ML20176A222

Ile As-Administered Scenarios

ML20176A222
Person / Time
Site:	LaSalle
Issue date:	12/11/2018
From:	Chuck Zoia NRC/RGN-III/DRS/OLB
To:	Exelon Nuclear
Zoia C
Shared Package
ML17164A409	List: ML20176A209 ML20176A213 ML20176A222 ML20176A229 ML20176A341 ML20176A348
References
NRC 17-1-1
Download: ML20176A222 (116)

Text

LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-1 Rev. 00 6/13/2018 DEVELOPED BY:

Colin Betken 10/12/18 Exam Author Date TECHNICAL REVIEW: Pratt / Polega / Vanderhyden / Neitzel 7/9/18 SME/Tech Reviewer Date REVIEWED BY:

Tyler Messner 10/12/18 Training Department Date APPROVED BY:

Joe Messina 10/12/18 Operations Representative Date

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 2 of 29 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-1 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Swap EHC Pumps. The crew will swap from A to B; EHC Pump per LOP-EH-06.

2. A RR Pump Bearing Temp High. A RR Pump Upper bearing will have increased temp which will cause the crew to lower Reactor Power. Once Bearing temperature exceeds its limit the crew will take action to trip A RR Pump.

3. Single Loop Operations. Once the A RR Pump has been tripped the Unit Supervisor will enter Tech Spec 3.4.1.

4. Feed water Pump Flow Instrument Fails Downscale. The A Feed water Pump Flow instrument will fail downscale which will cause the min flow valve to open. This will cause a fluctuation in Reactor Water Level and the crew must take manual control of the min flow valve and close it.

5. Single Rod Scrams. Rod 18-59 scrams and the crew must take action to disarm the control rod in RCMS.

6. The Unit Supervisor must declare rod 18-59 INOP and enter Tech Spec 3.1.3.

7. Reactor Building Closed Cooling Water Pump Trip. When the running WR pump trips the crew will take action to start a standby WR pump.

8. Turbine Building Exhaust Fan Trip. When the B VT Fan Trips the crew will take action to start the C VT Fan.

9. LOCA with Bypass path through failed vacuum breaker. A LOCA will occur in A RR Loop and when the crew takes scram action the A Vacuum breaker will fail open creating a containment bypass path.

10. Blowdown. When containment parameters increase to the point of violating PSP the crew will take action per LGA-004 to blowdown, Critical Tasks 1.) 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 prior to starting Drywell sprays.

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 drywell sprays using RHR pumps not needed for adequate core cooling prior to 60 psig drywell pressure.

3) When suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure (PSP),

INITIATE emergency depressurization. (or anticipates Blowdown and depressurizes rapidly via the main turbine bypass valves.)

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 3 of 29 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

1. 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. Supervisory oversight role

2. Recognition and mitigation of risk

3. Worker performance

4. Tolerance of repetitive/long standing issues and degradation of standards

5. Operating Experience Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 17-1 NRC Exam

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 4 of 29 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION

1. Recall a full power IC

2. Place simulator in RUN

3. Load and run the SmartScenario file NRC 17-1-1.ssf

4. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/

Component Required Action REQUIRED ACTION Description Completion Time Expiration Date/Time N/A N/A N/A N/A N/A N/A

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

SCENARIO OUTLINE (NRC Evaluations Only)

Event No.

Malf.

No.

Event Type*

Event Description 1

none N (BOP)

Swap EHC Pumps (LOP-EH-04) 2 l1076 l1121 R (ATC)

A Reactor Recirc Pump Bearing High Temp/Trip 3

none T (US)

Single Loop 4

mcf072 I ( ATC)

Feedwater Pump Flow Instrument Fails Downscale 5

sri002 C (ATC)

Single Rod Scrams 6

none T (US)

Rod INOP 7

mcw014 C (BOP)

Reactor Building Closed Cooling Water Pump Trip 8

k7d15wpg C (BOP)

Turbine Building Exhaust Fan Trip 9

mca006 mrc036 M

LOCA with Bypass Path through Failed Vacuum Breaker 10 none M

Blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 5 of 29 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE) 769.00.01 During performance of tasks, dynamic learning activities, or formal evaluations, demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

762.04.00 Given an operating experience document, paraphrase the lessons learned and methods to prevent recurrence at LaSalle Station, as described in the training material.

614.010 During performance of tasks, apply the administrative requirements of PROCEDURE USE AND ADHERENCE EXPECTATIONS, IAW station procedures.

TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram, IAW station procedures 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.

22.015 Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or both RR pumps, IAW station procedures.

25.048 Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control Room, IAW station procedures.

77.053 Given initial plant conditions, Perform Control Room actions to respond to a RFP recirculation valve full open alarm IAW station procedures.

413.000 Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 59.5 IAW LGA-001 414.000 Evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches on FZ using preferred injection systems and if needed alternate injection systems, IAW station procedures.

419.000 Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig, IAW LGA-003.

419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.

419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.

419.040 Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, IAW LGA-004.

421.000 Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool temperature less than HCTL, IAW LGA-003.

421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 6 of 29 RO - BOP/ASSIST 2.010 Respond to a Transformer Trouble and take the appropriate actions to restore.

73.005 Given Unit Supervisor authorization, perform the in-plant actions to shift EHC Pumps, IAW station procedures.

114.019 Given initial plant conditions, Perform the Main Control Room actions for a Trip of a Reactor Building Closed Cooling Water (RBCCW) Pump, IAW station procedures.

114.027 Given initial plant conditions, Perform the Main Control Room actions for a Reactor Building Closed Cooling Water (RBCCW) Pump Discharge Pressure Low Alarm, IAW station procedures.

114.029 Given initial plant conditions, Perform Control Room actions for a loss of RBCCW, IAW station procedures.

119.014 Given initial plant conditions, Start-up the Turbine Building Ventilation System (VT), IAW station procedures.

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

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 7 of 29 SRO - UNIT SUPERVISOR 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.

22.015 Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or both RR pumps, IAW station procedures.

25.048 Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control Room, IAW station procedures.

73.005 Given Unit Supervisor authorization, perform the in-plant actions to shift EHC Pumps, IAW station procedures.

77.053 Given initial plant conditions, Perform Control Room actions to respond to a RFP recirculation valve full open alarm IAW station procedures.

114.019 Given initial plant conditions, Perform the Main Control Room actions for a Trip of a Reactor Building Closed Cooling Water (RBCCW) Pump, IAW station procedures.

114.027 Given initial plant conditions, Perform the Main Control Room actions for a Reactor Building Closed Cooling Water (RBCCW) Pump Discharge Pressure Low Alarm, IAW station procedures.

114.029 Given initial plant conditions, Perform Control Room actions for a loss of RBCCW, IAW station procedures.

119.014 Given initial plant conditions, Start-up the Turbine Building Ventilation System (VT), IAW station procedures.

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

413.000 Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 59.5 IAW LGA-001 414.000 Evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches on FZ using preferred injection systems and if needed alternate injection systems, IAW station procedures.

419.000 Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig, IAW LGA-003.

419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.

419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.

419.040 Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, IAW LGA-004.

421.000 Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool temperature less than HCTL, IAW LGA-003.

421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 8 of 29 Event - 1

==

Description:==

Swap EHC Pumps Initiation: Per Lead Evaluator, following the crew assuming the shift Cues: Turnover Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor Reactor Power, Level and Pressure

• Provide peer checks as required 73.005 BOP Per LOP-EH-04

• At the Turbine Control Panel 1PM02J:

• START the oncoming EHC Fluid Pump, 1EH02PB.

• OBSERVE the Discharge Pressure Normal (green) light comes ON for the EHC pump just started.

• OBSERVE that there is running current indication for the EHC pump just started on the 1II-EH006.

• OBSERVE that EHC Supply header pressure is approximately 1600 psig or slightly above as read on 1PI-EH001.

• STOP the offgoing EHC Fluid Pump from control room panel 1(2)PM02J.

• OBSERVE that EHC supply header pressure is still approximately 1600 psig 73.005 US

• Direct above actions

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 9 of 29 Event - 1

==

Description:==

Swap EHC Pumps Simulator Operator Actions none Simulator Operator Role Play When, requested, as EO in the field, report that step E1.6 and E.1.7 are complete. (Adjust pressure using local adjusting screw)

When, requested, as EO in the field, report that step E1.11 is complete. (lock nut for adjusting screw is tightened)

Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When A EHC Pump is secured and at the discretion of the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 10 of 29 Event - 2

==

Description:==

A Reactor Recirc Pump Bearing High Temp/Trip Initiation: Per Lead Evaluator Cues:

Expected Annunciator: 1H13-P602-B507, Reactor Recirculation Pump 1A/1B Temperature High Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 22.008 22.015 ATC Per LOR-1H13-P602-B507

• CHECK Reactor Recirculation Pump Motor 1A/1B Temperatures are equal to or greater

• than alarm setpoints on Pump/Motor 1A/1B Temperature recorder 1B33-R601AA, AB, BA, BB on panel 1H13-P614.

• If Bearing Temperature(s) (Point 1/2/3/4 on 1B33-R601AA/BA) are approaching their limits, REDUCE Reactor Power to stop the bearing temperature increase.

• If above Bearing temperature limits (Point 1/2/3/4 on 1B33-R601AA/BA) are exceeded and cannot be reduced, TRIP the affected RR Pump and refer to LOA-RR-101. Note: Motor Thrust Bearing Upper Face actual limit, requiring manual trip, is 220ºF.

Per LOA-RR-101

• CHECK at least one Recirc pump operating.

• 1H13-P603-A109, OPRM Hi Alarm-CLEAR.

• PERFORM Subsection B.1, Thermal Hydraulic Instabilities, while continuing below.

• VERIFY both RR Loop M/A stations are in MANUAL

• CHECK operating Recirc Pump in HIGH SPEED.

• At 1DS001, initiate TADS by DEPRESSING TDR icon.

• NOTIFY IMD

• DECREASE FCV position to minimum for tripped Recirc pump.

• Check OPEN the 1A and 3A Bkr

• VERIFY CLOSED 2A or 1A and 4A Bkr o If the Reactor Recirc Pump is being shutdown and the unit will remain in single loop operation for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, CLOSE either of the following to prevent reverse rotation 1B33-F067A/B, RR pump discharge (preferred) o After 5 minutes, RE-OPEN valve closed above to re-establish flow in the idle loop.

• CHECK SLO condition is allowed with current existing Equipment Out of Service conditions

• INSERT control rods to reduce Reactor Power to less than 65.7% FCL BOP Per LOR-1H13-P602-B507

• VERIFY proper operation of RBCCW System

• VERIFY proper operation of Primary Containment Ventilation System 22.008 22.015 US

• Direct above actions

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 11 of 29 Event - 2

==

Description:==

A Reactor Recirc Pump Bearing High Temp/Trip Simulator Operator Actions When directed by the Lead Evaluator (Initial Temp increase above alarm setpoint)

Release Event 2A When directed by the Lead Evaluator (Temp increase above max temp for RR Trip)

Release Event 2B Simulator Operator Role Play Respond as QNE and inform the crew that you will report to the Control Room.

Respond as IMD and report that preps are being made for LIS-NR-107.

Respond as required Floor Instructor Notes/OPEX/TRs Note: The crew should initially reduce power from the high bearing temp followed by tripping the RR Pump. If the crew fails conservatively and immediately trips the RR Pump the power reduction will occur later in LOA-RR-101 using Control Rods to reduce power below 65.7.% FCL.

Terminus: Following Power reduction and RR Pump Trip and with the concurrence of the Lead Evaluator.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 12 of 29 Event - 3

==

Description:==

Single Loop Initiation: Per Lead Evaluator Cues: Manual Trip of 1A RR Pump Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Continue with actions of Event 2 BOP

• Continue with actions of Event 2 201.011 US

• INITIATE Tech Spec 3.4.1 Required Action C.1 requirements for Single Loop Operation.

• REDUCE APLHGR. (LCO 3.4.1.a)

• REDUCE LHGR (LCO 3.4.1.b)

• REDUCE MCPR. (LCO 3.4.1.c)

• PERFORM LIP-NR-519A/B, Unit 1 APRM Channel A, B, C, D, E, and F and RBM Channel A/B Single Recirculation Loop Setpoint Entry and Exit. (LCO 3.4.1.d/e)

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 13 of 29 Event - 3

==

Description:==

Single Loop Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: Per NOTE in LOA-RR-101 Tech Spec 3.2.1, 3.2.2 AND 3.2.3 do not need to be entered.

Terminus: Following Tec Spec Call and with concurrence from the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 14 of 29 Event - 4

==

Description:==

Feedwater Pump Flow Instrument Fails Downscale Initiation: Per Lead Evaluator Cues:

Automatic Actions: None Expected Annunciator: 1H13-P603-A511, RWLCS Trouble Key Parameter Response: Reactor Level Fluctuations Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 77.053 ATC Per LOR-1H13-P603-A511

• At the 1DS001 Operation Station Event List, Check alarm message.

• If alarm message is "Dev Header/Pump Flow" then CHECK for failing reactor feed pump discharge flow signal.

• If a Reactor feed pump discharge flow signal has failed,

• VERIFY the corresponding reactor feed pump minflow M/A station is in manual.

• POSITION the corresponding reactor feed pump minflow as required for plant conditions.

• REFER to LOP-FW-16 to determine cause of alarm and required actions.

BOP

• Monitor plant conditions and update the crew as required 77.053 US

• Direct above actions

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 15 of 29 Event - 4

==

Description:==

Feedwater Pump Flow Instrument Fails Downscale Simulator Operator Actions When directed by the Lead Evaluator Release Event 4 Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: The corresponding position for the Min Flow Valve is full closed for plant conditions.

Terminus: When the Min Flow Valve is closed in Manual and at the discretion of the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 16 of 29 Event - 5

==

Description:==

Single Rod Scrams Initiation: Per Lead Evaluator Cues:

Automatic Actions: None Expected Annunciator: 1H13-P603-A503, CRD Hydraulic Accumulator Trouble 1H13-P603-A504, Control Rod Drive Drift Alarm Key Parameter Response: Rod 18-59 Inserts Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 25.048 ATC Per LOA-RD-101 Continually check rod status CHECK no control rod currently moving CHECK control rod remains at position 04 or less If insert pushbutton is NOT being held depressed:

If desired o

PLACE control rod OOS on RCMS o

DISARM control rod electrically on RCMS Perform LPRM diagnostic RUN OD-20 Per LOP-RM-02 DETERMINE desired control rod to be Electrically disarmed SELECT SET PARAMETERS SELECT ELECTRICALLY DISARM/RESTORE ROD on the SET HCU screen SELECT control rod to be electrically disarmed Press ACCEPT to change the desired control rod to electrically disarm ACKNOWLEDGE popup messages The electrically disarmed rod will appear in white text on light gray back round with orange border RETURN to the SELECT screen, if desired, when all ED operations are complete.

o May Place Rod OOS per LOP-RM-02 SELECT SET PARAMETERS on the ROD SELECT Display or the STATUS Display, whichever is in the CONTROL mode.

SELECT DECLARE/RESTORE ROD OUT OF SERVICE on the SET HCU/ROD screen.

SELECT the control rod(s) to be declared out-of-service.

PRESS ACCEPT to place the control rod out of service.

• ACKNOWLEDGE the popup message BOP

• Provide peer checks as required 25.048 US Direct above actions Set manual Scram criteria o

More than 1 rod moving at the same time o

More than 3 rods SCRAMMED OR DRIFTED Full in Contact system Engineering and QNE

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 17 of 29 Event - 5

==

Description:==

Single Rod Scrams Simulator Operator Actions When directed by the Lead Evaluator Release Event 5 Simulator Operator Role Play Respond as QNE and System Engineering.

If asked for Local indications at the HCU, as an EO in the Field report that there are no abnormal; indications at the HCU. Call the Unit Supervisor and report Local Accumulator pressure for rod 18-59 is 850 psig.

If requested the to take follow up action per LOR-1H13-P603-A503, inform the crew that Field Supervisor will brief 2 Eos and inform the crew when they are briefed.

Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 18 of 29 Event - 6

==

Description:==

Rod INOP Initiation: Event 5 Cues: Rod 18-59 Scrams Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 25.048 ATC

• Monitor plant parameters and update the crew as required.

BOP

• Provide peer checks as required 25.048 201.011 US Enter Tech Spec 3.1.3 Condition C Required action C.1 fully insert inop control rod in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND C.2 disarm the associated CRD in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Enter Tech Spec 3.1.5 Condition A Required action A.1 declare the associated rod scram time slow OR Required Action A.2 declare the associated control rod inoperable.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 19 of 29 Event - 6

==

Description:==

Rod INOP Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 20 of 29 Event - 7

==

Description:==

Reactor Building Closed Cooling Water Pump Trip Initiation: Per Lead Evaluator Cues:

Automatic Actions: A WR Pump Trip Expected Annunciators: LOR-1PM10J-A101, Reactor Building Closed Cooling Water Pump Automatic Trip Key Parameter Response:

Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC Monitor Plant parameters and update the crew as required.

o Refer to LOA-RT-101 114.019 114.027 114.029 BOP 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 Reactor Building Closed Cooling Water Pump for abnormalities 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 Check RBBCW header discharge pressure - greater than 50 psig Response not obtained Start standby RBCCW pump o Refer to LOA-RT-101 Verify reject path aligned Substitute PPC points 114.019 114.027 114.029 US Direct above actions Set manual Scram Criteria for a loss of all WR

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 21 of 29 Event - 7

==

Description:==

Reactor Building Closed Cooling Water Pump Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 7 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 Note: RT may isolate due to WR Pump trip. RT recovery will not be performed.

Terminus: When a standby WR Pump is running and at the discretion of the Lead Evaluator.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 22 of 29 Event - 8

==

Description:==

Turbine Building Exhaust Fan Trip Initiation: Per Lead Evaluator Cues:

Automatic Actions: 1VT02CB Trips Expected Annunciators: 1PM06J-B403, Turbine Building Exhaust Fan 1VT02CB Automatic Trip Key Parameter Response: None Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor Reactor Power, Level and Pressure 119.015 BOP Per LOR-1PM06J-B404

• VERIFY above automatic actions occur

• Start idle exhaust fan

• Determine cause of trip

• Enter LOA-VT-101

• Refer to LOP-VT-01

• INITIATE appropraite corrective action Per LOA-VT-101

• CHECK two Turbine Building Exhaust Fans OPERATING

• START additional Turbine Buuilding Exhaust Fan(s)

• Verify Main Stack flow is isokinetic

• Check TB DP between -2.0 and 0 in. H2O 119.015 US

• Direct above actions

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 23 of 29 Event - 8

==

Description:==

Turbine Building Exhaust Fan Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 8 Simulator Operator Role Play When ordered to investigate the VT Fan Trip, as EO, wait 3 minutes and report it tripped on Over Current.

If requested, as EO, report Turbine Building DP is -1.0 H2O Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following the start of the 1C VT Exhaust Fan and at the discretion of the Lead Evaluator

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 24 of 29 Event - 9

==

Description:==

LOCA with Bypass Path through Failed Vacuum Breaker Initiation: Per Lead Evaluator Cues:

Automatic Actions: Reactor Scram, ECCS initiations, PCIS Isolations Expected Annunciators: 1H13P603-B501 PRI CNMT PRESSURE HI/LO Key Parameter Response: Rising Containment Pressure Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 419.000 304.010 414.000 419.020 419.030 421.000 421.010 413.000 ATC o

Responds to PRI CONT PRESSURE HI/LO annunciator and informs the Unit supervisor When directed, manually scrams the reactor ARM and DEPRESS Scram Pushbuttons PLACE Reactor Mode Switch in SHUTDOWN INSERT IRMs and SRMs CHECK Control Rods INSERTED and Power Decreasing REPORT to the Unit Supervisor the status of RPV Level and Pressure VERIFY Reactor Recirculation Pumps have downshifted VERIFY Main Turbine and Generator Trip STABILIZE Reactor Pressure <1020 psig REFER to LGP-3-2 Monitors and reports RPV water level throughout

• Controls injection from Condensate and Feed system 419.000 304.010 414.000 419.020 419.030 421.000 421.010 BOP To prevent losing Chamber Spray/ECCS runout with DW Spray prior to 500 psig.

Place Div 1/2 Inj Override Switch to NON-ATWS Div I: With an ECCS signal present Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated Div II: With an ECCS signal present Verify White Manual Override light for 1E12-F042B AND 1E12-F042C Illuminated Per LGA-RH-103 When directed places Suppression Pool Cooling in service:

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 Start 1A/1B RHR Pump Establish RHR flow of 1500 to 7450 gpm:

Throttle 1E12-F024A/B (Test Valve) OPEN.

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

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 25 of 29 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 419.000 304.010 414.000 US o

May direct a manual reactor scram prior to reaching 1.93 psig in the Drywell Enters and directs actions of LGA-001 LEVEL LEG Establishes a RPV water level band of 20 to +50 inches Enters and directs actions of LGA-001 PRESSURE LEG STABILIZE Reactor Pressure below 1059 psig When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003 Before Suppression Chamber Pressure exceeds 12 psig Verifies Containment Flood level below 723 ft.

Directs start of Suppression Chamber Sprays (CT)

When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays Verifies Containment Flood level below 722 ft.

Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D Verifies both Recirc Pumps are tripped Direct initiation of Drywell sprays (CT)

When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling Event - 9

==

Description:==

LOCA with Bypass Path through Failed Vacuum Breaker Simulator Operator Actions When directed by the Lead Evaluator Release Event 9 Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: If level 1 is received LPCS.1C RHR override will clear and LPCS/1C RHR will Inject Terminus: continued

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 26 of 29 Event - 10

==

Description:==

Blowdown Initiation: Automatic Cues:

Automatic Actions: 7 SRVs Open Expected Annunciators: Multiple Key Parameter Response: Lowering RPV Pressure Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Control RPV Level in band 419.040 BOP 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)

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) 419.040 US

• If cannot restore chamber pressure and pool level inside Pressure Suppression Pressure and hold it there, blowdown per LGA-004 or anticipate blowdown using Turbine Bypass Valves.

Determines if SC pressure will remain within the Pressure Suppression Pressure (PSP) limit.

o May anticipate Blowdown and directs actions to rapidly depressurize via turbine bypass valves Directs actions per LGA-004 if Sup Chamber pressure cannot be maintained below the PSP limit.(CT)

Verifies DW pressure at or above 1.77 psig.

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. (CT)

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 27 of 29 Event - 10

==

Description:==

Blowdown Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When ADS has been initiated or blowdown anticipated, Reactor Level within 20-50 inches, Containment pressure lowering and at the discretion of the Exam lead.

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 28 of 29 REFERENCES Procedure Rev Title

1. INPO 15-004 Operations Fundamentals

2. SOER 10-2 Engaged, Thinking Organizations

3. LOP-EH-04 18 SHIFTING PUMPS AND PRESSURE ADJUSTMENT IN THE ELECTRO

4. LOA-RR-101 38 UNIT 1, REACTOR RECIRCULATION SYSTEM ABNORMAL

5. LOR-1H13-P602-B507 20 Reactor Recirculation Pump 1A/1B Temperature

6. LOR-1H13-P603-A511 2

RWLCS Trouble

7. LOA-RD-101 21 Control Rod Drive Abnormal

8. LOR-1H13-P603-A503 8

CRD Hydraulic Accumulator Trouble

9. LOR-1H13-P603-A504 4

Control Rod Drive Drift Alarm

10. LGA-001 18 RPV Control

11. LGA-003 17 Primary Containment Control

12. LGA-004 9

RPV Blowdown

13. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.

14. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation

15. OP-AA-106-101 21 Significant Event Reporting

16. OP-LA-STA-1001 5

LaSalle Shift Technical Advisor (STA) Checklists

17. EP-AA-1005 Add. 3 3

Emergency Action Levels for LaSalle Station

18. EP-MW-114-100-F-01 J

Nuclear Accident Reporting System(NARS) Form

NRC 17-1-1 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 29 of 29 U1 SUPERVISOR TURNOVER Shift:

Date:

Mode:

OLR:

Work Week:

Days Today 1

Green 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.

• Swap to B EHC Pump at 1PM02J per LOP-EH-04 Comments, evolutions, problems, etc.

• Non-Div Workweek. OLR is Green

LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-2 Rev. 00 6/13/2018 DEVELOPED BY:

Coline Betken 10/12/18 Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:

Tyler Messner 10/12/18 Training Department Date APPROVED BY:

Joe Messina 10/12/18 Operations Representative Date

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 2 of 27 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-2 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Bypass Valve Surveillance. Following turnover the crew will commence LOS-TG-M4 and bypass valve #1 will operate normally.

2. Bypass Valve Fails open. When the crew performs the surveillance on bypass valve #2 the valve will not close. The crew will take action per LOA-EH-101 and lower Reactor Power.

3. Bypass Valve INOP. The Unit Supervisor will enter Tech Specs for a failed open bypass valve.

4. Off Gas Post Treat B Fails downscale. The crew will take action to bypass the failed PRM.

5. Spurious HPCS initiation. The crew will take action per LOA-PWR-101 to secure HPCS.

6. HPCS INOP. The Unit Supervisor will enter Tech Specs for HPCS being INOP.

7. TDRFP Oil Leak, Manual Trip. The crew will receive low oil pressure indications and receive field reports of an oil leak. The crew will take action to trip the 1B TDRFP and verify operation of the MDRFP.

8. Single MSIV Closure. D MSIV will close and the crew will take action to place RWLC in Single Element.

9. Multiple Rods Fail Full in, Hydraulic ATWS. When multiple rods scram full in the crew will take action to manually scram the reactor. This will lead to a hydraulic ATWS and crew will take action per LGA-010 and LGA-NB-01 to insert control rods and lower Reactor Power.

Critical Tasks

1) With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron or inserting control rods, to protect the primary containment within 2 minutes following Reactor Level 2 being reached (-55 inches).

2) With a reactor scram required, the reactor not shutdown, and conditions for ADS blowdown are met, or will be, INHIBIT ADS prior to initiation to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion.

3) During an ATWS with reactor power above 3% or unknown, RAPIDLY DROP LEVEL in the RPV to at least -

60 within 16 minutes.

4) During an ATWS with reactor power above 3% or unknown, and RPV level less than -60 HOLD RPV level between -60 and -150 on Wide Range.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 3 of 27 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

1. 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. Supervisory oversight role

2. Recognition and mitigation of risk

3. Worker performance

4. Tolerance of repetitive/long standing issues and degradation of standards

5. Operating Experience Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 17-1 NRC Exam

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 4 of 27 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION

1. Recall a full power IC

2. Place simulator in RUN

3. Load and run the SmartScenario file NRC 17-1-2.ssf

4. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/

Component Required Action REQUIRED ACTION Description Completion Time Expiration Date/Time N/A N/A N/A N/A N/A N/A

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

SCENARIO OUTLINE (NRC Evaluations Only)

Event No.

Malf.

No.

Event Type*

Event Description 1

none N (BOP)

Bypass Valve Surveillance 2

mms044 R (ATC)

Bypass Valve Fails Open 3

none T (US)

Bypass Valve INOP 4

mrm012 I (BOP)

Off Gas Post Treat B Fails Downscale 5

mnb078 C (BOP)

Spurious HPCS Initiation 6

none T (US)

HPCS INOP 7

g4c14g1y C (ATC)

TDRFP Oil Leak, Manual Trip 8

k1p40e12 C (ATC)

Single MSIV Closure 9

sri010/20/

20/40 mrd277 mrd278 M

Multiple Rods Scram Full-In, Hydraulic ATWS (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 5 of 27 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE) 769.00.01 During performance of tasks, dynamic learning activities, or formal evaluations, demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

762.04.00 Given an operating experience document, paraphrase the lessons learned and methods to prevent recurrence at LaSalle Station, as described in the training material.

614.010 During performance of tasks, apply the administrative requirements of PROCEDURE USE AND ADHERENCE EXPECTATIONS, IAW station procedures.

TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 31.014 Given plant conditions, perform control room actions to respond to a failure of automatic RWLCS, IAW station procedures.

61.006 Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto Initiation, IAW station procedures.

73.013 Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW station procedures.

77.046 Given plant conditions, perform Control Room actions to respond to a TDRFP low hydraulic pressure alarm, IAW station procedures.

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

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

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

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 6 of 27 RO - BOP/ASSIST 52.004 Given plant conditions, perform the Main Control Room actions to startup and operate the Combined Off Gas Post-Treatment Monitoring System, IAW station procedures.

61.006 Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto Initiation, IAW station procedures.

71.042 Given Unit Supervisor authorization, perform Control Room actions for main turbine generator monthly surveillances, IAW station procedures.

73.013 Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW station procedures.

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

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 7 of 27 SRO - UNIT SUPERVISOR 31.014 Given plant conditions, perform control room actions to respond to a failure of automatic RWLCS, IAW station procedures.

52.004 Given plant conditions, perform the Main Control Room actions to startup and operate the Combined Off Gas Post-Treatment Monitoring System, IAW station procedures.

61.006 Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto Initiation, IAW station procedures.

71.042 Given Unit Supervisor authorization, perform Control Room actions for main turbine generator monthly surveillances, IAW station procedures.

73.013 Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW station procedures.

77.046 Given plant conditions, perform Control Room actions to respond to a TDRFP low hydraulic pressure alarm, IAW station procedures.

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

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

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

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

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 8 of 27 Event - 1

==

Description:==

Bypass Valve Surveillance Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:

Automatic Actions: #1 Bypass Valve Opens and Closes Expected Annunciators: LOR-1PM02J-B304, Turbine Bypass Valve (BPV) 1/2/3/4/5 Open Key Parameter Response: Reactor Pressure Fluctuates Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor Reactor Power, Level and Pressure

• Provide peer checks as required 71.042 BOP Per LOS-TG-M4

• On the BV #1 screen, TEST Bypass Valve #1 as follows:

• PUSH the Test START pushbutton and OBSERVE:

• Bypass Valve #1 fully opens in approximately 10 seconds.

• Bypass Valve #1 exhibits Fast Open characteristics.

• Approximately 10 seconds after reaching full open, Bypass Valve #1 FULLY CLOSES.

• ALLOW the plant to stabilize for at least 2 minutes before testing the next bypass valve.

71.042 US

• Direct above actions

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 9 of 27 Event - 1

==

Description:==

Bypass Valve Surveillance Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:

Terminus: Continued

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 10 of 27 Event - 2

==

Description:==

Bypass Valve Fails Open Initiation: Per Lead Evaluator Cues:

Automatic Actions: #2 Bypass Valve Opens Expected Annunciators: LOR-1PM02J-B304, Turbine Bypass Valve (BPV) 1/2/3/4/5 Open Key Parameter Response: Reactor Pressure Fluctuates Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 73.013 ATC Per LOA-EH-101

• CHECK EHC is CONTROLLING reactor pressure.

• REFER TO LOA-PWR-101 while continuing.

• REDUCE Reactor power by lowering RR Flow until one of the following conditions exist:

• Core flow is 70 Mlbm/hr.

• Turbine Bypass Valves -CLOSED.

• As necessary, INSERT CRAMS or Control Rods in reverse sequence to ensure adequate margin to operational limits.

Per LOA-PWR-101

• CHECK RPS setpoints NOT exceeded.

• CHECK Reactor Power is < 100% RTP (3546 MWt) o REDUCE Power to < 100% RTP by using RR FCVs or Control Rods.

71.042 73.013 BOP Per LOS-TG-M4

• On the BV #2 screen, TEST Bypass Valve #2 as follows:

• PUSH the Test START pushbutton and OBSERVE:

• Bypass Valve #2 fully opens in approximately 10 seconds.

• Bypass Valve #2 exhibits Fast Open characteristics.

• Approximately 10 seconds after reaching full open, Bypass Valve #1 FULLY CLOSES. (NO)

Per LOA-EH-101

• REFER TO LOA-HD-101 while continuing.

• CHECK Turbine Bypass Valve(s) - OPERABLE.

• CHECK Turbine Bypass Valve(s) - OPEN.

• CHECK both 1H13-P603-A211 and A212 - NOT LIT.

71.042 73.013 US

• Set Manual Scram Criteria EHC not controlling Reactor Pressure

• DECLARE Turbine Bypass Valve(s) - INOPERABLE.

• Direct above actions

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 11 of 27 Event - 2

==

Description:==

Bypass Valve Fails Open Simulator Operator Actions none Simulator Operator Role Play As the EO/Field Supervisor, when requested to close 1B21-MSBPV2 (B.4.12), inform the crew that the Field Supervisor and RP will brief for the evolution.

Respond as QNE/System Engineering.

Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: continued

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 12 of 27 Event - 3

==

Description:==

Bypass Valve INOP Initiation: Continued Cues: Event 2 Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant conditions and update the crew as required

• Continue with actions of LOA-EH-101 BOP

• Monitor plant conditions and update the crew as required

• Continue with actions of LOA-EH-101 201.011 US o Notify QNE to make applicable LCO 3.2.2 limits for an inoperable Main Turbine Bypass System as specified in the COLR

• Enter TS 3.7.7 Required Action

• A.1 Satisfy the requirements of the LCO in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> o Refer to TS 3.3.1.1 and TS 3.3.4.1

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 13 of 27 Event - 3

==

Description:==

Bypass Valve INOP Simulator Operator Actions none Simulator Operator Role Play Respond as QNE.

Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 14 of 27 Event - 4

==

Description:==

Off Gas Post Treat B Fails Downscale Initiation: Per Lead Evaluator Cues:

Automatic Actions: none Expected Annunciators: 1N62-P600-B208, Off Gas Post-Treatment Radiation Trouble Key Parameter Response: B OG Post Treat Rad Monitor Downscale Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor Reactor Power, Level and Pressure and update the crew as required 52.004 BOP Per LOR-1N62-P600-B208

• IF R1200 is alarming, Then CHECK OG Post Treat PRM's, 1D18-K601A/B, for INOP/DWNSCL alarms and VERIFY proper operation per LOP-PR-03, Startup and Operation of Combined Off Gas Post-treatment Monitoring System.

• NOTIFY Unit Supervisor

• NOTIFY Rad Protection Department to check 0PL99J (OG BLDG 690') for proper

• operation and to RESET any alarms.

• IF OG Post-Treat PRM is INOP, Then REFER to ODCM Section 12.2.2.A.

• IF required to place the channel in trip to comply with ODCM Required Actions:

PLACE the 1A(B) Off Gas Post Treatment Radiation Monitor mode switch in standby.

52.004 US

• Direct above actions

• Enter ODCM12.2.2

• Required action C.1 Place Instrument Channel in Trip in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 15 of 27 Event - 4

==

Description:==

Off Gas Post Treat B Fails Downscale Simulator Operator Actions When directed by the Lead Evaluator Release Event 4 Simulator Operator Role Play Respond as RP, when asked to check for proper operation of 0PL99J, wait 1 minute and report that it is operating normally and alarms are reset Respond as an EO, when order to check the status of 1AP66E-C5 (134Y-1 C5) and 1AP66E-D1 breaker 6 (134Y-1 D1 Breaker 6), wait 1 minute and report that they are closed.

Respond as an EO, when order to check the status of 0PL99J F1 fuse, wait 1 minute and report that the fuse is not blown.

Respond as required.

Floor Instructor Notes/OPEX/TRs Verifiable action of BOP occurs if SRO recognizes ODCM entry requirement and orders 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action requirement performed.

Terminus: When the B OG Post Treat Rad Monitor is placed in trip and at the discretion of the Lead Evaluator.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 16 of 27 Event - 5

==

Description:==

Spurious HPCS Initiation Initiation: Per Lead Evaluator Cues:

Automatic Actions: HPCS Pump Starts Expected Annunciators: 1H13-P601-A208, Reactor Vessel Water Level 2 Lo-Lo; 1H13-P601-A308, Reactor Vessel Water Level 2 Lo-Lo Key Parameter Response: HPCS Injection Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 61.006 ATC Per LOR-1H13-P601-A208/A308

• CHECK Reactor Vessel Water Level indication on panels 1H13-P601 and 1H13-P603.

• If Reactor Vessel Water Level is actually low, REFER to LGA-001, RPV Control and LGA-003, Primary Containment Control. (NO)

Per LOA-PWR-101

• STOP any power increase.

• STABILIZE the Unit.

o RUN OD-20.

61.006 BOP Per LOR-1H13-P601-A208/A308 o If Shutdown of HPCS after Auto Initiation is required, REFER to LOP-HP-04 Per LOA-PWR-101

• If there is a spurious HPCS injection, IMMEDIATELY SHUTDOWN HPCS.

o VERIFY lineup of HPCS with LOP-HP-04, Shutdown of HPCS After an Automatic Initiation.

61.006 US

• Direct above actions

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 17 of 27 Event - 5

==

Description:==

Spurious HPCS Initiation Simulator Operator Actions When directed by the Lead Evaluator Release Event 5 Simulator Operator Role Play Respond as IMD As the EO sent to investigate the HPCS initiation report that no abnormal conditions are present.

Respond as required Floor Instructor Notes/OPEX/TRs Note: HPCS will be INOP but available.

Terminus: continued

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 18 of 27 Event - 6

==

Description:==

HPCS INOP Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:

Automatic Actions: HPCS Pump Starts Expected Annunciators: 1H13-P601-A208, Reactor Vessel Water Level 2 Lo-Lo; 1H13-P601-A308, Reactor Vessel Water Level 2 Lo-Lo Key Parameter Response: HPCS Injection Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant conditions and update the crew as required BOP

• Monitor plant conditions and update the crew as required 201.011 US Enter TS 3.3.5.1

• Required Action B.2 Declare HPCS inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS Initation Capabilty

• Required Action B.3 Place channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• Enter TS 3.5.1

• Required Action B.1 Verify by adminastrative means RCIC System is OPERABLE when RCIC is required to be operable immediately

• Required Action B.2 Restore HPCS to OPERABLE status in 14 days o

Enter TS 3.8.1 (Note in 3.8.1 states not required with HPCS INOP) o Required Action C.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuits in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter o Required Action C.2 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery o Required Action C.3.1 Determine OPERABLE DG(s) are not inoperable due to common cause failure in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR o Required Action C.3.2 Perform SR 3.8.1.2 for OPERABLE DG(s) in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> o Required Action C.4 Restore required DG(s) to OPERABLE status

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 19 of 27 Event - 6

==

Description:==

HPCS INOP Simulator Operator Actions none Simulator Operator Role Play Respond as IMD Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 20 of 27 Event - 7

==

Description:==

TDRFP Oil Leak, Manual Trip Initiation: Per Lead Evaluator Cues:

Automatic Actions: none Expected Annunciators: 1PM03J-A104, Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low Key Parameter Response: Lowering B TDRFP Oil Pressure Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 77.046 ATC Per LOR-1PM03J-A104

• DETERMINE which Turbine Driven Reactor Feedwater Pump (TDRFP) has Low Bearing Oil Pressure.

• If entire Turbine Oil System is failing, immediately REDUCE power per LGP-3-1 and/or LGP-2-1 to within capacity of MDRFP. ENTER LOA-TO-101. (NO) o PLACE an idle Reactor Feedwater Pump in service per procedure LOP-FW-03, Startup of Motor Driven Reactor Feed Pumps (MDRFP), or LOP-FW-04, Startup of a Turbine Driven Reactor Feed Pump (TDRFP).

o SHUTDOWN affected TDRFP per procedure LOP-FW-05, Shutdown of Turbine Driven Reactor Feed Pump.

• DISPATCH operator to INSPECT Turbine Bearing Oil System for abnormalities and DETERMINE cause for Low Bearing Oil Pressure Alarm Per OP-LA-101-111-1002

• Trip 1B TDRFP

• Verfiy MDRFP Auto starts

• Monitor Reactor Level BOP

• Monitor plant parameters and update the crew as required 77.046 US

• Direct above actions

• Set Manual Scram Criteria of Reactor Level outside of 20-50 and/or not in control

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 21 of 27 Event - 7

==

Description:==

TDRFP Oil Leak, Manual Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 7 When directed by the crew Release Isolate 1B TDRFP Oil Simulator Operator Role Play When an EO is dispatched to investigate the B TDRFP, wait 1 minute and report that there an oil leak from one of the bearings on the1B TDRFP and that you cant get close enough to see if you can isolate it or locally trip it.

As an EO, when requested to perform post start checks of the MDRFP, wait 1 minute and report post start checks are SAT.

AFTER the TDRFP is tripped if the crew orders the EO to isolate the oil side of 1B TDRFP by closing 1TO061-HP/LP release the above action and after 1 minute inform the crew that oil to 1B TDRFP is isolated.(M-84 Sh. 4)

Respond as required Floor Instructor Notes/OPEX/TRs Note: The Oil pressure will decrease gradually until it reaches 5.5 psig which is at the alarm set point and above the automatic trip set point of 4 psig.

Terminus: When 1B TDRFP is tripped and at the discretion of the Lead Evaluator.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 22 of 27 Event - 8

==

Description:==

Single MSIV Closure Initiation: Per Lead Evaluator Cues:

Automatic Actions: None Expected Annunciators: 1H13-P603-B202, Main Steam Isolation Valves C and D Not Full Open Key Parameter Response: 1D Outboard MSIV Closes, RPV Level Rises in 3 Element Control Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 31.014 ATC Per LOR-1H13-P603-B202

• If any steam line is affected, PLACE RWLC in SINGLE Element control.

• At 1H13-P601 panel, INSPECT limit switch indications for 1B21-F022C/D and 1B21-F028C/D:

• If MSIV C Inboard and/or Outboard shows dual indication, TURN handswitch to full OPEN position.

• If MSIV D Inboard and/or Outboard shows dual indication, TURN handswitch to full OPEN position.

• If applicable, STOP all surveillance testing related with Main Steam System.

• ENTER LOA-MS-101 for MSIV closure.

• If RPS Subchannel A2 tripped (NO)

Per LOA-MS-101

• CHECK all MSIVs - OPEN (NO)

• If a single MSIV is closed enter LOA-FW-101 to transfer RWLC to Single Element.

• Using Reactor Recirc Flow, LOWER core flow to 70 Mlbm/hr OR 75% Reactor Power

• CONTACT QNE for further direction or guidance to reduce power further by control rod insertion if power is still greater than 75%.

• CONTACT QNE to determine if current degraded condition is covered by the active CMSS Thermal Limit Set.

Per LOA-FW-101

• CHECK RPV level is 20 to 50 and/or IN CONTROL.

• CHECK single MSIV NOT closed, or failure of automatic RWLC not caused by failure of steam flow instruments. (NO)

• SELECT Single Element at the RWLC Level Setpoint Station BOP

• Monitor plant parameters and update the crew as required 31.014 US

• Direct above actions

• Set Manual Scram Criteria of Reactor Level outside of 20-50 and/or not in control

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 23 of 27 Event - 8

==

Description:==

Single MSIV Closure Simulator Operator Actions When directed by the Lead Evaluator Release Event 8 Simulator Operator Role Play Respond as QNE, inform the crew that you will report to the Control Room If sent to Inspect the MSIV, as an EO/Field Sup inform the crew that we will make preps to inspect the MSIV locally.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: While in 3 Element Control RWLC will continue itinerary Terminus: When RWLCS is in Single Element Control and at the discretion of the Lead Evaluator.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 24 of 27 Event - 9

==

Description:==

Multiple Rods Scram Full-In, Hydraulic ATWS Initiation: Per Lead Evaluator Cues: Key Parameter Response: Multiple Rods Scram Full-In Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 431.000 431.010 433.000 434.000 ATC 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 Recognize that all rods did not insert and notify US (Hydraulic ATWS)

Per the POWER Leg of LGA-010 If control rods remain out:

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

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

Method 3 Single Rod Insert Bypass RWM Place CRD Drive Flow Trip Circuit in BYPASS Insert control rods using Continuous Insert or Insert Button Per the Level Leg of LGA-010

• 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)

RUNBACK Reactor Recirculation flow to minimum If power is >3% then TRIP RR Pumps Method 4 Reset Scram/Drain SDV/Re-Scram Reset Scram/Drain SDV/Re-Scram 433.000 BOP Per LGA-010 Inhibit ADS (CT)

Prevent injection from HPCS, LPCS and LPCI (CT)

Per the PRESSURE Leg STABILIZE pressure <1059 psig using main turbine bypass valves VERIFY required automatic actions occur

• May request LGA-RH-101 jumper installation 431.000 433.000 434.000 431.020 431.010 US Directs Inhibit ADS (CT)

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

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

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

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

• May direct Method 3 Single Rod Insert

• May direct Method 4 Reset Scram/Drain SDV/Re-Scram

• Directs bypassing MSIV low level isolation per LGA-MS-01

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 25 of 27

==

Description:==

ATWS, After Control rods inserted Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 304.010 433.000 ATC When directed, stops SBLC pump VERIFY Main Turbine and Generator Trip STABILIZE Reactor Pressure <1020 psig BOP Monitors control room panels and notifies the SRO of any unusual or unexpected conditions 433.000 US When rods inserted, direct securing SBLC injection When rods inserted, exits LGA-010 and enters LGA-001 Directs water level band of +11" to +59.5" (+20" to +50" preferred)

Event - 9

==

Description:==

Multiple Rods Scram Full-In, Hydraulic ATWS Simulator Operator Actions When directed by the Lead Evaluator Release Event 9 When directed by the Crew Release LGA-MS-101 When directed by the Crew Release LGA-NB-01 When directed by the Crew Release LGA-RH-101 Simulator Operator Role Play Role Play Unit 2 NSOs as necessary to complete LGA-NB-01, LGA-MS-101, and LGA-RH-101 ATWS Actions Respond as required Floor Instructor Notes/OPEX/TRs Terminus: LGA-NB-01 in progress to insert control rods and upon approval of Lead Examiner.

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 26 of 27 REFERENCES Procedure Rev Title

1. INPO 15-004 Operations Fundamentals

2. SOER 10-2 Engaged, Thinking Organizations

3. LOS-TG-M4 9

TURBINE BYPASS VALVE SURVEILLANCE

4. LOA-EH-101 35 UNIT 1 EHC ABNORMAL

5. LOA-PWR-101 14 UNIT 1 UNPLANNED REACTIVITY ADDITION

6. LOR-1PM02J-B304 5

Turbine Bypass Valve (BPV) 1/2/3/4/5 Open

7. LOR-1N62-P600-B208 5

Off Gas Post-Treatment Radiation Trouble

8. LOR-1H13-P601-A208 3

Reactor Vessel Water Level 2 Lo-Lo

9. LOR-1H13-P601-A308 3

Reactor Vessel Water Level 2 Lo-Lo

10. LOR-1PM03J-A104 1

Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low

11. LOR-1H13-P603-B202 3

Main Steam Isolation Valves C and D Not Full Open

12. LOA-MS-101 13 UNIT 1 MAIN STEAM SYSTEM ABNORMAL

13. LOA-FW-101 11 REACTOR LEVEL/FEEDWATER PUMP CONTROL TROUBLE

14. LGA-001 18 RPV Control

15. LGA-010 18 Failure to Scram

16. LGA-MS-101 2

Using Main Condenser as Heat Sink in ATWS

17. LGA-RH-101 4

Alternate Vessel Injection Using Shutdown Cooling Return

18. LGA-NB-01 19 Alternate Rod Insertion

19. OP-LA-101-111-1002 73 LaSalle Operations Philosophy Handbook.

20. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation

21. OP-AA-106-101 21 Significant Event Reporting

22. OP-LA-STA-1001 5

LaSalle Shift Technical Advisor (STA) Checklists

23. EP-AA-1005 Add. 3 3

Emergency Action Levels for LaSalle Station

24. EP-MW-114-100-F-01 J

Nuclear Accident Reporting System(NARS) Form

NRC 17-1-2 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 27 of 27 U1 SUPERVISOR TURNOVER Shift:

Date:

Mode:

OLR:

Work Week:

Days Today 1

Green 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 LOS-TG-M4 None Equipment removed from service or currently unavailable None None Grid Status is Green Comments, evolutions, problems, etc.

• Perform LOS-TG-M4 on all Bypass Valves

• Generation Dispatch has been Notified and a Gen Manager Ticket has been activated Comments, evolutions, problems, etc.

• Non-Div Workweek. OLR is Green

LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-3 Rev. 00 6/14/2018 DEVELOPED BY:

Colin Betken 10/2/18 Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:

Tyler Messner 10/2/18 Training Department Date APPROVED BY:

Joe Messina 10/2/18 Operations Representative Date

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 2 of 31 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-3 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Upshift RR Pumps IAW LGP-1-1. The crew will upshift B RR Pump per LOP-RR-05.

2. Raise Reactor Power IAW LGP-1-1. The crew will raise power using RR FCVs at a rate of 300 MWe/hr and above 61 Mlbm/hr.

3. B; FCV Fails Closed. After the crew raises Reactor Power using FCVs the B FCV will Fail closed causing a flow mismatch.

4. Flow Mismatch. The Unit Supervisor will make a Tech Spec call for the Flow Mismatch.

5. 1A VR Exhaust Fan Trip. The crew will take action to start the 1C VR Exhaust fan and verify all parameters are normal.

6. 1A GC Pump Trip, Standby Fails to Auto start. The crew will take action to start the standby GC Pump and verify that a Generator Runback has not occurred.

7. SBLC Tank Low Level. The crew will receive an annunciator to indicate that the SBLC Tank level is low, upon investigation it is found to be a leaking valve and the Unit Supervisor will make a Tech Spec Call for SBLC.

8. FRV Fails Open. With the MDRFP online the FRV will fail open and the crew will take action per LOA-FW-101 to control level with 1FW003, MDRFP Discharge Stop Valve.

9. An EHC Leak will cause the crew to the crew to scram. The crew will scram and follow-up by either taking EHC Pumps to PTL or allowing the Turbine to trip on low EHC pressure.

10. Electrical ATWS. When the crew scrams the unit A RPS will fail and ARI will insert rods.

11. Main Steam Line Break Inside Containment. Following all rods inserting by ARI a leak on the Main Steam Line will develop inside Containment.

Critical Tasks

1) With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by inserting control rods, to protect the primary containment.

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 prior to starting Drywell sprays.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 3 of 31 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

1. 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. Supervisory oversight role

2. Recognition and mitigation of risk

3. Worker performance

4. Tolerance of repetitive/long standing issues and degradation of standards

5. Operating Experience Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 17-1 NRC Exam

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 4 of 31 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION

1. Recall IC 354 Password 0354

2. Place simulator in RUN

3. Load and run the SmartScenario file 17-1-3.ssf

4. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/

Component Required Action REQUIRED ACTION Description Completion Time Expiration Date/Time N/A N/A N/A N/A N/A N/A

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

SCENARIO OUTLINE (NRC Evaluations Only)

Event No.

Malf.

No.

Event Type*

Event Description 1

none N (BOP)

Reactor Recirc Upshift 2

none R (ATC)

Raise Reactor Power using RR FCVs 3

k2l12p1l C (ATC)

B FCV fails Closed 4

none T (US)

Flow Mismatch 5

k7d18wpg C (BOP) 1A VR Exhaust Fan Trip 6

mgc001 mgc004 C (BOP) 1A GC Trip, Standby Fails to Auto Start 7

r0744 T (US)

SBLC Tank Level Low 8

mcf086 C (ATC)

FRV Fails Open 9

mms007 M

EHC Leak, Scram 10 mrp017 M

Electrical ATWS, ARI inserts rods 11 mcf034 M

Main Steam Line Break Inside Containment (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 5 of 31 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE) 769.00.01 During performance of tasks, dynamic learning activities, or formal evaluations, demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

762.04.00 Given an operating experience document, paraphrase the lessons learned and methods to prevent recurrence at LaSalle Station, as described in the training material.

614.010 During performance of tasks, apply the administrative requirements of PROCEDURE USE AND ADHERENCE EXPECTATIONS, IAW station procedures.

TASKS RO - ATC 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.

22.015 Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or both RR pumps, IAW station procedures.

23.003 Given initial plant conditions, Respond to a Reactor Recirc Flow Control System failure to minimum demand, IAW station procedures.

23.004 Given initial plant conditions, Respond to a Reactor Recirc Flow Control Valve lockup, IAW station procedures.

28.018 Given plant conditions, perform the in plant actions to respond to SBLC tank LVL Hi/Lo, IAW station procedures.

78.010 Given plant conditions, complete Control Room actions to respond to a failure of the MDRFP FRV/Low Flow FRV, IAW station procedures.

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

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 6 of 31 RO - BOP/ASSIST 9.001 Given plant conditions, perform the Main Control Room actions for a loss of Generator Stator Water Cooling, IAW station procedures.

22.002 Given Unit Supervisor authorization, Transfer Reactor Recirc Pumps from slow to fast speed, IAW station procedures 73.019 Given plant conditions, perform the in plant actions for a hi/lo level in the EHC reservoir, IAW station procedures.

118.008 Given plant conditions, adjust reactor building to outside differential pressure, IAW station procedures.

419.000 Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig, IAW LGA-003.

419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.

419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.

419.040 Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, IAW LGA-004.

421.000 Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool temperature less than HCTL, IAW LGA-003.

421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.

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

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 7 of 31 SRO - UNIT SUPERVISOR 9.001 Given plant conditions, perform the Main Control Room actions for a loss of Generator Stator Water Cooling, IAW station procedures.

22.002 Given Unit Supervisor authorization, Transfer Reactor Recirc Pumps from slow to fast speed, IAW station procedures 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.

22.015 Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or both RR pumps, IAW station procedures.

23.003 Given initial plant conditions, Respond to a Reactor Recirc Flow Control System failure to minimum demand, IAW station procedures.

23.004 Given initial plant conditions, Respond to a Reactor Recirc Flow Control Valve lockup, IAW station procedures.

28.018 Given plant conditions, perform the in plant actions to respond to SBLC tank LVL Hi/Lo, IAW station procedures.

73.019 Given plant conditions, perform the in plant actions for a hi/lo level in the EHC reservoir, IAW station procedures.

78.010 Given plant conditions, complete Control Room actions to respond to a failure of the MDRFP FRV/Low Flow FRV, IAW station procedures.

118.008 Given plant conditions, adjust reactor building to outside differential pressure, IAW station procedures.

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

419.000 Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig, IAW LGA-003.

419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.

419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.

419.040 Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, IAW LGA-004.

421.000 Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool temperature less than HCTL, IAW LGA-003.

421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.

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

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 8 of 31 Event - 1

==

Description:==

Reactor Recirc Upshift Initiation: Per Lead Evaluator, following the crew assuming the shift Cues: Turnover Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor Reactor Power, Level and Pressure

• Provide peer checks as requird 22.002 BOP Per LGP-1-1

• TRANSFER Recirculation Pumps to fast speed per LOP-RR-05, Changing Reactor Recirc Pump Speed From Slow to Fast Speed.

Per LOP-RR-05

• UNLOCK the desired RR Flow Control Valve as Follows:

• At Control Room Panel 1(2)H13-P602 VERIFY Individual Loop M/A Transfer Station 1B33-R611A/B is set as follows:

MANUAL light ON.

Servo Error at zero.

• DEPRESS valve INHIBIT RESET push-button for Loop B and CHECK MOTION INHIBIT light goes off.

• DEPRESS Lower pushbutton on Reactor Recirc Loop B M/A Station for loop in which pump speed will be changed until BOTH of the following conditions are met:

1B33-F060B, HI Speed Start Permissive indicating light 1B33-DS02B is ON Flow Control Valve minimum position is < 20% indicated.

• PLACE second pump's Breaker 3B Control Switch to START position and RELEASE.

• OBSERVE the following:

1B breaker (LFMG Drive Motor) opens.

2B breaker (LFMG Generator) opens.

3B breaker (RR Motor Bkr) closes after pump speed decreases to 350 rpm.

Pump speed increases to approximately 1750 rpm.

Reactor level drops, then returns to level controller setpoint.

Reactor power initially increases, then stabilizes.

Loop A flow is approximately the same as Loop B flow.

• At the 1DS001 Operator Station RRFC Interlocks screen, PLACE both A and B RR Interlocks in NORMAL 22.002 US

• Direct above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 9 of 31 Event - 1

==

Description:==

Reactor Recirc Upshift Simulator Operator Actions none Simulator Operator Role Play Acknowledge reports as required Floor Instructor Notes/OPEX/TRs Note: The crew should raise power from step E.2.6 of LOP-RR-05 which sends them back to LGP-1-1.

The crew may receive the SAT Under-voltage annunciator, this is expected during an upshift due to the load transient.

LPRM Downscales may come in and clear, this expected during the start-up due to the rod configuration.

Terminus: continued

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 10 of 31 Event - 2

==

Description:==

Raise Reactor Power using RR FCVs Initiation: Per Lead Evaluator Cues: Turnover Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC Per LOP-RR-07

• VERIFY AUTO light on A AND B Recirculation Loop Flow Controller M/A Station is ON.

• DEPRESS the Ganged Flow Setpoint Station RAISE/LOWER pushbutton(s) as required.

• If FCV Position is 60%, then START RECORDING RR Pump Seal Pressures and Temperatures per Attachment C.

BOP Per LOP-RR-07

• Monitor FCV Position demand signals to allow for immediate recognition and communication of an abnormal response US

• Direct above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 11 of 31 Event - 2

==

Description:==

Raise Reactor Power using RR FCVs Simulator Operator Actions none Simulator Operator Role Play Acknowledge reports as required.

Floor Instructor Notes/OPEX/TRs Terminus: When 100 MWe power has been raised per the Lead evaluator

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 12 of 31 Event - 3

==

Description:==

B FCV fails Closed Initiation: Per Lead Evaluator Cues:

Automatic Actions: B FCV Closing Expected Annunciators: None Key Parameter Response: Lowering MWe and lowering Core Flow Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 22.008 22.015 23.003 23.004 ATC Per LOA-RR-101

• CHECK FCV position -STABLE.

• Lock up FCV.

• If OPRM inop and in or near Regions 1 or 2, PERFORM Subsection B.1, Thermal Hydraulic Instability, while continuing below.

• CHECK recirculation loop jet pump flows - LESS THAN TECH SPEC MISMATCH.

• At 1DS001, initiate TADS by DEPRESSING TDR icon.

o Perform section B.7 to unlock the FCV o Perform section B.10 to match loop flows BOP

• Monitor plant conditions and update the crew as required.

22.008 22.015 23.003 23.004 US

• Direct above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 13 of 31 Event - 3

==

Description:==

B FCV fails Closed Simulator Operator Actions When directed by the Lead Evaluator Release Event 3 Simulator Operator Role Play As an EO, when sent to investigate the 1B RR HPU, wait 2 minutes and report that you see no reason for FCV malfunction.

Acknowledge reports as required.

Floor Instructor Notes/OPEX/TRs Terminus: continued

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 14 of 31 Event - 4

==

Description:==

Flow Mismatch Initiation: Event 3 Cues: Event 3 Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Continue with actions of Event 3 BOP

• Continue with actions of Event 3 201.011 US

• Enter Tech Spec 3.4.1

• Required Action B.1 Declare the recirculation loop with lower flow to be not in operation

• Supervise above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 15 of 31 Event - 4

==

Description:==

Flow Mismatch Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:

TECH SPEC MISMATCH:

Within 5.425 Mlb/hr as read from 1B21-R611A/B, if core flow is greater than or equal to 75.95 Mlbm/hr.

Within 10.85 Mlb/hr as read from 1B21-R611A/B, if core flow is less than 75.95 Mlbm/hr.

TS 3.4.2 RA A.1 may be applied if the FCV is declared INOP.

Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 16 of 31 Event - 5

==

Description:==

1A VR Exhaust Fan Trip Initiation: Per Lead Evaluator Cues:

Automatic Actions: 1A VR Exhaust Fan Trip Expected Annunciators: 1PM06J-A305, Reactor Building Ventilation Exhaust Fan 1VR02CA Auto Trip Key Parameter Response: Rising Reactor Building Differential Pressure Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant parameters and update the crew as required.

118.008 BOP Per LOR-1PM06J-A305

• Suspend IMFs and OPDRVs

• If at least oe exhaust fan is running, then IMMEDIATELY START standby VR fan 1VR02CC

• MONITOR temperature as needed

• Dispatch an operator to SWGR 131X, Comp 403C 118.008 US

• Direct above actions

• Monitor for LGA-002 entry conditions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 17 of 31 Event - 5

==

Description:==

1A VR Exhaust Fan Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 5 Simulator Operator Role Play When sent to investigate the fan breaker, as an EO, wait 2 minutes and report that the breaker tripped on overcurrent.

Respond as required.

Floor Instructor Notes/OPEX/TRs NOTE: TS 3.6.4.1 RA A.1 may be entered if the crew observes RB D/P greater than -0.25 prior to starting the standby fan.

This Event is intended for the BOP.

Terminus: when the standby VR exhaust fan has been started and at the discretion of the Lead Evaluator.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 18 of 31 Event - 6

==

Description:==

1A GC Pump Trip, Standby Fails to Auto start Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:

Automatic Actions: 1A GC Pump Trip Expected Annunciators: 1PM02J-B310, Generator Stator Coolant Runback Circuit Energized Key Parameter Response: Lowering GC Pump Amps Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant parameters and update the crew as required 9.001 BOP Per LOA-GC-101

• CHECK a Generator Stator Cooling Pump 1GC02P/3P is running.

• START a Generator Stator Cooling Pump 1GC03P.

• Continuously CHECK Generator Runback NOT initiated

• DETERMINE cause of Stator Cooling degradation/ loss and RESTORE Cooling.

9.001 US

• Set manual scram criteria of GC runback initated

• Direct above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 19 of 31 Event - 6

==

Description:==

1A GC Pump Trip, Standby Fails to Auto start Simulator Operator Actions When directed by the Lead Evaluator Release Event 6 Simulator Operator Role Play As the EO in the field, when sent to investigate the tripped Pump and Breaker, wait 2 minutes and report that the breaker tripped on overcurrent and there is an acrid odor.

As EO, when asked, report that post start checks of the 1B GC Pump are sat.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: The Runback Circuit energized annunciator does not mean that a generator runback is occurring. There is a 15 second time delay from the annunciator coming in and the generator runback to initiate. If the condition which caused the runback circuit to energize clears within the 15 second time delay, a generator runback will not occur.

Terminus: When the standby GC Pump is running and at the discretion of the Lead Evaluator.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 20 of 31 Event - 7

==

Description:==

SBLC Tank Low Level Initiation: Per Lead Evaluator Cues:

Automatic Actions: none Expected Annunciators: 1H13-P603-A205, Standby Liquid Control Tank 1C41-A001 Level High/Low Key Parameter Response: Lowering SBLC Tank level.

Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 28.018 ATC Per LOR-1H13-P603-A205

• CHECK Standby Liquid Control Tank Level is at one of alarm setpoints.

• T-Square method (preferred)

• DISPATCH operator to Standby Liquid Control Tank area to VERIFY proper air flow thru Standby Liquid Control Tank Instrument Air Pressure Indicating Controller 1C41-R004.

• START Special Log to monitor SBLC Tank level locally until level restored to normal band.

• Low Level: Consult Chemistry Lead for recommendations on restoring from low level. Available options are to add water/sodium pentaborate or simply water to the tank. The Chemistry Lead trends solution tank level/concentration and can assist in raising level and maintain optimum point on the Technical Specification concentration vs. volume graph. Level may be raised per LOP-SC-04, "SBLC Solution Tank Filling."

BOP

• Monitor plant conditions and update the crew as required 28.018 US

• Direct above actions

• Enter Tech Spec 3.1.7

• Required Action A.1 Restore SLC subsystem to OPERABLE status within 7 days

• Required Action B.1 Restore one SLC subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 21 of 31 Event - 7

==

Description:==

SBLC Tank Low Level Simulator Operator Actions When directed by the Lead Evaluator Release Event 7 When directed by the crew to refill the SBLC Tank (After TS Call)

Release SBLC Low Level Clear Simulator Operator Role Play As an EO, when asked to investigate the low level alarm, wait 1 minute and report, There was a leak below the level glass and it stopped when I took the root valve (1C41-F310) to the closed direction, there was a quarter turn of movement. The leak has stopped and all water in is contained in the skid. No drums are overflowing. (M-99)

As the EO in the field, when ordered to check SBLC Tank level, wait 2 minutes and report that Tank Level is 4700 gallons via T-Square method and 1C41-R004 flow is normal.

As Chemistry when asked, report that the last logged Concentration of the Unit 1 SBLC tank, report that it was 13%.

As the Chemistry Lead, when asked, inform the crew that you recommend refilling the SBLC Tank with water to 5000 Gallons with water only.

When ordered to refill tank follow the above actions to clear the alarm and wait 1 minute report that level is 5000 gallons.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: If the tank is not refilled it will not affect the Event 10 because ARI will work.

Terminus: Following the Tech Spec call and at the discretion of the Lead Evaluator

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 22 of 31 Event - 8

==

Description:==

FRV Fails Open Initiation: Per Lead Evaluator Cues:

Automatic Actions: none Expected Annunciators: 1H13-P603-A511, RWLCS Trouble Key Parameter Response: Reactor Level Fluctuates and MDRFP Flow will go up Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 78.010 ATC Per LOR-1H13-P603-A511

• At the 1DS001 Operation Station Event List, Check alarm message. (FRV Pos Err)

• REFER to LOP-FW-16 to determine cause of alarm and required actions.

Per LOP-FW-16

• VERIFY proper operation of the FRV

• ENTER LOA-FW-101 Per LOA-FW-101

• CHECK RPV level is 20 to 50 and/or IN CONTROL.

• CHECK FRV lockout - RESET.

• CHECK FRV operating - NORMALLY

• If FRV is stuck open, THROTTLE 1FW003, C MDRFP Discharge Stop Valve to control flow.

• If desired, attempt to establish flow with the LFFRV.

BOP

• Monitor plant conditions and provide peer checks as required 78.010 US

• Set manual scram criteria outside of 20-50 and/or not in control

• Direct above actions

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 23 of 31 Event - 8

==

Description:==

FRV Fails Open Simulator Operator Actions When directed by the Lead Evaluator Release Event 8A Following the field report of the status of the FRV.

Release Event 8B Simulator Operator Role Play As the EO in the Field, When directed to investigate the FRV, wait 1 minute and report, the feedback arm has fallen off the FRV.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note:

Allow time for the crew to brief in order to determine level control following scram.

Terminus: Following the crew taking control of level using 1FW003 and at the discretion of the Lead Evaluator.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 24 of 31 Event - 9

==

Description:==

EHC Leak, Scram Initiation: Per Lead Evaluator Cues:

Automatic Actions:

Standby EHC Pump starts (1300 psig EHC Fluid Pressure)

Turbine Trip (1100 psig EHC Fluid Pressure)

Expected Annunciators: 1PM02J-B505, EHC MINOR TROUBLE Key Parameter Response: EHC Fluid Pressure lowering Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 304.010 ATC

• Manually Scram the Unit 73.019 BOP Per LOR-1PM02J-B505

• CHECK EHC Workstation alarm screen

• Refer to LOP-EH-11 Per LOP-EH-11

• Dispatch an oerator to look for leaks

• If reservoir level reaches +1 inch, then PLACE both EHC pumps in PTL to prevent pump damage. (The EHC pump suction line is approximately 1 inch from the bottom of the reservoir with the end of the suction pipe cut at a 45 degree angle. Pumps must be secured prior to loss of suction to prevent damage).

73.019 US

• Direct above actions o Establish critical parameter EHC Pressure/Resovoir Level

• Order the crew to manuall scram the reactor

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 25 of 31 Event - 9

==

Description:==

EHC Leak, Scram Simulator Operator Actions When directed by the Lead Evaluator Release Event 9 When directed by the Crew Release Open 1EH-FV1 Simulator Operator Role Play As the EO sent to investigate the leak, wait 1 minute and report that there is a large leak coming from the upstream side of the A EHC Pump suction valve and is not isolable.

If ordered to open 1EH-FV1, perform the above action, wait 1 minute and report 1EH-FV1 is open.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: The crew may either depressurize EHC or close MSIVs. When the Leak commences, it will be what controls reactor pressure.

Terminus: continued.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 26 of 31 Event - 10

==

Description:==

Electrical ATWS, ARI inserts rods Initiation: Event 9 Cues: Event 9 Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 419.000 304.010 414.000 419.020 419.030 421.000 421.010 431.000 431.010 ATC

• When directed, manually scrams the reactor

• ARM and DEPRESS Scram Pushbuttons

• PLACE Reactor Mode Switch in SHUTDOWN

• INSERT IRMs and SRMs

• CHECK Control Rods INSERTED and Power Decreasing (NO)

• Insert rods using ARI (CT)

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

• VERIFY Reactor Recirculation Pumps have downshifted

• VERIFY Main Turbine and Generator Trip

• STABILIZE Reactor Pressure <1020 psig BOP

• Take action per OP-LA-103-102-1002 431.000 431.010 US

• Direct above actions

• Enter LGA-001 and LGA-010

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 27 of 31 Event - 10

==

Description:==

Electrical ATWS, ARI inserts rods Simulator Operator Actions none Simulator Operator Role Play Respond as required.

Floor Instructor Notes/OPEX/TRs Note: The crew may either depressurize EHC or close MSIVs. When the Leak commences, it will be what controls reactor pressure.

Terminus: continued.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 28 of 31 Event - 11

==

Description:==

Main Steam Line Break Inside Containment Initiation: Automatic Cues:

Automatic Actions: ECCS Initiation Expected Annunciators: 1H13-P603-B501, Primary Containment Pressure Hi/Lo Key Parameter Response: Rising Containment Pressure Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC Control RPV Level and Pressure as directed by the Unit Supervisor 419.000 304.010 414.000 419.020 419.030 421.000 421.010 BOP To prevent losing Chamber Spray/ECCS runout with DW Spray prior to 500 psig.

Place Div 1/2 Inj Override Switch to NON-ATWS Div I: With an ECCS signal present Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated Div II: With an ECCS signal present Verify White Manual Override light for 1E12-F042B AND 1E12-F042C Illuminated 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 Pump.

Startup RHR Start 1A/1B RHR Pump Establish RHR flow of 1500 to 7450 gpm:

Throttle 1E12-F024A/B (Test Valve) OPEN.

Close 1E12-F048A/B (HX Bypass) o Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B. o 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 419.000 304.010 414.000 US Enters and directs actions of LGA-001 LEVEL LEG Establishes a RPV water level band of 20 to +50 inches Enters and directs actions of LGA-001 PRESSURE LEG

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 29 of 31 STABILIZE Reactor Pressure below 1059 psig When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003 Before Suppression Chamber Pressure exceeds 12 psig Verifies Containment Flood level below 723 ft.

Directs start of Suppression Chamber Sprays (CT)

When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays Verifies Containment Flood level below 722 ft.

Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D

Verifies both Recirc Pumps are tripped Direct initiation of Drywell sprays (CT)

• When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling Event - 11

==

Description:==

Main Steam Line Break Inside Containment Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Containment Cooling online and RPV Level in control and at the discretion of the Lead Evaluator.

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 30 of 31 REFERENCES Procedure Rev Title

1. INPO 15-004 Operations Fundamentals

2. SOER 10-2 Engaged, Thinking Organizations

3. LGP-1-1 122 Normal Unit Startup

4. LOP-RR-05 52 Changing Reactor Recirc Pump Speed from Slow to Fast Speed

5. LOP-RR-07 45 Operation of the Reactor Recirculation Flow Control System

6. LOA-RR-101 38 Unit 1 Reactor Recirculation System Abnormal

7. LOR-1PM02J-B310 3

Generator Stator Coolant Runback Circuit Energized

8. LOA-GC-101 10 UNIT 1 GENERATOR STATOR COOLING ABNORMAL

9. LOR-1H13-P603-A205 4

Standby Liquid Control Tank 1C41-A001 Level High/Low

10. LOA-FW-101 11 REACTOR LEVEL/FEEDWATER PUMP CONTROL TROUBLE

11. LOR-1H13-P603-A511 2

RWLCS Trouble

12. LOR-1H13-P603-B501 4

Primary Containment Pressure Hi/Lo

13. LOP-FW-16 36 1(2)DS001 Operator Station Alarm Message Interpretation

14. LOA-EH-101 35 Unit 1 EHC Abnormal

15. LOP-EH-11 23 EHC Workstation Alarm Response and other information

16. LOR-1PM02J-B505 6

EHC Minor Trouble

17. LGA-001 18 RPV Control

18. LGA-003 17 Primary Containment Control

19. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.

20. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation

21. OP-AA-106-101 21 Significant Event Reporting

22. OP-LA-STA-1001 5

LaSalle Shift Technical Advisor (STA) Checklists

23. EP-AA-1005 Add. 3 3

Emergency Action Levels for LaSalle Station

24. EP-MW-114-100-F-01 J

Nuclear Accident Reporting System(NARS) Form

NRC 17-1-3 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 31 of 31 U1 SUPERVISOR TURNOVER Shift:

Date:

Mode:

OLR:

Work Week:

Days Today 1

Green Non-Div Unit 1 power level Unit 2 power level 35 % Power with LGP-1-1 In-progress

• 100 % Power A TDRFP and C MDRFP are in Auto

'1A' RR Pump in Fast

'1B' RR Pump in Slow 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.

• Currently in step E.8.27 of LGP-1-1

• Upshift B RR Pump per LOP-RR-05 (BOP)

• Raise Reactor Power per LOP-RR-07 using Reactor Recirc 100 MWe (ATC)

Comments, evolutions, problems, etc.

• Non-Div Workweek. OLR is Green

LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-4 Rev. 00 6/26/18 DEVELOPED BY:

Colin Betken/s 10/3/18 Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:

Tyler Messner/s 10/3/18 Training Department Date APPROVED BY:

Joe Messina/s 10/3/18 Operations Representative Date

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 2 of 29 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-4 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.

SUMMARY

OF EVENTS

1. Start C and D RHR Service Water Pumps per LOP-RH-05. The crew will start Div 2 RHR Service Water to support Surveillance

2. D RHR Service Water Pump Trip. D RHR Service Water Pump it will Trip and the crew will have to make a Tech Spec determination.

3. B CD/CB Pump will TRIP and the Standby will Fail to Auto Start, the crew will manual start the Standby CD/CB Pump.

4. CD/CB Pump TRIP. The Crew will take action to set Heater Drain Tank level controller. Emergent Power Reduction. The crew will have to reduce Reactor Power to stabilize plant conditions RR flow.

5. 1A CRD Fan Trip. The crew will start the standby CRD Pump Room Ventilation.

6. TDRFP High Vibrations. The crew will have to trip A TDRFP when vibes reach 5 mils and place the MDRFP online.

7. SBGT Heater Failure. The crew will determine Unit 1 SBGT is inoperable and enter Tech Specs.

8. RR LOCA. The crew will scram the reactor and enter LGA-001 and LGA-003

9. Loss of U-1 SAT, 0 DG Fails to Auto-Start. The crew will restore power to Div 1 by locally starting the 0 DG and maintaining power to the ESF Buses.

10. 1E12-F017B Fails CLOSED. This will cause the crew to initiate Drywell spray using Div 1 RHR when power is restored to 141Y.

Critical Tasks

1. With a loss of off-site power, a failure of a diesel generator to start, and containment spray required, restore power to establish drywell sprays.

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 prior to starting Drywell sprays.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 3 of 29 TRAINING REQUESTS (if applicable)

1. None OPEX (if applicable)

1. 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. Supervisory oversight role

2. Recognition and mitigation of risk

3. Worker performance

4. Tolerance of repetitive/long standing issues and degradation of standards

5. Operating Experience Record of Revisions (Summary)

Rev. 0 Developed new for the ILT 17-1 NRC Exam

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 4 of 29 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION

1. Recall a full power IC

2. Place simulator in RUN

3. Lower Reactor Power using RR flow to 90%.

4. Load and run the SmartScenario file Spare.ssf

5. Update the Tech Spec Timeclock Sheet as follows:

TS/TRM/ODCM System/

Component Required Action REQUIRED ACTION Description Completion Time Expiration 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. Have a copy of LOP-RH-05 marked up to step E.2.2 (entire procedure) and LOS-RH-SR1 marked up to step 3.1 SCENARIO OUTLINE (NRC Evaluations Only)

Event No.

Malf.

No.

Event Type*

Event Description 1

none N (BOP)

Start C and D RHR Service Water Pumps per LOP-RH-05 2

mcw008 T (US)

D RHR Service Water Pump INOP 3

mcf119 C (ATC)

B CD/CB Pump TRIPS and Standby Fails to Auto Start 4

mcf118 R (ATC)

A CD/CB Pump TRIP, Emergent Power Reduction 5

k7d30epg C (BOP) 1A CRD Pump Room Fan Trip 6

g5d04gd6 r0869 C (ATC)

TDRFP High Vibrations 7

mrd353 T (US)

SBGT Heater Power Failure 8

mrc034 M

RR LOCA 9

mee041 mdg016 C (BOP)

Loss of U-1 SAT, 0 DG Fails to Auto-Start 10 k1j10jcn C (BOP) 1E12-F017B Fails CLOSED (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 5 of 29 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE) 769.00.01 During performance of tasks, dynamic learning activities, or formal evaluations, demonstrate applicable Human Performance behaviors IAW the appropriate procedures.

762.04.00 Given an operating experience document, paraphrase the lessons learned and methods to prevent recurrence at LaSalle Station, as described in the training material.

614.010 During performance of tasks, apply the administrative requirements of PROCEDURE USE AND ADHERENCE EXPECTATIONS, IAW station procedures.

TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 75.004 Respond to a Loss of Condensate Pump.

77.042 Perform Control Room actions to respond to a TDRFP high vibration alarm.

304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 413.000 Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 59.5 IAW LGA-001 419.000 Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig.

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

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

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 6 of 29 RO - BOP/ASSIST 11.008 Perform the Main Control Room actions for a Diesel Generator start failure.

64.062 Perform Control Room actions to respond to a loss of RHR Service Water.

65.016 Perform the in plant actions to startup the RHR service water system.

75.004 Respond to a Loss of Condensate Pump.

77.042 Perform Control Room actions to respond to a TDRFP high vibration alarm.

304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 413.000 Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 59.5 IAW LGA-001 419.000 Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig.

419.020 Spray the Suppression Pool.

419.030 Spray the Drywell.

421.000 Evaluate plant conditions and control and maintain suppression pool temperature less than HCTL.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 7 of 29 SRO - UNIT SUPERVISOR 11.008 Perform the Main Control Room actions for a Diesel Generator start failure.

64.062 Perform Control Room actions to respond to a loss of RHR Service Water.

65.016 Perform the in plant actions to startup the RHR service water system.

75.004 Respond to a Loss of Condensate Pump.

77.042 Perform Control Room actions to respond to a TDRFP high vibration alarm.

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

304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 413.000 Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level

+11 to 59.5 IAW LGA-001 419.000 Evaluate plant conditions and control and maintain Primary Containment Pressure to less than 1.93 psig.

419.020 Spray the Suppression Pool.

419.030 Spray the Drywell.

421.000 Evaluate plant conditions and control and maintain suppression pool temperature less than HCTL.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 8 of 29 Event - 1

==

Description:==

Start C and D RHR Service Water Pumps per LOP-RH-05 Initiation: Turnover Cues: Turnover Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant parameters and update the crew as required 65.016 BOP Per LOP-RH-05 PLACE the appropriate Thermal Overload Bypass switch to TEST OPEN 1E12-F068B, B RHR Hx Wtr Otlt Vlv.

At approximately 9 to 10 seconds after taking the 1E12-F068B switch to OPEN, START RHR Service Water Pump 1E12-C300C.

When A/B Loop RHR Service Water flowrate increases to greater than 3000 gpm, as indicated on FI-1E12-R602B, START RHR Service Water Pump 1E12-C300D.

When Service Water Heat Exchanger Outlet Valve reaches the full open position, CHECK B Loop RHR Service Water flow increased to greater than 7400 gpm on RHR Heat Exchanger Service Water Flow Indicator 1E12-R602B or on computer point F472.

PLACE the appropriate Thermal Overload Bypass switch to NORMAL.

o O/L Bypass For 1E12-F003B, 4B, 4C, 6B, 47B, 68B, 73B, 74B, 93, 94.

65.016 US

• Direct above actions

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 9 of 29 Event - 1

==

Description:==

Start C and D RHR Service Water Pumps per LOP-RH-05 Simulator Operator Actions none Simulator Operator Role Play Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: When division 2 RHR WS is running and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 10 of 29 Event - 2

==

Description:==

D RHR Service Water Pump Trip Initiation: Per Lead Evaluator Cues:

Key Parameter Response: B RHR Service Water flow Lowers Expected Annunciators: 1H13-P601-B105, RHR Service Water Pump 1D Auto Trip Automatic Actions: 1D RHR Service Water Pump Trips Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant parameters and update the crew as required 64.062 BOP Per LOR-1H13-P601-B105 DISPATCH operator to 1D RHR Service Water Pump and to SWGR 136Y to determine cause for overload.

o Direct EO to Locally throttle 1E12-F332C to establish 4000 GPM as indicated on 1E12-R602B OR o

Shutdown RHR per LOP-RH-05 64.062 201.011 US Direct above actions Enter Tech Spec 3.7.1 Required Action A.1, restore subsystem in 7 days Enter Tech Spec 3.6.2.3 Required Action A.1, restore Division 2 RHR Suppression Pool Cooling to operable in 7 days

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 11 of 29 Event - 2

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Description:==

D RHR Service Water Pump Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 2 When directed by the crew to throttle Service Water Outlet to maintain flow to 4000 gpm Throttle 1E12-F014B to 0.26 Simulator Operator Role Play As the operator in the field, when sent to investigate cause of trip, wait 2 minutes and report, 1D RHR Service Water Pump Breaker tripped on overcurrent with no signs of a leak Respond as required.

Floor Instructor Notes/OPEX/TRs Note: The crew may Elect to shut down RHR Service Water per LOP-RH-05 Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 12 of 29 Event - 3

==

Description:==

B CD/CB Pump TRIP Initiation: Per Lead Evaluator Cues:

Key Parameter Response: CB Pump Suction Pressure Lowers Expected Annunciators:

1PM03J-A110, CONDENSATE/CONDENSATE BOOSTER PUMP AUTOMATIC TRIP Automatic Actions: B CD/CB Pump Trips Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 75.004 ATC Report B CD/CB Pump trip to Unit Supervisor Per LOR-1PM03J-A110 VERIFY selected Condensate/Condensate Booster Pump Auto Starts if NPSH to Feedwater Pumps is Low (NO)

Start 1D CD/CB Pump PLACE tripped condensate/Condensate Booster Pump Control switch to STOP REFER to LOP CD-03, startup and operation of the condensate and condensate booster system for pump trips Determine cause of TRIP and initiate action request if applicable. Possible causes are as follows:

o Low Lube Oil Pressure o

Overcurrent o

Neutral Overcurrent o

Bus UV BOP

• Monitor plant parameters and update the crew as required 75.004 US

• Direct above actions

• Set Scram criteria, Reactor level outside 20-50 and not in control

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 13 of 29 Event - 3

==

Description:==

B CD/CB Pump TRIP Simulator Operator Actions When directed by the Lead Evaluator Release Event 3 Simulator Operator Role Play As the EO in the Field when ordered to investigate the trip of 1B CD/CB Pump wait 1 minute and report that it tripped on Neutral Overcurrent If Asked, report that post start checks of the D CD/CB Pump are Sat Respond as required.

Floor Instructor Notes/OPEX/TRs Note: This Event is intended for the ATC.

Terminus: When D CD/CB Pump is running and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 14 of 29 Event - 4

==

Description:==

A CD/CB Pump TRIP Initiation: Per Lead Evaluator Cues:

Key Parameter Response: CB Pump Suction Pressure Lowers and Reactor Water Level Lowers Expected Annunciators:

1PM03J-A110, CONDENSATE/CONDENSATE BOOSTER PUMP AUTOMATIC TRIP 1PM03J-A102, FW PUMPS NPSH LO 1PM03J-A410, CB PUMPS SUCTION HDR PRESS LO Automatic Actions: CD/CB Pump Trips Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 75.004 ATC Per LOR-1PM03J-A110 If the standby Condensate/Condensate Booster Pump is not available and a RAPID power reduction is required, promptly perform the following:

• Rapidly REDUCE power with Reactor Recirc Flow to 70 Mlbm/hr (do not enter Region 2) o Using Ganged Flow Controller depress lower pushbutton and monitor core flow o

Using individual RR Flow M/A Stations:

o Place in Manual o Depress LOWER pushbuttons and alternate to maintain loop mismatch

• INSERT CRAM rods in reverse order to maintain Condensate Booster Suction Pressure in the green band and running CD/CB pump amps in the green band.

75.004 BOP Report A CD/CB Pump trip to Unit Supervisor Per LOR-1PM03J-A110 SET 1HK-HD066, Heater Drain Tank level control setpoint to 5ft in Automatic PLACE tripped condensate/Condensate Booster Pump Control switch to STOP REFER to LOP CD-03, startup and operation of the condensate and condensate booster system for pump trips Determine cause of TRIP and initiate action request if applicable. Possible causes are as follows:

o Low Lube Oil Pressure o

Overcurrent o

Neutral Overcurrent o

Bus UV 75.004 US

• Direct above actions

• Set Scram criteria, Reactor level outside 20-50 and not in control

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 15 of 29 Event - 4

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Description:==

A CD/CB Pump TRIP Simulator Operator Actions When directed by the Lead Evaluator Release Event 4 Simulator Operator Role Play As the EO in the Field when ordered to investigate the trip of 1B CD/CB Pump wait 1 minute and report that it tripped on Neutral Overcurrent Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: Following Reactor Power reduction when plant conditions stabilize and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 16 of 29 Event - 5

==

Description:==

1A CRD Pump Room Fan Trip Initiation: Per Lead Evaluator Cues:

Automatic Actions: 1VR03CA Trips Expected Annunciators: 1PM06J-A404, Control Rod Drive Pump Cubicle Ventilation Fan 1VR03CA Automatic Trip Key Parameter Response: none Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Monitor plant parameters and update the crew as required o Swap CRD Pumps per LOP-RD-03 BOP Per LOR-1PM06J-A404

• START Control Rod Drive Pump Cubicle Ventilation Fan 1VR03CB by placing its Control Switch in AUTO

• DETERMINE cause for TRIP of Control Rod Drive Pump Cubicle Ventilation Fan 1A at 480V MCC 133-2

• Send an EO to Investigate Pump Room.

o Followup with LOP-RD-03 o CHECK at 1PL27JC that CRD Pump Cubicle Vent Fan Damper B 1VR03YB opens US

• Direct above actions

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 17 of 29 Event - 5

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Description:==

1A CRD Pump Room Fan Trip Simulator Operator Actions When directed by the Lead Evaluator Release Event 5 Simulator Operator Role Play When ordered to investigate the fan trip, as an EO, wait 1 minute and report that the breaker is tripped and there is an acrid odor present.

If asked, as the EO, 1A CRD Pump bearing Temperature is going up 1 degree per minute.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: Per Limitation D.8 of LOP-RD-03, the Control Rod Pump Room Fan in operation should correspond to the CRD Pump in operation and if not pump bearing temperature increases of 25 degrees van be expected.

Terminus: Following the 1B CRD Pump Room Fan Running and at the discretion of the Lead Evaluator

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 18 of 29 Event - 6

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Description:==

A TDRFP High Vibrations Initiation: Per Lead Evaluator Cues:

Key Parameter Response: 1FW01PA Vibes Rising Expected Annunciators: 1PM02J-A403, TDRFP VIBR HI Automatic Actions: none Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 77.042 ATC Per LOR-1PM02J-A403 o

If vibrations increase to 4 mils, COMMENCE preparations to START a Standby Reactor Feed Pump per LOP-FW-03, Startup of Motor Driven Reactor Feed Pump (MDRFP), OR per LOP-FW-04, Startup of a Turbine Driven Reactor Feed Pump (TDRFP) so that the pump is running before reaching 5 mils.

o If desired to stabilize TDRFP vibration levels by lowering speed with BOTH TDRFPs in Automatic: DEPRESS the LOWER pushbutton on the TDRFP M/A Station for the effected Feed Pump in small increments, while monitoring vibrations, until the desired vibration level is attained. Unaffected TDRFP parameters must be monitored to prevent exceeding operating limits during bias insertion.

o Before vibrations reach 5 mils, SHUTDOWN Reactor Feed Pump Turbine A/B per LOP-FW-05, Shutdown of Turbine Driven Reactor Feed Pump.

If vibration exceeds 5 mils, TRIP Reactor Feed Pump Turbine A/B and COMPLETE shutdown per LOP-FW-05, Shutdown of Turbine Driven Reactor Feed Pump.

o Close 1FW010A Verify MDRFP Auto Starts Verify FW Flow and RWL stabilizes o

Direct EO to perform post start checks on MDRFP 77.042 BOP Per LOR-1PM02J-A403 CHECK Reactor Feed Pump Turbine 1FW01PA/B vibration is equal to or greater than 3 mils.

77.042 US Direct above actions Set Scram Criteria, RPV level outside 20-50 and not in control

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 19 of 29 Event - 6

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Description:==

A TDRFP High Vibrations Simulator Operator Actions When directed by the Lead Evaluator Release Event 6 Simulator Operator Role Play If sent to investigate TDRFP vibrations, wait 1 minutes and report, There is a loud rumbling sound coming from the TDRFP Room Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: When A TDRFP is secured and the MDRFP is running and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 20 of 29 Event - 7

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Description:==

SBGT Heater Failure Initiation: Per Lead Evaluator Cues:

Key Parameter Response: none Expected Annunciators: 1PM07J-A402, STANDBY GAS TREATMENT ELECTRIC HEATER POWER FAILURE Automatic Actions: TRIPS SBGT Electric Heater 1VG01A Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Dispatch an operator to investigate heater and breaker BOP Per LOR-1PM07J-A402

• Dispatch an operator to reset the overload on the breaker.

• If overload does not reset, initiate IR and repair

• If directed place 1VG01C in PTL 201.011 US

• Direct above actions

• Enter Tech Spec 3.6.4.3 Condition A, Required Action A.1, restore SBGT subsystem in 7 days

• Inform Unit 2

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 21 of 29 Event - 7

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Description:==

SBGT Heater Failure Simulator Operator Actions When directed by the Lead Evaluator Release Event 7 Simulator Operator Role Play When sent to investigate the breaker, wait 1 minute and report, appears to be closed If asked to reset the overload, wait 1 minute and report, the overload will not reset Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec Call and at the discretion of the Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 22 of 29 Event - 8

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Description:==

RR LOCA Initiation: Per Lead Evaluator Cues:

Key Parameter Response: Lowering RPV Level and Rising Drywell Pressure Expected Annunciators: Multiple Automatic Actions: Scram (Unless Manually Scrammed)

Task/

Obj.

Position EXPECTED OPERATOR RESPONSE 413.000 419.000 304.010 ATC When directed, manually scrams the reactor ARM and DEPRESS Scram Pushbuttons PLACE Reactor Mode Switch in SHUTDOWN INSERT IRMs and SRMs CHECK Control Rods INSERTED and Power Decreasing REPORT to the Unit Supervisor the status of RPV Level and Pressure VERIFY Reactor Recirculation Pumps have downshifted VERIFY Main Turbine and Generator Trip STABILIZE Reactor Pressure <1020 psig REFER to LGP-3-2 304.010 413.000 419.000 419.020 419.030 421.000 BOP Reports the status of the Electric Plant (0 DG failed to start)

Verify RCIC is operating properly When directed places Suppression Pool Cooling in service:

Startup RHR Service Water as follows:

OPEN 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 RHR Service Water Pump 1C Verify indicated flow reaches 4000 gpm o

If not already performed, dispatch EO to throttle C RHR Service Water flow to 4000 gpm Startup RHR Start 1A/B RHR Pump Establish RHR flow of 1500 to 7450 gpm:

Throttle 1E12-F024A/B (Test Valve) OPEN.

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

o Place B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B When directed establish Suppression Chamber Spray:

VERIFY 1B RHR Pump is running OPEN 1E12-F027A/B (CT)

When directed establish Drywell Spray:

VERIFY 1B RHR Pump is running THROTTLE 1E12-F024B CLOSED OPEN:1E12-F016B and 1E12-F017B (FAILED)

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 23 of 29 304.010 413.000 419.000 419.020 419.030 421.000 US o

May direct a manual reactor scram prior to reaching 1.93 psig in the Drywell Enters and directs actions of LGA-001 LEVEL LEG Establishes a RPV water level band of 20 to +50 inches Enters and directs actions of LGA-001 PRESSURE LEG STABILIZE Reactor Pressure below 1059 psig When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003 Before Suppression Chamber Pressure exceeds 12 psig Verifies Containment Flood level below 723 ft.

Directs start of Suppression Chamber Sprays (CT)

When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays Verifies Containment Flood level below 722 ft.

Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D

Verifies both Recirc Pumps are tripped Direct initiation of Drywell sprays Direct initiation of Suppression Pool Cooling Event - 8

==

Description:==

RR LOCA Simulator Operator Actions When directed by the Lead Evaluator Release Event 8 Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 24 of 29 Event - 9

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Description:==

Loss of U-1 SAT, 0 DG Fails to Auto-Start Initiation: Automatic Cues:

Key Parameter Response: Lighting Dims and Breaker indications on the 1PM01J Expected Annunciators: Multiple Automatic Actions: Div 2 and Div 3 Diesels close in on Buses Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Control RPV Level and Pressure and update the crew as required 11.008 BOP Per LOA-LOOP-101 o

CHECK Division 1 and/or Division 2 EDG supplying their respective ESS buses.

o Stabilize reactor pressure and level per LGA-001 o

Start at least one loop of Suppression Pool Cooling per LGA-RH-103 o

VERIFY CLOSED MSIVs and MSL Drain Valves.

o VERIFY all DGs running supplying power to their respective Bus. (no) o Restore the DG to service per LOA-DG-101.

Per LOA-DG-101 CHECK 0 DG READY FOR AUTO START light - LIT.

CHECK DC power - AVAILABLE.

ESTABLISH communications between Unit 1 Control Room and 0 DG Room to OBSERVE Air Start Motor operation during start attempts.

START the 0 DG from the Main Control Room. (CT)

CHECK 0 DG - NOT RUNNING. (no)

Per LOA-AP-101 o

Perform LOA-AP-101 Hardcard 11.008 US Direct above actions Direct actions to restore power to bus 141Y Start 0 DG per LOA-DG-101 (CT) o Energize bus 141Y from Unit 2

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 25 of 29 Event - 9

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Description:==

Loss of U-1 SAT, 0 DG Fails to Auto-Start Simulator Operator Actions none Simulator Operator Role Play As U-2 NSO, 241Y is powered by U-2 SAT.

As U-2 NSO, ACB 2415 is OPEN.

As U-2 NSO, when contacted to cross-tie 241Y with 141Y and directed to synchronize and close ACB 2414, respond that ACB 2414 failed to close and you are dispatching an EO to investigate.

As U-2 NSO, the 0 DG CWP is running on U-2 and U-2 SBGT is running.

Respond as required.

Floor Instructor Notes/OPEX/TRs Terminus: continued.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 26 of 29 Event - 10

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Description:==

1E12-F017B Fails Initiation: Automatic Cues: Key Parameter Response: 1E12-F017B wont open Task/

Obj.

Position EXPECTED OPERATOR RESPONSE ATC

• Controls RPV Level and Pressure and updates the crew as required 419.020 419.030 421.000 413.000 BOP o

Identifies failure of 1E12-F017B to open if attempt to place Drywell Spray on DIV 2

o Direct an EO to De-energize and Locally open 1E12-F017B When the 0 DG is restored When directed establish Drywell Spray:

VERIFY 1A RHR Pump is running THROTTLE 1E12-F024A CLOSED OPEN:1E12-F016A and 1E12-F017A 419.020 419.030 421.000 413.000 US When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003 When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays Verifies Containment Flood level below 722 ft.

Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D Verifies both Recirc Pumps are tripped Direct initiation of Drywell sprays

• When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 27 of 29 Event - 10

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Description:==

1E12-F017B Fails Simulator Operator Actions When directed by the Crew Release 1E12-F017B Actuator Feed Breaker Simulator Operator Role Play As EO, if directed to OPEN 1E12-F017B wait 3 minutes and perform Sim Actions, then wait 2 minutes and report that the 1E12-F017B is mechanically bound CLOSED and you are unable to OPEN it.

• • • • This event will only be discovered if the crew attempts to place drywell sprays on division 2 prior to starting the 0 DG.

Respond as required.

Floor Instructor Notes/OPEX/TRs Note: If the crew is unable to maintain Reactor Level >150 they may blowdown per LGA-004 Terminus: When Drywell Spray has been initiated and at the discretion of Lead Evaluator.

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 28 of 29 REFERENCES Procedure Rev Title

1. INPO 15-004 Operations Fundamentals

2. SOER 10-2 Engaged, Thinking Organizations

3. LOP-RH-05 34 Operation of RHR Service Water System

4. LOR-1H13-P601-B105 3

RHR Service Water Pump 1D Trip

5. LOR-1PM03J-A110 5

CD/CB Pump Automatic Trip

6. LOR-1PM02J-A403 6

TDRFP Vibration High

7. LOA-LOOP-101 6

Loss of Offsite Power

8. LOA-DG-101 10 DG Failure

9. LOR-1PM03J-A102 1

FW Pup NPSH Lo

10. LOR-1PM03J-A410 4

CB Pumps Suction HDR Press Lo

11. LOR-1PM06J-A404 2

CRD Pump Cubicle Ventilation Fan 1VR03CA Auto Trip

12. LOP-RD-03 15 Startup of Standby CRD Pump in non-emergency Conditions

13. LOP-PR-06 18 Startup and Operation of Liquid Process Radiation Monitoring System

14. LOP-RH-14 14 Backwash of RHR WS Strainers

15. LOP-FW-03 44 Startup of MDRFP

16. LOP-FW-05 36 Shutdown of TDRFP

17. LOR-1PM07J-A402 3

Standby Gas Treatment System Electric Heater Power Failure

18. LOR-1H13-P603-B501 4

Primary Containment Pressure Hi/Lo

19. LOA-AP-101 58 Unit 1 AC Power System Abnormal

20. LGA-001 18 RPV Control

21. LGA-003 17 Primary Containment Control

22. LGA-004 9

RPV Blowdown

23. LGP-3-1 66 Power Changes

24. LGP-3-2 73 Reactor Scram

25. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.

26. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation

27. OP-AA-106-101 21 Significant Event Reporting

28. OP-LA-STA-1001 5

LaSalle Shift Technical Advisor (STA) Checklists

29. EP-AA-1005 Add. 3 3

Emergency Action Levels for LaSalle Station

30. EP-MW-114-100-F-01 J

Nuclear Accident Reporting System(NARS) Form

NRC 17-1-4 Revision 00 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.

Page 29 of 29 U1 SUPERVISOR TURNOVER Shift:

Date:

Mode:

OLR:

Work Week:

Days Today 1

Green Div 2 Unit 1 power level Unit 2 power level 90 % 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.

• Reactor power is currently 90% for upcoming Control Rod sequence exchange

• Currently performing LOP-RH-05 step E.2.2 to support LOS-RH-SR1 for Div 2

• Div 2 Work Week

• OLR is Green Comments, evolutions, problems, etc.

• RCIC Workweek. OLR is Green