) 411.000 428.000 BOP

Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons

Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons

Verifies 7 ADS valves open (CT) o May anticipate Blowdown and directs actions to rapidly depressurize via turbine bypass valves

Directs actions per LGA-004 if RPV level cannot be maintained > -150 411.000 (CT)

US

Verifies DW pressure at or above 1.77 psig.

428.000 o May direct NSO to prevent LPCS and LPCI not needed for cooling

Verifies SP level greater than -18 ft.

Directs NSO to initiate ADS.

Page 30 of 35

NRC 15-1-4 Revision 00 Event - 9

==

Description:==

RPV Blowdown Simulator Operator Actions none Simulator Operator Role Play none Floor Instructor Notes/OPEX/TRs none Terminus: when ADS has been initiated or blowdown anticipated and at the discretion of the Exam lead.

Page 31 of 35

NRC 15-1-4 Revision 00 REFERENCES Procedure Title Revision

1. LGA-001 RPV CONTROL 017

2. LGA-003 PRIMARY CONTAINMENT CONTROL 016

3. LGP-3-1 POWER CHANGES 062

4. LGP-3-2 REACTOR SCRAM 072

5. LOP-VR-01 REACTOR BUILDING VENTILATION SYSTEM 048 STARTUP AND OPERATION

6. LOA-TG-101 UNIT 1 TURBINE GENERATOR 017

7. LOA-NR-101 NEUTRON MONITORING TROUBLE 019

8. LOR-1PM10J-B104 UNIT 1 STATION AIR COMPRESSOR AUTOMATIC TRIP 004

9. LOR-1H13-P603- LOCAL POWER RANGE MONITOR DOWNSCALE 002 A407

10. LOR-1H13-P603- OPRM / INOP TROUBLE 005 B507

11. LOR-1H13-P602- RRFCS TROUBLE 002 A507

12. LOR-1PM02J-B405 U1 TURBINE GENERATOR VIBRATION HIGH 001

13. LOR-1H13-P601- DRYWELL PRESSURE HIGH 003 A106

14. LOR-1H13-P601- DRYWELL PRESSURE HIGH 004 A107

15. LOR-1H13-P601- HPCS SYSTEM ACTUATED 003 A205 ALTERNATE VESSEL INJECTION USING BOTH CRD

16. LGA-RD-01 013 PUMPS

17. LGA-RH-103 Unit 1 A and B RHR Operations in the LGAs and SAMGs 012

18. LOA-RM-101 UNIT 1 RCMS ABNORMAL SITUATIONS 018 STATION AIR COMPRESOR STARTUP AND 038

19. LOP-SA-02 SHUTDOWN Page 32 of 35

NRC 15-1-4 Revision 00 SMART SCENARIO ESG NRC 15-1-4 Revision: 00 Revision Date: 7/13/2016 Developed By: C. M. Betken Page 33 of 35

NRC 15-1-4 Revision 00 THIS PAGE INTENTIONALLY LEFT BLANK Page 34 of 35

NRC 15-1-4 Revision 00 U1 SUPERVISOR TURNOVER Shift: 2 Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level

100 % Power

100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions

None

None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance

None

None LOSs in progress or major maintenance LOSs in progress or major maintenance

None

None Equipment removed from service or currently unavailable

C CD/CB Pump

None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.

Perform LOP-VR-01 Section E.3.6 to

Non-Div workweek swap from A to C VR Supply/Exhaust

OLR is Green Fans

Non-Div workweek

OLR is Green Page 35 of 35

Facility NRC EXAM Scenario __

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 5 Op-Test No.: _2016301_______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Shutdown in progress at approximately 35% power. Currently at Step E.1.9, ready to downshift RR Pumps to Slow Speed per LOP-RR-08.

Turnover: Continue Shutdown and swap to the A VP Chiller and follow-up with RR downshift.

Event Malf. No. Event Event No. Type* Description 1 none N (BOP) Swap VP Chiller Trains IAW LOP-VP-02 2

none R (ATC) Downshift RR Pumps IAW LOP-RR-08 3

k2h06jti C (ATC) RR Pump TRIPs to Zero Speed after Downshift 3

none T (SRO) RR Pump TRIPs to Zero Speed after Downshift 4

k1k21p1n C (BOP) Spurious LPCS Initiation 4

none T (SRO) Spurious LPCS Initiation 5

k9d782rr I (BOP) Primary Containment Pressure Controller Fails 6

vhtm60ad C (ATC) TDRFP Oil Leak 7

mrc041 M (ALL) RR LOCA 8 mrp018 C (ATC) B RPS Channel Fails to De-Energize (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification

LaSalle County Station ILT DYNAMIC SIMULATOR SCENARIO GUIDE ESG NRC 15-1-5 Rev. 0 07/30/2016 DEVELOPED BY: Colin Betken 8/16/2016 Instructor Date VALIDATED BY: J. Martin / Hawkins / Jozwiak / Clark 7/31/2016 SME/Instructor Date REVIEWED BY: Mark Smith 8/17/2016 Operations Manager Date APPROVED BY: Dan Moren 8/17/2016 Exam Author Date

NRC 15-1-5 Revision 00 Facility: LaSalle County Station Scenario No.: NRC 15-1-5 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Swap VP Chiller Trains IAW LOP-VP-02

2. Downshift RR Pumps IAW LOP-RR-08.

The crew is directed at the beginning of their shift to continue the down power to shutdown by downshifting RR pumps IAW LGP-2-1 and LOP-RR-08.

3. Following the downshift the A RR Pump will Trip The crew will take action to prevent reverse flow of the pump.

4. Spurious LPCS Initiation.

An inadvertent initiation of LPCS. The crew responds, and when it is confirmed that no initiation signal is present, the crew shuts down LPCS. The US will declare LPCS inoperable.

5. Primary Containment Pressure Controller Fails.

Primary Containment Pressure Controller fails resulting in 1H13-P603-B501, Primary Containment Pressure HI/LO. The BOP takes manual control of the malfunctioning instrument and may perform a primary containment vent to lower drywell pressure per LOP-VQ-04.

6. RR Pump TRIPs to Zero Speed after Downshift.

A RR Pump will trip and the crew will take action per LOA-RR-101 to verify location and the power to flow map and enter applicable Tech specs.

8.6. TDRFP Oil Leak.

The crew performs an emergency shutdown per LOP-FW-05.

9.7. RR LOCA .

A Recirc Suction line breaks in the Drywell. This will drive the crew into the LGAs. The crew will take actions per LGA-001 and establish RPV Level and Pressure control. Per LGA-003 they will take actions in the Containment Pressure Leg, including Chamber Sprays and Drywell Sprays.

10.8. B RPS Channel Fails to De-Energize When the reactor is scrammed, the crew will discover that RPS Trip System B has failed to scram..

When it is recognized that the rods did not insert, the ATC will manually initiate Alternate Rod Insertion (ARI). Rods will go full in. The crew may enter LGA-010 but should exit it promptly after ARI is initiated. The scenario is terminated when the crew has RPV and Containment parameters stable and under control and with the concurrence of the lead examiner Critical Tasks

1. With a reactor scram required and insufficient control rod worth inserted to maintain the reactor shutdown under all conditions without boron; take action to insert control rods (ARI)Manually insert control rods by initiating ARI.

2. With suppression chamber pressure above 12 psig, containment flood level below 722 feet, and drywell parameters below the Drywell Spray Initiation Limit; trip all recirculation pumps and start Page 2 of 33

NRC 15-1-5 Revision 00 drywell sprays using RHR pumps not needed for adequate core coolingPlace the Residual Heat Removal (RHR) heat exchangers in service to establish containment cooling.

Page 3 of 33

NRC 15-1-5 Revision 00

3. TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

2. None Operator Fundamentals

1. Monitoring plant indications and conditions closely

2. Controlling plant evolutions precisely

3. Operating the plant with a conservative bias

4. Working effectively as a team

5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2

1. Oversight ensures proper focus

2. Equipment restoration risk evaluation

3. Preparation for high risk evolution

4. Control Room resources adequate for EOP response

5. Sufficient engagement of others in decision making Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 15-1 NRC Exam Page 4 of 33

NRC 15-1-5 Revision 00 INITIAL SIMULATOR SETUP/REQUIRED DOCUMENTATION

1. Recall a 35% Ready to Downshift IC: 326 Passwrd: 3263

2. Place simulator in RUN.

3. Load and run the smart scenario: NRC 15-1-5.ssf

4. Place Protected Equipment rings and/or robust barriers on the following components: None

5. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A

6. Perform the pre-scenario checklist. (TQ-LA-150-0308)

7. Perform the following panel manipulations:

8.7. Provide copiscopies of the following procedures:

LGP-2-1 marked up to Step E.1.9

LOP-RR-08 marked up to Step E.2

LOP-RR-07 Sections B, C, and D marked up

LOP-VP-02 Sections B, C, and D marked up 9.8. Verify the following:

B VP Train Online

A TDRFP Online

Check CRD drive flow and pressure are normal

Both VP Trains online

1PL78J - DW Light is off 10.9. Perform the pre-scenario checklist. (TQ-LA-150-0308)

Page 5 of 33

NRC 15-1-5 Revision 00 Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: NRC Scenario 5 Op-Test No.: _2016301__

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Shutdown in progress at approximately 35% power. Currently at Step E.1.9, ready to downshift RR Pumps to Slow Speed per LOP-RR-08.

Turnover: Continue Shutdown and swap to the A VP Chiller and follow-up with RR downshift.

Event Malf. No. Event Event No. Type* Description 1

none N (BOP) Swap VP Chiller Trains IAW LOP-VP-02 2

none R (ATC) Downshift RR Pumps IAW LOP-RR-08 3 C (ATC) k2h06jti RR Pump TRIPs to Zero Speed after Downshift 34 none T (SRO) RR Pump TRIPs to Zero Speed after Downshift 45 k1k21p1n C (BOP) Spurious LPCS Initiation 46 none T (SRO) Spurious LPCS Initiation 57 k9d782rr I (BOP) Primary Containment Pressure Controller Fails 68 vhtm60ad C (ATC) TDRFP Oil Leak 79 mrc041 M (ALL) RR LOCA 810 mrp018 C (ATC) B RPS Channel Fails to De-Energize (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)echnical Specification ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal: 1 Malfunction(s) after EOP (1-2): 1 ATC Reactivity (1 per set): 1 Abnormal Events (2-4): 4 BOP I/C (4 / set): 2 Major Transient(s) /E-Plan entry (1-2): 1 ATC I/C (4 / set): 3 EOPs (1-2): 2 SRO-I I/C (4 / set inc 2 as ATC): 5 EOP Contingencies (0-2): 0 SRO Tech Spec (2 per set): 2 Critical Tasks (2-3): 2 ALL Major Transients (2 per set): 1 Formatted: Indent: Left: 0", Hanging: 0.62" APPROXIMATE SCENARIO RUN TIME 90xx Minutes Page 6 of 33

NRC 15-1-5 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)

During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

TASKS RO - ATC Given Unit Supervisor authorization, transfer Reactor Recirc Pumps from Fast 22.004 to Slow Speed IAW station procedures.

Given Unit Supervisor authorization, perform CR actions to respond to a loss 22.015 of one or both RR pumps IAW station procedures.

Given Unit Supervisor authorization, Perform the in plant actions to respond to 77.046 a turbine driven reactor feed pump low hydraulic oil pressure alarm IAW station procedures.

Given Unit Supervisor authorization, respond to a primary containment 93.013 pressure high or low alarm IAW station procedures.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and 431.000 shutdown the reactor, IAW station procedures.

RO - BOP/ASSIST Given Unit Supervisor authorization, transfer Reactor Recirc Pumps from Fast 22.004 to Slow Speed IAW station procedures.

Given Unit Supervisor authorization, perform Control Room actions to 63.006 shutdown LPCS following an auto initiation IAW station procedures.

Given Unit Supervisor authorization, Perform the in plant actions to respond to 77.046 a turbine driven reactor feed pump low hydraulic oil pressure alarm IAW station procedures.

Given Unit Supervisor authorization, respond to a primary containment 93.013 pressure high or low alarm IAW station procedures.

Given Unit Supervisor authorization, startup the Primary Containment Chilled 96.001 Water and Ventilation System IAW station procedures.

Given Unit Supervisor authorization, perform actions for a reactor scram IAW 304.010 station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and 413.000 control RPV level +11 to 59.5 IAW LGA-001 Given LGA-01, RPV Control in progress, evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches on FZ using 414.000 preferred injection systems and if needed alternate injection systems IAW station procedures.

Given entry in LGA-01, RPV Control, evaluate plant conditions and control 414.040 RPV water level using LPCI, IAW LGA-RH-103 IAW station procedures.

Given LGA-03, Primary Containment Control, in progress, evaluate plant 421.000 conditions and control and maintain suppression pool temperature less than HCTL IAW station procedures.

Page 7 of 33

NRC 15-1-5 Revision 00 SRO - UNIT SUPERVISOR Given Unit Supervisor authorization, transfer Reactor Recirc Pumps from Fast 22.004 to Slow Speed IAW station procedures.