ML102230441

2010 Initial License Exam, Scenarios

ML102230441
Person / Time
Site:	Dresden
Issue date:	03/08/2010
From:	NRC/RGN-III
To:	Exelon Generation Co, Exelon Nuclear
References
Download: ML102230441 (82)

Text

Dresden Generating Station ILT-N-1 LOWER REACTOR POWER USING RECIRCULATION FLOW REMOVE 345KV L0302 POWERTON FROM SERVICE INSTRUMENT AIR COMPRESSOR TRIP CONTROL ROD RPIS FAILURE ISOLATION CONDENSER INADVERTENT INITIATION FWLC CONTROLLER SETPOINT DRIFTS HIGH LOSS OF INSTRUMENT AIR / REACTOR SCRAM STEAM LEAK IN THE DRYWELL / EMERGENCY DEPRESSURIZATION Rev. 00 10/09

Developed By:

Exam Author Date Approved By:

Facility Representative Date

Scenario Outline Station: Dresden Generating Station Scenario No.: ILT-N-1 Class ID: 2010-301 Evaluators Operators /

crew position / ATC / BOP / CRS Initial Conditions: 91% power.

Turnover: Lower power with Recirc flow.

Switching orders received to remove 345KV L0302 from service.

Event No. Malf. No. Event Type* Event Description 1 NONE R ATC RECIRC - Lower Reactor Power using Recirculation Flow.

2 NONE N BOP SWITCHYARDS - Remove 345KV L0302 Powerton From Service. 3 N33 C BOP INST AIR - Instrument Air Compressor Trip.

4 RDFAILF5 I ATC CRD - RPIS failure for rod F-05.

T 5 ICSPDFT I BOP ISO COND - Inadvertent Initiation.

T 6 RLLMLS I ATC FW - FWLC Controller Drifts High.

7 NP2 M TEAM Instrument Air System Leak / Team Takes a Manual Scram. 8 I21 K23 K40 M TEAM Steam Leak inside the Drywell & Loss of Bus 23-1 & 28, Losing Ability to Spray Drywell / Team Emergency Depressurizes. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec SCENARIO ILT-N-1 Page 2 of 27 Rev. 00 (10/09)

Scenario Objective Evaluate the Team's ability to operate the plant with a Drywell Steam Leak requiring Emergency Depressurization.

Scenario Summary

1. Unit is at 91% power.

2. The following equipment is OOS:

a. None 3. LCOs: a. None Scenario Sequence The Team continues reactor power reduction using recirculation flow. The TSO directs the Team to remove 345KV L0302 Powerton from service. 3C Instrument Air Compressor (IAC) trips. Instrument Air pressure begins slowly dropping. Standby Air Compressor 2B is started to restore air pressure. Control rod F-05 loses all RPIS indication. The Team will insert the control rod, reference Tech Specs and direct taking it OOS. The Isolation Condenser initiates due to setpoint drift. The Team will stop operation of the Isolation Condenser and reference Tech Specs. The FWLC setpoint drifts high. The Team will take manual control of the FWLC system. A large leak develops in the Instrument Air system. The Team will scram the reactor due to the leak severity. A short time after the scram, a steam leak in the Drywell begins. When the Team attempts to spray the Drywell, Bus 23-1 trips resulting in a loss of one Division of Drywell Spray. The leak worsens and Primary Containment pressure will exceed the PSP limit and require the Team to Emergency Depressurize.

Event One - Lower Reactor Power Using Recirculation Flow The Team continues reactor power reduction using recirculation flow. Malfunctions required: 0 (None) Success Path: The Team continues reactor power reduction using recirculation flow.

SCENARIO ILT-N-1 Page 3 of 27 Rev. 00 (10/09)

Event Two - Remove 345KV L0302 Powerton from Service The Team will remove 345KV L0302 Powerton from Service. Malfunctions required: 0 (None) Success Path: Removes 345KV L0302 Powerton from Service per the switching orders.

Event Three - Instrument Air Compressor Trip 3C Instrument Air Compressor trips. Instrument Air pressure begins slowly dropping. Malfunctions required: 1 (3C Instrument Air Compressor trips) Success Path: Standby Air Compressor 2B is started.

Event Four - Control Rod RPIS Failure Control rod F-05 will lose all RPIS indication. Malfunctions required: 1 (Loss of Control Rod F-05 RPIS indication) Success Path: Inserts Control Rod F-05 and references Tech Specs.

Event Five - Isolation Condenser Inadvertent Initiation The Isolation Condenser initiates due to setpoint drift. Malfunctions required: 1 (Isolation Condenser initiation setpoint drift) Success Path: The Team will stop operation of the Isolation Condenser and reference Tech Specs.

SCENARIO ILT-N-1 Page 4 of 27 Rev. 00 (10/09)

Event Six - FWLC Setpoint Drifts High The FWLC setpoint will drift high. Malfunctions required: 1 (FWLC setpoint failure) Success Path: The Team performs DOA 0600-01, Transient Level Control, and takes manual control of FWLC.

Event Seven - Loss of Instrument Air / Reactor Scram A large leak develops in the Instrument Air system. Malfunctions required: 1 (Instrument Air Leak) Success Path: Performs a manual scram.

Event Eight - Steam Leak Inside the Drywell / Emergency Depressurization A steam leak develops in the Drywell. When the Team attempts to spray the Dr ywell, Bus 23-1 trips on overcurrent. The leak worsens and Primary Containment pressure exceeds the PSP limit. The Team performs an Emergency Depressurization.

Malfunctions required: 2 (Steam leak in the Drywell). (Loss of Drywell Sprays).

Success Path:

The Team performs an Emergency Depressurization.

SCENARIO ILT-N-1 Page 5 of 27 Rev. 00 (10/09)

PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre-scenario activities in accordance with TQ-JA-150-08, SIMU LATOR EXAMINATION BRIEFING.

a. Direct the crew to perform their briefs prior to entering the simulator.

b. Provide the Team a copy of DGP 03-01, Power Changes, marked up for load drop through inserting control rods to reduce FCL prior to reducing recirc flow.

c. Provide a marked up CRSP for the rod insertion including a REMA for routine load drop.

d. Provide the Team with switching orders to remove 345KV Line 0302 from service.

e. Provide the Team a copy of DOP 6400-13, Electrical Yard Switching.

2 Simulator Setup (the following steps can be done in any logical order) a. Initialize simulator in an IC which allows establishing the following: 1) FCL @ 90-94%. 2) Recirc flow adjusted to establish ~840 MWe. b. Cut in/out Cond Demins as needed, to maintain DP within limits.

c. Ensure running Condensate pump amps within limits.

d. Advance the chart recorders.

3 Verify the following simulator conditions:

a. Verify control rod F-05 at position 48.

b. Verify 2A and 2C IAC running with 2B IAC off. c. Verify TR 86 LTC in MANUAL.

NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.

4 Run the initial setup CAEP file: ILT-N-1.cae

5 Place the following equipment out of service:

a. None 6 Complete the Simulator Setup Checklist.

SCENARIO ILT-N-1 Page 6 of 27 Rev. 00 (10/09)

SCENARIO ILT-N-1 Page 7 of 27 Rev. 00 (10/09)

Symbols are used throughout the text to identify specific items as indicated below: Critical Tasks Required Actions Optional Actions

SCENARIO ILT-N-1 Page 8 of 27 Rev. 00 (10/09)

Event One - Lower Reactor Power Using Recirculation Flow Trigger Position Crew Actions or Behavior Note: The turnover directs the crew to reduce load to 775 MWe.

1 Floor Instructor / Simulator Operator / Role Play:

If the team announces that they will adjust gains, inform them an extra NSO will perform the adjustment. Then: Tell the team you are time compressing. Direct the simulator operator to activate trigger 1 and verify gains within limits. Inform the team the gains are adjusted. (Note: trigger 1 can be toggled OFF, then back ON as many times as necessary to adjust gains) 2 Simulator Operator / Role Play:

EO to cut out a condensate demin bed: wait 1 min, and then activate Trigger 2 which isolates 2G condensate demin bed. After the Instructor Station indicates 2G condensate demin bed is isolated, then report that "2G condensate demin bed is cut out". CRS Directs NSO to reduce load to 775 MWe using recirculation flow.

ATC Performs the following actions per DGP 03-01, Power Changes, and DOP 0202-03, Reactor Recirculation Flow Control System Operation, as directed: Uses MASTER RECIRC FLOW CONTLR, 2(3)-262-22, potentiometer to reduce flow AND control reactor power. Notifies CRS when at 775 MWe.

BOP Monitors Panels. Event 1 Completion Criteria:

Load dropped to 775 MWe, AND / OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-1 Page 9 of 27 Rev. 00 (10/09)

Event Two- Remove 345KV L0302 Powerton From Service Trigger Position Crew Actions or Behavior Role Play:

At the discretion of the Lead Examiner, call as the TSO and direct "remove 345KV L0302 Powerton from service per the switching orders".

Role Play:

EO in 345KV Switchyard: Check the 345KV Instructor Station drawing for equipment status and then report its st atus to the control room.

3 Simulator Operator:

Operator directed to open 345KV L0302 line disconnect and hang an ELOT card on it: activate trigger 3, which opens the 345KV L0302 disconnect. Wait 2 min and then report "the 345KV L0302 line disconnect is open and the ELOT card is hung".

BOP Acknowledges the TSO directions and performs the following per the switching orders and DOP 6400-13, Electrical Yard Switching, step G.3: Checks 345KV ring bus normal. Checks open 345KV BT 4-8 CB. Opens 345KV BT 4-5 CB. Opens 345KV BT 3-4 CB.

Directs operator to open 345KV L0302 disconnect and hang an ELOT card on it. Closes 345KV BT 4-5 CB. Closes 345KV BT 3-4 CB. Reports to TSO and CRS that switching is complete.

ATC Monitors the panels.

CRS Directs control room activities.

Event 2 Completion Criteria:

345KV L0302 Powerton removed from service, AND/OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-1 Page 10 of 27 Rev. 00 (10/09)

Event Three - Instrument Air Compressor Trip Trigger Position Applicant's Actions or Behavior 4 SIMULATOR OPERATOR:

At the direction of the Lead Examiner, activate trigger 4, which trips the 3C Instrument Air Compressor and inserts a small IA leak to cause pressure to slowly drop.

ROLE PLAY:

EO to investigate 3C IAC trip: (Wait 2 min) Report "the 3C IAC tripped on low lube oil pressure. There is nothing else abnormal at the compressor". EO to check 3C IAC breaker: (Wait 2 min) Report "the 3C IAC breaker is closed and looks normal". Note: The compressor will NOT be restored to operation.

5 SIMULATOR OPERATOR / ROLE PLAY:

EO to lineup 2B IAC to U2 Instrument Air System, wait 2 min, activate trigger 5 and then report "2B IAC is lined up to U2 Instrument Air System".

ROLE PLAY:

EO to verify proper operation of 2B IAC: (Wait 2 min) Report "the 2B IAC is operating normally". If not yet directed to line up 2B IAC to U2 Instrument Air System, then also report that "2B IAC Dryer is not lined up to the Instrument Air header".

BOP Announces alarm 923-1 B-5, U2 OR U3 INST AIR COMP TRIP: Reports 3C IAC tripped Directs an EO to investigate the cause of the 3C Instrument Air Compressor trip. May send an EO to check 3C IAC breaker.

CRS May enter DOA 4700-01, Instrument Air System Failure. Directs BOP to perform DOP 6700-20, 480 Volt Breaker Trip.

BOP Performs DOA 4700-01, Instrument Air System Failure, as directed: Starts the 2B IAC. Directs an EO to verify proper operation of 2B IAC. Directs an EO to line up 2B IAC to the IA header. Performs DOP 6700-20, 480 Volt Breaker Trip.

Event 3 Completion Criteria

Team has started 2B IAC, AND/OR At the discretion of the Lead Examiner.

SCENARIO ILT-N-1 Page 11 of 27 Rev. 00 (10/09)

Event Four - Control Rod RPIS Failure Trigger Position Crew Actions or Behavior 6 SIMULATOR OPERATOR:

At the direction of the Lead Examiner, activate trigger 6, RPIS failure for control rod F-05. ROLE PLAY:

Respond as Support Groups notified.

ATC Reports and responds to DANs 902-5 A-3 ROD DRIFT, and B-3 ROD WORTH MIN

BLOCK. Views Full Core Display and identifies CRD with Rod Drift light. Selects Control Rod F-05 and reports no indication on Four Rod Display for Control Rod F-05.

ATC Recognizes loss of control rod F-05 position indication on Full Core Display, Four Rod Display, RWM, and/or Process Computer.

CRS Enters DOA 0300-06, RPIS Failure, and directs its actions.

ATC Performs subsequent actions of DOA 0300-06, RPIS FAILURE: Stops any power change or control rod motion in progress. May insert Rod F-05 to 00 prior to entering DOA 0300-06. Enters substitute position of 48 for F-05. Inserts control rod F-05 one notch. Determines no control rod position indication at alternate position.

Drives rod F-05 to fully inserted position. Calls WEC to electrically or hydraulically isolate the control rod F-05 HCU. May enter a substitute position and take OOS on the RWM per DOP 0400-02, Rod Worth Minimizer.

CRS References appropriate plant licensing documents and determines: TS 3.1.3, condition C, required actions: C.1 Fully insert inoperable control rod within 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 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Directs electrically or hydraulically isolating control rod F-05 HCU.

ROLE PLAY As QNE acknowledge reports. If concurrence is requested for any action, report "I concur with (insert requested action here)"

BOP Monitors panel, provides assistance as directed.

SCENARIO ILT-N-1 Page 12 of 27 Rev. 00 (10/09) Event Four - Control Rod RPIS Failure Trigger Position Crew Actions or Behavior TEAM May enter DOA 0300-12, Mispositioned Control Rod.

Notifies the Shift Manager, QNE, Work Week Manager, Fin team, IMD, OR EMD.

ROLE PLAY:

When EO directed to disarm control rod F-05, report: "I'll disarm F-05 after I receive a pre-job brief" (it is not intended for this to be completed).

ATC Records failed RPIS indication per DOS 0300-06, CRD Abnormality Record. Event 4 Completion Criteria:

DOA 0300-06 actions have been taken, Technical Specifications have been referenced, AND/OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-1 Page 13 of 27 Rev. 00 (10/09)

Event Five - Isolation Condenser Inadvertent Initiation Trigger Position Crew Actions or Behavior 7 SIMULATOR OPERATOR:

At the direction of the Lead Examiner, activate trigger 7 , which drifts the Isolation Condenser Initiation setpoint.

ROLE PLAY:

Respond as Support Groups notified.

BOP Reports and responds to DANs: 902-3 B-4, ISOL CONDR VLVS OFF NORM. 902-3 C-4, ISOL CONDR TEMP HI. 902-4 A-15, ISOL CONDR CH A/B INITIATION. Determines Isolation Condenser in operation due to MO 2-1301-3 valve open.

TEAM Determines Isolation Condenser initiation spurious due to RPV pressure in normal band. CRS Directs removing the Isolation Condenser from service.

BOP Places MO 2-1301-3 in PTL. When MO 2-1301-3 indicates closed, reports that the Isolation Condenser is removed from service.

ATC Monitors reactor water level, pressure, and power.

TEAM May enter DGA 07, Unpredicted Reactivity Addition.

CRS References appropriate plant licensing documents and determines: TS 3.3.5.2, condition A. required actions:

A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE immediately, AND, A.2 Restore IC System to OPERABLE status within 14 days. TS 3.5.3, condition A. required actions: (May wait for IMD investigation) A.1 Declare IC System inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; AND, A.2 Place channel(s) in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

TEAM Notifies Security to limit access to area under Isolation Condenser vent.

Notifies Radiation Protection to survey under the Isolation Condenser vent.

SCENARIO ILT-N-1 Page 14 of 27 Rev. 00 (10/09) Event Five - Isolation Condenser Inadvertent Initiation Trigger Position Crew Actions or Behavior Event 5 Completion Criteria:

Isolation Condenser removed from operation, Technical Specifications have been referenced, AND/OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-1 Page 15 of 27 Rev. 00 (10/09)

Event Six - FWLC Controller Setpoint Drifts High Trigger Position Crew Actions or Behavior 8 Simulator Operator:

At the discretion of the Lead Examiner, activate trigger 8, which causes the FWLC setpoint to drift high.

Role Play:

Support Personnel: respond you will assist as directed.

TEAM Determines RPV level is increasing.

CRS Enters DOA 0600-01, Transient Level Control. Directs ATC to control RPV level manually.

ATC Places FWLC in MAN and manually controls RPV level.

BOP Assists as directed.

TEAM May enter DGA 07, Unpredicted Reactivity Addition.

CRS Contacts support personnel for assistance. Event 6 Completion Criteria:

RPV level stabilized, AND/OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-1 Page 16 of 27 Rev. 00 (10/09)

Event Seven - Instrument Air Leak / Reactor Scram Trigger Position Applicant's Actions or Behavior 9 Simulator Operator:

At the direction of the Lead Examiner, activate trigger 9 to initiate a large Instrument Air leak. Role Play:

EO sent to check air compressor and air dryer operation, wait 3 min. then report, "The air compressors are all running loaded and there are no problems at the air dryers."

Personnel sent to inspect IA system for rupture, acknowledge the order. If asked, U1 air system is not is service BOP Announces alarm 923-1 F-4, U2 INST AIR PRESS LOW. May start the standby IAC. Verifies U2 SA to IA Auto Crosstie Valve opens at 85 psig CRS Announces entry into DOA 4700-01, Instrument Air System Failure, and directs team actions. Briefs team to be prepared to manually scram the reactor and close the outboard MSIVs IF Instrument Air pressure drops to 55 psig. Announces entry into DOA 0600-01, Transient Level Control, and directs concurrent performance with DOA 4700-01, IA System Failure.

BOP Directs EO(s) to check air compressors and air dryers for proper operation Directs in-plant personnel to inspect U2 IA system for proper lineup and leaks. May direct EO to cross-connect U2 to U3 IA Systems per DOP 4700-03, U2/3 IA Cross-Connect Operation. May direct EO to cross-connect U2 to U3 SA Systems CRS May direct scram preparations per DGP 02-03, Reactor Scram.

ATC Performs scram preparations per DGP 02-03, Reactor Scram, as directed:

o Reduces power with Recirc fl ow to 56 Mlbm/hr core flow o Starts the turbine motor suction pump AND turning gear oil pump.

o Trips H2 addition.

CRS When IA pressure drops to 55 psig, directs team to: Scram the reactor per DGP 02-03, Reactor Scram. Close the outboard MSIVs.

SCENARIO ILT-N-1 Page 17 of 27 Rev. 00 (10/09) Event Seven - Instrument Air Leak / Reactor Scram Trigger Position Applicant's Actions or Behavior ATC Performs the following actions per DGP 02-03, Reactor Scram, and DEOP 100, RPV Control, as directed: Places Mode Switch to Shutdown and depresses the Scram pushbuttons. Determines all rods are inserted. Maintains RPV level as directed by CRS. Inserts SRMs and IRMs.

CRS Enters DEOP 100, RPV Control, Directs actions of DEOP 100. Directs actions of DGP 02-03. Verification of all isolations, ECCS and EDG starts. Holding RPV/L +8 to +48 inches. Maintaining RPV/P <1060 psig using the Isolation Condenser.

BOP Closes the outboard MSIVs. If directed, maintains RPV/P <1060 psig using the Iso Cond to control RPV/P (may use Hardcard) Performs Reactor Scram actions per his Hardcard. Event 7 Completion Criteria

Team has performed a reactor scram and stabilized the plant, AND/OR At the discretion of the Lead Examiner.

SCENARIO ILT-N-1 Page 18 of 27 Rev. 00 (10/09)

Event Eight -Steam Leak Inside The Drywell / Emergency Depressurization Trigger Position Crew Actions or Behavior 10 SIMULATOR OPERATOR:

At the discretion of the Lead Evaluator, activate trigger 10, which causes a steam leak in the DW that is large enough to require initiating Drywell sprays.

TEAM Recognizes and announces that Drywell pressure is rising rapidly.

CRS Enters DEOP 0200-01, Primary Containment Control, when Drywell pressure reaches 2 psig and performs/directs: Verifying of Torus water level <27.5 ft. Initiation of Torus sprays. Monitoring of Drywell temperature (Drywell sprays may be initiated for temperature control) Monitoring Torus Temperature. Monitors Torus level.

Role Play:

EO to check operation of the EDGs after auto start: Wait 3 minutes and then report "the EDGs are operating normally".

CRS Per DEOP 0200-01, Primary Containment Control, when Drywell pressure reaches 9 psig directs: Verifying Recirc Pumps and Drywell Coolers tripped. Verifies the Drywell spray initiation curve prior to the operator manually opening any of the Drywell spray valves. Then directs the Operator to initiate Drywell Sprays. Initiation of Drywell sprays.

BOP Performs DEOP 0200-1, Primary Containment Control, actions as directed: Monitors Drywell temperature and pressure and attempts to initiate torus sprays and drywell sprays pre Hard Card LPCI/CCSW OPERATION, as directed.

11 SIMULATOR OPERATOR:

Verify trigger 11 automatically activates when MO 1501-27A begins to open. This trips Bus 23-1 on overcurrent. As a result, Div. I of Drywell sprays cannot be initiated.

ATC / BOP Initiates Drywell Sprays.

Notices and reports the loss of ECCS equipment powered from Bus 23-1. Reports the loss of Bus 23-1 and 28. Reports the "B" LOOP of Drywell Spray is initiated, but "A" LOOP could not be initiated.

SCENARIO ILT-N-1 Page 19 of 27 Rev. 00 (10/09)

Event Eight -Steam Leak Inside The Drywell / Emergency Depressurization Trigger Position Crew Actions or Behavior US Directs Operators to investigate the loss of Bus 23-1. Directs entry into DGA-12 for Partial Loss of AC Power.

BOP Refers to DAN 902-8 F-5, 4KV Bus 23-1 Overcurrent, annunciator. As directed, Performs DGA-12, Partial or Complete Loss of AC power: Takes actions per DGA 12 for any faulted buses. Recognizes the loss of Bus 28. Dispatches EO to Bus 23-1 to investigate the loss of Bus 23-1. May enter DOA 6500-01, 4kV Breaker Trip.

ROLE PLAY:

EO to bus 23-1: Wait 2 min. then report "The feed breaker to Bus 23-1 from Bus 23 has an overcurrent flag up on it and will not reset". EO to Bus 28: Wait 2 min. then report "Bus 28 has an overcurrent flag up and will not reset" ROLE PLAY:

If contacted as EMD Fore man: Respond, "I will report to Bus 23-1". Note: EMD personnel will not report back. DO NOT REPORT BACK ON ATTEMPTS TO OPEN DW SPRAY VALVE TILL after Torus bottom pressure is > 20 #.

ATC / BOP May dispatch an Operator to attempt to manually open "A" LOOP of drywell spray. Role Play:

EO to open "A" LOOP of drywell spray: Wait 2 min, then report "The handwheel for MO 2-1501-28A will not engage".

12 SIMULATOR OPERATOR:

After the Team has attempted to put on Drywell Sprays and at the discretion of the Lead Evaluator, activate trigger 12, which increases the Main Steam line leak enough to require the Team to Emergenc y Depressurize due to exceeding PSP curve.

SCENARIO ILT-N-1 Page 20 of 27 Rev. 00 (10/09)

Event Eight -Steam Leak Inside The Drywell / Emergency Depressurization Trigger Position Crew Actions or Behavior CRS Recognizes that Emergency Depressurization per DEOP 0400-02 is necessary due to one of the below:

o Drywell temperature cannot be maintained below 281 o F. o Exceeding the PSP. Enters DEOP 400-02, Emergency Depressurization, and directs

If Drywell pressure >2 psig, prevention of injection from LPCI/CS pumps not needed for core cooling. Initiation of Iso Condenser to maximum flow. Verification of Torus level > 6ft. Opening all ADS valves.

Verifying all relief valves open.

BOP Performs DEOP 400-02, Emergency Depressurization, as directed. If Drywell pressure is greater than +2 psig, prevents injection from LPCI/CS pumps not needed for Core cooling per Hard Card, LPCI INJ/CC CONTROL/SHUTDOWN. Initiates Iso Condenser to maximum flow per Hard Card, ISOLATION CONDENSER. Verifies Torus level >6 feet. Open all ADS valves Verifies all relief valves open. Scenario Completion Criteria:

Emergency depressurization in progress. Or at the discretion of the Lead Evaluator.

SCENARIO ILT-N-1 Page 21 of 27 Rev. 00 (10/09)

Critical Tasks (RPV-5.1) When drywell pressure exceeds the suppression chamber spray initiation pressure or before containment pressure exceeds the Pressure Suppression Pressure, INITIATE drywell/containment sprays, while in the safe region of the drywell spray initiation limit or above the containment spray initiation pressure. (PC-6.1) When suppression chamber pressure cannot be maintained below the pressure suppression pressure limit, INITIATE emergency depressurization before drywell design pressure is exceeded.

SCENARIO ILT-N-1 Page 22 of 27 Rev. 00 (10/09) REFERENCES PROCEDURE TITLE DAN 902-3 B-4 ISOL CONDR VLVS OFF NORM DAN 902-3 C-4 ISOL CONDR TEMP HI DAN 902-4 A-15 ISOL CONDR CH A/B INITIATION DAN 902-5 A-3 ROD DRIFT DAN 902-5 B-3 ROD WORTH MIN BLOCK DAN 902-8 F-5 4KV BUS 23-1 OVERCURRENT DAN 923-1 B-5 U2 OR U3 INST AIR COMP TRIP DAN 923-1 F-4 U2 INST AIR PRESS LOW DEOP 0100 RPV CONTROL DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DEOP 0400-02 EMERGENCY DEPRESSURIZATION DGA 07 UNPREDICTED REACTIVITY ADDITION DGA 12 PARTIAL OR COMPLETE LOSS OF AC POWER DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DOA 0300-06 RPIS FAILURE DOA 0300-12 MISPOSITIONED CONTROL ROD DOA 0600-01 TRANSIENT LEVEL CONTROL DOA 4700-01 INSTRUMENT AIR SYSTEM FAILURE DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0202-03 REACTOR RECIRCULATION FLOW CONTROL SYSTEM OPERATION DOP 0400-02 ROD WORTH MINIMIZER DOP 4700-03 U2/3 IA CROSS-CONNECT OPERATION DOP 6400-13 ELECTRICAL YARD SWITCHING DOP 6700-20 480 VOLT BREAKER TRIP DOS 0300-06 CRD ABNORMALITY RECORD TS 3.1.3 CONTROL ROD OPERABILITY TS 3.3.5.2 ISOLATION CONDENSER (IC) SYSTEM INSTRUMENTATION TS 3.5.3 IC SYSTEM

SCENARIO ILT-N-1 Page 23 of 27 Rev. 00 (10/09) Simulator Scenario Review Checklist (cont'd)

ILT-N-1 Quantitative Attributes 7 Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 4 Abnormal events (2 to 4) 2 Major transients (1 to 2) 2 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 2 Crew critical tasks (2 to 3)

SCENARIO ILT-N-1 Page 24 of 27 Rev. 00 (10/09)

CAEP Files

1. ILT-N-1.cae

1. For ILT Class 09-1 NRC Exam # Written by DRDR9

1. Rev 00 # Date 10/09

1. INITIAL CONDITIONS

1. Sets APRM Master Gain pot to 1.0 irf niagain 1.0

1. Close 2B IAC Disch Vlv (OPS says it would be closed if the Comp is OFF) irf vp2 0.0

1. Opens 345 KV Line 0302 Remote breaker irf kvr302t open

1. EVENT TRIGGERS

1. Event Trigger 1 sets gain for all 6 APRMs.

trgset 1 "0" trg 1 "irf niagainf true" # Event trigger 2 Cuts out 2G Cond Demin Bed.

trgset 2 "0"l2 irf s47 (2) falsel2

1. Event trigger 3 Opens 345 KV Line 0302 disconnect. trgset 3 "0"l2 irf kvr302d (3) openl2

1. Event trigger 4 inserts an IAC trip and IA leak to cause pressure to slowly drop. trgset 4 "0"l4 imf n33 (4)l4 imf np2 (4) 12.0l4

1. Event trigger 5 # Opens 2B IAC Disch Vlv. # Deletes IA leak. trgset 5 "0"l6 trg 5 "dmf np2"l6 irf vp2 (5) 100.0l6

1. Event Trigger 6 Fails all control rod F-05 RPIS indications. trgset 6 "0"l6

imf rdfailf5 (6)l8 imf cr043s (6) badl8

1. Event Trigger 7 Drifts the Iso Cond Initiation setpoint. trgset 7 "0"l8 imf icspdft (7) 0.0l8

1. Event Trigger 8 Drifts the FWLCS setpoint. trgset 8 "0"l10 irf rllmls (8) 40.0 5:00l10 # Event trigger 9 Inserts a large IA leak.

SCENARIO ILT-N-1 Page 25 of 27 Rev. 00 (10/09) trgset 9 "0"l10 trg 9 "imf np2 87.0 10:00 40.0"l10

1. Event Trigger 10 Inserts a DW MSL leak of 0.5%. trgset 10 "0"l12 imf i21 (10) 0.5l12

1. Event Trigger 11 Activates when DW Spray valve MO 1501-27A starts to open. # Trips Bus 23-1 on over current. trgset 11 "lpv27a .gt. 0.01"l12 imf k23 (11)l12 imf k40 (11)l12

1. Event Trigger 12 Increases the steam leak from 2.0% to 6.0% over 5 minutes. trgset 12 "0"l14 trg 12 "mmf i21 6.0 5:00 2.0"l14

1. END SCENARIO ILT-N-1 Page 26 of 27 Rev. 00 (10/09)

Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 1 at 840 MWe, Leading Thermal Limit: MFLCPR @ 0.881 Action limit: 0.980 Equipment Unavailable: None Protected Equipment: None Unit 3 is in Mode 1 at 913 MWe Leading Thermal Limit: MAPRAT @ 0.819 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started:

LCO Expires:

TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Seperator Pit as required. Outside operator monitor and pump as necessary.

Today Chem Cleaning ventilation status:

HV-1A/EF-1A are secured due to HV-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV-1B throwing its belts. WO 1156150. HVAC -1 ON. HV-2 running.

Switchyard Status Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area. Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood. SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work.

Be careful.

Today Switching orders received for removing 345KV L0302 from service. Backfeed is off. An operator is standing by in the 345KV Switchyard.

SCENARIO ILT-N-1 Page 27 of 27 Rev. 00 (10/09)

Unit 2 Plant Status Today Unit 2 Activities **** Shift 1 Activities ****

~ ~ **** Shift 2 Activities **** ~ Load was dropped last shift with control rods. ~ Drop load to 775 MWe using recirc flow at beginning of shift. Do not secure a RFP or a condensate/booster pump. Load is expected to be picked up early next shift. ~ After the load drop, perform 345 KV switching. **** Shift 3 Activities ****

~

~ Today **** Unit 2 Procedures In-Progress **** Do Not Delete ****

~ DGP 03-01, Power Changes.

~

Dresden Generating Station ILT-N-2 MASTER RECIRC FLOW CONTROLLER FAILS DOWNSCALE CRD SUCTION FILTER PLUGGING / SWAP CRD PUMPS EMERGENCY DIESEL GENERATOR INOPERABLE B MED RANGE LEVEL INSTRUMENT FAILS LOW WITH A PARTIAL HALF SCRAM MAIN SEAL OIL PUMP TRIP

/ FAILURE OF EMERGENCY SEAL OIL PUMP TO AUTO START RBCCW PUMP TRIP LOSS OF RBCCW DUE TO LEAK / MANUAL SCRAM ELECTRICAL ATWS / ARI UNSUCCESSFUL Rev. 00 10/09

Developed By:

Exam Author Date Approved By:

Facility Representative Date

SCENARIO ILT-N-2 Page 2 of 30 Rev. 00 (10/09)

Scenario Outline Station: Dresden Generating Station Scenario No.: ILT-N-2 Class ID: 2010-301 Evaluators Operators /

crew position / ATC / BOP / CRS Initial Conditions: Full Power.

Turnover: Event No. Malf. No. Event Type* Event Description 1 RRMASDND I ATC RECIRC - Master Recirc Flow Controller Fails Downscale.

2 RDFILTB C ATC CRD - 2B Pump Suction Filter Plugging, Must Swap.

3 SER1589 SER0710 T18 C BOP EDG - Diesel Generator Inop Due to Cooling Water Pump

Failure. T 4 B15 NVM100BP I ATC NBI - B Med Range Level Inst Fails Low with Partial Half Scram. T 5 K50 C BOP H2 SEAL OIL - Main Seal Oil Pump Trip / Failure Of Emergency Seal Oil Pump To Auto Start.

6 Q01 C BOP RBCCW - Pump Trip.

7 SER1784 WRPPDSH1 SER1735 SER0369 SER0322 RRMPMAHI RRMPMBHI M TEAM Loss of RBCCW System / Team Takes a Manual Scram.

8 B12 SER1026 SER1060 AW4 M TEAM ATWS - Electrical, ARI Unsuccessful / Team Takes Actions To Insert Rods. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

SCENARIO ILT-N-2 Page 3 of 30 Rev. 00 (10/09) Scenario Objective Evaluate the Team's ability to operate the plant with an electrical ATWS.

Scenario Summary

1. Unit is at full power.

2. The following equipment is OOS:

a. None 3. LCOs: a. None Scenario Sequence The Master Recirc Flow Controller fails downscale. The NSO will lockout both recirc scoop tubes. 2B CRD pump suction filter becomes clogged. The NSO will swap CRD pumps, placing 2A CRD pump in service. (2B will eventually trip if no action is taken) The Unit 2 Emergency Diesel Generator (EDG) cooling water pump breaker fails rendering the EDG Inoperable. Medium Range B RPV level instrument fails low. A partial half scram results requiring the Team to insert a manual half scram on the B RPS channel. The SRO will reference Tech Specs for failed level instrument and partial half scram. The Main Hydrogen Seal Oil pump trips with a failure of the Emergency Hydrogen Seal Oil pump to start. The team starts the Emergency Hydrogen Seal Oil pump and verifies the generator load does not exceed the capacity limit curves for possibly reduced generator hydrogen pressure. A RBCCW pump trips. The Team will start the standby pump. A large leak develops in the RBCCW system. The Team will scram the reactor and trip the recirculation pumps to prevent damage to them. An electrical ATWS occurs when the reactor is scrammed. ARI is unsuccessful. The Team inserts control rods by pulling scram fuses, venting the scram air header, and / or driving control rods.

Event One - Master Recirc Flow Controller Failure Master Recirc Flow Controller fails downscale. Malfunctions required: 1 (Master Recirc Flow Controller fails down) Success Path: Locks out both scoop tubes. Performs DOA 0202-03, Reactor Recirc System Flow Control Failure.

SCENARIO ILT-N-2 Page 4 of 30 Rev. 00 (10/09) Event Two - CRD Suction Filter Plugging / Swap CRD Pumps 2B CRD pump suction filter clogs causing the Team to swap CRD pumps, placing 2A CRD pump in service. If the operators do not swap CRD pumps in a timely manner, 2B CRD pump eventually trips. Malfunctions required: 1 (CRD pump suction filter Plugging) Success Path: Swap CRD pumps.

Event Three - Emergency Diesel Generator Inoperable The Unit 2 EDG cooling water pump breaker fails rendering the EDG Inoperable. Malfunctions required: 1 (U2 EDG cooling water pump breaker trip) Success Path: Places U2 EDG control switch to STOP. Determines Technical Specifications requirements.

Event Four - B Med Range Level Instrument Fails Low with a Partial Half Scram B Medium Range Level Instrument fails low and a partial half scram occurs. Malfunctions required: 2 (Failure of Medium Range B level Instrument) (Partial Half Scram on the B channel) Success Path: Manually inserts a B RPS channel half scram. References the Tech Specs for an inoperable level instrument and the partial half scram.

Event Five - Main Seal Oil Pump Trip / Failure of Emergency Seal Oil Pump to Auto Start The Main Hydrogen Seal Oil pump trips with a failure of the Emergency Hydrogen Seal Oil pump to start. Malfunctions required: 1 (Main Seal Oil Pump Trip / Failure Of Emergency Seal Oil Pu mp To Auto Start) Success Path: The team starts the Emergency Hydrogen Seal Oil pump.

SCENARIO ILT-N-2 Page 5 of 30 Rev. 00 (10/09) Event Six - RBCCW Pump Trip A RBCCW pump trips. Malfunctions required: 1 (RBCCW pump trip) Success Path: The team starts the standby RBCCW pump.

Event Seven - Loss of RBCCW / Manual Scram A leak develops in the RBCCW system. Malfunctions required: 1 (RBCCW system leak) Success Path: The team performs DOA 3700-01, Loss of Reactor Building Closed Cooling Water (RBCCW) System. Performs a manual scram.

Event Eight - Electrical ATWS / ARI Unsuccessful An electrical ATWS occurs when the reactor is scrammed. ARI is unsuccessful. Malfunctions required: 1 (Electrical ATWS) Success Path: The Team inserts control rods by pulling scram fuses, venting the scram air header, and / or driving control rods.

SCENARIO ILT-N-2 Page 6 of 30 Rev. 00 (10/09) PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre-scenario activities in accordance with TQ-JA-150-08, SIMU LATOR EXAMINATION BRIEFING.

a. Direct the crew to perform their briefs prior to entering the simulator.

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

a. Initialize simulator in a full power IC. b. Cut in/out Cond Demins as needed, to maintain DP within limits.

c. Ensure running Condensate pump amps within limits.

d. Advance the chart recorders.

3 Verify the following simulator conditions:

a. Verify Master Recirc Controller demand at 95%. b. Verify 2B CRD pump is running with 2A CRD pump off.

c. Verify 2A and 2/3 RBCCW pumps are running with 2B OFF.

d. Verify TR 86 LTC in MANUAL.

NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.

4 Run the initial setup CAEP file: ILT-N-2.cae NOTE: Some analog overrides do not lo ad correctly from a CAEP file. (See SWR #8652) Therefore it is necessary to setup override WRPPDSH1 manually.

a. Open the ACTION Program and perform the following:

1) Select tab OVERRIDE AO

2) Locate override WRPPDSH1 and open it.

3) Set Ramp Start Value 65.0

4) Set Ramp time to 5:00

5) Set Delay Time to 10:00

6) Set Analog Value to 10.0

7) Set Event Trigger to 12

8) Click Insert.

5 Place the following equipment out of service:

a. None 6 Complete the Simulator Setup Checklist.

SCENARIO ILT-N-2 Page 7 of 30 Rev. 00 (10/09)

Symbols are used throughout the text to identify specific items as indicated below: Critical Tasks Required Actions Optional Actions

SCENARIO ILT-N-2 Page 8 of 30 Rev. 00 (10/09)

Event One - Master Recirc Flow Controller Fails Downscale Trigger Position Crew Actions or Behavior 1 SIMULATOR OPERATOR / ROLE PLAY:

If requested to set gains to 1, (wait 3 min) 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).

2 Simulator Operator:

When the BOP is NOT near the 902-4 panel and at the discretion of the Lead Examiner, activate trigger 2, which will cause Master Recirc Flow Controller to fail downscale.

ATC Determines and announces Recirculation Flow transient occurring by observing any of the following:

o Decrease in Recirc Loop Flow as indicated on FR 2-260-7.

o Decrease in Rx Power indicated on WI 2-6040-59.

o Decrease in Core Flow and DP on DPR/FR 2-263-110.

o Decrease in Total Stm Flow on UR 2-640-27.

o Decrease in Rx Pressure on P/FR 2-640-28.

o Decrease in Total Feedwater Flow on UR 2-640-26.

o Decrease in Power Level on RR 2-750-10A/D, & RR 2-750-10B/C.

CRS Enters DOA 0202-03, Reactor Recirc System Flow Control Failure. May enter DGA 07, Unpredicted Reactivity Addition.

ATC Performs the following actions per DOA 0202-03, Reactor Recirc System Flow Control Failure: Places 2A & B M-G Set Scoop Tube Power Lockout Reset Switches in the Lockout position. Verifies Core thermal power <2957 MWt. Verifies Recirc Pump NOT operating in the instability region of the MG Set voltage regulator AND uncontrolled pump flow AND speed oscillations are NOT occurring.

Verifies NOT operating in the unstable region of the Power / Flow Map.

SCENARIO ILT-N-2 Page 9 of 30 Rev. 00 (10/09)

Event One - Master Recirc Flow Controller Fails Downscale Trigger Position Crew Actions or Behavior ATC Completes actions of Recirc M-G Lockout in DOP 0202-12, Recirculation Pump Motor Generator Set Scoop Tube Operation. Verifies alarm is received on annunciator 902-4 C-1(5), 2A(B) RECIRC M-G SCOOP TUBE PWR FAILURE. Places BOTH recirc pump speed control transfer stations in manual (MAN) at panel 902-4: 2A(B) RECIRC PP SPEED CONTLR, 2-262-25A(B) Verify MASTER RECIRC FLOW CONTLR, 2-262-22, is in manual (MAN). At the recirc pump speed control transfer station with the locked out scoop tube, rotate the potentiometer counterclockwise to set speed demand to minimum (30%): 2A(B) RECIRC PP SPEED CONTLR, 2-262-25A(B) At panel 902-4, place an Equipment Status Tag on 2A(B) M-G SET SCOOP TUBE POWER LOCKOUT RESET switch stating the reason the recirc MG set scoop tube is locked out.

BOP Assist ATC as directed.

CRS Verifies actions of DOA 0202-03 and DOP 0202-12 are carried out. May reference DOA 0500-01, Inadvertent Entry into the Unstable Region of the Power to Flow Map. Event 1 Completion Criteria:

2A & 2B Recirc Scoop Tubes locked out, AND/OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-2 Page 10 of 30 Rev. 00 (10/09)

Event Two - CRD Suction Filter Plugging / Swap CRD Pumps Trigger Position Crew Actions or Behavior 3 SIMULATOR OPERATOR / ROLE PLAY:

At the discretion of the Lead Examiner, activate trigger 3. This will cause a simulated Plugging of 2B CRD pump suction filter, and finally trip the pump on low suction pressure if the crew has not swapped the pump yet. Note: It may take several minutes before an alarm occurs. As the EO, if asked, wait 2 min. and then report: "The 2B CRD pump suction pressure is 14 Hg and getting worse". NSO may follow DOP 0300-01 and have the EO check 2A CRD pump ready to start... Wait 1 min, then report: "2A CRD pump is ready to start".

ATC Announces alarm 902-5 D-2, 2B ROD DRIVE PP SUCT LO, and degrading CRD system parameters. Carries out actions of DOP 0300-01, Control Rod Drive System Start Up And Operation: Directs EO vent 2A CRD pump casing. Directs EO vent 2A CRD pump suction filter. Directs EO to verify 2A CRD pump oil levels. Directs EO to verify 2A CRD pump suction and discharge valves open. Starts 2A CRD pump. Secures 2B CRD pump. Verifies normal CRD system pressures and flow.

ROLE PLAY:

As the EO, if asked, report: "2A CRD pump is operating normally".

CRS Directs swapping CRD pumps per DOP 0300-01, Control Rod Drive System Start Up and Operation, due to degrading operation of 2B CRD pump.

BOP Monitors panels and assists as directed.

NOTE: If the Team wait until the 2B CRD pump trips, the following actions apply:

ATC Announces 2B CRD pump trip. Per immediate action of DOA 0300-01, Control Rod Drive System Failure, starts the standby CRD pump.

CRS Enters DOA 0300-01, Control Rod Drive System Failure, due to failure of 2B CRD pump. Enters DOA 6500-10, 4KV Circuit Breaker Trip, due to trip of 2B CRD pump. May reference TRM 3.3.h Reactor Vessel Water Level Instrumentation System (RVWLIS) Backfill System due to short loss of RVWLIS supply.

SCENARIO ILT-N-2 Page 11 of 30 Rev. 00 (10/09)

Event Two - CRD Suction Filter Plugging / Swap CRD Pumps Trigger Position Crew Actions or Behavior Event 2 Completion Criteria:

2A CRD pump has been started and the immediate actions of DOA 300-01 are complete, AND/OR At the direction of the Lead Examiner.

SCENARIO ILT-N-2 Page 12 of 30 Rev. 00 (10/09)

Event Three - Emergency Diesel Generator Inoperable Trigger Position Crew Actions or Behavior 4 Simulator Operator:

At the discretion of the Lead Examiner, activate trigger 4, which simulates Unit 2 EDG cooling water pump breaker control power transformer failure.

5 Simulator Operator / Role Play:

EO to U2 EDG to check Trouble alarm: wait 3 min, activate trigger 5, which clears the U2 EDG Trouble alarm. Then report "I acknowledged the local alarm on panel DG2A Tile C-3 which is 'Diesel Clg Wtr Pump Failure Or Locked Out'. It will not reset".

Role Play:

EO in U2 EDG room to check cooling water pump control switch: report, "the cooling water pump control switch is in its normal position and all control switch indicating lights are OFF". EO to verify fuse 2-3903-F1 in EDG 2 Aux Control Panel: wait 2 min, the report that "fuse 2-3903-F1 is NOT blown". EO to check the U2 EDG cooling water pump breaker: Wait 2 min, then report "the U2 EDG cooling water pump breaker is closed, but there is an acrid smell coming from the cubicle". Support personnel: Acknowledge requests.

BOP Announces alarms: 902-8 A-7, U2 Diesel Gen Trouble. 902-7 G-8, U2 Diesel Gen Clg Wtr PP Trip/Lkout Sends an operator to check the U2 EDG Trouble alarm. Directs operator to verify fuse 2-3903-F1 in EDG 2 Aux Control Panel. Sends an operator to check the U2 EDG cooling water pump breaker. Performs DOA 6600-01, Diesel Generator Failure, as directed: Places the U2 EDG output breaker to the Pull-To-Lock position. (Optional / required only if EDG is running) Places the U2 EDG control switch to STOP. Informs the Unit Supervisor of the field reports.

ATC Monitors panels, provide assistance as directed.

CRS Enters DOA 6600-01, Diesel Generator Failure, and directs actions. Declares the U2 EDG inoperable.

TEAM May enter DOP 6700-20, 480V Circuit Breaker Trip.

SCENARIO ILT-N-2 Page 13 of 30 Rev. 00 (10/09)

Event Three - Emergency Diesel Generator Inoperable Trigger Position Crew Actions or Behavior CRS Determines following Technical Specifications apply: TS 3.7.2, Diesel Generator Cooling Water (DGCW) System, Condition A. Declare associated DG inoperable immediately. TS 3.8.1, AC Sources-Operating, Condition B.

CRS Directs performance of DOS 0040-08, Unit 2 Operating Power Sources and Distribution. Directs Engineering to determine the EDG is not inoperable due to common cause failure OR directs performing operability surveillance fo r the 2/3 EDG. Event 3 Completion Criteria:

U2 EDG declared inoperable; and, Technical Specification determination completed, AND/OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-2 Page 14 of 30 Rev. 00 (10/09)

Event Four - B Med Range Level Instrument Fails Low with a Partial Half Scram Trigger Position Crew Actions or Behavior 6 7 SIMULATOR OPERATOR / ROLE PLAY:

At the discretion of the Lead Examiner, activate trigger 6, which fails B medium range downscale and inserts B RPS partial half scram.

Verify trigger 7 automatically activates when CH B RPS scram pushbutton is depressed. This inserts an electrical ATWS ATC Notices and reports the B Medium Range level instrument trending down. Announces: The partial half scram condition on the B RPS channel. Scram Solenoid Group lights B2 and B3 did NOT extinguish. Refers to DOA 0500-02, Partial 1/2 or Full Scram Actuation. (May insert the manual half scram as an immediate action of DOA 0500-02 then refer to the procedure). Depresses RPS Channel B Manual Scram pushbutton.

SIMULATOR OPERATOR / ROLE PLAY:

As the EO sent to the ATS Panel (wait 2 min AND the 902-4 G-20 alarm is up), then report: "The 'B' medium range level instrument MTU LIS 2-263-140B is reading full downscale and its gross failure light is lit." As the EO sent to the MCC 28-1 circuit 15 and/or 125vdc Bus 2A-1 Dist Panel, circuit 27 (wait 3 min), then report: "The breaker is NOT tripped and looks normal." IF asked: "The Yarway LI-2(3)-263-59A on the 2202-5 rack is indicating 30 inches and steady." ATC / BOP Refers to DAN 902-4 G-20: Dispatches an operator to inspect the Div 1 ATS panel 2202-73A Notifies the Unit Supervisor of inspection results.

CRS Announces entry into DOA 0500-02, Partial 1/2 or Full Scram Actuation and performs/directs: Directs NSO to insert manual scram on RPS Channel A. May refer to DOP 0010-10, Unit 2(3) Technical Specification Instrumentation Operability Manual.

CRS References Technical Specifications and determines: TS 3.3.1.1 Action A1 or A2 and C1 apply. Most limiting is Restore RPS trip capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. TS 3.3.3.1 Action A1. Restore required channel to OPERABLE status within 30 days. TS 3.3.6.1 Condition A1. Place channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. TS 3.3.6.2 Condition A1. Place channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SCENARIO ILT-N-2 Page 15 of 30 Rev. 00 (10/09)

Event Four - B Med Range Level Instrument Fails Low with a Partial Half Scram Trigger Position Crew Actions or Behavior Event 4 Completion Criteria:

Half Scram inserted, and Appropriate Tech Specs referenced, AND/OR At the direction of the Lead Examiner.

SCENARIO ILT-N-2 Page 16 of 30 Rev. 00 (10/09)

Event Five - Main Seal Oil Pump Trip / Failure Of Emergency Seal Oil Pump To Auto Start Trigger Position Crew Actions or Behavior Note: The Emergency Hydrogen Seal Oil (ESOP) pump control switch TRIP position is overridden to TRIP so the ESO P will NOT start automatically.

8 Simulator Operator:

At the direction of the Lead Evaluator, insert trigger 8 to trip the Main Hydrogen Seal Oil Pump (MSOP).

10 Simulator Operator / Role Play:

EO directed to investigate local panel trouble alarm, wait 1 min., activate trigger 10 , and then report that "The local alarm is Differential seal oil pressure low. If the ESOP is running, add to the report "and it reset". EO to report local Generator H 2 pressure: Wait 1 min, and then report "the local Generator H 2 pressure indicates (use value from Instructor Station drawing EG3) psig."

Role Play:

EO sent to check the MSOP breaker: Wait 3 min. then report, "The MSOP breaker is tripped in the tripped free position". If directed to check the MSOP, report, "I can't find anything wrong with the MSOP. EO to align Seal Oil and H 2 valves: Wait 2 min, then report "the (Insert nomenclature of requested valves) are (insert position requested)". Note: The simulator does not model the Seal Oil and H 2 valves. BOP Announces: 902-7 A-11, H 2 Seal Oil Sys Oil Pp/Vac Pp Trip, alarm. MSOP tripped. Generator machine gas pressure dropping.

BOP Determines ESOP did NOT automatically start as expected. Starts the ESOP.

TEAM Makes PA announcement warning of H 2 and /or oil vapor around the main generator.

CRS Directs starting ESOP. Enters DOP 6700-20, 480V Circuit Breaker Trip.

BOP Announces 902-7 E-11, H 2 Seal Oil & Alterrex Pnl Trouble, alarm Dispatches EO to investigate local panel trouble alarm.

BOP Performs DOP 6700-20, 480V Circuit Breaker Trip, as directed: Dispatches EO to MCC 28-2 to investigate the MSOP trip. Places MSOP in PTL.

SCENARIO ILT-N-2 Page 17 of 30 Rev. 00 (10/09)

Event Five - Main Seal Oil Pump Trip / Failure Of Emergency Seal Oil Pump To Auto Start Trigger Position Crew Actions or Behavior BOP Performs DAN 902-7 A-11, H 2 Seal Oil Sys Oil Pp/Vac Pp Trip, additional actions: Directs EO to close:

o H-09, U2 H2 SEAL OIL VACUUM TK INLET SPRYA SV.

o H-13, U2 MAIN SEAL OIL PMP DISCH STOP CHC VLV. Stops the Seal Oil Vacuum Pump. Monitors 250 VDC electrical system (DOP 6900-01). Periodically monitors seal oil bearing pressure, hydrogen purity, and hydrogen differential pressure. Enters DOP 5320-11, Filling and Venting the Generator with Hydrogen to Raise Purity and/or Pressure during Normal Operation, if necessary. Directs an Operator to check for hydrogen at Generator shaft seal in Alterrex housing. ATC Assists as directed. Event 5 Completion Criteria:

ESOP started, AND/OR, At the discretion of the Floor Instructor

SCENARIO ILT-N-2 Page 18 of 30 Rev. 00 (10/09)

Event Six - RBCCW Pump Trip Trigger Position Crew Actions or Behavior 11 Simulator Operator:

At the discretion of the Lead Examiner, activate trigger 11, which trips 2A RBCCW pump. Role Play:

EO to check 2B RBCCW pump operation: Wait 2 min, then report "2B RBCCW pump is operating normally". EO to check 2A RBCCW pump breaker: Wait 2 min, then report "2A RBCCW pump breaker has an overcurrent target up". EO to check 2A RBCCW pump: Wait 2 min, then report "2A RBCCW pump motor is very hot to the touch".

BOP Acknowledges and announces alarm(s):

o 923-1 C-1, U2 or U3 RBCCW Pump Trip o 923-1 D-1, U2 or U3 RBCCW Press Lo (may not come up) Starts 2B RBCCW pump. Sends an operator to check RBCCW system status. Performs DOA 6500-10, 4KV Circuit Breaker Trip, actions as directed.

CRS May enter DOA 3700-01, Loss of Reactor Building Closed Cooling Water (RBCCW) System. Directs BOP to start 2B RBCCW pump.

Enters DOA 6500-10, 4KV Circuit Breaker Trip.

ATC Assists as directed.

CRS Contacts support personnel for assistance.

Event 6 Completion Criteria:

Standby RBCCW pump started, AND/OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-2 Page 19 of 30 Rev. 00 (10/09)

Event Seven -Loss of RBCCW / Reactor Scram Trigger Position Crew Actions or Behavior 12 13 14 22-25 SIMULATOR OPERATOR:

At the discretion of the Lead Examiner, activate trigger 12, which simulates a leak in the Reactor Building from the RBCCW system. As the EO sent to defeat the RBV high Drywell pressure and RPV water level interlocks (wait 5 min) activate trigger 13 and then report: "the RBV high Drywell pressure and RPV water level interlocks are defeated".

Verify trigger 14 automatically activates when East RBFDS mass is >7950.0 (variable wamrfsa2). This holds the East RBFDS mass above the High High level.

Verify triggers 22 thru 25 automatically activate when all RBCCW pumps are OFF. This returns overrides to normal.

ROLE PLAY:

As the EO sent to check RBCCW head tank level: (wait 2 min) then report: "RBCCW head tank level is out of the sight glass low. The head tank makeup valve is open". As the EO to check RBCCW head tank drain sightglass: (wait 1 min) then report "there is no flow through the RBCCW head tank drain sightglass". As the EO sent to check RBCCW system: (wait 2 min) then report: "There is a very large leak coming from the RBCCW HX area. The floor is flooded with water". If asked as the EO about isolating the leak, report: The leak cannot be isolated". As the EO sent to check the RBFDS (wait 2 min) then report: "the East Reactor Building Floor Drain sump is overflowing onto the Torus basement floor". If called as the Radwaste Control Room Operator and asked about the inputs into the Radwaste sumps, report: "the Floor Drain input has increased significantly". As the EO sent to check RBCCW leak after the pumps are stopped: (wait 1 min) then report: "the flow rate from the RBCCW leak has slowed down significantly".

BOP Announces alarm 923-1 F-1, U2 RBCCW Head Tank Lvl Hi/Lo Refers to DAN and performs actions. Monitors operation of the RBCCW system. Dispatches EO to check U2 RBCCW Head tank level.

Announces entry into DOA 3700-01, Loss of Cooling by Reactor Building Closed Cooling Water (RBCCW) System, is required.

CRS Enters DOA 3700-01, Loss of Cooling by Reactor Building Closed Cooling Water (RBCCW) System, and directs actions.

BOP Performs DOA 3700-01, Loss of Cooling by Reactor Building Closed Cooling Water (RBCCW) System, actions as directed. Announces alarm 923-4 A-3, U2 E. RBFD Sump Lvl Hi-Hi Dispatches operators to check sumps Announces entry to DEOP 300-01, Secondary Containment Control, is required.

SCENARIO ILT-N-2 Page 20 of 30 Rev. 00 (10/09)

Event Seven -Loss of RBCCW / Reactor Scram Trigger Position Crew Actions or Behavior CRS Enters DEOP 0300-01, Secondary Containment Control. May enter DOA 0040-02, Localized Flooding in Plant, and direct actions.

BOP Performs DOA 0040-02, Localized Flooding in Plant, actions as directed.

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

ATC / BOP Performs scram preparatory actions per DGP 02-03, Reactor Scram, as directed.

o Inserts control rods to reduce FCL to <93%.

o Start the motor suction pump and turning gear oil pump.

o Trip hydrogen addition.

CRS Determines RBCCW System loss CANNOT be prevented and performs / directs: Manual scram per DGP 02-03, Reactor Scram. Tripping RBCCW pumps.

BOP Trips RBCCW pumps. Event 7 Completion Criteria:

Reactor scram ordered, AND/OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-2 Page 21 of 30 Rev. 00 (10/09)

Event Eight - Electrical ATWS / ARI Unsuccessful Trigger Position Crew Actions or Behavior 15 16 Simulator Operator / Role Play:

Operator to pull scram fuses: wait 4 min, then activate trigger 15. This sequentially pulls the scram fuses. Operator to vent the scram air header: wait 5 min, the activate trigger 16. This vents the scram air header.

17 Simulator Operator / Role Play:

Operator to install GP 1 -59 in. and Off Gas Hi Hi Rad jumpers: wait 3 min, activate trigger 17, and then report "the GP 1 -59 in. and Off Gas Hi Hi Rad jumpers are installed".

ATC Performs the following actions per DGP 02-03, Reactor Scram, as directed: Presses scram pushbuttons Places mode switch in shutdown Check rods inserted / Determines control rods did not insert. Initiates ARI / Determines ARI did not insert control rods. Announces ATWS condition and RX power is >6%. May resets scoop tubes so Recirc Pumps run back / trips recirc pumps Initiates SBLC. Announces failure to inject. Maintains RPV/L between +8 and +48 inches or as directed by Unit Supervisor.

BOP Performs DGP 02-03, Reactor Scram, as directed.

CRS Enters DEOP 100, RPV Control, and directs actions. Due to report of ATWS condition, exits DEOP 100 AND enters DEOP 0400-05, Failure to Scram, and directs/performs: Placing ADS to inhibit. (Not expected to be a Critical Task for this scenario) Placing Core Spray pumps in PTL. Inserting control rods using Alternate Rod Insertion. Directs driving control rods.

Directs pulling scram fuses.

Directs venting scram air header.

Verifying required auto actions. Installing of the jumpers for the MSIV low level isolations and the Off Gas high Rad isolations. If RX power >6%, terminating and preventing all injection except boron and CRD until RPV level 35 inches. Holding RPV level between -164 inches and the level lowered to. Stabilizing RPV pressure below 1060 psig.

SCENARIO ILT-N-2 Page 22 of 30 Rev. 00 (10/09)

Event Eight - Electrical ATWS / ARI Unsuccessful Trigger Position Crew Actions or Behavior CRS Based on report that SBLC failed, directs DEOP 0500-01, Alternate Boron Injection, performed.

ATC Terminates and prevents all injection except boron and CRD at the 902-5 panel in automatic as follows: Using the RX LOW FLOW CONTROL STATION, 2(3)-640-20, lowers FWLC SETPOINT to -40 inches.

BOP Terminates and prevents all injection except boron and CRD at the 902-3 panel as follows: Place HPCI Aux Oil Pump AND HPCI 14 valve in PTL. Verify HPCI flow controller in AUTO AND reduce setpoint to 2000 gpm. PLACES LPCI 22 valves in Pull-to-Close.

ATC Drives control rods per DEOP 500-05, Alternate Insertion Of Control Rods, as follows: (RPV-6.1) Bypasses the RWM. Maximizes CRD drive water pressure. Inserts Control Rods by either using the ROD MOVEMENT CONTROL switch or the EMERG ROD IN position of the ROD OUT NOTCH OVERRIDE switch.

CRS Based on report that all control rods are inserted, exits DEOP 0400-05 and enters DEOP 0100. Directs securing SBLC.

ATC Performs as directed: Secures SBLC.

ATC / BOP Performs as directed: Re-establishes injection using available injection systems to MAINTAIN RPV water level above -164" (in band directed by Unit Supervisor). Event 8 / Scenario Completion Criteria:

Control rods inserted, AND / OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-2 Page 23 of 30 Rev. 00 (10/09)

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, 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. (Conditions may not occur to cause this to be critical for this scenario) (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 re-establish injection use available injection systems to MAINTAIN RPV water level above -164".

SCENARIO ILT-N-2 Page 24 of 30 Rev. 00 (10/09) REFERENCES PROCEDURE TITLE DAN 902-4 C-1(5) 2A(B) RECIRC M-G SCOOP TUBE PWR FAILURE DAN 902-4 G-20 ANALOGTRIP SYS DIV 1 2202-73A TRBL DAN 902-5 D-2 2B ROD DRIVE PP SUCT LO DAN 902-7 A-11 H 2 SEAL OIL SYS OIL PP/VAC PP TRIP DAN 902-7 E-11 H 2 SEAL OIL & ALTERREX PNL TROUBLE DAN 902-7 G-8 U2 DIESEL GEN CLG WTR PP TRIP/LKOUT DAN 902-8 A-7 U2 DIESEL GEN TROUBLE DAN 923-1 C-1 U2 OR U3 RBCCW PUMP TRIP DAN 923-1 D-1 U2 OR U3 RBCCW PRESS LO DAN 923-1 F-1 U2 RBCCW HEAD TANK LVL HI/LO DAN 923-4 A-3 U2 E. RBFD SUMP LVL HI-HI DEOP 0100 RPV CONTROL DEOP 300-01 SECONDARY CONTAINMENT CONTROL DEOP 0400-05 FAILURE TO SCRAM DEOP 0500-05 ALTERNATE INSERTION OF CONTROL RODS DGA 07 UNPREDICTED REACTIVITY ADDITION DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DOA 0040-02 LOCALIZED FLOODING IN PLANT DOA 0202-03 REACTOR RECIRC SYSTEM FLOW CONTROL FAILURE DOA 0300-01 CONTROL RO D DRIVE SYSTEM FAILURE DOA 0500-02 PARTIAL 1/2 OR FULL SCRAM ACTUATION DOA 3700-01 LOSS OF COOLING BY REACTOR BUILDING CLOSED COOLING WATER (RBCCW) SYSTEM DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOA 6600-01 DIESEL GENERATOR FAILURE DOP 0202-12 RECIRCULATION PUMP MOTOR GENERATOR SET SCOOP TUBE OPERATION DOP 6700-20 480V CIRCUIT BREAKER TRIP DOS 0040-08 UNIT 2 OPERATING POWER SOURCES AND DISTRIBUTION TS 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TS 3.3.3.1 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TS 3.3.6.1 PRIMARY CONTAINMEN T ISOLATION INSTRUMENTATION TS 3.3.6.2 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TS 3.7.2 DIESEL GENERATOR COOLING WATER (DGCW) SYSTEM TS 3.8.1 AC SOURCES-OPERATING, CONDITION

SCENARIO ILT-N-2 Page 25 of 30 Rev. 00 (10/09) Simulator Scenario Review Checklist (cont'd)

ILT-N-2 Quantitative Attributes 9 Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 6 Abnormal events (2 to 4) 2 Major transients (1 to 2) 1 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 3 Crew critical tasks (2 to 3)

SCENARIO ILT-N-2 Page 26 of 30 Rev. 00 (10/09)

CAEP Files

1. ILT-N-2.cae # For ILT Class 09-1 NRC Exam

1. Written by DRDR9

1. Rev 00 # Date 10/09

1. INITIAL CONDITIONS

1. Sets APRM Master Gain pot to 1.0 irf niagain 1.0

1. Inserts CH B RPS partial half scram.

imf b15 # Disables CH A RPS Manual Scram pushbutton;

1. in case wrong pushbutton depressed in partial 1/2 scram event.

imf b20

1. Overrides Panel 2202-70A(B) Trouble alarm points OFF so pulling ARI fuses does not cause alarm. # Pulls ARI fuses. Imf ser1026 off imf ser1060 off irf aw4 pulledl2

1. Inserts failure of Emergency Hydrogen Seal Oil pump to auto start.

imf t53l2

1. Inserts trip of 2A SBLC pump. imf scpmpocal2

1. Sets 2B SBLC Relief valve setpoint to 100.0 psig imf scrlfvbd 100.0l2

1. EVENT TRIGGERS

1. Event Trigger 1 sets gain for all 6 APRMs. trgset 1 "0"l4 trg 1 "irf niagainf true"l4

1. Event Trigger 2 Causes master recirc flow controller to fail downscale.

trgset 2 "0"l4 imf rrmasdnd (2) 0.3 4:00 0.95l4

1. Event Trigger 3 Ramps the CRD suction filter closed over 8 min. to cause the low suct pres alarm. # After 8 min, isolates the 2B CRD pump suction filter to simulate a clogged filter causing a trip of the 2B CRD pump trgset 3 "0"l6 trg 3 "ramp rdvstrnr(2) 0.25 .01 8:00"l6 irf rdfiltb (3 8:00) falsel6

1. Event trigger 4 Simulates U2 EDG cooling water pump breaker control power transformer failure: # Forces up alarm 902-8 A-7, U2 Diesel Gen Trouble.

1. Forces up alarm 902-7 G-8, U2 Diesel Gen Clg Wtr PP Trip/lkout.

1. Inserts U2 Diesel Gen Clg Wtr PP Trip malfunction. Trgset 4 "0"l6 SCENARIO ILT-N-2 Page 27 of 30 Rev. 00 (10/09) imf ser1589 (4) onl8 imf ser0710 (4) onl8 imf t18 (4)l8

1. Event trigger 5 Clears alarm 902-8 A-7, U2 Diesel Gen Trouble. Trgset 5 "0"l10 trg 5 "imf ser1589 normal"l10

1. Event Trigger 6 fails B medium range downscale. trgset 6 "0"l10 imf nvm100bp (6) -120.0 4:00l10

1. Event Trigger 7 Activates when CH B RPS scram pushbutton depressed. # Inserts an electrical ATWS. trgset 7 "rpl301b"l12 imf b12 (7)l12

1. Event Trigger 8 Trips the Main Hydrogen Seal Oil Pump.

trgset 8 "0"l12 imf k50 (8)l12

1. Event Trigger 10 Acknowledges the Alterrex panel trouble alarm. trgset 10 "0"l14

irf t81 (10) truel14

1. Event Trigger 11 Trips 2A RBCCW pump. Trgset 11 "0"l16 imf q01 (11)l16

1. Trigger 12 Simulates a RBCCW leak in the Rx Bldg. # Ramps E. RBFDS mass to fill it. # Overrides alarm 923-1 E-2 RBCCW Head Tank Lvl Lo. # After 10 min, ramps RBCCW Disch pressure meter to 10 psig over 5 min. # After 11 min, overrides alarm 923-1 D-1. # After 12 min, overrides 902-4 G-3 ON.

1. After 12:15 min, overrides 902-4 G-7 ON. Trgset 12 "0"l16 trg 12 "ramp wamrfsa2 5000.0 8000.0 3:00"l16 imf ser1784 (12) onl18 imf ser1735 (12 11:00) onl18 imf ser0369 (12 12:00) onl18 imf ser0322 (12 12:15) onl18

1. Trigger 13 Jumpers the RBV Group II Isolation signal.

Trgset 13 "0"l20 irf cirbvnt (13) liftedl20

1. Event Trigger 14 Activates when E. RBFDS mass is >7950.0, which holds E. RBFDS mass above Hi Hi level. Trgset 14 "wamrfsa2 .gt. 7950.0"l20 trg 14 "ramp wamrfsa2 7950.0 8000.0 10:00"l20

1. Event trigger 15 Simulates pulling RPS scram fuses. Trgset 15 "0"l22 irf rpfusea1 (15 0) pulledl22 irf rpfusea2 (15 20) pulledl22 irf rpfusea3 (15 40) pulledl22 irf rpfusea4 (15 60) pulledl24 irf rpfuseb1 (15 80) pulledl24 irf rpfuseb2 (15 100) pulledl24 irf rpfuseb3 (15 120) pulledl24 SCENARIO ILT-N-2 Page 28 of 30 Rev. 00 (10/09) irf rpfuseb4 (15 140) pulledl26

1. Event trigger 16 Simulates venting scram air header. trgset 16 "0"l26 irf rdscrair (16) openl26

1. Event Trigger 17 installs MSL Group 1 RPV level byp and Offgas High Rad byp jumpers. trgset 17 "0"l26 irf ci59jp (17) inl28 irf ogogjp (17) inl28

1. 1. 1. 1. 1. Triggers 22-25 Activate when no RBCCW pumps are running. #####

1. Event Trigger 22 Deletes RBCCW pressure meter override.

Trgset 22 ".not. (wrsp(1) .or. wrsp(2) .or. wrsp(3))"l34 trg 22 "dor wrppdsh1"l30

1. Event Trigger 23 Returns alarm 923-1 D-1 override to normal. Trgset 23 ".not. (wrsp(1) .or. wrsp(2) .or. wrsp(3))"l36 trg 23 "imf ser1735 normal"l30

1. Event Trigger 24 Returns alarm 902-4 G-3 override to normal. Trgset 24 ".not. (wrsp(1) .or. wrsp(2) .or. wrsp(3))"l38 trg 24 "imf ser0369 normal"l32

1. Event Trigger 25 Returns alarm 902-4 G-7 override to normal.

Trgset 25 ".not. (wrsp(1) .or. wrsp(2) .or. wrsp(3))"l40 trg 25 "imf ser0322 normal"l32

1. END SCENARIO ILT-N-2 Page 29 of 30 Rev. 00 (10/09)

Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 1 at 912 MWe, Leading Thermal Limit: MFLCPR @ 0.881 Action limit: 0.980 Equipment Unavailable: None Protected Equipment: None Unit 3 is in Mode 1 at 913 MWe Leading Thermal Limit: MAPRAT @ 0.819

Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started:

LCO Expires:

TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Separator Pit as required. Outside operator monitor and pump as necessary.

Today Chem Cleaning ventilation status: HV-1A/EF-1A are secured due to HV-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV-1B throwing its belts. WO 1156150. HVAC -1 ON.

HV-2 running.

Switchyard Status Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area. Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood. SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work. Be careful.

SCENARIO ILT-N-2 Page 30 of 30 Rev. 00 (10/09)

Unit 2 Plant Status Today Unit 2 Activities **** Shift 1 Activities ****

~

~

• • • • Shift 2 Activities ****

~ ~ **** Shift 3 Activities ****

~ ~ Today **** Unit 2 Procedures In-Progress **** Do Not Delete ****

~

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Dresden Generating Station ILT-N-3 REMOVE FWRV FROM SERVICE CONDENSATE/BOOSTER PUMP TRIP WITH FAILURE OF STBY TO AUTO START SECONDARY CONTAINMENT DOORS FOUND OPEN IRM FAILS UPSCALE WITH HALF SCRAM LOSS OF EHC / MANUAL REACTOR SCRAM LOSS OF HIGH PRESSURE FEED / RECIRC LOOP LEAK /

EMERGENCY DEPRESSURIZATION Rev. 00 10/09 Developed By:

Exam Author Date Approved By:

Facility Representative Date

SCENARIO ILT-N-3 Page 2 of 25 Rev. 00 (10/09)

Scenario Outline Station: Dresden Generating Station Scenario No.: ILT-N-3 Class ID: 2010-301 Evaluators Operators /

crew position / ATC / BOP / CRS Initial Conditions: 2% Power Startup On Hold For REMA Re-evaluation By QNE.

Turnover: Remove 'B' FWRV From Service After Assuming Shift.

Event No. Malf. No. Event Type* Event Description 1 NONE N ATC FW - Remove 'B' FWRV From Service.

2 H21 C ATC FW - Cond/Cond Bstr Pump Trip with Failure of Standby to Auto Start. 3 NONE T CRS CONTAINMENT - Secondary Containment Doors Found Open.

T 4 NII12POT I ATC NI - IRM Channel Fails Upscale with Half Scram.

T 5 J33 M TEAM Loss of EHC System / Team Takes a Manual Scram.

6 F41 RLMFAFC RLMFBFC RLMLFFC M TEAM Recirc System Leak and Loss of All Feedwater Reg Valves / Team Emergency Depressurizes Due to Lowering RPV Level. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

SCENARIO ILT-N-3 Page 3 of 25 Rev. 00 (10/09) Scenario Objective Evaluate the Team's ability to operate the plant with a loss of high pressure feed requiring an emergency depressurization.

Scenario Summary

1. Unit is at ~2%.

2. The following equipment is OOS:

a. None 3. LCOs: a. None Scenario Sequence The Team removes 'B' FWRV from service. 2A Condensate/Booster Pump trips with failure of the STBY pump to auto start. Also the first pump the Team attempts to start will trip. The other non-running pump will start. A report comes from the field that Secondary Containment is breached by doors found open. The crew directs the doors be closed. The Team references Tech Specs. IRM channel 12 then fails upscale and a half-scram occurs on the RPS "A" channel. The SRO addresses the technical specification requirements for the failure. Then the NSO bypasses the failed IRM channel and resets the half scram. A leak occurs in the EHC hydraulics system which eventually results in loss of the EHC hydraulic system. The Team will perform a manual scram before RPV pressure control is lost. Shortly after the manual scram, a problem in the FWLC system causes all the feedwater regulating valves to fail closed. After the Team addresses RPV level control, a recirculation loop develops a leak causing drywell pressure to slowly increase and RPV level to begin dropping. When HPCI starts, it spuriously isolates, resulting in a total loss of high pressure feed. The team performs the RPV Control and Primary Containment Control DEOPs. When RPV level drops to TAF, the team Emergency Depressurizes and restores RPV level with low pressure injection systems.

Event One - Remove 'B' FWRV from Service The Team removes 'B' FWRV from service. Malfunctions required: 0 (None) Success Path: Performs DOP 0600-01, Feedwater Regulating Valve (FWRV) Operation, to remove 'B' FWRV from service.

SCENARIO ILT-N-3 Page 4 of 25 Rev. 00 (10/09) Event Two - Condensate/Booster Pump Trip with Failure of STBY to Auto Start 2A Condensate/Booster Pump trips with failure of the STBY pump to auto start. Also the first pump the Team attempts to start will trip. Malfunctions required: 1 (Condensate/Booster pump trip with failure of STBY to auto start) Success Path: Starts a Condensate/Booster pump.

Event Three - Secondary Containment Doors Found Open A report is received that Secondary Containment Doors are open. Malfunctions required: 0 (None) Success Path: Directs the Secondary Containment Doors closed. Determines Technical Specifications requirements.

Event Four - IRM Channel Fails Upscale The crew recognizes and responds to an IRM failing upscale resulting in a half scram. Malfunctions required: 1 (IRM Fails Upscale) Success Path: Bypasses the IRM and resets the half scram. Determines Technical Specifications requirements.

Event Five - Loss of EHC / Manual Reactor Scram A leak occurs in the EHC hydraulics system. Malfunctions required: 1 (EHC hydraulic leak) Success Path: The Team performs a manual scram per DGP 02-03, Reactor Scram, before RPV pressure control is lost.

SCENARIO ILT-N-3 Page 5 of 25 Rev. 00 (10/09)

Event Six - Loss of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization A loss of high pressure feed and a recirculation loop leak causes Drywell pressure to increase and RPV level to drop below TAF. Malfunctions required: 2 (Loss of high pressure feed) (Recirc loop leak) Success Path: Spray the Drywell. Emergency Depressurize to restore RPV level with low pressure systems.

SCENARIO ILT-N-3 Page 6 of 25 Rev. 00 (10/09) PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre-scenario activities in accordance with TQ-JA-150-08, SIMU LATOR EXAMINATION BRIEFING.

a. Direct the crew to perform their briefs prior to entering the simulator.

b. Provide the Team a marked-up copy of DGP 01-01, Unit Startup.

c. Provide the Team a copy of DOP 0600-06, Feedwater Regulating Valve (FWRV) Operation.

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

a. Initialize simulator in an IC with Reactor power ~2%. b. Cut in/out Cond Demins as needed, to maintain DP within limits.

c. Ensure running Condensate pump amps within limits.

d. Advance the chart recorders.

3 Verify the following simulator conditions:

a. Verify both FWRVs in Master Auto.

b. Verify 2B CRD pump running with 2A OFF.

c. Verify 2A & 2C Cond/Boost pumps running with 2B & 2D pumps off.

d. Verify 2D Cond/Boost pump in STBY.

e. Verify 3 cond demin beds cut in.

f. Verify the Cond Boost Min Flow open 90-95%.

g. Verify the Turbine is reset.

h. Verify TR 86 LTC in MANUAL.

NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.

4 Run the initial setup CAEP file: ILT-N-3.cae

5 Place the following equipment out of service:

a. None 6 Complete the Simulator Setup Checklist.

SCENARIO ILT-N-3 Page 7 of 25 Rev. 00 (10/09)

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-3 Page 8 of 25 Rev. 00 (10/09)

Event One - Remove 'B' FWRV from Service Trigger Position Crew Actions or Behavior 1 SIMULATOR OPERATOR / ROLE PLAY:

If requested to set gains to 1, (wait 3 min) 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).

CRS Directs ATC to remove 'B' FWRV from service per DOP 0600-06, Feedwater Regulating Valve (FWRV) Operation.

ATC Removes 'B' FWRV from service per DOP 0600-06, Feedwater Regulating Valve (FWRV) Operation. Verifies total Feedwater flow is 8.3 Mlbm/hr. Verifies reactor level stable. (LFRV is controlling level) Places 'B' FWRV REG VLV CONTROL STATION in MAN. Verify 'A' FWRV operating in MASTER AUTO. Slowly reduces 'B' FWRV DEMAND to cl ose 'B' FWRV while verifying 'A' FWRV automatically adjusts. (Both valves are closed at start of evolution) Closes isolation valve MO 2-3206B, 2B FW REG ISOL. Places 'B' FWRV in test at the OIS 2 3 SIMULATOR OPERATOR / ROLE PLAY:

When the operator goes to the OIS station, which is not modeled in the simulator, then:

o When the operator indicates he is placing the 'B' FWRV in test, activate trigger 2 , which forces up alarm 902-6 H-3, FW Control System Panel Trouble. Cue the operator that 'B' FWRV is in test.

o When the operator indicates he is acknowledging the OIS alarm, activate trigger 3 , which returns alarm 902-H-3 to normal. Cue the operator that the OIS alarm is acknowledged.

BOP Assist ATC as directed. Event 1 Completion Criteria:

2B FWRV removed from service, AND/OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 9 of 25 Rev. 00 (10/09)

Event Two - Condensate/Booster Pump Trip with Failure of STBY to Auto Start Trigger Position Crew Actions or Behavior NOTE: The first Cond/Boost pump the ATC attempts to start will also trip. The other non-running Cond/Boost pump will start and remain running.

2 14 15 SIMULATOR OPERATOR / ROLE PLAY:

At the discretion of the Lead Examiner, activate trigger 2. This will cause a trip of 2A Cond/Boost pump.

Verify trigger 14 automatically activates when 2B Cond/Boost PP breaker closes and if 2D Cond/Boost PP trip malfunction is not true. This trips 2B Cond/Boost PP.

Verify trigger 15 automatically activates when 2D Cond/Boost PP breaker closes and if 2B Cond/Boost PP trip malfunction is not true. This trips 2D Cond/Boost PP.

ROLE PLAY:

EO to check operation of started Cond/Boost pump: wait 2 min, the report "the 2B (Or 2D) Cond/Boost pump is operating normally". EO to check the breaker for tripped pump: wait 2 min, and then report "the breaker has an overcurrent target up".

ATC Announces alarms 902-6 F-5, CONDENSATE BOOSTER PP TRIP. 902-6 G-4, CONDENSATE PP DISCH PRESS LO. 902-5 H-7, RFP SUCTION PRESS LO Determines STBY pump (2D) did not start. May place STBY PP SELECTOR switch to OFF. Attempts to start either 2B or 2D Condensate Booster pump. Determines Condensate Booster pump started tripped. Starts other non-tripped pump. .Determines it started and is operating properly.

ROLE PLAY:

As the EO, if asked, report: "2B (or 2D) Condensate Booster pump is operating normally".

CRS Enters DOA 0600-01, Transient Level Control. Directs starting an available Condensate Booster pump.

BOP Monitors panels and assists as directed. Event 2 Completion Criteria:

An available Condensate Booster pump started, AND/OR At the direction of the Lead Examiner.

SCENARIO ILT-N-3 Page 10 of 25 Rev. 00 (10/09)

Event Three - Secondary Containment Doors Open Trigger Position Crew Actions or Behavior Role Play:

At the discretion of the Lead Evaluator, call the control room as the U2 EO and report, "Both the inner and outer U2 Reactor Building Truck Interlock doors are blocked open with an air hose running through them". EO to have the doors unblocked and closed: Wait 5 min, then report, Both the inner and outer U2 Reactor Building Truck Interlock doors are blocked closed".

TEAM Receives report that both the inner and outer U2 Reactor Building Truck Interlock doors are blocked open. Directs EO to close at least one of the doors.

CRS References Technical Specifications and determines: TS 3.6.4.1.A: Determines must restore Secondary Containment within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Event 3 Completion Criteria:

Secondary Containment Doors closed and Tech Specs referenced, AND/OR, At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 11 of 25 Rev. 00 (10/09)

Event Four - IRM Fails Upscale with Half Scram Trigger Position Crew Actions or Behavior 3 SIMULATOR OPERATOR / ROLE PLAY:

At the discretion of the Lead Examiner, activate trigger 3, which fails IRM channel 12 upscale. ATC Perform the following actions per DAN 902-5 C-10, CHANNEL A IRM HI HI/INOP: If not in the RUN Mode, verifies the following occurred:

o Channel A half scram o No rods Scrammed.

o Rod Block. Verifies IRM 12 readings against other IRMs on 902-5 panel. Verifies IRM range switch in correct position Bypasses IRM 12 after T. S. compliance verified by CRS. Resets RPS channel A per DOP 0500-07, Insertion/Reset of Manual Half Scram, as follows: o Verifies half scram no longer required Turns the Scram Reset switch in each direction and verifies all eight white group solenoid lights are lit.

o Verifies alarm 902-5 A-10, Channel A Manual Trip, resets.

BOP Performs the following actions per DAN 902-5 C-10: Verifies IRM 12 readings against other IRMs on 902-36 panel. Verifies IRM 12 function switch in operate. Verifies power supplies operating properly.

CRS Directs IRM 12 bypassed and the half scram reset per DOP 0500-07, Insertion/Reset of Manual Half Scram. Notifies the Shift Manager and IMD.

ROLE PLAY:

At the discretion of the Lead Examiner, as the QNE, phone the control room and report "While analyzing the rod pattern I determined that control rods G-08 and J-08 do not comply with the analyzed rod sequence".

CRS References plant technical documents and determines: TS 3.1.6 Condition A.1: Move associated control rod(s) to correct position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; OR , TS 3.1.6 Condition A.2: Declare associated control rod(s) inoperable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SCENARIO ILT-N-3 Page 12 of 25 Rev. 00 (10/09)

Event Four - IRM Fails Upscale with Half Scram Trigger Position Crew Actions or Behavior Event 4 Completion Criteria:

IRM 12 bypassed, Half scram reset, AND Tech Spec determination complete. AND / OR At the direction of the Lead Examiner.

SCENARIO ILT-N-3 Page 13 of 25 Rev. 00 (10/09)

Event Five - Loss of EHC / Manual Reactor Scram Trigger Position Applicant's Actions or Behavior Note: The next Event begins when the reactor is scrammed.

4 Simulator Operator:

At the direction of the Lead Examiner, activate trigger 4 to simulate EHC Hydraulic Oil leak. Role Play:

EO sent to check EHC hydraulic system, wait 3 min. then report, "The EHC hydraulic oil tank level is dropping rapidly."

EO directed to fill EHC reservoir: report "I will contact t he store room to have EHC oil sent to the reservoir".

BOP Announces alarm 902-7 B-6, EHC RESERVOIR LVL HI/LO. Determines from SER that the alarm is due to low EHC level. May direct EO to fill the EHC reservoir. May access the DEHC "Monitor/Hydrau lics" display to track EHC level.

CRS Determines EHC system loss is imminent. May direct scram preparations per DGP 02-03, Reactor Scram.

ATC Performs scram preparations per DGP 02-03, Reactor Scram, as directed:

o Conditions are already met.

CRS Before EHC hydraulics is lost, directs Team to scram the reactor per DGP 02-03, Reactor Scram.

ATC Performs the following actions per DGP 02-03, Reactor Scram, and DEOP 100, RPV Control, as directed: Places Mode Switch to Shutdown and depresses the Scram pushbuttons. Determines all rods are inserted. Maintains RPV level as directed by CRS. Inserts SRMs and IRMs.

CRS Enters DEOP 100, RPV Control, Directs actions of DEOP 100. Directs actions of DGP 02-03. Verification of all isolations, ECCS and EDG starts. Holding RPV/L +8 to +48 inches. Maintaining RPV/P <1060 psig using the Isolation Condenser.

BOP If directed, maintains RPV/P <1060 psig using the Iso Cond to control RPV/P. (may use Hardcard) Performs Reactor Scram actions per his Hardcard.

SCENARIO ILT-N-3 Page 14 of 25 Rev. 00 (10/09) Event Five - Loss of EHC / Manual Reactor Scram Trigger Position Applicant's Actions or Behavior Event 5 Completion Criteria

Team has performed a reactor scram, AND/OR At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 15 of 25 Rev. 00 (10/09)

Event Six - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior 5 SIMULATOR OPERATOR

Verify trigger 5, automatically activates when the Mode Switch is placed to S/D. After 1 min, this causes all feedwater regulating valves to fail closed.

6 SIMULATOR OPERATOR:

After the loss of DEHC and at the discretion of the Lead Evaluator, activate trigger 6 cause a recirc loop leak.

7 SIMULATOR OPERATOR:

When HPCI starts, verify trigger 7 automatically activates, which causes a spurious HPCI isolation.

8 SIMULATOR OPERATOR / ROLE PLAY

EO sent to lineup CRD crosstie: wait 4 min, activate trigger 8, then report: "the CRD crosstie is lined up".

9 10 SIMULATOR OPERATOR / ROLE PLAY

EO sent to lineup makeup to SBLC Boron tank: wait 4 min, activate trigger 9, and report: "makeup lined up to SBLC Boron tank". EO sent to lineup makeup to SBLC Test tank: wait 4 min, activate trigger 10, and report: "makeup lined up to SBLC Test tank".

ROLE PLAY:

EO sent to check EDG operation: wait 3 min, then report: "Both EDGs are operating normally". EO sent to cut out Cond Demin beds: wait 3 min, cutout Demin beds as needed (using instructor station), then report: "Cond Demin beds cutout". BOP checks OIS: Inform BOP that "the OIS display lost power". ROLE PLAY:

Acknowledge other requests; delay as necessary.

ATC Determines/announces all feedwater regulating valves are failed closed.

CRS Directs use of HPCI if needed to maintain RPV level.

TEAM Determines/announces Drywell pressure rapidly rising. Determines/announces RPV level is dropping.

CRS Directs starting HPCI to maintain Level.

BOP Starts HPCI as directed. Determines/announces HPCI isolated.

SCENARIO ILT-N-3 Page 16 of 25 Rev. 00 (10/09) Event Six - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior CRS Determines insufficient high pressure feed is available, then performs/directs: Inhibiting ADS before -59 inches. Initiating the Isolation Condenser Lining up high pressure Alternate Injection systems. Verifying at least two low pressure injection systems available. Waiting until RPV level drops to TAF. Verifying any low pressure system lined up with a pump running.

BOP Inhibits ADS as directed.

CRS Enters DEOP 0200-01, Primary Containment Control, when PC/P reaches 2 psig and performs/directs: Monitoring of PC/P. Initiation of torus sprays before PC/P of 9 psig. When PC/P is above 9 psig or before DW/T reaches 281F: Verification of DSIL. Tripping of recirc pumps. Tripping of DW coolers. Initiation of DW sprays. Monitoring of DW/T. (D/W sprays may be initiated for temp control) Monitoring of SP/T and initiation of torus cooling. Monitors SP/L. Verifies initiation of drywell and torus H 2/O 2 monitors.

BOP Performs DEOP 0200-01, Primary Containment Control, actions as directed: Monitors PC/P and initiates torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed. 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 H 2/O 2 monitors.

NOTE: Above a RPV pressure of 500 psig, TAF is -170 inches on the Fuel Zone indicators. Below 500 psig, TAF is -143 inches.

SCENARIO ILT-N-3 Page 17 of 25 Rev. 00 (10/09) Event Six - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior CRS Before RPV level reaches -164 inches, enters DEOP 0400-02, Emergency Depressurization, and directs: Initiation of Iso Condenser to maximum flow. Verification that SP/L >6 feet. Opening all ADS valves.

Verification all relief valves are open.

BOP Performs DEOP 0400-02, Emergency Depressurization, as directed: Initiates Iso Condenser to maximum flow per Hard Card, ISOLATION CONDENSER. Verifies SP/L >6 feet. Opens all ADS valves.

Verifies all relief valves are open.

CRS Directs ATC/BOP to control RPV level above TAF using any of the preferred injection systems listed below: Condensate Core Spray LPCI ATC / BOP Restores RPV level to that directed by the CRS (above TAF) using the systems specified by the CRS. Event 6 / Scenario Completion Criteria:

Sprays the Drywell Performs an Emergency Depressurization. Restores RPV level above TAF. AND / OR, At the direction of the Lead Examiner.

SCENARIO ILT-N-3 Page 18 of 25 Rev. 00 (10/09)

Critical Tasks Inhibits ADS before Automatic Blowdown conditions are met. (RPV-1.1) With Reactor pressure greater than shutoff head of the low pressure system(s) and when RPV water level reaches TAF, INITIATE emergency depressurization, before level reaches Minimum Zero-Injection RPV Water Level. (RPV-1.2) Action is taken to restore RPV water level above TAF, by OPERATING available low pressure system(s), when RPV pressure decreases below the shutoff head of the low pressure system(s). (RPV-5.1) When drywell pressure exceeds the suppression chamber spray initiation pressure or before containment pressure exceeds the Pressure Suppression Pressure, INITIATE drywell/containment sprays, while in the safe region of the drywell spray initiation limit or above the containment spray initiation pressure.

SCENARIO ILT-N-3 Page 19 of 25 Rev. 00 (10/09) REFERENCES PROCEDURE TITLE DAN 902-5 C-10 CHANNEL A IRM HI HI/INOP DAN 902-5 H-7 RFP SUCTION PRESS LO DAN 902-6 F-5 CONDENSATE BOOSTER PP TRIP DAN 902-6 G-4 CONDEN SATE PP DISCH PRESS LO DAN 902-7 B-6 EHC RESERVOIR LVL HI/LO DEOP 0100 RPV CONTROL DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DEOP 0400-02 EMERGENCY DEPRESSURIZATION DGP 01-01 UNIT STARTUP DGP 02-03 REACTOR SCRAM DOA 0600-01 TRANSIENT LEVEL CONTROL DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0500-07 INSERTION/RESET OF MANUAL HALF SCRAM DOP 0600-06 FEEDWATER REGULATING VALVE (FWRV) OPERATION TS 3.1.6 REACTIVITY CONTROL TS 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TS 3.6.4.1 SECONDARY CONTAINMENT TRM 3.3.a CONTROL ROD BLOCK INSTRUMENTATION

SCENARIO ILT-N-3 Page 20 of 25 Rev. 00 (10/09) Simulator Scenario Review Checklist (cont'd)

ILT-N-3 Quantitative Attributes 5 Total malfunctions (5 to 8) 2 Malfunctions after EOP entry (1 to 2) 2 Abnormal events (2 to 4) 2 Major transients (1 to 2) 2 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 4 Crew critical tasks (2 to 3)

SCENARIO ILT-N-3 Page 21 of 25 Rev. 00 (10/09)

CAEP Files

1. ILT-N-3.cae # For ILT Class 09-1 NRC Exam

1. Written by DRDR9

1. Rev 00 # Date 10/09

1. INITIAL CONDITIONS

1. Sets APRM Master Gain pot to 1.0 irf niagain 1.0

1. Prevents 2D Cond/Boost PP from Auto starting by:

1. Overriding OFF the PUMP 2D position of the STBY SELECT switch, # and overiding ON the 2D Cond/Boost PP STANDBY light. ior fwdselcb2 off ior fwdselcb4 off ior fwlsbycb4 on

1. Removes alarm 902-3 A-2, MSL Rad Mon Hi alarm. (Should not be up) imf ser0024 offl2 imf ser0058 offl2 imf ser0060 offl2 imf ser0062 offl2

1. Removes alarm 902-3 B-2, MSL Rad Mon Dwnscl alarm. (Should not be up) imf ser0007 offl4 imf ser0034 offl4 imf ser0035 offl4 imf ser0064 offl4

1. EVENT TRIGGERS

1. Event Trigger 1 sets gain for all 6 APRMs. trgset 1 "0"l6 trg 1 "irf niagainf true"l6

1. Event Trigger 2 Forces up alarm 902-6 H-3, FW Control System Panel Trouble. trgset 2 "0"l6 imf ser1274 (2) onl6

1. Event Trigger 3 Forces up alarm 902-6 H-3, FW Control System Panel Trouble. trgset 3 "0"l8 trg 3 "imf ser1274 (2) normal"l8

1. Event Trigger 4 Trips 2A Cond/Boost PP. # Overrides FW PP Suct Hdr Press meter to 135 psig. # Forces up alarm 902-5 H-7, RFP Suction Press Lo. trgset 4 "0"l8 imf h21 (4)l8 ior fwpsucta (4) 135.0l10 imf ser1031 (4 2) onl10

1. Event Trigger 5 IRM 12 channel fails upscale over a two minute ramp. trgset 5 "0"l10 imf nii12pot (5) 125.0l10

SCENARIO ILT-N-3 Page 22 of 25 Rev. 00 (10/09) # Event Trigger 6 simulates EHC Hydraulic Oil leak. trgset 6 "0"l12 imf daisehc_level (6) 0.0 4:00 14.0l12 irf ehcrfv1o (6 4:00) 0.0 4:00l12 imf ser0662 (6) onl12

1. Event Trigger 7 Activates when Mode Switch is placed to S/D.

1. After 1:00 min, fails ALL FW Reg valves closed. trgset 7 "rpdmode4_drw"l14 imf rlmfafc (7 1:00)l14 imf rlmfbfc (7 1:00)l14 imf rlmlffc (7 1:00)l14

1. Event Trigger 8 Inserts a small leak in A Recirc suction line. trgset 8 "0"l16 imf f41 (8) 0.8l16

1. Event Trigger 9 Activates when HPCI speed >2000 rpm.

1. Causes a spurious HPCI isolation. trgset 9 "hpsturb .gt. 2000.0"l16 imf at37 (9) 0.0l16 imf at43 (9) 0.0l18

1. Event Trigger 10 opens U3/U2 CRD cross-tie valve trgset 10 "0"l18 irf rdxtieu3 (10) truel18

1. Event Trigger 11 lines up makeup to SBLC Main Boron tank. trgset 11 "0"l20 irf scmumntk (11) truel20

1. Event Trigger 12 lines up SBLC pumps to test tank and makeup to test tank trgset 12 "0"l20 irf scoptttk (12) truel20

1. Event Trigger 14 Activates when 2B Cond/Boost PP breaker closes and # if 2D Cond/Boost PP trip malfunction is not true. # Trips 2B Cond/Boost PP.

trgset 14 "fwsacbcb(2) .and. (.not. fwm433f(4))"l22 imf h22 (14)l22

1. Event Trigger 15 Activates when 2D Cond/Boost PP breaker closes and # if 2B Cond/Boost PP trip malfunction is not true. # Trips 2B Cond/Boost PP.

trgset 15 "fwsacbcb(4) .and. (.not. fwm433f(2))"l22 imf h24 (15)l22

1. Event Trigger 16 Activates when 2B Cond/Boost PP breaker closes and # if 2D Cond/Boost PP trip malfunction is true. # Deletes override on FW PP Suct Hdr Press meter. trgset 16 "fwsacbcb(4) .and. fwm433f(2)"l24 trg 16 "dor fwpsucta"l24

1. Event Trigger 17 Activates when 2D Cond/Boost PP breaker closes and # if 2B Cond/Boost PP trip malfunction is true.

1. Deletes override on FW PP Suct Hdr Press meter. trgset 17 "fwsacbcb(2) .and. fwm433f(4)"l24 trg 17 "dor fwpsucta"l24

1. Event Trigger 18 Activates when either trigger 16 or 17 is active.

SCENARIO ILT-N-3 Page 23 of 25 Rev. 00 (10/09) # Returns alarm 902-5 H-7, RFP Suction Press Lo, to NORMAL. trgset 18 "et_array(16) .or. et_array(17)"l26 trg 18 "imf ser1031 (0 2) normal"l26

1. END SCENARIO ILT-N-3 Page 24 of 25 Rev. 00 (10/09)

Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 2 at ~2% power Leading Thermal Limit: NA

Action limit: NA Equipment Unavailable: None Protected Equipment: None Unit 3 is in Mode 1 at 913 MWe Leading Thermal Limit: MAPRAT @ 0.819

Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started:

LCO Expires:

TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Separator Pit as required. Outside operator monitor and pump as necessary.

Today Chem Cleaning ventilation status: HV-1A/EF-1A are secured due to HV-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV-1B throwing its belts. WO 1156150. HVAC -1 ON.

HV-2 running.

Switchyard Status Today TSO notified of oil leaks on 345 Kv BT 2-3 CB (IR 810135) ComEd WO 6396128 Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area.

Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood. SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work. Be careful.

SCENARIO ILT-N-3 Page 25 of 25 Rev. 00 (10/09)

Unit 2 Plant Status Today Unit 2 Activities **** Shift 1 Activities ****

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• • • • Shift 2 Activities **** ~ Immediately after assuming the shift, remove 2B FWRV from service for maintenance per DOP 0600-06, step G.11. (2A FWRV was placed in service at the end of last shift ) ~ Continue Unit Startup when QNE completes REMA Re-evaluation. **** Shift 3 Activities ****

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~ Today **** Unit 2 Procedures In-Progress **** Do Not Delete ****

~ DGP 01-01, Unit Startup

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