ML042940203

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Initial Submittal of Scenarios for Dresden Initial Exam August 2004
ML042940203
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 08/16/2004
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
50-237/04-301, 50-249/04-301 50-237/04-301, 50-249/04-301
Download: ML042940203 (56)
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Text

Dresden Generating Station ILT-N-1 VACUUM BREAKER STUCK 20% OPEN CONTROL ROD DRIFT CRD PUMP SWAP APRM 5 FAILS UPSCALE SMALL LEAK IN DRYWELL 2B CRD PUMP TRIPS ON LOW SUCTION PRESSURE ATWS AND LEAK GETS WORSE Rev. 00 04/04 Operations Review:

Facility Representative Date Training Approval:

Exam Author Date

Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-N-1 Op-Test No: ILT 03-1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: Rx Power ~ 95%, 2B Stator Cooling Pump OOS, IRM 16 OOS.

Turnover: DOS 1600-09, is in progress.

Event No.

Malfunction Number Event Type*

Event Description 1

P00 C

SRO Vacuum breaker stuck approximately 20% open.

2 RODL06DI C

NSO SRO Control Rod Begins to drift in.

3 RDPPATRP C

NSO SRO 2A CRD Pump is making a grinding noise, must swap.

4 NIA5POT I

NSO SRO APRM 5 Fails Upscale. Bypass and Reset Half Scram.

5 I21 Small Leak in Drywell.

6 RDPPBTRP 2B CRD pump trips on low suction pressure and Accumulator alarms begin to come in.

7 RODST I22 M

All Several control rods remain withdrawn. The leak in drywell gets worse.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

SCENARIO ILT-N-1 Page 3 of 29 Rev. 00 (04/04)

Scenario Objective Evaluate the crews ability to control the plant during a condition requiring Emergency Depressurization.

Scenario Summary

1. Unit is in Mode 1 at ~95% power, operating per BPO.
2. The following equipment is OOS:
a. 2B Stator Cooling Pump
b. IRM Channel 16
3. LCOs:
a. None
4. Scenario Description After shift turnover, a Torus to Drywell vacuum breaker sticks open 20% during performance of DOS 1600-9. The team begins a plant shutdown.

Control rod H-01 will begin drifting in.

A report comes into the Main Control Room that the 2A CRD pump is making a loud grinding noise. The NSO will swap CRD pumps, placing 2B CRD pump in service.

APRM Channel 5 fails upscale. The NSO will bypass the APRM and Reset the half scram.

A small steam leak upstream of the restrictors occurs. The Team will begin to execute the DOA for slow leak.

The running CRD pump trips on low suction pressure and accumulator alarms begin to come in. When the Team scrams three rods stay out. The CRD pump can be restarted after an NLO swaps suction filters to drive in rods.

The steam leak will get worse and pressurize the containment, forcing an Emergency Depressurization.

Scenario Run Time:

55 min.

Scenario Sequence Event One - Torus to Drywell Vacuum Breaker Fails Open After shift turnover, a Torus to Drywell vacuum breaker sticks open 20% during performance of DOS 1600-9.

Attempts by the team to close the valve are unsuccessful. The team references Tech Specs and determines a plant shutdown is required.

Malfunctions required: 1 Torus/D/W vacuum breaker failed 20% open Success Path:

Identifies Tech Spec requires unit shutdown.

SCENARIO ILT-N-1 Page 4 of 29 Rev. 00 (04/04)

Event Two - Control Rod Drift Control rod H-01 will begin drifting in.

Malfunctions required: 1 Rod H-01 Drifts In Success Path:

Executes DOA 0300-05, Inoperable or Failed CRDs.

Executes DOA 0300-12, Mispositioned CRD.

SRO references Tech Specs and determines the control rod must be inserted and disarmed.

Event Three - CRD Pump Swap A report comes into the Main Control Room that the 2A CRD pump is making a loud grinding noise. The NSO will swap CRD pumps, placing 2B CRD pump in service.

Malfunctions required: 1 CRD pump trip if NSO does not swap pumps in a timely manner.

Success Path:

NSO swaps running CRD pumps.

Event Four - APRM 5 Fails Upscale APRM Channel 5 fails upscale.

Malfunctions required: 1 APRM Channel 5 Fails Upscale.

Success Path:

Bypass APRM Channel 5 Performs DOP 0500-07, Manual Half Scram Reset.

Event Five - Slow Leak A small steam leak upstream of the restrictors occurs.

Malfunctions required: 1 Small steam leak before restrictors.

Success path:

Performs DOA 0040-01, Slow Leak

SCENARIO ILT-N-1 Page 5 of 29 Rev. 00 (04/04)

Event Six - Running CRD Pump Trips on Low Suction Indications of a clogged suction filter eventually result in 2B CRD pump trip and the team receives an accumulator trouble alarm. The Operators should scram after the first accumulator alarm is received.

Malfunctions required: 2 Trip of 2B CRD pump Numerous accumulator alarms Success Path:

Scram, perform DGP 2-3 Event Seven - Reactor Fails to scram and pressurizes the containment forcing an Emergency Depressurization As the steam leak propagates, the failed open vacuum breaker will prevent proper condensation of the steam and consequently, Torus and Drywell pressures will rapidly rise.

Malfunctions required: 2 Large steam leak after restrictors Several control rods remain withdrawn.

Success Path:

Performs DEOP 400-02, Emergency Depressurization.

NSO drives in withdrawn control rods.

SCENARIO ILT-N-1 Page 6 of 29 Rev. 00 (04/04)

PRE-SCENARIO ACTIVITIES 1

If applicable, conduct pre-scenario activities in accordance with TQ-AA-106-0107, SIMULATOR EXAMINATION BRIEFING.

a. Inform the crew that (select an individual) is the QNE present in the Control Room.
b. Direct the crew to perform their briefs prior to entering the simulator.
c. Inform the crew to maintain full power operations per Bulk Power direction.
d. Inform the Crew that Torus to Drywell vacuum breaker surveillance, DOS 1600-09 Pressure Suppresion Chamber to Drywell Vacuum Breaker Full Stroke Exercise Test, is in progress.

2 Simulator Setup

a. Initialize simulator in IC 12 and perform the following before continuing below:
b. Establish the DW to Torus DP equalization lineup as it would be per DOP 1600-18 as follows:
1) Place the DW pressure controller PIC 2-8540-1 to manual and set for zero demand
2) Place the DW/Torus DP controller PIC 2-1602-14 to manual and set for zero demand
3) Open AO 2-1601-21
4) Wait until DW to Torus DP equalizes, then close AO 2-1601-56
5) Open AO 2-1601-58
6) Open AO 2-1601-59
c. ONLY after DW/Torus DP has been equalized with DW pressure < 1.0 psig, run the initial setup CAEP file: ILT-N-1.cae.
d. Balance individual recirc pump controllers.
e. Advance the chart recorders.
f.

Copy files j05 and l07 into s:\\opensim\\triggers 3

Verify the following simulator conditions:

a. Reactor Power ~ 912 MWe.
b. Verify ~100% FCL
c. CRD Drive Water pressure ~260#.
d. Feedwater flows and Reactor level stable.
e. 2A CRD pump is running.
f.

Set H2 Cooling Water controller in Auto balanced at 40OC.

g. RWCU flow 610- 650 gpm.
h. If alarm 902-4 C-23 for Torus low level comes up, then to quickly raise Torus level:

Open Instructor Station Drawing CS1, Core Spray System, to observe valve operation in the steps below.

1) Activate trigger 17, which opens core spray CST suction valve 1402-2A.
2) Verify trigger 18 automatically activates when 1402-2A reaches full open. This will close the valve.
3) Check if the Torus level alarm clears.
4) If the alarm does not clear, toggle triggers 17 and 18 OFF and repeat the above steps.

SCENARIO ILT-N-1 Page 7 of 29 Rev. 00 (04/04) 4 Place the following equipment out of service:

a. 2B Stator Cooling Pump
b. IRM Channel 16 5

Complete the Simulator Setup Checklist.

6 Delete files j05 and l07 from s:\\opensim\\triggers after the last time running this scenario.

SCENARIO ILT-N-1 Page 8 of 29 Rev. 00 (04/04)

Symbols are used throughout the text to identify specific items as indicated below:

Critical Tasks



Time Critical Tasks PRA Key Operator Actions

 Required Actions

 Optional Actions

SCENARIO ILT-N-1 Page 9 of 29 Rev. 00 (04/04)

Event One - Torus to Drywell Vacuum Breaker Fails Open Trigger Position Crew Actions or Behavior Role Play:

About 5 minutes after the team assumes the shift and at the discretion of the NRC Lead Examiner, as Extra NLO, report We are staged and ready to perform DOS 1600-09 beginning with valve 2-1601-32A. Do we have permission to begin?

1 Simulator Operator:

About 1 minutes after receiving permission to begin DOS 1601-09, activate trigger 1, which fails Torus to DW Vacuum Breaker 2-1601-32A 20% open.

Role Play:

About 2 min after Trigger 1 is activated, as Extra NLO, report The Torus to Drywell Vacuum Breaker 2-1601-32A valve is about 20% open and will not move. It appears there is something broken in the valve.

MMD if asked on time to repair, There is something broken internal to the valve, the repair will take at least 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

Note: The remainder of this 4 hr. clock can be used to attempt to close the vacuum breaker and reestablish 1 psid DW to Torus.

Unit Operators May review the following:

DAN 902-4 G-14, Torus to DW Div I Vac Bkr Vlv Open DAN 902-4 H-14, Torus to DW Div II Vac Bkr Vlv Open DAN 902-4 B-15, DW to Torus DP Hi/Lo



Reviews DGP 02-01, Unit Shutdown, and DGP 02-03, Reactor Scram, in preparation for Unit Shutdown as directed.

SRO Following the MMD report, references Tech Specs and determines the following:

LCO 3.6.1.8 Condition B1, close the open vacuum breaker within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

 Based on TS requirement to close the valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, may direct preparatory actions for DGP 02-01, Unit Shutdown, and DGP 02-03, Reactor Scram.



Notifies QNE, IMs, and Chemistry for RETs for the impending shutdown.

May contact any/all of the following to inform of situation or request assistance:



Shift Manager



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week Manager

SCENARIO ILT-N-1 Page 10 of 29 Rev. 00 (04/04)

Event One - Torus to Drywell Vacuum Breaker Fails Open Trigger Position Crew Actions or Behavior Event 1 Completion Criteria:

References Tech Specs Determines that a unit Shutdown is required.

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-1 Page 11 of 29 Rev. 00 (04/04)

Event Two - Control Rod Drift Trigger Position Crew Actions or Behavior 2

Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, activate trigger 2, which initiates Control Rod H-01 to drift in.

ROLE PLAY:

NLO to investigate CRD H-01: (wait 3 min.)

Report, the exhaust riser for the HCU is hot to the touch. Everything else appears normal.

If asked Temp: 240OF with heat gun.

3 ROLE PLAY:

NLO to disarm and isolate CRD H-01: (wait 4 min)

Verify Trigger 3 activated and report CRD H-01 is hydraulically isolated and electrically disarmed.

If asked: Shift Manager directs shutdown to continue.

NSO Announces alarms for the Control Rod H-01 and refers to the following DANs:

 902-5 A-3, Rod Drift alarm.

 Views Full Core Display AND identifies CRD with Rod Drift light illuminated.

 Selects drifting control rod.

 Observes selected CRD position on four rod display.

Performs actions of DOA 0300-05, Inoperable or Failed CRDs

 Bypass the RWM.

 Inserts the rod to 00 using Emergency Rod In switch.



May take H-01 out of service on RWM as directed by Unit Supervisor:



On RWM, select SECONDARY FUNCTION.



On RWM, select ROD OUT OF SERVICE



On RWM, select inoperable CRD



On RWM, verify correct inoperable CRD selected, then select ENTER REQUEST.



Continuously insert inoperable CRD to 00.



On RWM, select EXIT FUNCTION.

Performs actions of DOA 0300-12, Mispositioned CRD:



Discontinues reactivity changes.



Compares Off-Gas readings.



Refers to DOA 0500-04, Thermal Limits and Fuel Conditioning Violation, and DGA 16, Coolant Activity/ Fuel Element Failure.



Dispatches an Operator to investigate the cause of the drifting control rod.

 Dispatches an operator to hydraulically isolate and electrically disarm the CRD per DOP 0300-08, CRD System HCU isolation.

SCENARIO ILT-N-1 Page 12 of 29 Rev. 00 (04/04)

Event Two - Control Rod Drift Trigger Position Crew Actions or Behavior SRO

 Enters DOA 0300-05, Inoperable or Failed CRDs, and directs NSO actions.

 Enters DOA 0300-12 and contacts QNE to evaluate core and verify SDM requirements met IAW LCO 3.1.1



As time permits, completes DOA 0300-05, Datasheet 1 information sheet and initiates a CR and an SWR

 Refers to LCO 3.1.3, Condition C1 and C2, and determines that H-01 shall be inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarmed electrically or hydraulically within four hours.

 Directs/verifies Operators take action per DOA 0300-12.

SRO



Refers to DOA 0500-04, Thermal Limits and Fuel Conditioning Violation, and DGA 16, Coolant Activity / Fuel Element Failure.

Event 2 Completion Criteria:

DOA 300-5 and 300-12 are entered and Technical Specifications are referenced and making progress towards electrically disarming H-1,

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-1 Page 13 of 29 Rev. 00 (04/04)

Event Three - CRD Pump Swap Trigger Position Crew Actions or Behavior Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, begin this event.

ROLE PLAY:

(Wait 3 minutes), NLO from field:

Report, the 2A CRD pump is making a loud metallic grinding noise, I cannot see any oil in the pump, smoke is starting to come from the pump, and it is very hot.

NSO may follow DOP 300-1 and have the NLO vent the pump. Wait 1 minute and report, 2B CRD pump has been vented.

4 21 Simulator Operator Actions: Insert trigger 4 when the report of the failing CRD pump is reported. This will begin to ramp up pump amps over a nine minute period, and finally trip the pump on overcurrent if amps get too high and the crew has not swapped the pump yet.

Verify Trigger 21 automatically activates when the 2A CRD pump breaker opens. This deletes the override on the pump ammeter.

NSO Carries out actions of DOA 300-01, Control Rod Drive System Failure:

 Stops any rod motion or power changes.

 Starts 2B CRD pump.

 Secures 2A CRD pump.



Verifies normal CRD system pressures and flows.

Role Play: If asked, 2B CRD pump is operating normally.

SRO

 Enters DOA 300-01, Control Rod Drive System Failure, due to failure of 2A CRD pump.

May contact any/all of the following to inform of situation or request assistance:



Shift Manager



WEC Supervisor



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week Manager Event 3 Completion Criteria:

2B CRD pump has been started and the immediate actions of DOA 300-01 are complete,

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-1 Page 14 of 29 Rev. 00 (04/04)

Event Four - APRM 5 Fails Upscale Trigger Position Crew Actions or Behavior 5

SIMULATOR OPERATOR:

At the discretion of the NRC Lead Examiner, activate trigger 5, which will cause APRM 5 to fail upscale.

NSO

 Notices and announces Channel B half scram.

Carries out actions of DAN 902-5 D-13

 Investigates and reports cause of APRM failed upscale.

 As directed Bypass APRM 5.

 Reset half-scram.

 Verifies the 4 White Group Solenoid lights are lit.

Resets the Half Scram IAW DOP 500-07

 Verifies Half Scram no longer required.

 Turns the SCRAM RESET switch in EACH direction AND verifies ALL (eight) SCRAM SOLENOID GROUP lights are lit.

 Verifies annunciators 902-5 A-10 AND A-15 are reset.

ANSO

 Checks Panel 902-37 for abnormalities.

SRO

 Verifies actions of DAN 902-5 D-13 and/or D-15 and/or B-11 carried out.

 References TS 3.3.1.1 and Table 3.3.1.1-1 (No LCO RA).

 ReferencesTRM 3.3.a (No LCO RA)

 Orders bypassing of APRM 5.

 Orders reset of Half Scram IAW DOP 500-07 or the DANs.

May contact any/all of the following to inform of situation or request assistance:



Shift Manager



WEC Supervisor



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week Manager Event Four Completion Criteria:

Appropriate Tech Specs referenced APRM 5 bypassed Half Scram reset

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-1 Page 15 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior 6

7 Simulator Operator:

At the discretion of the NRC Lead Examiner, activate trigger 6, which inserts a small steam leak upstream of the restrictors.

Verify trigger 7 activates when Drywell pressure is > 1.0 psig OR the team scrams (Mode Switch to S/D). This gradually isolates the 2B CRD pump suction filter to simulate a clogged filter. After 5 min. the suction filter totally isolates causing the CRD pump to trip. Then, several accumulator alarms are received over a period of time.

Role Play:

If asked Drywell pressure on Unit 3, Report, Drywell pressure is 1.1# and steady NSO Reports rising drywell pressure and performs DOA 0040-01, Slow Leak:

Maintains RPV/L using FWLC and monitoring multiple indications.



Attempts to locate and isolate leak ANSO



Makes PA announcement



Secures H2 Addition System



Operates Drywell Sump Pumps as necessary per DOP 2000-24, Drywell Sump Operation



Monitors/calculates leakage rates using all available indications

 Monitors Torus bulk temperature and initiates Torus Cooling as directed



Directs NLO to obtain Cribhouse intake temperature or gets temp from computer screen.



Verifies normal operation of RBCCW SRO

Enters DOA 0040-01, Slow Leak, and directs actions.

 May direct DGP 02-03, Reactor Scram, preparatory actions.

 May direct an operator to calculate the leak rate.



Notifies RP of leak and possible changing radiological conditions.



Directs team to identify and isolate the leak.



Verifies release limits are NOT violated.

 Establishes contingencies for when the unit will be taken off line.

References Tech Specs

 LCO 3.4.4 RCS Operational Leakage.

May contact any/all of the following to inform of situation or request assistance:



Shift Manager



WEC Supervisor



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week Manager



Load Dispatcher

SCENARIO ILT-N-1 Page 16 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior NOTE:

Team may decide to conservatively scram the unit with the leak in the drywell and a CRD pump going away.

ROLE PLAY:

NLO to 2B CRD pump: (wait 3 min.) and if the pump is running, Report the 2B CRD pump suction gage indicates 10" of vacuum, slowly decreasing. (Pressure is rising)

IF pump is NOT running, report The 2B CRD pump suction pressure is about 10#.

NLO to Bus 23: (wait 3 min.)

Report the 2B CRD pump breaker at Bus 23 is tripped, but NO targets are up.

Acknowledge as personnel directed to place CRD pump suction filter in service.

NSO Acknowledges pump trip and refers to DANs 902-5:



B-2, ROD DRIVE PP TRIP



D-2, 2B ROD DRIVE PP SUCT LO



F-2, ACCUMULATOR CHARGING WTR PRESS LO Performs DOA 300-1, Control Rod Drive System Failure, as directed



Stops any rod motion or power changes.



May dispatch NLO(s) to the 2B CRD pump and/or Bus 24 to investigate cause of trip.

SRO Enters DOA 300-01, Control Rod Drive System Failure



Directs in-plant operator(s) to place standby suction filter in service or isolate and replace the 2B CRD pump suction filters.



Makes Crew aware of criteria for manually scramming the reactor for CRD problems.

May contact any/all of the following to inform of situation or request assistance:



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week manager

SCENARIO ILT-N-1 Page 17 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior 14 15 Simulator Operator:

Verify the following triggers automatically activate when the associated rod is selected, drive water pressure is restored to > 200 psig and an insert signal is given:

Trigger 14: deletes the stuck malfunction for J05.

Trigger 15: deletes the stuck malfunction for L07 8

25 Simulator Operator:

Verify trigger 8 followed by trigger 25 automatically activate when the first rod is fully inserted.

Trigger 8 modifies the steam leak to 0.2%.

Trigger 25 automatically activates when the leak size is changed to 0.2%

and modifies the steam leak to 10% after a 5 min. delay.

SRO

 References TS section 3.1.5. Required Action D, Control Rod Accumulators operability.



Orders Reactor scram after first accumulator alarm.

 Enters DEOP 100, RPV Control following the scram, and when report is received of not all rods inserted, exits DEOP 100 and enters DEOP 400-

5.

 Enters DEOP 200-1. Primary Containment Control.

NSO



Acknowledges 902-5 G 2 (Accumulator trouble) alarm, and references the DAN.



Sends NLO to determine if rod B-8 is low nitrogen pressure or high water level.



Acknowledges and identifies additional accumulator alarms.



Performs DOA 0300-01 as directed.

Performs DGP 02-03, Reactor Scram,

 Presses scram pushbuttons

 Places mode switch in shutdown

 Checks rods inserted - not all are in

 Initiates ARI

 Runs recirc pumps back to minimum



Inserts SRM/IRMs

 Controls Rx water level +25 to +35 or as directed by SRO Power Leg

 Runs back recirc to minimum.

 Inserts control rods using Alternate Rod Insertion DEOP 500-05 When US exits power leg of DEOP 400-5, performs DGP 02-03, Reactor Scram, as directed:

 Maintain RPV/L between +25 and +35 inches or as directed by DEOPs

 Inserts SRM/IRMs

SCENARIO ILT-N-1 Page 18 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior NSO Performs manual control rod insertion per DEOP 500-5, Alternate Insertion of Control Rods, as directed (this method will be successful):

 Bypasses the RWM

 Starts the available CRD pump or use CRD x-tie from Unit 3.

 Maximizes drive water pressure using one or more of the methods in DEOP 500-05.

 Inserts rods using RONOR in EMERG ROD IN or the normal rod movement control switch Crossties Unit 2 and Unit 3 CRD system per DEOP 500-5, Alternate Insertion of Control Rods, and manually inserts control rods as directed (will be successful):

 Requests starting stby pump on Unit 3

 Dispatches Operator to complete steps G.6.e.(2) - G.6.e.(5) of DEOP 500-05.

 Maximizes drive water flow on Unit 2 by:

 Opening CRD FCV maintaining <39 amps and CRD suction Pressure <18 Hg AND Adjusting Drive water pressure using MO 2-302-8 Drive Water PCV.



Dispatches Operator to close CRD 25 valve (if not already done)

 Inserts control rods using ROD MOVEMENT CONTROL switch or EMER ROD IN position of the ROD OUT NOTCH OVERRIDE switch.

Performs repeated scram/resets per DEOP 500-5, Alternate Insertion of Control Rods, as directed (one rod will stay out):

 Depresses close pushbuttons for SDV vent and drain valves

 Attempts to reset scram

 Installs scram jumpers (if required)

 Resets the scram

 Verifies all scram valves closed

 Opens the SDV vent and drains

 When 902-5 C-1 clears, scrams reactor

 Repeats as necessary



Carries out actions of DEOP 200-1 as directed by SRO.

14 15 Simulator Operator:

When the scram has been reset AND if the following triggers are not already activated, then activate the following triggers:

Trigger 14: deletes the stuck malfunction for J05.

Trigger 15: deletes the stuck malfunction for L07 9

ROLE PLAY & Simulator Operator Actions:

Operator to install RPS jumpers

- Wait 5 min.

Activate trigger 9 Report, the scram jumpers are installed.

SCENARIO ILT-N-1 Page 19 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior 10 ROLE PLAY & Simulator Operator Actions:

Operator to install -59" MSIV closure jumpers and Off Gas Hi Rad jumpers:

Wait 5 min.

Activate trigger 10 Report the -59" MSIV closure jumpers and Off Gas Hi Rad jumpers are installed.

11 SIMULATOR OPERATOR / ROLE PLAY:

Operator to pull ARI fuses:

- Wait 5 min

- Activate trigger 11

- Report the ARI fuses are pulled.

12 ROLE PLAY & Simulator Operator Actions:

- Wait 5 minutes from being sent to cross connect suction filters

- Activate trigger 12

- Report that the standby CRD suction filter has been placed in service.

13 ROLE PLAY & Simulator Operator Actions:

- Wait 3 minutes from being sent to shut the CRD 25 valve

- Activate trigger 13

- Report that the CRD 25 valve is closed.

16 ROLE PLAY & Simulator Operator Actions:

- Wait 5 minutes from being sent crosstie the Unit 2 and Unit 3 CRD systems

- Activate trigger 16

- Report that the Unit 2 and Unit 3 CRD systems are crosstied.

ANSO Performs DEOP 400-5, Failure to Scram, actions as directed:

 Places ADS to inhibit (RPV-6.2)

 Places both CS pumps in PTL Level Leg

 Verifies Isolations, ECCS starts except Core Spray and EDG start

 Directs jumpers installed for MSIV low level and Off Gas high Rad isolations if any MSIV is open.

 If power is < 6%, maintains level between +8 to +48 inches (Ops Standards)

Pressure Leg

 If ADS valve is cycling, drops RPV/P to 945 psig using IC and ADSVs

 Stabilizes pressure <1060 psig using BPVs/IC/HPCI/ADSVs

SCENARIO ILT-N-1 Page 20 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior Performs DEOP 100, Reactor Control actions as directed:



Verifies automatic isolations and ECCS initiations



Holds RPV/L band of +8 to +48



Maintain RPV/P < 1060 psig



Verifies turbine and generator tripped



Check auxiliary power transferred to RAT Performs DEOP 200-1, Primary Containment Control, actions as directed:

 Initiates torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed (PC 5.1)



Monitors DW/T



Monitors SP/T and initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed



Monitors SP/L



Verifies initiation of drywell and torus H2/O2 monitors Performs DEOP 400-02, Emergency Depressurization, as directed (PC 6.1):



Prevents injection from LPCI/CS pumps per Hard Card, LPCI INJ/CC CONTROL/SHUTDOWN

 Initiates Iso Condenser to maximum flow per Hard Card, ISOLATION CONDENSER

 Verifies SP/L > 6 feet

 Places all ADS valve control switches to MAN.

 Verifies all relief valve positions.

If RPV level drops below minimum useable level, performs DEOP 400-01, RPV Flooding actions as directed.

SRO Acknowledges report of increasing Drywell pressure.

Enters DEOP 100, Reactor Control due to high PC/P and/or low RPV/L and performs/directs:



Entering DGP 2-3



Verification of water level instrument accuracy



Verification that automatic actions have occurred



Verification of all isolations, ECCS and EDGs starts



Holding RPV/L +8 to +48 with HPCI or Feedwater



Maintaining RPV/P < 1060 psig

SCENARIO ILT-N-1 Page 21 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior When receives report that ATWS condition exists, exits DEOP 100 and enters DEOP 400-5, Failure to Scram, and directs the following:

 Placing ADS to inhibit (RPV-6.2)



Placing both CS pumps in PTL



Power Leg



Running back recirc to minimum.

 Refers to DEOP 500-05, Alternate Insertion of Control Rods, and determines manual rod insertion, repeated scram/resets, cross-tying Unit 2 and Unit 3 CRD systems, and venting over-piston areas should be successful. Directs performance of DEOP 500-05.

 Exits DEOP 400-5 Rx/Q when IRMs are less than Range 7 and dropping and there is no boron injection in progress, enters DGP 2-3, Reactor Scram OR Reactor will stay shutdown under all conditions.

Level Leg

 Verification water level instruments are accurate

 Verification any required automatic actions have occurred

 If any MSIV is open, directing jumpers installed for MSIV low level and Off Gas high Rad isolations

 Maintaining RPV/L between +8 to +48 inches (Ops. Stds.)

Pressure Leg

 If any ADS valve is cycling, lowering RPV/P to 945 psig using BPVs, IC and ADSVs

 Stabilizing pressure <1060 psig (Ops. Stds. 800 - 1060)

 Exits DEOP 400-05 and re-enters DEOP 100 when reported only one rod out.

SRO Enters DEOP 200-1, Primary Containment Control, if PC/P reaches 2 psig and performs/directs:

 Determines if DW pressure can be held < 2.0 psig with SBGT or DW purge.

 Verifying of torus water level < 27.5 ft.

 Initiation of torus sprays before PC/P of 9 psig

 When PC/P is above 9 psig or before DW/T reaches 281°F:

Verification of DSIL Tripping of recirc pumps Tripping of DW coolers

 Initiation of DW sprays (PC-5.1)

 Securing of torus (drywell) sprays before torus (drywell) pressure drops to 0 psig (PC-5.2)

 Continuing efforts to reduce drywell pressure below 9 psig

 Monitoring of DW/T (drywell sprays may be initiated for temperature control)

 Monitoring of SP/T and initiation of torus cooling

 Monitors SP/L May direct all main turbine bypass valves opened per DEOP 100 RPV/P, anticipating an ED

SCENARIO ILT-N-1 Page 22 of 29 Rev. 00 (04/04)

Event Five, Six, and Seven - Small steam leak, Running CRD Pump Trips on Low Suction Pressure, Accumulator Alarms come in. Leak gets worse after Reactor scram. Emergency Depressurize.

Trigger Position Crew Actions or Behavior Enters DEOP 400-02, Emergency Depressurization due to either DW/T cannot be maintained <281 °F or SP/P cannot be maintained less than the Pressure Suppression Pressure Limit and directs (PC 6.1):

 Prevention of injection from LPCI/CS pumps not needed for core cooling.

 Initiation of Iso Condenser to maximum flow

 Verification that SP/L > 6

 Opening all ADS valves

 Verification all relief valves are open Verifies operable RPV water level instruments on emergency depressurization. If they are not operable, enters DEOP 400-1, RPV Flooding.

May contact any/all of the following to inform of situation or request assistance:



Operations Manager



Shift Operating Supervisor



Duty Maintenance Supervisor



Duty Engineering Manager



Work Week Manager Event 6 and 7 Completion Criteria:

Emergency Depressurization is complete Rods are inserted

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-1 Page 23 of 29 Rev. 00 (04/04)

Critical Tasks (PC 5.1)

When drywell pressure exceeds the suppression chamber spray initiation pressure (Mark I, II) or before containment pressure exceeds the Pressure suppression Pressure (mark III), Initiate drywell/containment sprays, while in the safe region of the drywell spray initiation limit (Mark I, II) or above the containment spray initiation pressure (Mark III).

(PC 6.1)

When suppression chamber/containment pressure cannot be maintained below the Pressure Suppression Pressure (PSP), INITIATE emergency depressurization before the drywell/containment design pressure is exceeded.

(PC 4.1)

When drywell temperature cannot be maintained below the drywell design temperature, INITIATE emergency depressurization.

SCENARIO ILT-N-1 Page 24 of 29 Rev. 00 (04/04)

REFERENCES PROCEDURE TITLE DGP 02-01 UNIT SHUTDOWN DGP 02-03 REACTOR SCRAM DOP 0500-07 INSERTION/RESET OF MANUAL HALF SCRAM DOP 1500-02 TORUS WATER COOLING MODE OF LOW PRESSURE COOLANT INJECTION SYSTEM DOA 0040-01 SLOW LEAK DOA 0300-01 CRD SYSTEM FAILURE DOA 0300-05 INOPERABLE OR FAILED CONTROL ROD DRIVES DOA 0300-12 MISPOSITIONED CONTROL ROD DOA 0500-04 THERMAL LIMITS AND FUEL CONDITIONING VIOLATION DEOP 100-00 RPV CONTROL DEOP 200-01 PRIMARY CONTAINMENT CONTROL DEOP 400-02 EMERGENCY DEPRESSURIZATION DEOP 400-05 FAILURE TO SCRAM DEOP 500-05 ALTERNATE INSERTION OF CONTROL RODS DAN 902-4 G-14 TORUS TO DW DIV I VAC BKR VLV OPEN DAN 902-4 H-14 TORUS TO DW DIV II VAC BKR VLV OPEN DAN 902-4 B-15 DW TO TORUS DP HI/LO DAN 902-5 A-3 ROD DRIFT ALARM DAN 902-5 A-6 APRM HI DAN 902-5 A-15 CHANNEL B MANUAL TRIP DAN 902-5 B-2 ROD DRIVE PUMP TRIP DAN 902-5 B-11 CHANNEL A/B NEUTRON MONITOR DAN 902-5 C-2 2A ROD DRIVE PUMP SUCTION LO DAN 902-5 C-3 ROD OUT BLOCK DAN 902-5 D-2 2B ROD DRIVE PP SUCT LO 3B ROD DRIVE PP SUCT LO DAN 902-5 D-13 CHANNEL 4-6 APRM HI-HI/INOP DAN 902-5 D-15 CHANNEL B RX SCRAM DAN 902-5 F-2 ACCUMULATOR CHARGING WTR PRESS LO DAN 902-5 G-2 ACCUMULATOR LVL HI/PRESS LO

SCENARIO ILT-N-1 Page 25 of 29 Rev. 00 (04/04)

I.

ILT-N-1 QUANTITATIVE ATTRIBUTES 8

Total malfunctions inserted (4 to 8) / (10 to 14) 2 Malfunctions that occur after EOP entry (1 to 4) / (3 to 6) 5 Abnormal events (1 to 2) / (2 to 3) 2 Major transients (1 to 2) / (2 to 3) 1 EOPs used beyond primary scram response EOP (1 to 3) / (3 to 5) 4 EOPs contingency procedures used (0 to 3) / (1 to 3) 55 mins Approximate scenario run time (45 to 60 min) / (one scenario may approach 90 minutes) 25 mins EOP run time (40 to 70% of scenario run time) 2 Crew critical tasks (2 to 5) / (5 to 8)

Yes Technical Specifications exercised (Yes or No)

SCENARIO ILT-N-1 Page 26 of 29 Rev. 00 (04/04)

Computer Aided Exercise Programs

  1. SCENARIO ilt-n-1.cae
  1. Setup for ILT 03-1 NRC Exam scenario ILT-N-1
  1. Written by SWF
  1. Rev 00
  1. 4/04
  1. Initial Conditions:
  1. Sets APRM gains to 1.0 irf niagain 1.0 irf niagainf (0 5) true
  1. Sticks 2 rods, J-5 and L-7 imf rodj05st imf rodl07st
  1. SETUP EVENT TRIGGERS
  1. Event Trigger 1 Fails Torus to Drywell vacuum breaker 20% open.

Trgset 1 "0"l2 imf P00 (1)l2

  1. Event Trigger 2 Drifts CRD H-01 into the core.

Trgset 2 "0"l2 imf rodh01di (2)l2

  1. Event Trigger 3 Electrically disarms rod H-01 and removes the drift-in malfunction for rod H-01 irf rodh01da (3) true trgset 3 "0"l2 trg 3 "dmf rodh01di"l2
  1. Event Trigger 4 ramps 2A CRD PP amp meter to 49.0 over 9:00 min.

trgset 4 "0"l4 ior rdipfake1 (4) 49.0 9:00l4 imf rdppatrp (4 9:00)l4

  1. Trigger 21 deletes 2A CRD PP amp meter override when the pump breaker opens.

trgset 21 "et_array(4).and. (.not. rdrpump(1))"l18 trg 21 "dor rdipfake1"l18

  1. Event Trigger 5 fails APRM Channel 5 to 125%

trgset 5 "0"l4 imf nia5pot (5) 125l4

  1. Event Trigger 6 Inserts a 0.007% steam leak upstream of the restrictors trgset 6 "0"l6 imf i21 (6) 0.007l6
  1. Event Trigger 7 activates when DW pressure > 1.0 or Mode SW is plced to S/D
  1. Ramps the CRD suction filter closed over 5 min. to cause the
  1. Isolates the 2B CRD pump suction filter to simulate a clogged filter causing a trip of the 2A CRD pump
  1. Causes CRD N06 accumulator trouble alarm to annuncuate and several others at timed intervals.

trgset 7 "(ppc268.gt. 1.0).or. (rpdmode4)"l6 trg 7 "ramp rdvstrnr(2) 0.25.01 5:00"l6 irf rdfiltb (7 5:02) falsel8 imf rodn06at (7 7:00)l8 imf rodg11at (7 8:35)l8 imf rodk13at (7 9:06)l8 imf rodd05at (7 9:30)l8

SCENARIO ILT-N-1 Page 27 of 29 Rev. 00 (04/04)

  1. Event Trigger 8 increases the size of the steam leak upstream of the restrictors to 0.2%.

trgset 8 "rdlfling(46).or. rdlfling(77)"l10 trg 8 "mmf I21 0.2"l10

  1. Trigger 25 increases the steam leak to 10% after a 5:00 min. delay trgset 25 "et_array(8).and. nbm459d.gt. 0.0019"l10 trg 25 "imf i21 (0 5:00) 10.0"l10
  1. Event Trigger 9 installs scram jumpers trgset 9 "0"l10 irf rpjumpas (9) onl10
  1. Event Trigger 10 installs MSL Group 1 RPV level bypass and Offgas High Radiation bypass jumpers.

trgset 10 "0"l10 irf ci59jp (10) inl10 irf ogogjp (10) inl10

  1. Event Trigger 11 pulls ARI fuses trgset 11 "0"l12 irf aw4 (11) pulledl12
  1. Event Trigger 12 opens crd pump suction xtie valve.

trgset 12 "0"l12 irf rdsuctie (12) truel12

  1. Event Trigger 13 close CRD 25 valve trgset 13 "0"l12 irf rd25pos (13) 0.0l12
  1. Event Trigger 14 clears stuck rod J-05.

trg 14 j05l14 trg 14 "dmf rodj05st"l14

  1. Event Trigger 15 clears stuck rod L-07.

trg 15 l07l14 trg 15 "dmf rodl07st"l14

  1. Event Trigger 16 valves in CRD xtie from U-3.

trgset 16 "0"l14 irf rdxtieu3 (16) truel14

  1. Event Trigger 17 Opens core spray CST suction valve 1402-2A to add water torus.

trgset 17 "0"l16 trg 17 "irf csppacst open"l16

  1. Event Trigger 18 activates when core spray CST suction valve 1402-2A reaches full open to close the valve.

trgset 18 "csv2a.gt. 0.98"l16 trg 18 "irf csppacst close"l16

  1. END Trigger Files:

File: j05 (rds303em.or. rds302in).and. rdlselw(46).and. rddpdriv.gt. 200.0 File: j07 (rds303em.or. rds302in).and. rdlselw(77).and. rddpdriv.gt. 200.0

SCENARIO ILT-N-1 Page 28 of 29 Rev. 00 (04/04)

Date: TODAY Unit 2 Turnover Online Information Protected Pathway(s)

Shutdown Information Unit 2 Priorities Maintain full power per BPO direction.

LCORAs Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Activities Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress DOS 1600-09 Pressure Suppression Chamber to Drywell Vacuum Breaker Full Stroke Exercise Test: operators have been briefed and are staging in the plant to begin the surveillance.

2B Stator cooling pump for motor replacement.

IRM 16 OOS for power supply replacement.

Unit 2 Conditions, Status, Abnormalities 2A CRD Pump Started 2A CRD Pump and secured 2B CRD pump due to suction filter being at 8 psid. Suction Filters to be changed on midnights.

Compensatory Actions Degradation WR/WO Frequency Compensatory Action None Unit 2 Abnormal Component Positions None Unit 2 Open Operability Determinations with Compensatory Actions:

None Events and Misc Information None 912 MWe Online Risk: Green Risk Equipment None Time to Boil: N/A Shutdown Risk: N/A Limit: MFLCPR 0.852 Steady Action Level: 0.98 S/D Method: Fast Shutdown Sequence A.

REACTIVITY INFO

SCENARIO ILT-N-1 Page 29 of 29 Rev. 00 (04/04)

Date: TODAY Unit 3 Turnover Online Information Protected Pathway(s)

Shutdown Information Unit 3 Priorities Maintain full power per BPO direction.

LCORAs None Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Activities Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities None Compensatory Actions Degradation WR/WO Frequency Compensatory Action None Unit 3 Abnormal Component Positions Unit 3 Open Operability Determinations with Compensatory Actions:

None Events and Misc Information None 912 MWe Online Risk: Green Risk Equipment None Time to Boil: N/A Shutdown Risk: N/A Limit: MFLCPR 0.883 Steady Action Level: 0.98 S/D Method: Fast Shutdown Sequence B.

REACTIVITY INFO

SCENARIO ILT-N-2 Page 1 of 27 Rev. 00 (04/04)

Dresden Generating Station ILT-N-2 RAISE POWER WITH RODS CONTROL ROD DOUBLE NOTCHES B CORE SPRAY LOOP LOW PRESURE ALARM ACCUMULATOR LOW PRESSURE ALARM FWLC SETPOINT DRIFTS HIGH RECIRC PUMP SEAL FAILURE ATWS Rev. 00 04/04 Operations Review:

Facility Representative Date Training Approval:

Exam Author Date

Appendix D Scenario Outline Form ES-D-1 SCENARIO ILT-N-2 Page 2 of 27 Rev. 00 (04/04)

Facility: Dresden Scenario No: ILT-N-2 Op-Test No: ILT 03-1 Examiners: ___________________________ Operators: ____________________________

Initial Conditions: Rx Power ~ 13%, 2B Stator Cooling Pump OOS, IRM 16 OOS.

Turnover: Continue with startup per DGP 1-1.

Event No.

Malfunction Number Event Type*

Event Description 1

None R

NSO SRO Raise power with rods 2

DORC13DO C

NSO SRO Control rod double notches while withdrawing control rods 3

CSV4B SCBFILOF S

ANSO SRO B CS system low pressure alarm 4

RODK08AT C

SRO Accumulator alarm due to low pressure 5

RLLMLS I

NSO SRO FWLC setpoint drifts high 6

RRMASL1F RRMASL2F Recirc pump seal failure 7

RDHLDEGA RDHLVFPA M

All All rods do not go in

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

SCENARIO ILT-N-2 Page 3 of 27 Rev. 00 (04/04)

Scenario Objective Evaluate the crews ability to control the plant during an ATWS condition.

Scenario Summary

1. Unit is at ~13% power. Continue with startup per DGP 1-1.
2. The following equipment is OOS:
a. 2B Stator Cooling Pump
b. IRM 16
3. LCOs:
a. None
4. Scenario Description The Team increases reactor power by withdrawing control rods per DOP 0400-01, and DGP 01-01.

The Team recognizes and responds to a control rod that double notches. The Team will insert the control rod to its target position.

B CS System low-pressure alarm is received and the SRO must review Tech Specs and declare the loop INOP.

An accumulator alarm comes up due to low pressure. The SRO will reference Tech Specs and declare the accumulator INOP.

The Team recognizes and responds to a failure of the automatic mode of the FWLC system by taking FWLC to manual and restores level to normal.

The 2A recirc pump seal fails and begins to pressurize the drywell, the suction valve will not close due to being shorted out from the leak and the Team will be forced to scram.

When the Team scrams the reactor, all the rods do not go in initially. Repeated scram resets will be successful in getting the rods to go in.

Scenario Run Time: 50 min Scenario Sequence Event One - Raise power by withdrawing control rods The Team increases reactor power by withdrawing control rods per DOP 0400-01, and DGP 01-01.

Malfunctions required:

0 Success Path:

Control rods pulled per applicable procedures.

SCENARIO ILT-N-2 Page 4 of 27 Rev. 00 (04/04)

Event Two - Control Rod Double Notches The Team recognizes and responds to a control rod that double notches. The Team will insert the control rod to its target position.

Malfunctions required: 1 Control rod double notches.

Success Path:

The control rod is moved to its target position.

Event Three - B CS System Low Pressure Alarm B CS System low-pressure alarm is received and the SRO must declare the loop INOP.

Malfunctions required: 1 B CS System low-pressure alarm.

Success Path:

SRO declares the system INOP.

Event Four - Accumulator Alarm An accumulator alarm comes in due to a low pressure alarm.

Malfunctions required: 1 Accumulator alarm.

Success Path:

References Tech Spec and declares the accumulator INOP.

SCENARIO ILT-N-2 Page 5 of 27 Rev. 00 (04/04)

Event Five - Failure of the FWLC Auto Mode The Team recognizes and responds to a failure of the automatic mode of the FWLC system.

Malfunctions required: 1 FWLC setpoint drift Success Path:

Takes manual control of the FWLC system.

Event Six - Recirc Pump Seal Failure The 2A recirc pump seal fails and begins to pressurize the drywell, the suction valve will not close due to being shorted out from the leak.

Malfunctions required: 3 Recirc pump seal failures.

Suction valve fails to close.

Success Path:

Scram prior to drywell reaching 2.0 psig.

Event Seven - ATWS When the Team scrams the reactor, all the rods do not go in initially. Repeated scram resets will be successful in getting the rods to go in.

Malfunctions required: 1 Partial CRD hydraulic lock.

Success Path:

Manually drives control rods, performs repeated scram resets per DEOP 500-1.

SCENARIO ILT-N-2 Page 6 of 27 Rev. 00 (04/04)

PRE-SCENARIO ACTIVITIES 1

If applicable, conduct pre-scenario activities in accordance with TQ-AA-106-0107, SIMULATOR EXAMINATION BRIEFING.

a. Inform the crew that (select an individual) is the QNE present in the Control Room.
b. Direct the crew to perform their briefs prior to entering the simulator.
c. Provide the crew with a copy of DGP 01-01 Unit Startup marked up and completed through G.59.
d. Crew directed to continue with plant startup, per Shift Manager.
e. Rod moves have been completed up to and including step 39.

2 Simulator Setup (the following steps can be done in any logical order)

a. Initialize simulator in IC 8 and perform the following before continuing below:
1) Insert control rods, until ~ 2.5 bypass valves open (~step 40).
2) Verify reactor power to be ~13%.
3) If Rod Move is used then, clear drift lights.
b. When rod moves complete, Run the initial setup CAEP file: ILT-N-2.cae.
c. Verify CAEP file ILT-N-2_ClrHydLk.cae opens and is waiting for trigger 15.
d. Cut in/out Cond Demins as needed, to maintain dp within limits (may need to cut in a bed).
e. Ensure running Condensate pump amps within limits.
f.

Advance the chart recorders..

3 Verify the following simulator conditions:

a. Reactor Power ~13 %.
b. CRSP marked up through appropriate step left off, from above.
c. CRD drive water pressure ~260#.
d. Only 2A and 2C Circ Water Pumps running.
e. 902-3 B-4 annunciator is CLEAR.
f.

Open 2B2 Startup vent MO 2-3606B.

g. Emergency Hydrogen Seal Oil Pump is OFF.
h. Drywell pressure is ~1.05#. May have to vent containment.
i.

Start E Drywell Cooler.

j.

Balance Recirc Pump controllers.

k. Set H2 Cooling Water controller in Auto balanced at 40OC.
l.

RWCU flow 610- 650 gpm.

m. 2A CRD pump running.
n. Verify Drywell pressure controllers in auto.

SCENARIO ILT-N-2 Page 7 of 27 Rev. 00 (04/04) 4 Place the following equipment out of service:

a. IRM channel 16.
b. 2B Stator Cooling Pump.

5 Complete the Simulator Setup Checklist.

SCENARIO ILT-N-2 Page 8 of 27 Rev. 00 (04/04)

Symbols are used throughout the text to identify specific items as indicated below:

Critical Tasks



Time Critical Tasks PRA Key Operator Actions

 Required Actions

Optional Actions

SCENARIO ILT-N-2 Page 9 of 27 Rev. 00 (04/04)

Event One - Raise power by withdrawing control rods Trigger Position Crew Actions or Behavior 1,2,3, 4,5 SIMULATOR OPERATOR / ROLE PLAY:

If requested as IMD to set gains to 1, (wait 3 minutes) then activate trigger 1, then report: gains set to 1. (This trigger can be toggled OFF, then back ON to adjust the gains more than once.)

If requested as an NLO to cut in a Condensate Demineralizer Bed (wait 3 min),

then activate the appropriate trigger, to cut in the desired bed (triggers: 2-D, 3-E, 4-F, OR 5-G), then report:: Cond Demin Bed (whichever) is cut in.

SRO Directs pulling control rods:

 Reviews REMA.

 Designates second verifier.

 Directs NSO to pulls rods.

NSO Performs the following actions per DOP 0400-01, Reactor Manual Control System Operation, and DGP 03-04, Control Rod Movements, as directed by the SRO:

Verifies the following prior to moving any control rod:

 Control rod selected on the select matrix is correct rod.

 Second Verification requirements satisfied.

 Rod Out Permit light is illuminated.

Withdraws rods as follows:

 Moves RONOR Switch to NOTCH OVERRIDE (use of the RONOR Switch is optional) and the Rod Movement Control switch to ROD OUT.

 Verifies ON light and proper Control Rod Timer operation.

 Releases switches before target position is reached.

Verifies rod settles to target position and proper response of nuclear instrumentation.

ANSO Performs the following second verification checks, for Control Rod moves, as requested/directed:

For first rod in a step:

 Verifies correct control rod pattern

 Verifies correct step and array.

 Verifies RWM rod blocks enabled For all rods moved:

 Verifies correct control rod selected.

 Verifies planned control rod motion is correct.

Verifies control rod at target position.

SCENARIO ILT-N-2 Page 10 of 27 Rev. 00 (04/04)

Event One - Raise power by withdrawing control rods Trigger Position Crew Actions or Behavior Event 1 Completion Criteria:

NONE-next event automatically occurs.

SCENARIO ILT-N-2 Page 11 of 27 Rev. 00 (04/04)

Event Two - Rod Double Notches Trigger Position Crew Actions or Behavior 16 17 Simulator Operator:

Verify Trigger 16 automatically activates when control rod G-1 passes beyond position 10. This inserts a Drift Out malfunction for control rod G-1.

Verify Trigger 17 automatically activates when control rod G-1 passes beyond position 12. This deletes the Drift Out malfunction for control rod G-1.

NSO Two possible paths can occur:

Either: Observes and announces that control rod G-1 has moved to position 14 (1 notch beyond its target position) and responds to alarms:



902-5 B-3, Rod Worth Min Block



902-5 C-3, Rod Out Block Should perform the following actions per DOA 0300-12, Mispositioned Control Rod:

 Discontinues rod movement and notifies SRO.

 Moves the mispositioned rod to its target position.



Records in DOS-0300-06, Control Rod Abnormality Record.

Or: When observes rod G-1 moving past its target position of 12, then:

 Uses the Emerg Rod In position of the Rod Out Notch Override switch to move the rod back to its target position prior to it latching in to position

14.

 Notifies the SRO.



Records in DOS-0300-06, Control Rod Abnormality Record.

SRO May enter and direct performance of DOA 0300-12, Mispositioned Control Rod.



Notifies the Shift Manager.



May refer to ITS 3.1.3 and determine that no actions are required.

May enter DOA 0300-05, Inoperable or Failed Control Rod Drives.

ROLE PLAY:

Respond as the Shift Manager as required.

QNE: If crew requests guidance from the QNE, respond I recommend inserting rod G-1 to position 12.

ANSO Monitors panels and assists as directed.

Event 2 Completion Criteria:

Rod returned to target position

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-2 Page 12 of 27 Rev. 00 (04/04)

Event Three - Core Spray System Low Pressure Alarm Trigger Position Crew Actions or Behavior 6

Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, activate trigger 6, which closes ECCS Keep Fill to 2B Core Spray loop and cracks open CS 4B valve to bleed the pressure down. Annunciator 902-3 D-7, 2A/B CORE SPRAY HDR PRESS LO will alarm.

ROLE PLAY:

NLO to investigate ECCS Jockey pump and LPCI relief valves. (wait 3 min.)

Report, the ECCS jockey pump appears to be operating normally.

If asked, wait 2 minutes Report, The relief valve appears to be leaking by.

If asked local CS system pressure, Wait 1 minute, Report, Local CS system pressure is approximately 0 pounds.

If sent to vent system:

Report, No water is coming out the vent.

If calling radwaste to ask about RBEDT levels:

Report, The input rate to the Unit 2 RBEDT has increased, level is currently 60%.

ANSO Reports alarm to SRO.

Carries out actions of DAN 902-3 D-7

 Verify FLOW TEST VLV MO 2-1402-4B is fully closed.

 Verify PP DISCH VLV MO 2-1402-24B is fully open.

 Check for relief valve RV 2-1402-28B 2B CORE SPRAY PMP DISCH HDR RV leaking to Reactor Building Equipment Drain Tank OR valves leaking into Torus.

 Notify Operations Shift Supervisor.

 Directs an Equipment Attendant to inspect ECCS jockey pump for proper operation.



Places 2B CS pump in PTL.

NSO



Assists ANSO with carrying out actions of DAN as necessary.

SRO



Directs carrying out actions of the DAN.

 References Tech Spec 3.5.1 Condition B1. Required action, restore Low pressure ECCS injection/spray subsystem to OPERABLE status within 7 days. (Surveillance Requirement SR 3.5.1.1.)



Orders 2B CS pump placed in PTL.



Notifies Shift manager and maintenance groups.

SCENARIO ILT-N-2 Page 13 of 27 Rev. 00 (04/04)

Event Three - Core Spray System Low Pressure Alarm Trigger Position Crew Actions or Behavior Event 3 Completion Criteria:

B CS declared inoperable.

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-2 Page 14 of 27 Rev. 00 (04/04)

Event Four - Accumulator Low Pressure Alarm Trigger Position Crew Actions or Behavior 7

8 Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, activate trigger 7, which causes annunciator 902-5 G-2, ACCUMULATOR LVL HI / PRESS LO to alarm and ACCUM light on full core display for M-3.

Role Play:

Operator sent to investigate accumulator alarm, wait 3 minutes Report M-3 is low, pressure, I will be recharging the accumulator.

IF asked, report accumulator pressure is 950#

Wait an additional 5 minutes and activate trigger 8, to clear the low pressure alarm.

report accumulator M-3 has been recharged and verified by (give a name).

NSO

 Acknowledges 902-5 G-2 (Accumulator trouble) alarm, and references the DAN.

 Sends NLO to determine if rod K-8 is low nitrogen pressure or high water level.

 Resets 902-5 G-2 when the NLO reports that accumulator has been charged ANSO



Documents the alarm per DOS 0300-06, Control Rod Drive Abnormality Record.

SRO



Acknowledges report of accumulator low pressure and recharging in progress.



Acknowledges report of accumulator low pressure condition has been corrected.

 References Tech Spec 3.1.5, Condition A, required Action A.2, Declare the associated control rod INOPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Event 4 Completion Criteria:

Tech Specs have been referenced Rod M-3 declared inoperable while recharging.

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-2 Page 15 of 27 Rev. 00 (04/04)

Event Five - FWLC Setpoint Drifts High Trigger Position Crew Actions or Behavior 9

Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, activate trigger 9, which causes feedwater level control system setpoint to drift high (to 60) over 10 min.

If the crew scrams the unit, begin the next event.

NSO Observes and announces RPV level rising or responds to alarm 902-5 E-8, RPV Lvl Hi.

Performs the following actions per DOA 0600-01 Transient Level Control:

 Takes manual control of the Feedwater Regulating Valves.

 Restores level to within band specified by the SRO ANSO Monitors panels and assists as directed.

SRO



Enters and directs performance of DOA 0600-01 Transient Level Control.



Notifies Shift Manager and IMD.

18 ROLE PLAY:

Respond to calls for assistance.

Cue:

If ANSO goes to check OIS screen, prompt him that the OIS Monitor is blank.

Time Compress and Role Play:

IM called to troubleshoot FWLC, wait 5 mins.

Insert trigger 18 to clear the FWLC setpoint drift, Report, FWLC has been fixed there was a problem with the Bailey system software.

If asked, FWLC can now be placed in Auto.

If asked, Shift Manager has directed FWLC be placed back in Auto. All notifications and approvals have been given.

SRO

 Directs restoring FWLC to AUTO IAW DOP 0600-06 Feedwater Regulating Valve (FRV) Operation.

NSO



Restores FWLC to AUTO IAW DOP 0600-06 Feedwater Regulating Valve (FRV) Operation. (depending on which steps of the procedure used, the following steps may be completed in a different order.)

 Verify applicable FRV(s) are in MASTER MANUAL.

 Verify Reactor Power and RPV Level are stable.

 Verify RX LO FLOW CONTROL STATION in MAN AND LOW FLOW FRV is closed.

 Match MASTER CONTROL STATION setpoint to actual RPV Level.

 Place MASTER CONTROL STATION in AUTO.

 Adjust MASTER CONTROL STATION setpoint to desired RPV Level.

 Place RX LO FLOW CONTROL STATION in AUTO.

SCENARIO ILT-N-2 Page 16 of 27 Rev. 00 (04/04)

Event Five - FWLC Setpoint Drifts High Trigger Position Crew Actions or Behavior ANSO Monitors panels and assists as directed.

Event 5 Completion Criteria:

Feedwater level control system returned to Automatic control and RPV level is stable.

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-2 Page 17 of 27 Rev. 00 (04/04)

Event Six and Seven - Recirc Pump Seal Failure and ATWS Trigger Position Crew Actions or Behavior 10 Simulator Operator Actions:

At the discretion of the NRC Lead Examiner, activate trigger 10, which fails the recirc pump seal # 1 and 1 minute later fails the number 2 seal. This trigger also prevents the 2A Recirc pump suction valve from closing.

NSO



Acknowledges 902-4 F-3 (2A Recirc PP #2 Seal Leak) alarm, and references the DAN.

 Notifies SRO of seal failure.



Verify CRD pump A OR B is running.

 Monitors Drywell pressure, PI 2-1640-5, on Panel 902-5 and reports Drywell pressure is slowly rising.

 SCRAMS the reactor prior to exceeding scram setpoint.

 Presses scram pushbuttons

 Places mode switch in shutdown

 Checks rods inserted; discovers ATWS condition

 Initiates ARI

 Verifies recirc pump speed at minimum.

ANSO



Dispatches NLO to verify seal purge flow is two gpm (1.5 gpm to 2.5 gpm)

 Monitors Drywell temperature, TR 2-1340-1, on Panel 902-3.

SCENARIO ILT-N-2 Page 18 of 27 Rev. 00 (04/04)

Event Six and Seven - Recirc Pump Seal Failure and ATWS Trigger Position Crew Actions or Behavior SRO

 Acknowledges Recirc Pump Seal Failure.

 Enters DOA 40-01, SLOW LEAK or may enter DGP 02-01 Normal Unit Shutdown or DGP 2-3, Reactor Scram.



Per the DAN, may enter and perform DOP 0202-04 Unit 2 Reactor Recirculation System Shutdown.



Per the DAN, may attempt to isolate the 2A Recirc Loop.



May enter DOA 0300-01, CRD SYSTEM FAILURE

 Orders the reactor scrammed prior to reaching scram setpoint.

Enters DEOP 100, RPV Control. Upon receiving report of ATWS condition, exits DEOP 100 and enters DEOP 400-5, Failure to Scram, and directs:

 Placing ADS to inhibit (RPV 6.2)

 Placing both CS pumps in PTL Power Leg

 Running back recirc to minimum.

 Trip the recirc pumps or verifies tripped.

 Directing Alternate Rod Insertion per DEOP 500-05: (RPV 6.1)

  • manually driving rods.
  • repeated scram/resets.

 Initiating SBLC before SP/T of 110°F.

Level Leg

 Verification water level instruments are accurate

 Verification any required automatic actions have occurred IF Rx power >6% or unknown then (path 8)



Terminating and Preventing injection except boron and CRD until RPV/L is -35 inches. (RPV 6.3)



If SP/T is above 110°F, lets level drop until:

  • Power is below 6%, OR
  • Level drops to -143 in. (TAF), OR
  • All ADSVs stay closed and PC/P stays below 2 psig IF Rx power <6 % then (path 7):

 Re-establishing injection to MAINTAIN RPV water level above

-164 inches. (RPV 6.4)

Pressure Leg

 Dropping RPV/P to 945 psig using ADSVs if ADSV cycling.



Maintaining <1060 psig using HPCI/ADSVs

SCENARIO ILT-N-2 Page 19 of 27 Rev. 00 (04/04)

Event Six and Seven - Recirc Pump Seal Failure and ATWS Trigger Position Crew Actions or Behavior NSO / ANSO Performs DEOP 400-5, Failure to Scram, actions as directed:

 Places ADS to inhibit (RPV 6.2)

 Places both CS pumps in PTL Power Leg



If Rx power > 6%, Trips recirculation pumps

 Performs Alternate Rod Insertion. (see below for specific actions) (RPV 6.1)

 Initiates boron injection.

Level Leg



Terminates and Prevents injection except boron and CRD until RPV/L is -35 inches. (RPV 6.3)



If SP/T is above 110°F, lets level drop until:

Power is below 6%, OR Level drops to -143 in. (TAF), OR All ADSVs stay closed and PC/P stays below 2 psig

 Re-establishes injection to MAINTAIN RPV water level above -164 inches. (RPV 6.4)

Pressure Leg

 Drops RPV/P to 945 psig ADSVs as directed.

 Maintains <1060 psig using HPCI/ADSVs.

NSO Performs manual control rod insertion per DEOP 500-05, Alternate Insertion of Control Rods, as directed: (RPV 6.1)

 Bypasses the RWM

 Starts the second CRD pump

 Maximizes drive water pressure using one or more of the methods in DEOP 500-05.

 Inserts rods using RONOR in EMERG IN or the normal rod movement control switch Performs repeated scram/resets per DEOP 500-05, Alternate Insertion of Control Rods, as directed: (RPV 6.1)

 Depresses close pushbuttons for SDV vent and drain valves



If RPV/L <-59 inches, directs pulling ARI fuses.

 Attempts to reset scram

 Directs scram jumpers installed.

 Resets the scram

 Verifies all scram valves closed

 Opens the SDV vent and drains

 When 902-5 C-1 clears, scrams reactor



Repeats as necessary 11 SIMULATOR OPERATOR / ROLE PLAY:

Operator to install -59" MSIV closure jumpers and Off Gas Hi Rad jumpers (wait 5 min), activate trigger 11 and Report the -59" MSIV closure jumpers and Off Gas Hi Rad jumpers are installed.

SCENARIO ILT-N-2 Page 20 of 27 Rev. 00 (04/04)

Event Six and Seven - Recirc Pump Seal Failure and ATWS Trigger Position Crew Actions or Behavior 12 13 SIMULATOR OPERATOR / ROLE PLAY:

Operator to pull ARI fuses (wait 5 min), verify trigger 12 activated and report the ARI fuses are pulled.

Operator to install scram jumpers (wait 5 min), verify trigger 13 activated and report the scram jumpers are installed.

SRO May enter DEOP 200-1, Primary Containment Control, and performs/directs:



Starting Drywell Coolers per DEOP 0500-02.



Initiation of torus sprays before PC/P of 9 psig



If PC/P is above 9 psig or before DW/T reaches 281°F:

Verification of DSIL Tripping of recirc pumps and DW coolers Initiation of DW sprays



Initiation of torus cooling



Verifies initiation of drywell and torus H2/O2 monitors 19 SIMULATOR OPERATOR / ROLE PLAY:

Operator to close CRD 25 valve (wait 4 min) then verify trigger 19 activated and report The CRD 25 valve is closed.

14 SIMULATOR OPERATOR / ROLE PLAY:

Operator to install jumpers to defeat DW Cooler trips (wait 5 min) then verify trigger 14 activated and report the DW Cooler trip jumpers are installed.

15 SIMULATOR OPERATOR:

After the crew has reset the scram AND at the discretion of the Lead examiner, insert trigger 15, which runs CAEP file: ILT-N-2_ClrHydLk.cae to remove the SDV hydraulic lock.

NSO

 Reports that all rods inserted and performs the following as directed:



Restores level to +8 to +48 inches.

SRO Based on report of all rods inserted:

 Directs securing of SBLC, exits DEOP 400-05, Failure to Scram



Continue actions in DGP 2-3, Rx Scram.

 Enters DEOP 100, RPV Control, and directs:

 Restoring RPV level to +8 to +48 inches.



Develop a cooldown strategy (i.e.; reopen MSIVs and/or restart RWCU)

Event 6 and 7 Completion Criteria:

Control rods inserted, RPV level and pressure stabilized.

AND, At the discretion of the NRC Lead Examiner.

SCENARIO ILT-N-2 Page 21 of 27 Rev. 00 (04/04)

Critical Tasks (RPV-6.1)

With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.

(RPV-6.2)

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

(RPV-6.3)

During an ATWS with conditions met to perform power/level control TERMINATE AND PREVENT INJECTION, with exception of boron and CRD, into the RPV until conditions are met to re-establish injection.

(RPV-6.4)

When conditions are met to establish injection use available injection systems to MAINTAIN RPV water level above -164.

SCENARIO ILT-N-2 Page 22 of 27 REFERENCES PROCEDURE TITLE DGP 02-01 NORMAL UNIT SHUTDOWN DGP 02-03 REACTOR SCRAM DGP 03-01 ROUTINE POWER CHANGES DGP 03-04 CONTROL ROD MOVEMENTS DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM OPERATION DOP 0202-04 UNIT 2 REACTOR RECIRCULATION SYSTEM SHUTDOWN DOS 0300-06 CONTROL ROD ABNORMALITY LOG DOA 04-01 SLOW LEAK DOA 0300-05 INOPERABLE OR FAILED CONTROL ROD DRIVES DOA 0300-12 MISPOSITIONED CONTROL ROD DOA 0600-01 TRANSIENT LEVEL CONTROL DEOP 0100 RPV CONTROL DEOP 200-1 PRIMARY CONTAINMENT CONTROL DEOP 400-5 FAILURE TO SCRAM DEOP 0500-01 ALTERNATE STANDBY LIQUID CONTROL INJECTION DEOP 0500-02 BYPASSING INTERLOCKS AND ISOLATIONS DEOP 0500-05 ALTERNATE INSERTION OF CONTROL RODS DAN 902-3 D-7 2A/B CORE SPRAY HDR PRESS LO DAN 902-4 F-3 2A RECIRC PP #2 SEAL LEAK DAN 902-5 B-3 ROD WORTH MIN BLOCK DAN 902-5 C-3 ROD OUT BLOCK DAN 902-5 E-8 RPV LVL HI DAN 902-5 G-2 ACCUMULATOR LVL HI / PRESS LO

SCENARIO ILT-N-2 Page 23 of 27 Simulator Scenario Review Checklist (contd)

ILT-N-2 Quantitative Attributes 7

Total malfunctions inserted (4 to 8) / (10 to 14) 1 Malfunctions that occur after EOP entry (1 to 4) / (3 to 6) 3 Abnormal events (1 to 2) / (2 to 3) 2 Major transients (1 to 2) / (2 to 3) 2 EOPs used beyond primary scram response EOP (1 to 3) / (3 to 5) 2 EOPs contingency procedures used (0 to 3) / (1 to 3) 50 mins Approximate scenario run time (45 to 60 min) / (one scenario may approach 90 minutes) 25 mins EOP run time (40 to 70% of scenario run time) 4 Crew critical tasks (2 to 5) / (5 to 8)

Yes Technical Specifications exercised (Yes or No)

SCENARIO ILT-N-2 Page 24 of 27 Computer Aided Exercise Programs

  1. SCENARIO ilt-n-2.cae
  1. Setup for ILT 03-1 NRC Exam scenario ILT-N-2
  1. Written by SWF
  1. Rev 00
  1. 4/04
  1. INITIAL CONDITIONS
  1. Set hydraulic lock imf rdhlvfpa 91.0 imf rdhlvfpb 90.0 imf rdhldega 90.0 imf rdhldegb 91.0
  1. Bypass Torus O2 Sample point due to high O2 in Torus.

ior podon4 bypass

  1. Sets APRM gains to 1 irf niagain 1.0l2 irf niagainf (0 2) truel2
  1. Prevents 2A recirc pump suction valve from closing.

ior rrd4aopn offl2

  1. SETUP EVENT TRIGGERS
  1. Event Trigger 1 sets gain for all 6 APRMs to 1.0 trgset 1 "0"l2 trg 1 "irf niagainf true"l2
  1. Event Trigger 2 places Condensate Demin D in service trgset 2 "0"l4 irf s44 (2) truel4
  1. Event Trigger 3 places Condensate Demin E in service trgset 3 "0"l4 irf s45 (3) truel4
  1. Event Trigger 4 places Condensate Demin F in service trgset 4 "0"l4 irf s46 (4) truel4
  1. Event Trigger 5 places Condensate Demin G in service trgset 5 "0"l6 irf s47 (5) truel6
  1. Event Trigger 6 causes 2B Core System Low Pressure Alarm (902-3 D-7)
  1. Cracks open 4B VLV and isolates Keep Fill to 2B Loop trgset 6 "0"l6 trg 6 "set csv4b = 0.001" irf csbfilof (6) closedl6
  1. Event Trigger 7 causes an accumulator alarm M-3.

Trgset 7 "0"l6 imf rodm03at (7)l6

  1. Event Trigger 8 allows resetting accumulator alarm M-3.

trgset 8 "0"l8 trg 8 "dmf rodm03at"l8

SCENARIO ILT-N-2 Page 25 of 27

  1. Event Trigger 9 allows causes feedwater level control system setpoint to drift high (60") over 10 minutes.

trgset 9 "0"l8 irf rllmls (9) 60 10:00l8

  1. Event Trigger 10 fails recirc pump seal # 1 then fails #2 1 minute later.

trgset 10 "0"l8 imf rrmasl1f (10)l8 imf rrmasl2f (10 1:00)l8

  1. Event Trigger 11 installs MSL Group 1 RPV level bypass and Offgas High Radiation bypass jumpers.

trgset 11 "0"l10 irf ci59jp (11) inl10 irf ogogjp (11) inl10

  1. Event Trigger 12 pulls ARI fuses trgset 12 "0"l10 irf aw4 (12) pulledl10
  1. Event Trigger 13 installs scram jumpers trgset 13 "0"l12 irf rpjumpas (13) onl12
  1. Event Trigger 14 installs DW cooler jumpers trgset 14 "0"l12 irf cidw28jp (14) inl12 irf cidw29jp (14) inl12
  1. Event Trigger 15 runs CAEP to clear SDV hydraulic lock trgset 15 "0"l14 cae a:ILT-N-2_ClrHydLk.cae /trig 15l14
  1. Event Trigger 16 Simulates a double notch of Rod G-01 by putting in a drift out malf when G-01 is past postion "10".

This works with next trigger.

trgset 16 "rdzactls(2).gt. 30.5"l16 trg 16 "imf rodg01do"l16

  1. Event Trigger 17 Removes drift out malf when G-01 is past postion "12". This works with previous trigger.

trgset 17 "rdzactls(2).gt. 37.0"l16 trg 17 "dmf rodg01do"l16

  1. Event Trigger 18 removes feedwater level control system setpoint drift.

trgset 18 "0"l16 trg 18 "drf rllmls"l16

  1. Event Trigger 19 closes CRD 25 valve.

trgset 19 "0"l16 irf rd25pos (19) 0.0l16

  1. END

SCENARIO ILT-N-2 Page 26 of 27 Date: TODAY Unit 2 Turnover ECCS Status:

All available Online Information Protected Pathway(s)

Shutdown Information Time to Boil: 0 Shutdown Risk: N/A Reactivity Management 0

MWe Online Risk:

Green Risk Equipment:

None Unit 2 Priorities Continue startup per DGP 1-1.

Limit: MFLCPR 0.78 Increasing slowly Action Level:

0.980 S/D Method: Fast Shutdown Sequence LCORAs LCORA None Start Title Clock Ends Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Activities Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress None Unit 2 Conditions, Status, Abnormalities 2B Stator cooling pump for motor replacement.

IRM 16 OOS for power supply replacement.

Compensatory Actions Degradation WR/WO Frequency Compensatory Action Unit 2 Abnormal Component Position None U2 Open Operability Determinations with Compensatory Actions None Events and Misc. Information Started 2A CRD pump and secured 2B CRD pump due to suction filter being at 8 psid. Suction filters to be changed on midnights.

SCENARIO ILT-N-2 Page 27 of 27 Date: TODAY Unit 3 Turnover ECCS Status: All available Online Information Protected Pathway(s)

Shutdown Information Time to Boil: 0 Shutdown Risk: N/A Reactivity Management 912 MWe Online Risk:

Green Risk Equipment:

None Unit 3 Priorities Maintain load per BPO direction.

Limit: MFLCPR 0.78 Increasing slowly Action Level:

0.980 S/D Method: Fast Shutdown Sequence LCORAs LCORA # None Start Title Clock Ends Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Activities Shift 1 Activities (X = Completed)

Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities None Compensatory Actions Degradation WR/WO Frequency Compensatory Action Unit 3 Abnormal Component Position None U3 Open Operability Determinations with Compensatory Actions None Events and Misc. Information None

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