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2019 DAEC Ile Scenarios
	ML22143B001
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Site:	Duane Arnold
Issue date:	04/08/2019
From:	Randy Baker; NRC/RGN-III/DRS/OLB
To:	; NextEra Energy Duane Arnold
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SIMULATOR EXERCISE GUIDE, SEG THREE COLUMN Page 1 of 33 SITE: DAEC Revision #: 0 LMS ID: PDA OPS 19-1 NRC Scenario #1 LMS Rev. Date:

SEG TITLE: NRC Exam Scenario #1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 2 of 3 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators ability to:

Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained Objectives:

Prerequisites: NONE Training A. Simulator Resources: B. Evaluation Team C. Operations Management Representative D. Simulator Operator E. Booth Communicator F. Simulator video recording equipment

References:

1 AOP 901, Rev 31 2 TS 3.4.1, Amendment 223 3 ARP 1C04B, A-1, Rev. 83 4 AOP 255.2, Rev 46 5 AOP 264, Rev 14 6 ARP 1C23C, Rev 55 7 ARP 1C08C, Rev 62 8 ARP 1C06B, Rev 64 9 AOP 639, Rev 36 10 EOP 1, Rev 20 11 ATWS, Rev 23 12 EOP 2, Rev 18 13 EOP 3, Rev 4 14 RIP 103.2, Rev 4 15 RIP 102.1, Rev 9 16 ARP 1C14A, Rev 20 17 OI 151, Rev 71 18 OI 152, Rev 116 19 ED, Rev 11 Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: In accordance with NUREG 1021 Operating NONE Experience:

TR-AA-230-1007-F13 , Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 3 of 4 Risk Significant Control Feedwater Following a Scram Operator Actions: Initiate an Emergency Depressurization TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.22 Respond to Earthquake Condition 94.58 Respond to Loss of Reactor Recirculation Pump(s) 94.03 Respond to Power/Reactivity Abnormal Change Condition 94.18 Respond to Reactor Water/Condensate High Conductivity Condition 95.57 Perform /Q to Reduce Reactor Power or Scram the Reactor 95.06 Perform Reactor SCRAM Using Repeated Manual Scram 95.08 Insert Control Rods by Increasing CRD Cooling Flow and Pressure 95.65 Spray the Drywell with RHR Not Required for Adequate Core Cooling 96.80 Perform an Emergency Depressurization Using SRVs 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 5.22 Direct Crew Response to Earthquake Condition 5.58 Direct Crew response to Loss of Reactor Recirculation Pump(s) 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.18 Direct Crew Response to Reactor Water/Condensate High Conductivity Condition Direct Crew Response to Control RPV Injection prior to, during and subsequent to 6.52 Emergency Depressurization during ATWS Direct Crew Response to Perform /Q to reduce Reactor Power / Scram the Reactor 6.56 During ATWS 6.06 Direct Crew Response to Perform Reactor SCRAM using Repeated Manual Scram Direct Crew Response to Insert Control Rods by Increasing CRD Cooling Flow and 6.08 Pressure 6.80 Direct Crew Response to Perform an Emergency Depressurization Using SRVs UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover 0.0 Initial Development for PDA 19-1 License exam N/A See Cover TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 4 of 5 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW See below event description for overview SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description

1. Shift EHC Pumps IAW OI 693.2, Section 6.2.1(2)

2. Raise Rx Power with Control Rods to 80% power for 1 hr hold (Xe)

3. The crew will respond to an accumulator alarm on control rod 22-07. The alarm will be low nitrogen pressure due to a packing leak on the V-18-296, Accumulator Instrument Cartridge Valve.

The Crew enters TS 3.1.5 Condition A to either declare the control rod slow, or to declare the control rod inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , for an inoperable accumulator.

4. A Design Basis Earthquake will occur at DAEC. The crew will enter AOP 901, Earthquake and take the appropriate actions.

5. H2 Main Seal Oil Pump fails and the crew will have to start the Emergency H2 Seal Pump and secure the H2 Seal Oil Vacuum Pump per ARP 1C08C D-6

6. a. The earthquake will also result in Hi Vibrations and trip of the B Recirc MG set.

b. The crew will respond to the trip of the Recirc MG set IAW AOP 255.2, Power/Reactivity Abnormal Change, and AOP 264, Loss of Recirc Pump (s).

The Crew will enter TS 3.4.1, Condition D to perform SLO STPs within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

7. When the events caused by the earthquake are under control, a condenser tube leak will occur. The crew will enter AOP 639, Reactor Water/Condensate High Conductivity. This tube leak will lead to a reactor scram.

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 5 of 6

8. On the scram, the Crew will determine that a Hydraulic ATWS has occurred. The Crew will insert ALL the control rods by either drifting them in, per RIP 103.2, Increase CRD Cooling Flow and Pressure, or by performing the scram reset scram IAW RIP 102.1, Repeated Manual Scram, as directed by the Hydraulic ATWS RIPS. (Critical)

Power will be high enough that the crew may enter Power Level Control Prior to all rods being inserted.

The crew will enter Power Level Control, they will Lock Out ADS (Critical), secure and prevent injection from HPCI, Condensate and Feedwater, CS and RHR, until RPV level lowered to below 87 (Critical)

Once they reach a level that will allow the crew to re-inject, prior to all rods inserting, they will maintain RPV level above -25 using Condensate and Feedwater and or RCIC.

(Critical)

9. An unisolable leak in the torus will develop. The crew will monitor the leak IAW EOP 2, and prior to the torus level lowering below 7.1 feet, they will enter an Emergency Depressurization. (Critical)

10. The scenario will end after the crew has depressurized the plant and are restoring RPV level to the desired band.

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 6 of 7 SIMULATOR SET UP INSTRUCTIONS

1. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist ____

2. Using the exam flash drive with the scenario simulator files, insert in the left instructor station computer and navigate to the D:\ directory ____

3. Copy the NRCScenario1.dat file from the exam flash drive to C:\Trex_Duane-TELEC\Executive\SiteSpecific\InitialCondition and rename the file to an available IC using the format ic_### ____

a. Reset to the newly created IC ____ ____

b. Place the Simulator in RUN ____

c. Run schedule file Weather.sch following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles ____

OR Reset to IC 23, place the simulator in RUN and perform the following (this will take approximately 15 minutes for the plant:

a. Insert Event Triggers, Malfunctions, Overrides, and Remotes using schedule ____

file SEG_Setup.sch located on the exam flash drive using the following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles

4. Have a second instructor verify:

b. Auto triggers are setup as indicated below and evaluate to FALSE ____

c. Malfunctions ____

d. Remotes ____

e. Overrides ____

5. Open Keypad file NRC_Scenario_1.key located on the exam flash drive using the following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles ____

6. Setup Thundersound on the Instructor Station computer to the right and verify the following settings:

a. Click on the checkbox under Playing for Earthquake ____

b. Click the STOP button to toggle audio model to playing ____

c. Verify Instructor Station sound volume is set to approximately 25% ____

d. Verify the dB controller (under the Instructor Station monitor) level 2 know is aligned to the detent (white line on the knob is pointing slightly counterclockwise) ____

e. Verify the Front Room (both) sub amplifiers are set to approximately 50% of scale ____

7. Place Guarded Equipment tags on: ____

1B35 Switch

1B43 Switch

8. Markup IPOI 3, Section 5, Steps 1 through 7, specifically the following:

a. Step 7.a mark N/A

b. Step 7.b.7 mark with a circle

c. Step 7.b.8 leave blank

d. Step 7.c.1 through 3 mark N/A

e. Step 7.d.1 through 8 mark N/A TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 7 of 8

9. Display DR and Power on the Operator Terminals ____

10. Markup MOL pull sheet STEP 37 for control rods withdrawn to their current position ____

11. Ensure MOL pull sheets are in the 1C05B hanging file ____

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 8 of 9 EVENT TRIGGER DEFINITIONS:

Trigger No Trigger Logic Statement Trigger Word Description 3 rxqic >= 0.8 Core Power at 80%

5 an_1c06b(1) 1C80 Trouble 7 !rpdis1run(1) MODE SW out of RUN 9 rd_fi All rods full in 11 ZDITCBPVJINCR l ZDITCBPVTSTG SEP 307 Attmpt MALFUNCTIONS:

Time Malf. No Malfunction Title ET Delay Ramp Initial Final Value Value As dir RD072207 CONTROL ROD ACCUMULATOR TROUBLE- 3 INACTIVE ACTIVE ROD 22-07 Set up RP05G HYDRAULIC LOCK SCRAM DISCHARGE VOLUME 0 65 (VARIABLE)

OVERRIDES:

Time OR # Override Title ET Delay Ramp Initial Final Value Value Set up DI-MS- HS-4535 RX WTR LVL LO-LO NORMAL NORMAL 076 TRIP OVRRD - A1 Set up DI-MS- HS-4536 RX WTR LVL LO-LO NORMAL NORMAL 077 TRIP OVRRD - A2 Set up DI-MS- HS-4427A GRP 1 CHAN A1 ALL NORMAL NORMAL 072 SIGNALS OVRRD Set up DI-MS- HS-4427C GRP 1 CHAN A2 NORMAL NORMAL 074 ALL SIGNALS OVRRD Setup DO-EG- X390 MAIN GENERATOR OFF ON 077 ALTERREX SUPPLEMENTARY TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 9 of 10 REMOTE FUNCTIONS:

Time RF # Remote Function Title ET Delay Ramp Initial Final Value Value KEYPAD FILE:

NRC_Scenario_1.key Key Key Action 1 Delete Malfunction RD072207 2 Insert Malfunction ZZ03 Schedule D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles\

3 Seal_Oil_Pump_Trip.sch Schedule D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles\

4 B_Recirc_Pump_VibTrip.sch 5 Toggle Event 2 Schedule D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles\

6 Condenser_Tube_Leak.sch Schedule D:\NRCOperational\NRCScenarios\NRC_Scenario_1\NRCScenario1_SimFiles\

7 Defeat_12_Install.sch SCHEDULE FILE(S):

Weather.sch At Time Event Action Description 00:00:01 None Insert remote hv01 to 223 in 7200 WIND DIRECTION AT 50 meters (165 ft)

Insert remote hv02 from 23 to 27 00:00:01 None WIND SPEED AT 50 meters (165 ft) in 7200 00:00:01 None Insert remote hv03 to 45 in 28800 DEW POINT TEMPERATURE AMBIENT TEMPERATURE AT 50 meters 00:00:01 None Insert remote hv05 to 68 in 28800 (165 ft)

AMBIENT TEMPERATURE AT 10 meters (35 00:00:01 None Insert remote hv06 to 73 in 28800 ft) 00:00:01 None Insert remote hv07 to 73 in 28800 RIVER WATER TEMPERATURE TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 10 of 11 Seal_Oil_Pump_Trip.sch At Time Event Action Description Create Event 20 00:00:00 None ZDIEGHS3640(4) -desc Emerg Seal Oil Pump HS Start Insert Override DO-EG-028 to HS-3641(1) MAIN SEAL OIL PUMP 1P-92 00:00:00 None OFF (GREEN)

Insert Override DO-EG-029 to HS-3641(2) MAIN SEAL OIL PUMP 1P-92 00:00:00 None OFF (RED)

Insert Malfunction AN1C08C(24) 1C08C (D-06) HYDROGEN SEAL OIL MAIN 00:00:00 None to ON PUMP 1P 92 AUTO TRIP HS-3640(1) EMERGENCY SEAL OIL PUMP 00:00:00 None Insert Override DO-EG-026 to ON 1P-93 (GREEN)

Insert Override DO-EG-027 to HS-3640(2) EMERGENCY SEAL OIL PUMP 00:00:00 None OFF 1P-93 (RED) 00:00:00 None Insert Malfunction EG08B LOSS OF SEAL OIL PUMP- RSOP 00:00:00 None Insert Malfunction EG08A LOSS OF SEAL OIL PUMP- MSOP HS-3640(1) EMERGENCY SEAL OIL PUMP None 20 Delete Override DO-EG-026 1P-93 (GREEN)

HS-3640(2) EMERGENCY SEAL OIL PUMP None 20 Delete Override DO-EG-027 1P-93 (RED)

None 20 Delete Malfunction EG08B LOSS OF SEAL OIL PUMP- RSOP None 20 Toggle Event 20 B_Recirc_PumpVibTrip.sch At Time Event Action Description Insert malfunction rr35b to 00:00:00 None Recirc Pump High Vibes - Pump B 50.00000 Insert malfunction rr05b to 00:00:00 None RECIRC PUMP SHAFT SEIZURE- PMP B 100.00000 on event 2 Insert malfunction rr06b after 2 on RECIRC M-G DRIVE MOTOR BREAKER 00:00:00 None event 2 TRIP- M-G B Insert malfunction pc14 to PRIMARY CONTAINMENT TORUS 00:00:01 None 35.00000 on event 9 LEAKAGE Insert malfunction ms19a on event SPURIOUS GROUP I ISOLATION- RELAY 00:00:01 None 11 A71-K7A Insert malfunction ms19b on event SPURIOUS GROUP I ISOLATION- RELAY 00:00:01 None 11 A71-K7B Condenser_Tube_Leak.sch At Time Event Action Description Insert malfunction mc07 to MAIN CONDENSER TUBE (1E-7A) 00:00:00 None 0.90000 LEAKAGE Modify malfunction mc07 after 180 MAIN CONDENSER TUBE (1E-7A)

None 5 from 0.90000 to 2.00000 in 240 LEAKAGE MAIN CONDENSER TUBE (1E-7A)

None 7 Delete malfunction mc07 LEAKAGE TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 11 of 12 Defeat_12_Install.sch At Time Event Action Description ATWS TEST SWITCH (AKA DEFEAT 12) HS-00:03:00 None Insert Remote RP02 to TEST 1863A (RUN,TEST)

ATWS TEST SWITCH (AKA DEFEAT 12) HS-00:03:40 None Insert Remote RP03 to TEST 1864A (RUN,TEST)

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 12 of 13 SHIFT TURNOVER INFORMATION

Day of week and shift o Today, day shift

Weather conditions o Cloudy, with a cold front coming in later today

Plant power:

o ~75% reactor power with the corresponding MWe, MWth, and core flow

Reactor coolant leakage is normal (if asked: 1.56 identified, 0.03 unidentified)

Plant PRA Status o CDF: 1.32 x 10-6, GREEN, 1 year to Yellow o LERF 3.32 x 10-7, GREEN, 1 year to Yellow o SFP risk is LOW, time to 200°F is 56 Hours

B side protected, specifically guarded equipment is o Skimmer Surge Tank Room o 1B3507, A Fuel Pool Cooling Pump Breaker o 1B4327, B Fuel Pool Cooling Pump Breaker o 1C136, Fuel Pool Filter/Demin Control Panel

No Locked in / failed annunciators or alarms

No Existing LCO action statements

Procedures or major maintenance in progress o Alternate EHC Pumps (A EHC pump is currently running) o Raise reactor power to approximately 80% using the Control Rod Withdrawal Sequence Sheets o Later in the shift, Security will be running a force-on-force drill

No equipment to be taken out of service or returned to service this shift

Comments, problems, operator workarounds, etc.

o The Radwaste Operator is NSPEO qualified o Two extra NSPEOs available in Work Control o Operations Management as agreed that the CRS will serve as the Reactivity SRO TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 13 of 14 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1: The Crew will perform the actions of OI 693.2, Section 6.2.1 and alternate Alternate EHC the EHC Pumps Pumps CRS Simulator Operator

Supervise the evolution If contacted to Acknowledge the request BOP verify the non-running EHC

Start standby EHC Pump 1P 97B by momentarily placing handswitch Pump is ready HS-3665B in the START position for start

Verify annunciator EHC PUMPS 1P-97A/B BOTH RUNNING (1C07A, C-4) is activated.

Simulator Operator

Verify the Amps for both EHC Pumps have stabilized wait 2 minutes Report the B EHC Pump is ready for

At 1C07, stop EHC Pump 1P 97A by momentarily placing handswitch HS start 3665A in the STOP position.

Verify all annunciators are reset for the evolution Simulator Operator If contacted to Report the B EHC Pump is running sat.

verify the B If asked about the status of the A EHC EHC Pump is pump, REPORT that all EHC running sat, parameters are normal TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 14 of 15 EVENT 2: Crew: Raise reactor power using Control Rod Sequence Sheets Raise Power with control rod withdrawal CRS:

Provide Control Rod Refocus Brief per IPOI 3

Direct control rod withdrawal to a target power of 80% reactor power ATC EVALUATOR NOTE: ATC:

The ATC Operator will withdraw the Repeat as necessary to establish the target power directed:

following control rods for RWM Step 37:

14-19

Select the desired control rod using the rod select matrix

14-27

Using control rod movement switch withdraw the control rods as

30-27 directed to establish the desired reactor power

30-19

Monitor core parameters as power is changed, such as:

The ATC Operator may plot on the Power o Recirc flow to Flow map and/or print a ACUMEN o Reactor jet pump total core flow Report after withdrawing control rods per o Total steam flow the control rod sequence sheets o Total feed flow o Reactor water level o Reactor pressure o APRM power BOP:

Provide peer checks are requested

Monitor plant parameters as power is changed, such as:

o Generator output TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 15 of 16 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3: Crew: Respond to annunciator 1C05A (F-7), CRD ACCUMULATOR LO When rxqic is SIMULATOR OPERATOR PRESSURE OR HI LEVEL

>= 0.8 or at the Verify ET 3 is active TRUE direction of the ATC:

Lead Evaluator, This will result in an Accumulator alarm for control rod 22-07.

Check the Full Core Display on 1C05 to determine which accumulator(s) is/are in the trouble condition.

When directed o Determines that the alarm is on Control Rod 22-07 to investigate BOOTH COMMUNCIATOR

Send an Operator to the accumulators to determine the cause of the control rod 22- Acknowledge the request, WAIT 3 alarm 07 for an minutes and REPORT, The alarm was

Inform the CRS to comply with Technical Specification requirements for accumulator due to low nitrogen pressure. Pressure Control Rod Scram Accumulators alarm, is currently 900 psig.

Direct the Second Assistant to either drain the water from the accumulator, or recharge the accumulator SIMULATOR OPERATOR When directed Click KEYPAD Key 1 to recharge the CRS (1.02)

This will delete Malfunction RD072207 and accumulator, clear the 1C05 indication and alarm. Will enter TS 3.1.5 Condition A to either declare the control rod slow, wait 4 min and or to declare the control rod inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , for an Accumulator 22-07 is recharged to 1090 then report, inoperable accumulator.

psig o Call for maintenance support to correct the problem BOOTH COMMUNCIATOR If called as the Acknowledge call and inform the RE to see if Operator that there are NO slow control there are any rods.

slow control rods, TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 16 of 17 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: CREW: Perform the actions directed from AOP 901, Earthquake Earthquake SIMULATOR OPERATOR Click KEYPAD Key 2 CRS (5.22)

After the CRD This will insert Malfunction ZZ03 for DBE,

Direct Crew Response to an Earthquake Condition accumulator, this malfunction will delete after 6 minutes

IF the amber DESIGN BASIS EARTHQUAKE, or amber OPERATING and at the direction of the BASIS EARTHQUAKE lights are ON, and not a malfunction, THEN Lead Evaluator: commence shutting down the reactor to be in cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Enter EOP 2 T/L on High/Low Torus Water Level (may be administratively exited)

Direct Health Physics to perform radiation surveys of the normally accessible areas inside DAEC Buildings, and the site grounds including the Independent Spent Fuel Storage Installation.

Direct chemist to review KAMAN data and perform sensor checks.

Direct control room operators monitor the control room panels for changes in some of the following critical plant parameters:

Spent fuel pool and skimmer surge tank levels

SBLC tank levels

SJAE and offgas flow changes When Simulator Operator:

Changes in jockey fire pump cycling contacted as Acknowledge the request

Core Spray and RHR system pressure any dept. in organization:

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 17 of 18 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: BOOTH COMMUNICATOR CREW: Enter and carry out the actions of AOP 901, Earthquake.

Earthquake Acknowledge the request.

ATC: (94.22)

If contacted as Duty Station

Monitor reactor power, pressure, and level on 1C05 Manager:

Monitor for any Control Rod out of position BOOTH COMMUNICATOR BOP:

At 1C06, verify River Water Supply system integrity by:

Acknowledge the request.

If contacted as

Verify all available RWS pumps will start and deliver >6000 gpm flow HP or

Using HS 4918, RIVER WATER SUPPLY LOOP SELECT switch, Chemistry: select A CV4915 and B CV4914, one at a time, to verify RWS BOOTH COMMUNICATOR makeup flow can be established with each loop ensuring RWS If contacted as Acknowledge the request to perform piping is intact an NSPEO: inside and outside plant walkdowns.

Monitor Process and Area Radiation Monitoring System channels on Keep track of which operator has been Panels 1C10 and 1C11 sent to what location in the plant.

Send operators, with portable radiation monitors, to perform a quick walk through of the plant to determine the general condition of the plant structure and system's integrity, and immediately report back any damage to the Control Room

Realign HPCI suction source to the CST per OI 152, Section 8.3:

Swap HPCI Suction lineup by placing the following valves on 1C03 BOOTH COMMUNICATOR in the indicated positions:

MO-2321, INBD Torus Suction ISOL to CLOSE There is no damage in the areas that

MO-2322, OUTBD Torus Suction ISOL to CLOSE you have walked down

MO-2300, CST Suction to OPEN Wait 15 min.

and report, TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 18 of 19 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5: Loss BOP EVALUTOR NOTE CREW: Determine that there is a loss of the Main H2 Seal Oil Pump and of Main H2 Seal take actions per ARP 1C08C (D-6)

This is a BOP action, ensure that the BOP Oil Pump Operator is nearby before inserting this event CRS At the direct of

Direct the start of the Emergency H2 Seal Oil Pump the Lead Evaluator: SIMULATOR OPERATOR BOP:

Click KEYPAD Key 3

Start the Emergency H2 Seal Oil Pump per the ARP This will run a schedule file for the H2 Seal

Secure the H2 Seal Oil Vacuum Pump per the ARP Oil Pump Trip

Send an operator to the H2 Seal Oil Skid to investigate If sent to the H2 Seal Oil Skid: BOOTH COMMUNICATOR Acknowledge the request and WAIT 3 minutes and REPORT, The Main H2 Seal Oil Pump has a sheared shaft.

If asked for the Acknowledge the request and REPORT, status of the The ESOP is running sat Emergency Seal If the ESOP has not been started, Oil Pump: REPORT it is ready for start If sent to breaker 1B33-01, Acknowledge the request, and WAIT 3 Hydrogen Seal minutes and REPORT, the breaker is in Oil Pump: the trip free position.

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 19 of 20 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6: Hi CREW: Respond to ARP 1C04B (B-1), ARP 1C04B (A-1), and AOP 264 vibrations and Trip of B SIMULATOR OPERATOR CRS Recirc MG at the direction of Click KEYPAD Key 4

Direct the actions for Hi Vibrations on B RR Pump the Lead This will run a schedule file for the high

Notify System Engineering of Hi vibration condition Evaluator: vibrations on the B Recirc Pump BOP:

When BOOTH COMMUNICATOR

Dispatch operator to 1C466C to investigate Hi Vibrations contacted to Acknowledge request and WAIT 2

At 1C21 Check Recirc Pump temperature recorder TRS 4600 for investigate B minutes and REPORT, All channels increasing B Recirc Pump bearing temperatures Reactor Recirc are reading 15 mils and stable. The

Send an Operator to 1C113B in the MG Set Room to monitor relays Pump Hi GREEN OK lights are lit. The vibration Vibrations probe gap is reading -7.2 EVALUTOR NOTE:

When the BOP goes to the back panel area to check 1C21, direct the SIMULATOR OPERATOR Click KEYPAD Key 5 This will trip the B Recirc Pump TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 20 of 21 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6: Trip CREW: Perform the actions of AOP 264, Loss of Recirc Pump (s) of Recirc continued CRS: (5.58)

Direct the actions of AOP 264 Loss of Recirc Pump (s)

Comply with Technical Specification 3.4.1 Condition D, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy the conditions of the LCO.

o May direct STP 3.4.1-02 Single Loop Operation.

If contacted as o May STP 3.4.2-03 Daily Jet Pump Operability Single Loop organization: Operation.

BOOTH COMMUNICATOR

Direct lowering reactor power by inserting control rods using the control Acknowledge the request rod sequence sheets to lower power less than or equal to () 60.0%

(1147 MWth)

Contact organization for assistance When contacted to ATC: (94.58) investigate B Acknowledge request and WAIT 2 RR pump trip: minutes and REPORT, That a B

Stabilize reactor water level between 186 and 195 Recirc MG Generator Lockout has

For the Recirc Pump that tripped, perform the following:

occurred and the B GENERATOR

Verify open B RECIRC PUMP DISCH BYP valve MO-4630 FIELD BREAKER is OPEN.

Close B RECIRC PUMP DISCHARGE valve MO-4628 If asked to

Plot operating point on Power/Flow map investigate 1A2:

For the Recirc Pump that tripped, after 5 minutes, reopen B RECIRC Acknowledge request and WAIT 2 PUMP DISCHARGE valve MO-4628 minutes and REPORT, The B RECIRC

Insert control rods as directed by the CRS to maintain power less than or MG SET MOTOR BREAKER 1A204 is equal to () 60.0% (1147 MWth)

If asked to OPEN investigate MG Acknowledge request and WAIT 2 Set fans: minutes and REPORT, 1VSF11 A BOP:

MGSET Handswitch is in AUTO.

Direct Operator to investigate the trip of the B recirc pump EVALUATOR NOTE: The conductivity event should be directed toward the end of this event (i.e. after MO-4628 is opened, or after power reduction < 60%). Due to the leak size, it will take approximately 2-3 minutes before the control room annunciator is received.

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 21 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6: Trip CREW: Perform the actions of AOP 255.2, Power/Reactivity Abnormal of Recirc Change continued ATC (94.03)

Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to:

o Assuming manual control of a malfunctioning system o Inserting control rods per the current rod pull sheet

Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal

Verify proper operation/indication of systems and/or indications

Verify control rod positions are correct for the established sequence, by using Rod Position Log EVALUATOR NOTE:

Verify thermal limits on the Official 3D Case Total core flow is to be determined by

When power is stabilized, plot location on the Stability Power / Flow Map assessing Core Plate D/P

In the event of inadvertent entry into area above the power to flow map exit this area by inserting control rods CRS (5.03)

Direct the actions of AOP 255.2, Power/Reactivity Abnormal Change

Establish critical parameter monitoring of Reactor Power, Reactor Pressure, and RPV Water Level, as priorities allow TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 22 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7: CREW: Respond to annunciator 1C06B (A-1) and AOP 639 Condenser Tube Leak At SIMULATOR OPERATOR BOP (94.18) the direction of the Lead Click KEYPAD Key 6

Send an Operator to 1C80 to investigate Evaluator, This will start a schedule file for condenser

Based on the report, the crew will enter AOP 639, Reactor tube leak which will drive a reactor scram Water/Condensate High Conductivity.

Verify that when 1C06B A-1, 1C-80 TROUBLE alarms, that ET 5 goes TRUE CRS: (5.18)

Direct entry in AOP 639, Reactor Water/Condensate High Conductivity BOOTH COMMUNCIATOR

IF a valid Condensate Demineralizer Influent Conductivity reading of Acknowledge the request and WAIT 3 greater than or equal to 1.0 mho/cm (CRS-1514 Pt 1 or 7 at 1C06 or CIT When called on 1704 at 1C80) is received and is not due to condensate system startup minutes and REPORT, Report that the to investigate or plant startup, THEN Reduce Reactor Recirc flow to 39 Mlbm/hr per alarm was the Influent High the alarm on IPOI 4, Fast Power Reduction AND SCRAM conductivity alarm, and it is currently 1C80, reading _____

On the PPC monitor, call up GD 24, this will give you the condensate filter demineralizer panel. When you relay your report, give them the reading of the Condensate influent conductivity.

EVALUATOR NOTE:

The only action of annunciator on 1C80 at power operation is to enter AOP 639, Reactor Water/Condensate High Conductivity TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 23 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7: CREW: Take actions directed by AOP 639 Condenser Tube Leak BOP:

BOOTH COMMUNCIATOR

Observe chart recorder CRS-2738 CLEANUP INFLUENT When called as Acknowledge the request and state that CONDUCTIVITY at 1C04 to determine the trend of reactor coolant chemistry, it will take about an hour and a half to conductivity get the sample.

Direct Plant Chemistry Department to sample as necessary, reactor water condensate, Hotwell, CSTs and makeup demin system to verify When any high conductivity levels identified in Steps 1 and 3 Acknowledge the request and inform contacted as

IF a suspected loop has been identified, and it is recommended that the the control room that you will review the system loop be isolated, THEN Isolate the suspected leaking Condenser Circ the information from PI and get back to engineer, Water loop per OI 442 them with a recommendation

IF condensate demineralizer influent conductivity is greater than 0.1 mho/cm, THEN maintain the filter demineralizer bypass valve MO-1708 closed If asked to Acknowledge the request

IF a valid Condensate Demineralizer Influent Conductivity reading of monitor Call up the conductivity monitor 1514 on greater than or equal to 1.0 mho/cm (CRS-1514 Pt 1 or 7 at 1C06 or CIT conductivity at THUNDERVIEW from panel 1C06, and 1704 at 1C80) is received and is not due to condensate system startup other places in monitor point CE1516A. or plant startup, THEN Reduce Reactor Recirc flow to 39 Mlbm/hr per the plant, IPOI 4, Fast Power Reduction AND SCRAM TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 24 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: CREW: AOP 639 action to insert a manual reactor scram ATWS ATC:

Inserts manual scram o Reports that there is a Hydraulic ATWS o Reports Reactor Power

Performs ATWS QRC o Reports that the ATWS QRC is complete, with the exception of SBL Control o Reports reactor power CRS: (6.56)

Enters EOP 1 and transitions to ATWS

Per ATWS directs the following; o Lockout ADS prior to ADS actuation (Critical) o Install Defeat 15 o Install Defeat 11 o Directs the ATWS QRC BOP: (95.57)

Lockout ADS prior to ADS actuation (Critical)

Install Defeat 15

Install Defeat 11 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 25 of 26 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: CREW: Take the actions directed from ATWS ATWS CRS:

Directs the initiation of SBLC If directed to BOOTH COMMUNCIATOR

Directs the Hydraulic ATWS RIPS (Critical) (6.08, 6.06) install Defeat Acknowledge the request AND direct 12, the Simulator Operator to ATC:

Click KEYPAD Key 7

Initiates SBLC This will run a schedule file to place the

Performs the ATWS RIPS until the reactor is shutdown under all conditions ATWS RPT switches in the TEST position (Critical) (95.06, 95.08) after a time delay o RIP 103,2, Increase CRD Cooling Flow and Pressure Start second CRD Place CRD Flow Controller FC-1814 in MANUAL and run the output to maximum Observe increased cooling water flow on FI-1838 and cooling water BOOTH COMMUNCIATOR dP increase on PDI-1832A When Defeat Throttle open MO-1830, DRIVE WATER P CONTROL, as 12 is installed: Call the control room and inform them necessary to maximize cooling water flow and pressure that you have installed Defeat 12 o RIP 102,1, Repeated Manual Scram Install DEFEAT 3 (RPS Scram Logic Defeat)

Direct the in-plant operator to install DEFEAT 12 (Reset of ARI)

Reset the reactor scram Confirm SDV high level trip is clear Determine control rod position Re-Scram the plant TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 26 of 27 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: CREW: Take the actions directed from ATWS (lower reactor water level to 87 ATWS inches)

EVALUATOR NOTE CRS:

IF the crew has not taken action to lower

Assess reactor power reactor water level to 87 inches AND large o If reactor power is > 5%, the crew will enter power level control irregular neutron flux oscillations induced by Directs to secure and prevent injection from, Condensate and Feed, neutronic/thermal-hydraulic instabilities is HPCI, RHR, and CS observed (APRMs), THEN the Critical Task Inform at an RPV level of 87 inches has been failed If conditions allow RPV injection, maintain RPV level > -25 inches ATC:

Secure and prevent injection from Condensate and Feed EVALUATOR NOTE

Take manual control of the Master Level Controller and close the feed IF the crew has not taken action to restore regulating valves (Critical) and/or maintain reactor water level > -25

Inform the CRS reactor power when level reaches 87 inches inches using the preferred injection

If directed, maintain RPV level > -25 inches (Critical) systems AND the crew transitions to Emergency Depressurization, THEN the BOP:

Critical Task has been failed

Secure and prevent injection from HPCI, RHR, and CS

Place the HPCI Aux Oil Pump to Pull-to-Lock

Trip the A and B CS Pumps if they receive an initiation signal (Critical)

Prevent injection from RHR as necessary by overriding the selected loop inject valve (Critical)

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 27 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: CREW: Determines that all control rods are inserted ATWS to EOP 1 CRS:

Exits ATWS and returns to EOP 1

Directs the following; o RPV level be maintained 170 to 211 using High Pressure injection systems o Control RPV pressure 800 to 1050 psig using EHC ATC:

Assess the Feedwater system for conductivity, and maintains RPV level using; o RCIC o If necessary uses Condensate and Feed

Controls RPV pressure using EHC TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 28 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 9: CREW: Determines that Torus Level is lowering, and perform the following EOP 2 and 3 for actions lowering Torus level SRO (6.65)

Direct the following actions from EOP 2 BOOTH COMMUNCIATOR o Obtain a round of Primary Containment Parameters When directed Determine that Torus level is lowering to the Torus Acknowledge the request and WAIT 4

Direct that torus level be raised by:

area to minutes and REPORT, There is a lot of o HPCI, OI 152 determine water flowing out of a cracked pipe o Core Spray, OI 151 where the leak right at the torus. The cracked pipe is

(Critical) Before 7.1 feet is, the A CS suction line.

o Perform an Emergency Depressurization

Direct the following actions from EOP 3 o Operate available sump pumps to restore and maintain water level below the Max Normal Operating Limit o Operate available coolers in the affected area BOP:

Deliver a round of Primary Containment Parameters

Report that Torus level is lower than expected for this condition o Attempt to raise torus water level:

With HPCI IAW OI 152 With Core Spray IAW OI 151

Responds to Annunciator 1C14, B-4, Area Water Levels Above Max Safe

Reports to the CRS that the Torus Room is above the Max Normal If contacted as Operating Limit the Rad Waste Acknowledge the request

Contact the Rad Waste Operator to lineup and pump the Torus area Operator:

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 29 of 30 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 9: CREW: EOP 2 actions continued using Core Spray EOP 2 and BOP:

lowering Torus

Attempt to raise torus water level; level BOOTH COMMUNICATOR o With the CS system When directed Monitor CST level on 1C06 to open the CS Acknowledge the request and WAIT 4 minutes and REPORT, You are at the Verify that the CS outboard and inboard torus suction valves are manual valves, open V-21-01 and 02, directed valve, but you cannot get the lock to work. You have to go and find a Unlock and open V-21-01, for A CS, and V-21-02, for B CS, bolt cutter to get the chain off of the as necessary.

handwheel.

(Critical) When the crew determines that they cannot maintain torus level Acknowledge the request and WAIT 4 above 7.1 feet, and BEFORE 7.1 feet in the torus, the crew will perform an minutes and REPORT, You attempted Emergency Depressurization (Critical)

When directed to open the CS valve, but it was hard to to go to the turn. While you were attempting to other CS, open it, there was a loud cracking CRS: (6.80) sound, and now the valve handwheel o May direct SEP 307 to anticipate ED spins freely.

Directs that ED be entered EVALUATOR NOTE:

Directs the following from ED The CRS may direct SEP 307 to anticipate o Verify torus level is above 4.5 ED, however a spurious GROUP 1 o Open 4 ADS SRVs BEFORE Torus level is below 7.1 (Critical) isolation will occur and will prevent this o Maintain RPV level using CS or RHR mitigation strategy ATC: (95.80)

Verify torus level is above 4.5

Open 4 ADS SRVs BEFORE Torus level is below 7.1 (Critical)

Maintains RPV level using the directed injection system TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 30 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the ED Simulator Operator has been Place the simulator in FREEZE.

performed and RPV level is being restored Announce the scenario is complete; to the directed please stand by your stations and do band, and at not discuss the scenario with your the direction of crew.

the Lead Evaluator,

- - END OF SCENARIO ***

TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 31 of 32 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. CRD Accumulator Alarm

2. Earthquake resulting in

Loss of Main H2 Seal Oil Pump

Hi Vibrations and Trip of B Recirc Pump

Condenser Tube Leak After EOP Entry:

1. ATWS

2. Unisolable Torus Leak Abnormal Events:

1. AOP 901, Earthquake

2. AOP 255.2, Power/Reactivity Abnormal Change

3. AOP 264, Loss of Recirc Pump (s)

4. AOP 639, Reactor Water/Condensate High Conductivity Major Transients:

1. Earthquake

2. Condenser Tube Leak

3. Torus leak resulting in ED Critical Tasks:

1. IF a reactor scram is required and the reactor is NOT shutdown under all conditions, THEN lockout ADS before automatic actuation.

2. IF a scram is required and Reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods:

Injection of Boron

Inserting control rods using RIPs

3. IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection

4. IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems

5. BEFORE torus level drops to 7.1 feet, THEN perform Emergency RPV Depressurization TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 32 of 33 Appendix D Scenario Outline Form ES-D-1 Facility: Duane Arnold Energy Center Scenario No.: ___1_____ Op-Test No.: 19-1 NRC Examiners: Operators:______________________

Initial Conditions/Turnover:

Reactor Power is 75%

Guarded Equipment: Spent Fuel Cooling Pumps, Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room 1B35, 1B43, Fuel Pool Pump Breakers, 1C136, Fuel Pool Panel Evolutions in progress or planned for upcoming shift

Alternate EHC Pumps for maintenance later in the shift

Raise Power with rods IAW the pull sheet to achieve 80% Reactor Power

Later this shift, Security will be running a force on force drill Plant PRA/PSA Status including CDF/LERF & color

Green-CDF 1.34 E-6/ ICDP to Yellow equal 1 year

Green-LERF 3.27 E-7 ILERP to Yellow equal to 1 year 2 Extra Non Licensed Personnel Available in Work Control Event No. Malf. No. Event Event Type* Description 1 N-BOP Shift EHC Pumps N-CRS 2 R-ATC Raise Power With Rods to 80% RTP R-CRS 3 TS- Control Rod 22-07 N2 Leak CRS Tech Spec 3.1.5 Condition A 4 zz03 C-CRS Entry into AOP 901, Earthquake C-BOP Verify river water supply piping integrity 5 eg08a C-BOP H2 Main Seal Oil Pump fails and the crew will have to start eg08c C-CRS the Emergency H2 Seal Pump ARP 1C08C D-6 do-eg-026 do-eg-027 6.a rr35b Respond to B Recirc MG Set high vibrations 6.b rr05b C-CRS B Recirc pump shaft seizure and subsequent pump trip rr06b CRS will direct entry into AOP 255.2 and 264 C-ATC ATC Operator will close tripped recirc pump discharge valve TS-CRS Tech Spec 3.4.1, Condition D TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 33 of 33 7 mc07 M-All Condenser Tube Leak will require the entry into AOP 639, resulting in inserting a manual reactor scram 8 rp05g C-ATC Entry into EOP 1, Transition to EOP ATWS C-CRS Hydraulic ATWS

Potential to enter Power Level Control Rods will insert via:

RIP 103.2, Increase CRD Cooling Flow and Pressure

RIP 102.1, Repeated Manual Scram 9 pc14 C-BOP Leak in the torus results in the performance of ED.

di-ms-076 C-CRS Anticipating ED will not be available due to a spurious di-ms-077 group 1 isolation di-ms-072 di-ms-074 ms19a ms19b TR-AA-230-1007-F13, Revision 0

SIMULATOR EXERCISE GUIDE, SEG THREE COLUMN Page 1 of 31 SITE: DAEC Revision #: 0 LMS ID: PDA OPS 19-1 NRC Scenario #2 LMS Rev. Date:

SEG TITLE: NRC Exam Scenario #2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 90 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 2 of 3 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators ability to:

Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained Objectives:

Prerequisites: NONE Training A. Simulator Resources: B. Evaluation Team C. Operations Management Representative D. Simulator Operator E. Booth Communicator F. Simulator video recording equipment

References:

1. AOP 301, Rev 73

2. AOP 411, Rev 29

3. AOP 903, Rev 59

4. AOP 358, Rev 32

5. ARP 1C03A, Rev 62

6. ARP 1C05A, Rev 90

7. ARP 1C06A, Rev 75

8. ARP 1C06B, Rev 65

9. ATWS, Rev 23

10. ED, Rev 11

11. EOP 1, Rev 20

12. EOP 3. Rev 22

13. IPOI 3, Rev 160

14. IPOI 5 QRC 1, Rev 6

15. SEP 307, Rev 4

16. OI 734 QRC 1, Rev 0

17. Technical Specifications Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: In accordance with NUREG 1021 TR-AA-230-1007-F13 , Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 3 of 4 Operating None Experience:

Risk Significant Initiate RPV Emergency Depressurization Operator Actions:

UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See cover Changed form number to match new industry SAT procedure 0.0 which superseded TR-AA-230-1003. See cover TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 4 of 5 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.16 Respond to GSW Abnormal Operation Condition 94.36 Respond to a Loss of 1A4 Perform Actions of EOP 3 for High Area Temperature, Radiation, and Water Level including 95.68 EOP 1 and ED 95.46 Perform actions of RC/P of EOP 1 95.47 Establish a Cooldown of the RPV at a Rate of <100 Degrees F/hr 95.55 Perform initial ATWS actions (/)

95.95 Initiate ATWS/ARI 1.02 Determine Operability for Technical Specification Required Components 5.16 Direct Crew Response to GSW Abnormal Operation Condition 5.24 Direct Crew Response to High Winds / Severe Thunderstorms / Tornado Condition 5.36 Direct Crew Response to a Loss of 1A4 Direct Crew Response for performance of EOP 3 for high area temperatures/radiation /water 6.67 level including EOP 1and ED 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.47 Direct Crew Response to Establish a Cooldown of the RPV at a Rate of <100 Degrees F/hr 6.55 Direct Crew Response to Perform Initial ATWS Actions (/)

TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 5 of 6 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW See below event description for overview SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description

1. Shift Stator Water Cooling Pumps in accordance with OI 697 Generator Stator Cooling Water System section 7.0

2. Reduce Rx Power with Control Rods using the Control Rod Sequence Sheets to approximately 95% RTP

3. After the completion of the power adjustment, the A Core Spray pump supply breaker will fail and close in. The pump will operate for 5 seconds and then the breaker will mechanically fail. The CRS will declare the A Core Spray Pump inoperable and enter TS 3.5.1 Condition B to Restore to operable within 7 days.

4. After the Core Spray pump is declared inoperable, a leak on 1T-218 develops and causes 1C05A E-3, SBLC Tank HI/LO Level alarm to come in.

The crew will direct an In-plant Operator to investigate. The leak is reported to be from 1T-218, at the combined suction line. The leak will be stopped when V-26-1 is CLOSED.

The CRS will declare SBLC Inoperable TS 3.1.7 Condition B (8 Hour LCO)

5. The Crew will receive a call from Security informing them that the National Weather Service has just issued a Severe Thunderstorm Warning for the DAEC vicinity. The warning will be in effect for the next hour.

The crew will enter AOP 903 Severe Weather and take the appropriate actions.

6. After the initial actions of AOP 903 are complete, a lightning strike will occur in the DAEC area and will result in the trip of the B GSW pump, the standby pump will not automatically start. The Crew will manually start the standby GSW pump.

This start will send a slug of mud through the GSW system. The Crew will perform the actions of ARP 1C06A B-4, GSW Auto Filter High Dp.

The Crew will also enter AOP 411 GSW Abnormal Operation

7. During the monitoring of GSW cooled components another lightning strike will occur and result in the trip of the C RBCCW pump, the Crew will receive a RBCCW low pressure alarm on 1C06B, (D-3). The Crew will determine that the standby RBCCW pump did not automatically start and start the standby RBCCW pump.

8. From the lowering of reactor power a leak will develop in the RWCU HX room.

The leak will propagate to the point where the RWCU system will try to isolate due to a high temperature in the RWCU Hx room.

TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 6 of 7 The leak will not be able to be isolated and the crew will have to insert a manual reactor scram prior to the RWCU Hx room reaching a Max Safe Temperature limit. (Critical)

9. On the reactor scram, there will be an electrical ATWS. ARI will be successful to insert all of the control rods except 1.

The crew will determine that they are no longer in ATWS and return to EOP 1.

10. With a primary system leaking into the secondary containment, the crew will rapidly cool down to a pressure band of 500 to 700 psig to take the driving head off of the leak.

11. After all but one of the control rods have inserted, 1A4 will lockout when the Turbine TRIPS.

The crew will enter AOP 301, Loss of Essential Electrical Power, and take the B SBDG to Pull-to-Lock due to running without ESW cooling flow.

12. When the area above the TIP room exceeds a Max Safe Temperature Limit, the crew will perform an Emergency Depressurization due to Two Areas above Max Safe Operating Limit. (Critical)

13. During the ED, only 2 ADS SRVs will open requiring the operator to open the 2 LLS SRVs to complete.

TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 7 of 8 SIMULATOR SET UP INSTRUCTIONS

1. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist ____

2. Using the exam flash drive with the scenario simulator files, insert in the left instructor station computer and navigate to the D:\ directory ____

3. Copy the NRCScenario2.dat file from the exam flash drive to C:\Trex_Duane-TELEC\Executive\SiteSpecific\InitialCondition and rename the file to an available IC using the format ic_### ____

a. Reset to the newly created IC ____ ____

b. Place the Simulator in RUN ____

c. Run schedule file Weather.sch following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles ____

OR Reset to IC 20, place the simulator in RUN and perform the following (this will take approximately 15 minutes for the plant to stabilize):

a. Insert Event Triggers, Malfunctions, Overrides, and Remotes using schedule ____

file SEG_Setup.sch located on the exam flash drive using the following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles

4. Have a second instructor verify:

b. Auto triggers are setup as indicated below and evaluate to FALSE ____

c. Malfunctions ____

d. Remotes ____

e. Overrides ____

5. Open Keypad file NRC_Scenario_2.key located on the exam flash drive using the following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles ____

6. Setup Thundersound on the Instructor Station computer to the right and verify the following settings:

a. Click on the checkbox under Playing for THUNDERSTORM ____

b. Click the STOP button to toggle audio model to playing ____

c. Verify Instructor Station sound volume is set to approximately 25% ____

d. Verify the dB controller (under the Instructor Station monitor) level 2 know is aligned to the detent (white line on the knob is pointing slightly counterclockwise) ____

e. Verify the Front Room (both) sub amplifiers are set to approximately 50% of scale ____

7. Place Guarded Equipment tags on: ____

1B35 Switch

1B43 Switch

8. Markup MOL pull sheet STEP 37 for control rods withdrawn to their current position ____

9. Ensure MOL pull sheets are in the 1C05B hanging file ____

TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 8 of 9 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 20 tc_trip Main Turbine Trip 21 rrltaf < 170 GP 3 Signal MALFUNCTIONS Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value 4.16 KV/480V BUS FAULT- BUS Set up ed08d 20 INACTIVE ACTIVE 1A4 RPS SCRAM CIRCUIT FAILURE Set up rp05a (ATWS)- AUTO SCRAM ACTIVE ACTIVE FAILURE RPS SCRAM CIRCUIT FAILURE Set up rp05b (ATWS)- MANUAL SCRAM ACTIVE ACTIVE FAILURE RPS SCRAM CIRCUIT FAILURE Set up rp05d (ATWS)- RPS FUSE REMOVAL ACTIVE ACTIVE FAILURE Set up ALL INDIVIDUAL ROD SCRAM rp05e ACTIVE ACTIVE SWITCHES FAIL CONTROL ROD BLADE Set up rd020227 ACTIVE ACTIVE STUCK- ROD 02-27 RE-7606B REAC BLDG MAIN As dir rm02re7606b 21 As Is 100 EXHAUST B OVERRIDES Time OR No. Override Title Delay Ramp ET Initial Final Value Value BPVJINCR BYPASS VALVE TRANSI TRANSI/

Set up DI-TC-009 OPENING JACK, INCREASE /OFF OFF Set up DI-AD-017 HS-4405 ADS PSV4405 AUTO AUTO Set up DI-AD-019 HS-4406 ADS PSV4406 AUTO AUTO REMOTE FUNCTIONS Time RF. No. Remote Function Title Delay Ramp ET Initial Final Value Value TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 9 of 10 KEYPAD FILE:

NRC_Scenario_2.key Key Key Action 1 Insert remote an07 to ACK Schedule 2 D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles\

ACS_BkrFailure.sch 3 Toggle Event 1 Schedule 4 D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles\

SBLCTankLeak.sch 5 Toggle Event 2 Schedule 6 D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles\

LightningStrikeOne.sch Schedule 7 D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles\

LightningStrikeTwo.sch Schedule 8 D:\NRCOperational\NRCScenarios\NRC_Scenario_2\NRCScenario2_SimFiles\

EOP3Scram_ED.sch 9 Toggle Event 3 SCHEDULE FILES:

Weather.sch At Time Event Action Description 00:00:01 None Insert remote hv01 to 223 in 7200 WIND DIRECTION AT 50 meters (165 ft)

Insert remote hv02 from 23 to 27 00:00:01 None WIND SPEED AT 50 meters (165 ft) in 7200 00:00:01 None Insert remote hv03 to 45 in 28800 DEW POINT TEMPERATURE AMBIENT TEMPERATURE AT 50 meters 00:00:01 None Insert remote hv05 to 68 in 14400 (165 ft)

AMBIENT TEMPERATURE AT 10 meters (35 00:00:01 None Insert remote hv06 to 73 in 14400 ft) 00:00:01 None Insert remote hv07 to 73 in 28800 RIVER WATER TEMPERATURE TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 10 of 11 ACS_BkrFailure.sch At Time Event Action Description MANUAL OPER OF 'A' CS PUMP (1P-211A 00:00:00 None Insert remote cs03 to CLOSE BREAKER)

CORE SPRAY PUMP TRIP- CORE SPRAY 00:00:05 None Insert malfunction cs01a PUMP A TRIP create event 19 zaocspi2106 <=

None 1 0.195 -desc Close A CS Vent Valve MANUAL CORE SPRAY A VENT VALVE None 1 Insert remote cs05 to OPEN (CLOSE,OPEN)

None 19 Modify remote cs05 to CLOSE SBLCTankLeak.sch At Time Event Action Description Insert malfunction sl07 to 00:00:00 None SBLC TANK 1T218 LEAK 100.00000 in 120 Modify malfunction sl07 to None 2 0.00000 in 10 LightningStrikeOne.sch At Time Event Action Description create event 10 zdiswhs4904a(4) -

00:00:00 None desc A GSW Pump started GSW PUMP 1P89A FAIL TO AUTO-00:00:00 None Insert malfunction SW37A ACTUATE Insert malfunction zz04 to 00:00:01 None Thunderstorm Event 100.00000 delete in 4 MAN OPER OF 'B' GSW PUMP (1P-89B 00:00:02 None Insert remote SW32 BREAKER)

Insert malfunction AN1C06A(17)

None 10 1C06A (B-04) GSW AUTO FILTER HI dP after 10 to ON delete in 120 create event 10 zdiswhs4904a(4) -

00:00:00 None desc A GSW Pump started TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 11 of 12 LightningStrikeTwo.sch At Time Event Action Description RBCCW PUMP 1P81A FAIL TO AUTO-00:00:00 None Insert malfunction stsw01a START Insert malfunction zz04 to 00:00:01 None Thunderstorm Event 100.00000 delete in 4 00:00:02 None Insert malfunction sw10c RBCCW PUMP TRIP- PUMP C Insert malfunction AN1C06B(33) 1C06B (D-03) RBCCW PUMP DISCH 00:00:15 None to ON HEADER LO PRESSURE create event 11 ZAOSWPI4821 00:00:15 None >= 0.32 -desc RBCCW Pressure Recovers 1C06B (D-03) RBCCW PUMP DISCH None 11 Delete malfunction AN1C06B(33)

HEADER LO PRESSURE EOP3Scram_ED.sch At Time Event Action Description Create event 22 rrprv < 400 -desc 00:00:00 None RPV Press less than 400 psig Create event 23 ZDICUHS2701(1) 00:00:00 None

-desc MO2701 HS to Close Create event 25 ZDIHVHS7611A 00:00:00 None & ZDIHVHS7611B -desc RX Exhaust Fans Running MO2700 THERMAL OVERLOAD BREAKER 00:00:01 None Insert malfunction cu11a TRIP GROUP 5 ISOLATION VALVE(S) FAIL(S) TO 00:00:01 None Insert malfunction ms28b CLOSE- MO2701 Insert malfunction cu07 to 0.5 in RWCU LEAK IN HEAT EXCHANGER ROOM 00:00:03 None 600 (VI)

Insert malfunction cu05 to TEMPERATURE TRANSMITTERS None 3 80.00000 in 300 2742G,J,H,K FAILURE Modify malfunction cu05 to None 22 43.00000 in 300 None 23 Insert malfunction ed22d BREAKER TRIP 1D4204 FOR MO2701 TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 12 of 13 SHIFT TURNOVER INFORMATION

Day of week and shift o Today, day shift

Weather conditions o Cloudy, with a chance for thunderstorms during the shift

Plant power:

o 100% reactor power with the corresponding MWe, MWth, and core flow

Reactor coolant leakage is normal (if asked: 1.56 identified, 0.03 unidentified)

Plant PRA Status o CDF: 1.32 x 10-6, GREEN, 1 year to Yellow o LERF 3.32 x 10-7, GREEN, 1 year to Yellow o SFP risk is LOW, time to 200°F is 56 Hours

B side protected, specifically guarded equipment is o Skimmer Surge Tank Room o 1B3507, A Fuel Pool Cooling Pump Breaker o 1B4327, B Fuel Pool Cooling Pump Breaker o 1C136, Fuel Pool Filter/Demin Control Panel

No Locked in / failed annunciators or alarms

No Existing LCO action statements

Procedures or major maintenance in progress o Shift Stator Water Cooling Pumps in accordance with OI 697 Generator Stator Water Cooling System o Lower Reactor power with control rods to achieve 95% for Load Line Adjustment by inserting control rods in the reverse sequence of the rod movement control sheet package. REs will deliver the adjustment sheet positions to the control room upon completion of the insertions

No equipment to be taken out of service or returned to service this shift

Comments, problems, operator workarounds, etc.

o The Radwaste Operator is NSPEO qualified o Two extra NSPEOs available in Work Control o Operations Management as agreed that the CRS will serve as the Reactivity SRO TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 13 of 14 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1: CREW: Shift Stator Water Cooling Pumps in accordance with OI 697 Shift Stator Stator Water Pumps CRS BOOTH COMMUNCIATOR When the

Direct RO to Swap Stator Water Cooling pumps in accordance with Report: V-45-13 B Stator Water OI 697 Generator Stator Cooling Water system crew assumes Cooling Pump suction isolation the watch, valve is OPEN BOP:

Verify B Stator Cooling Pump 1P91B suction valve V-45-13 is When OPEN contacted as in plant

Start B Stator Cooling Pump 1P91B by momentarily placing its operator to Handswitch to RUN on 1C08.

verify Stator

Annunciator 1C08C D-4 H2/Stator Cooling panel Trouble alarms Cooling Pump BOOTH COMMUNCIATOR due to reserve pump running suction valve

Verify both pumps are running Report: B Stator water cooling is OPEN

Stop the A Stator Cooling Pump 1P91A by placing switch to pump is operating normally.

STOP position momentarily Acknowledging the 1C83 alarms.

1C08C D-4 H2/Stator Cooling panel Trouble should clear If asked to report status SIMULATOR OPERATOR of Stator Click KEYPAD Key 1 Water Cooling pump This will acknowledge the alarms at 1C83 TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 14 of 15 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2: CREW: Lower reactor power using the Control Rod Sequence Sheets Insert Control to the specified reactor power level Rods to reduce power CRS:

ATC EVALUTOR NOTE:

This will require the ATC Operator to

Provide Control Rod Refocus Brief per IPOI 3 The Crew will insert control rods to position 18.

Direct control rod insertion to a target power of 95% reactor power reduce reactor power with ATC:

ATC EVALUATOR NOTE:

rods to Repeat as necessary to establish the target power directed:

achieve 95% The ATC Operator will insert the following control rods for RWM Step 37:

Select the desired control rod using the rod select matrix

30-19

Using control rod movement switch insert the control rods as

30-27 directed to establish the desired reactor power

14-27

Monitor core parameters as power is changed, such as:

14-19 o Recirc flow The ATC Operator may plot on the Power o Reactor jet pump total core flow to Flow map and/or print a ACUMEN o Total steam flow Report after inserting control rods per the o Total feed flow control rod sequence sheets o Reactor water level o Reactor pressure o APRM power BOP:

Provide peer checks are requested

Monitor plant parameters as power is changed, such as:

o Generator output TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 15 of 16 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3: CREW: Respond to annunciator 1C03A, A-9, A Core Spray Pump Core Spray 1P211A Trip or Motor Overload Pump Start and TRIP BOP:

At the

Determine that Drywell pressure is not > 2 psig direction of the SIMULATOR OPERATOR

Determine that RPV level is not < 64 Lead Click KEYPAD Key 2

Determine that the CS pump should not have initiated Evaluator, This will run a schedule file for the

May go to 1C43 to investigate the status of the Core Spray failure of A Core Spray Initiation relays

Inform the CRS CRS will (1.02)

Enter TS 3.5.1, Condition B to restore to Operable within 7 days.

BOP:

Will determine the Core Spray Pump has TRIPPED.

If contacted as the in plant BOOTH COMMUNCIATOR operator to ACKNOWLEDGE the request, and investigate WAIT 3 minutes and REPORT, The 1A3 A Core Spray breaker is heavily switchgear damaged with some breaker parts room report on the floor in front of the cubical.

There is no fire or smoke, just an acrid smell.

EVALUATOR NOTE: The next event will take approximately 2-3 minutes before a control room annunciator is received.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 16 of 17 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3: CREW: Respond to 1C03A annunciators Core Spray Pump Start and TRIP BOOTH COMMUNCIATOR If called as the BOP ACKNOWLEDGE the request and Second o May vent Core Spray per OI 151 Core Spray System WAIT 5 minutes and REPORT, You Assistant to o Coordinate with the in-plant Operator to vent the Core Spray are standing by the CS vent valve, vent the CS system per Section 8.1 you have you venting rig attached, system, and are ready to vent the A CS system.

When directed SIMULATOR OPERATOR to vent the CS Click KEYPAD Key 3 system, This will automatically cycle the A Core Spray discharge vent valve to lower the discharge pressure to clear the annunciator EVALUATOR NOTE: The next event will take approximately 2-3 minutes before a control room annunciator is received.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 17 of 18 EVENT 4: CREW: Respond to annunciator 1C05A, (E-3) SBLC Tank HI/LO Level SBLC Leak ATC:

At the direction SIMULATOR OPERATOR

Determine that SBLC Tank Level is lowering of the Lead Click KEYPAD Key 4

Report to the CRS Tank Level and Trend Evaluator,

Direct an In-plant Operator to investigate the SBLC skid This will cause a leak from 1T218 to be developed. SBLC Storage tank level will lower until the Low Level alarm comes in. CRS:

Direct V-26-01 to be closed when location of the leak is known If directed to

Determine both SBLC subsystems are INOPERABLE investigate the BOOTH COMMUNCIATOR

Enter LCO 3.1.7 Condition B restore 1 subsystem to OPERABLE within SBLC leak wait 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ACKNOWLEDGE the request and WAIT 3 minutes and 3 minutes and REPORT, The leak is report the downstream of V-26-01 SBLC Storage following Tank 1T218 Outlet Isolation and is isolatable.

If directed to CLOSE V ACKNOWLEDGE the request and WAIT 01 1 minute and REPORT, V-26-01 is directed SBLC Storage Tank 1T218 Outlet Isolation has been closed SIMULATOR OPERATOR Click KEYPAD Key 5 This will modify the malfunction to 0% and stop the leak.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 18 of 19 EVENT 5 CREW: Take the actions directed by AOP 903, for severe thunderstorm Lightning Strike warning BOOTH COMMUNCIATOR At the direction Call the Control Room Supervisor as of the Lead the Security Lieutenant and REPORT, Evaluator, The National Weather Service has issued a severe thunderstorm warning CRS:

for the DAEC area for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Enter and direct the actions of AOP 903, for severe thunderstorm warning ACKNOWLEDGE the report:

Contact ITC to check status of grid stability

For ITC, report that the grid

Contact the Real Time Desk and inform them of any known If contacted as models show that the grid is disturbances or plant malfunctions ITC and/or the stable Real Time

For the Real Time Desk, Desk, acknowledge the information provided BOP:

Verify the outside speakers are on

Make the site-wide announcement

Turn outside speakers off If contacted as ACKNOWLEDGE the REPORT.

Contact security to inform their personnel Security,

Monitor wind speed using AOP903 EVALUATOR NOTE: The next event is a lightning strike which trips the B GSW pump. This event was created for the BOP Operator to correct the abnormal condition of the GSW system.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 19 of 20 EVENT 5.a. Crew: Respond to Annunciator 1C06A, B-3 Lightning Strike SIMULATOR OPERATOR Click KEYPAD Key 6 BOP:

At the direction This will run a schedule file and cause a of the Lead lightning Strike and the trip the B GSW

At 1C06, confirm General Service Water Pumps Discharge Header Evaluator, Pump Press low on PI-4903 GSW PUMPS DISCH HDR PRESS o Verify auto start of the standby pump.

o Determine that the A GSW pump did not automatically start.

BOOTH COMMUNICATOR

Start the A GSW pump Call the CRS and REPORT as the CAS When the B Operator that, A lightning bolt just hit

Shortly after the start of the A GSW pump, the crew will respond to GSW pump has in the yard near warehouse. annunciator 1C06A B-4, GSW AUTO FILTER HIGH P tripped,

Send and operator to the GSW strainer 1S-24 to verify high differential pressure on PDIS-4906

Inform the CRS that AOP 411 is referenced in the ARP When Acknowledge the request and WAIT 2 contacted to minutes and REPORT, There is a CRS investigate B ground fault flag (Relay 409-150G) on GSW Breaker

Direct actions of ARP 1C06A B-3, B-4, C-4, and AOP 411 (Loss of breaker 1A409.

1A409, GSW). (5.16)

Acknowledge the request and WAIT 4 If sent to minutes and REPORT, The B GSW investigate the motor is warm to the touch but nothing auto strainer or else is abnormal. The GSW strainer, 1S-the B GSW 24, is turning, PDIS-4906 is reading 5 Pump, psid and lowering.

If sent to adjust Acknowledge the request.

Turbine Lube Oil temperature, SIMULATOR OPERATOR Adjust Remote Function SW 14 to lower Turbine Lube Oil temperature TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 20 of 21 EVENT 5.a. CREW: Perform actions per AOP 411 Lightning Strike BOP: (94.16)

IF there is insufficient GSW cooling OR less than 2 GSW pumps are running THEN make every effort to achieve at least 2 pumps running.

Monitor GSW combined outlet temperatures (Computer Point M004) and send an operator to monitor GSW load return line temperatures (local).

IF turbine bearing temperatures approach 250°F, THEN manually scram the reactor AND trip the main turbine AND start turbine lift pumps and turning gear oil pump.

IF a condensate or feed pump high temperature annunciator 1C06B(D-5)

TURB INSTRUMENT PANEL 1C-20 TROUBLE is received THEN perform the following as required:

Monitor generator hydrogen, stator, and exciter cooler temperatures.

ATC:

Reduce reactor power to 50% using IPOI 4 Fast Power Reduction if necessary and secure the affected pump(s).

Scram the reactor prior to securing both condensate or feed pumps EVALUATOR NOTE: The next event was developed for the ATC Operator and it is recommended to be inserted when the BOP is investigating GSW cooled component recorders located in the Control Room Back Panel area.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 21 of 22 EVENT 5.b. CREW: Respond the annunciator 1C06B D-3, RBCCW Pump Disch Header Lightning Strike Lo Pressure alarm When the BOP SIMULATOR OPERATOR ATC:

Operator is in Click KEYPAD Key 7

Confirm the low pressure condition on PI-4821 and/or Computer Contact the Control This will start a schedule file for Point M508 Room Back

Normally two pumps are in operation, confirm that A, B & C RBCCW panels or at the another lightning strike and a trip of the PUMPS 1P-81A, B & C are all running direction of the C RBCCW Pump Lead Evaluator:

If any pump fails to start, attempt to start that pump ONCE using the following control switch;

HS-4829 A RBCCW PUMP 1P-81A BOOTH COMMUNICATOR If sent to ACKNOWLEDGE the request and WAIT investigate the 3 minutes and REPORT, The C RBCCW RBCCW pump breaker is warm and in system and the trip free position. The pump seems breaker, normal, The A RBCCW pump is running Sat.

EVALUATOR NOTE: The next event will cause a leak in the RWCU HX Room and will take approximately 1-2 minutes for a control room annunciator to be received.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 22 of 23 EVENT 6 Crew: Respond to the following Annunciators:

RWCU HX o 1C04B B-4, Steam Leak Detection Ambient High Temperature room leak SIMULATOR OPERATOR o 1C04B D-4, Steam Leak Det Hi T At the o 1C04B A-9, RWCU LO FLOW direction of the Click KEYPAD Key 8 o 1C04B B-9, RWCU Filter/Demin Trouble Lead This will start a leak in the RWCU Hx Evaluator, room to drive the crew to insert a manual reactor scram BOP:

NOTE: If the BOP shifts main plant

Go to 1C21 and determine that the leak is from RWCU Hx room ventilation to a 3-2-3 lineup CU07

Maximize plant ventilation IAW OI 734, QRC1, Maximize Plant will modify to cause RWCU HX Ventilation Room temperature to rise above

Start 1V-EF-1, 1V-EF-2, and 1V-EF-3 MAIN PLANT MAX SAFE EXHAUST FANS and verify their respective dampers indicate OPEN If the crew SIMULATOR OPERATOR

Start the Reactor Building Exhaust Fans actions appear o Start the Reactor Building Supply Fans Raise the severity of MF CU07, to be keeping RWCU Leak in Hx Room, in the RWCU Hx increments of 0.1 with a 30 second ATC:

room from ramp.

Verify Automatic Actions reaching a o Determine that MO 2700, the RWCU Inboard Isolation Valve did Max Safe not close, and has a thermal overload on the breaker temperature, EVALUATOR NOTE o Send someone to 1B3219 to attempt to reset the thermal RWCU HX Room Ambient temps: overload MNOL: 130°F o Determine that MO 2701 did not close and attempt to close the MSOL: 212°F valve o When the HS for MO 2701 is taken to the close position, all If sent to indication for MO 2701 is lost attempt to BOOTH COMMUNCIATOR o Will report to the CRS that MO 2701 is not closed reset the ACKNOWLEGE the request, WAIT 2

Prompt the CRS that this is an EOP 3 entry thermal minutes and REPORT, I have

Insert a manual reactor scram prior to reaching a Max Safe overload on depressed the thermal overload for Operating Temperature Limit in the RWCU Hx room. (Critical) 1B3219, MO 2700 on breaker 1B3219.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 23 of 24 EVENT 6 Crew: In response to the leak in the RWCU Hx room RWCU HX room leak CRS: (6.67)

Enter EOP 3 and direct the following When the o Operate available coolers in the affected area SIMULATOR OPERATOR Operator o Operate available main plant supply and exhaust fans attempts to Verify that Event Trigger 23 goes TRUE Maximize plant ventilation IAW OI 734, QRC1, Maximize close MO Plant Ventilation 2701, This will result in the breaker trip for o Attempt to isolate the leaking system MO2701, and the valve will remain Determines that RWCU will not isolate due to the thermal open. overload on MO 2700

Direct that the thermal overload condition be reset and BOOTH COMMUNCIATOR the valve closed If sent to Acknowledge the request and WAIT Determine that MO 2701 did not isolate, and send an attempt to 2 minutes and REPORT, There is Operator to 1D4204 to investigate investigate an acrid odor near 1D4204, and the o Determine that a pressure reduction will decrease leakage into 1D42 ckt 04 breaker door is warm to the touch. secondary containment for MO 2701, o Determine that a reactor scram be inserted prior to the RWCU Hx room reaching a Max Safe Operation Limit Set a critical parameter on the RWCU Hx room for inserting a EVALUATOR NOTE reactor scram RWCU HX Room Ambient temps: o Insert a reactor scram prior to reaching a Max Safe Operation MNOL: 130°F Limit in the RWCU Hx room. (Critical)

MSOL: 212°F TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 24 of 25 EVENT 7: Crew: Perform the following in response to rising temperatures in the Reactor RWCU HX Room.

Scram ATWS CRS:

Enter EOP 1

Upon the ATC report, Exit EOP 1 and transition to ATWS (6.55)

Per ATWS o Lock out ADS o Install defeat 15 o Perform the ATWS QRC BOP: (95.55)

Lock out ADS prior to ADS Actuation (Critical)

Install Defeat 15 ATC:

Per the ATWS QRC o Verify the MODE Switch is in SD EVALUATOR NOTE: o FW Master Controller in Auto and set at 158.5 inches IF ARI automatically initiates due to low o HSS-4450 in 1 element RPV water level and all control rods are o Recirc run back to minimum inserted before the manual ARI o Initiate ARI (Critical) (95.95) pushbuttons have been depressed THEN o Verify Recirc Pumps trip this Critical Task is failed o Report that the ATWS QRC is complete with the exception of initiating SBLC o ARI DID work o Determines that all but one control rod has inserted TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 25 of 26 EVENT 8: Re- Crew: Exits ATWS and returns to EOP 1 and directs the following entry to EOP 1 actions 1A4 Lockout CRS: (6.45)

Per EOP 1 SIMULATOR OPERATOR o Restore and maintain RPV level to 170 to 211 When the o Install defeat 11 Verify Event Trigger 20 goes TRUE o Establishes an RPV pressure band of 800 psig to 1055 psig turbine trips, This will result in the lock out of 1A4 using SRVs and MSL drains (6.47) o When the plant is stable, assigns a new pressure band of 500 to 700 psig to remove the driving head of the leak in the RWCU HX room BOP: (95.46)

Install Defeat 11

When directed establish a new pressure band of 500 to 700 psig to remove the driving head from the leak in the RWCU HX room using EHC pressure set or SRVs.

ATC: (95.46)

Maintain RPV level 170 to 211 using Main Feedwater

Will establish a RPV pressure band of 800 psig to 1055 psig using EHC

When directed establish a new pressure band of 500 to 700 psig to remove the driving head from the leak in the RWCU HX room using EHC pressure set or SRVs. (95.47)

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 26 of 27 EVENT 8: Re- Crew: Respond to the lock out of 1A4, and perform the actions of AOP 301 entry to EOP 1 1A4 Lockout CRS: (5.36)

Enter and direct the performance of AOP 301 for the loss of 1A4 BOP: (94.36)

Will determine that the B EDG is running without any cooling water, and take the HS for the B EDG to the PTL position BOOTH COMMUNICATOR

Prompt CRS to enter AOP 358 to restore RPS If sent to

Send an operator to investigate 1A4 investigate the ACKNOWLEDGE the request, WAIT 3 lockout trip of minutes and REPORT, That 1A4 has a 1A4, lockout trip.

Verify A CRD is running

Verify A and C GSW pumps are running

Verify A and C RWS pumps are running

Verify that the A Chiller and CB air conditioning is in service

Verify that the A and C Battery Room Exhaust Fans are running EVALUATOR NOTE: The next event is to drive the crew to Emergency Depressurization. The ramp rate for the second area going above maximum safe operating limit (MSOL) is approximately 2 minutes.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 27 of 28 Event 9: Crew: Respond to the rising temperatures above the TIP room and continue in Second Area the actions of EOP 3 above MSOL /

SIMULATOR OPERATOR CRS:

ED Click KEYPAD Key 9

Direct that the Defeat 9 be installed to maximize cooling to the reactor This will begin the leak above the TIP building When the

If the temperature rise above the TIP room is identified early enough, the room and drive the crew to Emergency actions of AOP CRS will direct the crew to anticipate Emergency Depressurization Depressurize 301 have been o Direct the performance of SEP 307, Rapid Depressurization with Bypass directed, and at Valves. This will be unsuccessful as the Turbine Bypass Valve Jack will the direction of not engage (6.48) the Lead EVALUTOR NOTE:

Wait until two areas exceed Max Safe Evaluator, RWCU ABOVE TIP ROOM AMBIENT:

When two areas exceed Max Safe, enter ED MNOL: 111.5°F MSOL: 150°F BOP:

Determine that RM 7606B REACTOR BUILDING VENT SHAFT RAD IF the crew has NOT attempted opening MONITOR is failed upscale and cannot be reset preventing Defeat 9 from the necessary SRVs required for being installed.

emergency depressurization within 10

Verify torus level is > 4.5 ft minutes with both areas above MSOL

Open 4 ADS SRVs (Critical)

THEN the Critical Task is failed o Receive the report from 1C03, that 2 ADS SRVs opened, and 2 LLS SRV have opened SIMULATOR OPERATOR ATC:

Modify Malfunction CU07 by

Maintain RPV level using Condensate and Feed, CS or RHR during the ED If the increments of 0.1 until the area has

Restore RPV level to 170 to 211 temperature in gone above Max Safe again the RWCU Hx BOP: (95.68) room has fallen

Install Defeat 9 to maximize reactor building ventilation (UNSUCCESSFUL) below Max

Perform SEP 307, Rapid Depressurization with Bypass Valves.

Safe, (UNSUCCESSFUL)

Report Torus level

Report to the CRS that 2 ADS SRVs opened, and 2 LLS SRV opened

Place Torus Cooling in service o Utilize RHRSW Hard card to place RHRSW in service o Place Torus cooling in service using Torus Cooling Hard card TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 28 of 29 The Scenario will be complete when the RPV Simulator Operator is depressurized Place the simulator in FREEZE.

and RPV level is being Announce the scenario is complete; restored, and at please stand by your stations and do the direction of not discuss the scenario with your the Lead crew.

Evaluator

- - END OF SCENARIO ***

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 29 of 30 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Inadvertent initiation of the A Core Spray Pump

2. B GSW pump trip and initiating entry into AOP 411, Loss of GSW

3. Trip of the C RBCCW Pump

4. Leak in the RWCU HX Room After EOP Entry:

1. ATWS

ARI inserts all rods but 1

2. Loss of 1A4 Abnormal Events:

1. AOP 411, Loss of GSW

2. AOP 301, Loss of Essential Power Major Transients:

1. Steam leak in the RWCU Hx room spreads to area above TIP room

2. ATWS

3. Emergency Depressurization Critical Tasks:

1. If the reactor is at power and a primary system is discharging into secondary containment, THEN insert a manual scram before any parameter reaches the Max. Safe Operating Limit

2. IF a scram is required and Reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods

Initiation of ARI

3. IF a reactor scram is required and the reactor is NOT shutdown under all conditions, THEN lockout ADS before automatic actuation

4. WHEN a primary system is discharging into secondary containment and the same parameter is exceeding the Max. Safe Operating limits in more than one area, THEN perform Emergency RPV Depressurization TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 30 of 31 Facility: Duane Arnold Energy Center Scenario No.: ___2_____ Op-Test No.: 19-1 NRC Examiners Operators Initial Conditions/Turnover:

Reactor Power is 100%

Guarded Equipment: Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room, 1C136 Fuel Pool Cooling Panel, 1B3507 A Fuel Pool Cooling Pump Breaker, 1B4327 B Fuel Pool Cooling Pump Breaker.

Evolutions in progress or planned for upcoming shift

Shift Stator Water Cooling pumps in accordance with OI 697 Generator Stator Water Cooling System

Reduce Reactor Power to 95% with Control Rod Insertion for Load Line Adjustment Plant PRA/PSA Status including CDF/LERF & color

CDF GREEN - 1.47E-6/ Cumulative Core Damage Probability )CCDP) No Limit

LERF GREEN - 3.92 E-7/ Cumulative Large/Early Release Probability (CLERP) No Limit Rain will be moving into the area later in the shift.

2 Extra Non Licensed Personnel Available in Work Control Even Malf. Event Event t No. No. Type* Description 1 N-BOP Shift Stator Water Cooling Pumps in accordance with N-CRS OI 697 Generator Stator Water Cooling System section 7.0 2 R-ATC Reduce Rx Power with Rods In Accordance With Load R-CRS Line Adjustment to 95% RTP 3 DI-CS- I-BOP A Core Spray pump will receive an inadvertent start 008 I-CRS signal.

TS-CRS Tech Spec 3.5.1 Condition B (3.3.5.1 Also Possible)

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 31 of 31 4 sl07 TS- Leak on 1T-218 develops and causes 1C05A E-3, CRS SBLC Tank HI/LO Level alarm to come in Tech Spec 3.1.7, Condition B 5a./b. sw37a C-CRS Lightning Strike causes:

an1c06a C-BOP 5.a. Trip of B GSW Pump (17) o Standby Pump Fails to Auto Start AOP sw32 411 (Possible) stsw01a o High P across Auto Filter ARP Actions sw10c C-ATC 5.b. C RBCCW Pump o Standby Pump Fails to Auto Start ARP Actions 6 cu05 M-All A leak will develop in the RWCU HX room requiring cu11a EOP 3 Entry cu12a

Scram prior to Temperatures Reaching Max ms28b Safe cu07

Leak will not be Isolated DO-CU-

Defeat 9 will not work to restore ventilation 003 DO-CU-004 DO-CU-027 DO-CU-028 DO-PC-091 DO-PC-092 7 rp05a C-ATC On the reactor scram, there will be an electrical ATWS rp05b C-CRS

ARI will be effective at inserting all but 1 control rp05d rod rp05e rd02022 7

8 ed08d C-All After all but one of the control rods have inserted, 1A4 will lockout. The crew will take actions In Accordance With AOP 301 9 DI-AD- C-BOP TIP room exceeds a Max Safe Temperature Limit, the 015 C-CRS crew will enter ED.

DI-AD-

If the crew attempts to use the EHC Control 017 System, it will fail to control the B/P Valves

Only two ADS SRVs will open, requiring the crew to open the LLS SRVs to complete the ED TR-AA-230-1007-F13, Revision 0

SIMULATOR EXERCISE GUIDE, SEG THREE COLUMN Page 1 of 28 SITE: DAEC Revision #: 0 LMS ID: NRC Scenario 3 LMS Rev. Date:

SEG TITLE: NRC Scenario 3, Rev. 0 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 60 minutes Developed by:

Instructor/Developer Date Reviewed by:

Instructor (Instructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 2 of 3 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators ability to:

Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures.

Enabling Evaluation Guide, no tasks are trained Objectives:

Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation Team C. Simulator Operator D. Booth Communicator

References:

1. ARP 1C08B, Rev. 98

2. AOP 410, Rev. 30

3. TS 3.8.7, AMD 223

4. TS 3.7.2, AMD 223

5. IPOI 3, Rev 160

6. AOP 903, Rev, 59

7. ARP 1C04B, Rev. 64

8. ARP 1C23C, Rev. 55

9. AOP 408, Rev. 32

10. AOP 304.1, Rev.60

11. EOP 1, Rev, 20

12. EOP 2, Rev, 18

13. OI 416, Rev 67

14. OI 454, Rev 70

15. OI 644 QRC 1, Rev. 8

16. ED Rev. 11 Protected Content: Identify here and in training material as {C001}; See Comment for details.

None Evaluation Method: In accordance with NUREG 1021 Operating None Experience:

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NRC Scenario 3, Rev. 0 SEG Page 3 of 4 Risk Significant Initiate RPV Emergency Depressurization Operator Actions:

Filename: NRC Scenario 3 19-1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 4

NRC Scenario 3, Rev. 0 SEG Page 4 of 5 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.08 Respond to Loss of 4160V Non-essential Power Condition (1A1 or 1A2) 94.14 Respond to Well Water System Abnormal Operation Condition 94.15 Respond to the loss of River Water Supply 94.24 Respond to High Winds / Severe Thunderstorms / Tornado Condition 95.65 Spray the Drywell with RHR Not Required for Adequate Core Cooling 95.63 Perform DW/T leg of EOP 2 95.80 Perform an Emergency Depressurization Using SRVs 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 5.08 Direct Crew Response to Loss of 4160V Nonessential Power Condition Direct Crew Response to Well Water System Abnormal Operation 5.14 Condition 5.15 Direct Crew Response to the loss of River Water Supply Direct Crew Response to High Winds / Severe Thunderstorms / Tornado 5.24 Condition Direct Crew Response to Spray the Drywell with RHR Not Required for 6.65 Adequate Core Cooling Direct Crew Response for performance of ALC when injection systems 6.74 are lined up and available, or when no pumps are available 6.78 Direct Crew Response for performance of Emergency Depressurization Direct Crew Response to Perform an Emergency Depressurization Using 6.80 SRVs UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See cover 0.0 New for PDA 19-1 LOIT NRC Exam.

See cover TR-AA-230-1007-F13 , Revision 0

NRC Scenario 3, Rev. 0 SEG Page 5 of 6 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.03 Respond to Power/Reactivity Abnormal Change Condition 94.08 Respond to Loss of 4160V Non-essential Power Condition (1A1 or 1A2) 94.14 Respond to Well Water System Abnormal Operation Condition 94.15 Respond to the loss of River Water Supply 94.24 Respond to High Winds / Severe Thunderstorms / Tornado Condition 95.65 Spray the Drywell with RHR Not Required for Adequate Core Cooling 95.63 Perform DW/T leg of EOP 2 95.80 Perform an Emergency Depressurization Using SRVs 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.08 Direct Crew Response to Loss of 4160V Nonessential Power Condition 5.14 Direct Crew Response to Well Water System Abnormal Operation Condition 5.15 Direct Crew Response to the loss of River Water Supply 5.24 Direct Crew Response to High Winds / Severe Thunderstorms / Tornado Condition Direct Crew Response to Spray the Drywell with RHR Not Required for Adequate Core 6.65 Cooling Direct Crew Response for performance of ALC when injection systems are lined up and 6.74 available, or when no pumps are available 6.78 Direct Crew Response for performance of Emergency Depressurization 6.80 Direct Crew Response to Perform an Emergency Depressurization Using SRVs TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 6 of 7 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW See below event description for overview The Scenario will end when the plant has been depressurized and RPV level is returning to the directed band.

SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description

1. The plant is starting up following a failure of the lube oil system of the B Feedwater pump.

The plant is currently at 50% power and the startup was on hold due to the performance of STP 3.5.1-10, HPCI System Operability Test and Comprehensive Pump test. The STP has been completed SAT and torus cooling was in service.

After turnover, the crew will finish securing from torus cooling by securing A side RHRSW and A side ESW.

2. Raise Power with Recirc to 55%-60% in preparation of putting the B RFP in service.

3. Due to the electrical transients on the 1A3, Essential Switchgear, the feeder breaker 1A312, to 1B09 opens on ground fault. Subsequently, a loss of A side RWS occurs. The crew will start 1P-117B (D) IAW ARP 1C08A(B-6), LC XFMR 1X09 Breaker 1A312, or MCC 1B9 BKR 1B903 Trip, and AOP 410 Loss of River Water Supply. Based on the loss of 1B09.

The Control Room Supervisor will enter TS 3.8.7, Condition D, to declare associated River Water Supply subsystem(s) inoperable, Immediately. From 3.8.7, the crew will enter TS 3.7.2, Condition A, to restore the RWS subsystem to OPERABLE status within 7 days.

4. A report is received by the Control Room Supervisor that the National Weather Service has issued a Severe Thunder Storm Watch for the next 60 minutes. The Control Room Supervisor will enter AOP 903, for the Severe Thunder Storm.

Once the site wide announcement is completed, a lightning strike will cause a trip of the A Well Water Pump The Crew will respond to the trip of the A Well by performing the actions of ARP 1C23C, F-1, A Well Water Pump 1P58A Trouble. This will refer the Operator to AOP 408, Loss of Well Water Flow. The Operator will restore adequate Well Water flow via AOP 408.

When the Balance of Plant goes to monitor Well Water parameters at 1C23, an additional lightning strike will occur and trip the running RWCU pump. The crew will take action in accordance with 1C04B (A-9), RWCU Pump LO Flow, and B-9, RWCU Filter/Demin Trouble.

TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 7 of 8 The Control Room Supervisor will enter TRM Spec 3.3.4 for online chemistry monitoring is not met with RWCU OOS.

5. A LOCA will develop from the B recirculation loop due to raising reactor power. The crew will insert a manual scram prior to the DW reaching 2 psig and enter EOP 1 on the scram, and when the DW reaches 2 psig, the crew will re-enter EOP 1 and enter EOP 2.

6. As the DW temperature and pressure rise, the crew will take action to spray the DW prior to the DW temperature reaching 280°F. (Critical)

When drywell pressure rises above 2 psig, the following equipment issues will be identified by the crew:

The B CS pump will start and trip after operating for 3 minutes (B CS will be unavailable)

The A CS pump will fail to automatically start and will be manually started by the crew (Critical)

HPCI will initially start and inject to the vessel. The HPCI Aux Oil Pump will fail and HPCI will be unavailable when secured

7. On the turbine trip the Startup Transformer will develop an electrical fault and cause a loss of 1A1 and 1A2 Non-essential Electrical Buses. The Control Room Supervisor will enter and direct the actions of AOP 304.1, Loss of 4160V Non-Essential Electrical Power.

8. The primary leak will begin to worsen and overcome all high pressure makeup sources.

The Control Room Supervisor will enter Alternate Level Control and prepare for an Emergency Depressurization. When RPV level reaches +15, the crew will;

Open 4 ADS SRVs (Critical)

When RPV pressure lowers to 450 psig, the crew will determine that the selected RHR inject valve and A Core Spray Inject valve did not automatically open, and Operator action is necessary to manually open both valves (Critical)

The scenario will end when the crew has performed and Emergency Depressurization and RPV level is being returned to the directed band.

TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 8 of 9 SIMULATOR SET UP INSTRUCTIONS

1. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist ____

2. Using the exam flash drive with the scenario simulator files, insert in the left instructor station computer and navigate to the D:\ directory ____

3. Copy the NRCScenario3.dat file from the exam flash drive to C:\Trex_Duane-TELEC\Executive\SiteSpecific\InitialCondition and rename the file to an available IC using the format ic_### ____

a. Reset to the newly created IC ____

b. Place the Simulator in RUN ____

c. Run schedule file Weather.sch following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_3\NRCScenario3_SimFiles ____

OR

4. Reset to IC 13, place the simulator in RUN and perform the following (this will take approximately 15 minutes for the plant to stabilize):

a. Insert Event Triggers, Malfunctions, Overrides, and Remotes using schedule ____

file NRCScenario3Setup.sch located on the exam flash drive using the following directory path D:\NRCOperational\NRCScenarios\NRC_Scenario_3\NRCScenario3_SimFiles ____

b. Have a second instructor verify:

(1) Auto triggers are setup as indicated below and evaluate to FALSE ____

(2) Malfunctions ____

(3) Remotes ____

(4) Overrides ____

c. Verify that an A RWS Pump is in service (single river water supply pump) ____

d. The orange 45% runback placard is in place on 1C05 ____

e. Secure both B RFP and the B RFP Aux Lube Oil Pump ____

f. Secure the B Condensate pump ____

5. Setup Thundersound on the Instructor Station computer to the right and verify the following settings:

a. Click on the checkbox under Playing for THUNDERSTORM ____

b. Click the STOP button to toggle audio model to playing ____

c. Verify Instructor Station sound volume is set to approximately 25% ____

d. Verify the dB controller (under the Instructor Station monitor) level 2 know is aligned to the detent (white line on the knob is pointing slightly counterclockwise) ____

e. Verify the Front Room (both) sub amplifiers are set to approximately 50% of scale ____

TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 9 of 10

6. Place Guarded Equipment tags on: ____

1B35 Switch

1B43 Switch

7. Mark up IPOI 3, Power Operation (35%-100% Rated Power), Section 4.0, Raising Power Above 35%, up to Step 9 and leave for the crew ____

8. Markup the BOL pull sheets for a reactor power startup (withdrawn) to the current control rod position of the Initial Conditions ____

9. Ensure BOL pull sheets are in the 1C05B hanging file ____

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NRC Scenario 3, Rev. 0 SEG Page 10 of 11 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 1 rxqic >= 0.55 Calculated Core Power >= 55%

3 ZDIEG286B l ZDIEG286P Main Generator Trip 5 pcpdwg > 2.0 Drywell Pressure above 2.0 psig ZDIRHH2001(2) l 7 Drywell Sprays Initiated ZDIRHHS1903(2) 9, 11, 13 Manually activated MALFUNCTIONS:

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value CORE SPRAY INJECTION SETUP stcs01 VALVE FAILS TO OPEN - MO- INACTIVE ACTIVE 2117 CORE SPRAY PUMP A -

SETUP cs05a INACTIVE ACTIVE FAILURE TO AUTO-INITIATE LPCI A INJECT VALVE FAILS SETUP strh01 INACTIVE ACTIVE TO AUTO OPEN - MO-2003 LPCI B INJECT VALVE FAILS SETUP strh02 INACTIVE ACTIVE TO AUTO OPEN - MO-1905 4.16 KV/480V BUS FAULT- BUS As dir ed08m 1 INACTIVE ACTIVE 1B09 STARTUP TRANSFORMER As dir ed06c 3 ACTIVE ACTIVE LOSS CORE SPRAY PUMP TRIP-As dir cs01b 3 min 5 INACTIVE ACTIVE CORE SPRAY PUMP B TRIP As dir hp12 HPCI Aux Oil Pump Trips 5 sec 5 ACTIVE ACTIVE (new) RECIRC LOOP RUPT- DESIGN As dir BASES LOCA AT 100%- LOOP 20 min 7 1 3 rr15b B WELL WATER PUMP TRIP-As dir sw21a 9 INACTIVE ACTIVE PUMP A, 1P58A As dir cu01b RWCU PUMP TRIP - PUMP B 11 INACTIVE ACTIVE RECIRC LOOP RUPT- DESIGN As dir rr15b BASES LOCA AT 100%- LOOP 4 min 13 0 1 B

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NRC Scenario 3, Rev. 0 SEG Page 11 of 12 OVERRIDES:

Time OR No. Override Title Delay Ramp ET Initial Final Value Value REMOTE FUNCTIONS:

Time RF. No. Remote Function Title Delay Ramp ET Initial Final Value Value SCHEDULE FILE(S): NONE TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 12 of 13 SHIFT TURNOVER INFORMATION

Day of week and shift o It is Today Dayshift

Weather conditions o Cloudy and warm with a chance of storms.

Plant power, 50% and the associated MWE and Core Flow

Protected train o None o Guarded Equipment Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room, 1C136 Fuel Pool Cooling Panel, 1B3507 A Fuel Pool Cooling Pump Breaker, 1B4327 B Fuel Pool Cooling Pump Breaker Time to 200° F is 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months

There are no Technical Specification Action statements in effect

No Locked in / failed annunciators and alarms

Evolutions in progress or planned for upcoming shift o STP 3.5.1-10, HPCI system Operability Test and Comprehensive Pump Test, was completed SATISFACTORY early last shift and torus cooling shutdown is in progress:

A RHRSW is in service with A RHRSW pump in operation A ESW is in service to support plant conditions o The Plant is a 50% power due to repairs on the B Feedwater Pump lube oil system 4 days ago, 1P-2B, the B RFP Aux Lube Oil Pump, automatically started due to a faulty pressure switch. After the automatic start, 1P-2B catastrophically failed Power was reduced and the B Feedwater pump was removed from service The lube oil system has been repaired, the Mechanics have just signed off their post maintenance testing for the 1P-2B TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 13 of 14

Plant PRA/PSA Status including CDF/LERF & color o CDF GREEN - 1.47E-6/ Cumulative Core Damage Probability (CCDP) No Limit o LERF GREEN - 3.92 E-7/ Cumulative Large/Early Release Probability (CLERP) No Limit

Procedures or major maintenance in progress o The Plan is to perform the following; Prepare to start the B Feedwater Pump IAW OI 644, Feedwater System.

Currently in IPOI 3, Section 4.0, raising power above 35%, through step 8

Reactor Power must be raised with Recirc to between 55 and 60% power to start the B Feedwater Pump.

o The scheduled Reactivity SRO went home due to a family emergency. Operations Management will allow the CRS to oversee the 5 to 7% power rise with Recirc to position the plant for the start of the B Feedwater Pump.

The two extra ROs are currently in the simulator performing JITT on the start of the second Feedwater pump

The WCC is currently preparing a prejob brief the start of the B Feed water Pump

When the B Feedwater System is operating, the Reactor Engineers will come to the control room for a rod pull brief to continue with the power rise to 100%.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o Secure A RHRSW Pump and A ESW system

Comments, problems, operator workarounds, etc.

o Two (2) extra RO o Three (3) Extra NSPEO TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 14 of 15 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1: CREW: Secure A RHRSW and A ESW Secure A RHRSW Pump CRS:

and A ESW

Direct Operators to secure A RHRSW and A ESW BOP:

Close MO-2046, RHR HX Service Water Outlet using HS-2046A

Stop 1P-22A by placing HS-4925A momentarily to STOP

Verify associated pump ammeter on 1C03 indicates 0 amps

Verify flow indicator FI-2050 RHRSW INLET FLOW at 1C03 indicates 0 gpm

Stop A ESW Pump by placing HS-4928A on 1C06 in the STOP position ATC:

Provide peer-checks are requested TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 15 of 16 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 2: CREW: Raise Reactor Power with Recirc IAW OI 264, Sec 4.2 Raise reactor power with CRS:

recirc

Direct the ATC to raise reactor power to 55-60% with recirc

Supervise the manipulation of the Recirculation System ATC:

Raise Recirc Flow with SIC-9245A, A Recirc MG Set Speed Control, and SIC-9245B, B Recirc MG Set Speed Control.

Monitor core parameters as power is changed, such as:

o Recirc flow o Reactor jet pump total core flow o Total steam flow o Total feed flow o Reactor water level o Reactor pressure o APRM power BOP:

Provide peer-checks are requested

Monitor plant parameters as power is changed, such as:

o Generator output EVALUATOR NOTE: The loss of River Water Supply is automatically initiated when calculated core thermal power is 55%. The next event can be directed by the Lead Evaluator prior to this automatic initiation.

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NRC Scenario 3, Rev. 0 SEG Page 16 of 17 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3: CREW: Respond to ARP 1C08B (B-6) LC XFMR 1X09 Breaker 1A312, or Breaker 1A312 MCC 1B21 BKR 1B2003 Trip and AOP 410, Loss of River Water Supply.

TRIP SIMULATOR OPERATOR At the direction ACTIVATE ET 1/VERIFY ET 1 is active BOP:

of the Lead This will insert ED08N for loss of 1B09

Send an Operator to the Intake Structure to verify 1K-16B is maintaining Evaluator:

system air pressure and supplying both Intake Structure Instrument Air BOOTH COMMUNICATOR headers.

If sent to 1A3

Start River Water Supply Pumps 1P-117B and D as required per OI 410 switchgear to ACKNOWLEDGE the request, WAIT 2 minutes and REPORT, Breaker 1A312 is (River Water Supply System) and perform the following:

investigate, tripped with indication of ground fault, all o Monitor Circ Water Pit level on Computer Point F092 and Cooling other indications are normal. Tower Basin levels on LI-4231 and LI-4232 o Be prepared to perform AOP 410 (Loss of River Water Supply)

EVALUATOR NOTE:

Start Standby Pump (B or D RWS Pump) to restore needed makeup flow Time compression can be used for the

Send an operator to the Intake Structure to verify alarms and check RWS Intake Structure Report.

pump breaker condition. (94.15)

If/When sent to Intake Structure BOOTH COMMUNICATOR CRS:

to investigate. ACKNOWLEDGE the request, WAIT 10 minutes and REPORT, There is no

Enter AOP 410 Loss of River Water Supply (5.15) power for A side equipment at the intake

Comply with the Technical Specification requirements for Distribution structure, all equipment appears normal Systems-Operating (3.8.7 Condition D) and inoperable RWS and 1K-16B is running and operating subsystem. (3.7.2 Condition A) (1.02) normally.

Contact organization for support If necessary, acknowledge SIMULATOR OPERATOR annunciators at SET RF AN03 to ACK 1C102, This will acknowledge 1C102 annunciators EVALUATOR NOTE: The next event is to setup for the associated system/component failures in the follow-on events and can be directed at the Lead Examiners direction.

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NRC Scenario 3, Rev. 0 SEG Page 17 of 18 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4: AOP CREW: Perform actions directed by AOP 903, Severe Weather and for the 903, lightning loss of A Well Water Pump strike Simulator Operator The National Weather Service has just CRS:(5.24)

Call the control declared a Severe Thunderstorm

Enter and direct that AOP 903, Severe Weather, Section B be entered room as Warning For DAEC for the next 60 and the necessary announcements be made to DAEC Security and minutes

Will call ITC to determine the status of the grid and inform the ITC Real report, Time Desk of the severe storm warning Simulator Operator

Enter and direct AOP 408, Loss of Well Water When Inform the control room that the grid is contacted as BOP:(94.24) stable.

ITC,

Make the thunderstorm warning Simulator Operator

Request Security inform personnel working outside, who may not have When called as been able to hear the page announcement, of the WARNING condition security Inform the control room that you will notify any personnel working outside

Monitor wind speed using SPDS display SPMET1, YR9400 MET System personnel, Recorder, Group Display "AOP903", Real Time Plot "Wind", and other that may not have heard the warning available local wind speed display

Inform the CRS/SM to Refer to EPIP 1.1 and 1.2 for Emergency Action After the site Level Classification and Notification requirements wide Simulator Operator

Start the C Well Water Pump announcement Activate ET 9

Verify all Well Water Pump parameters at 1C23 is complete and This will trip the A Well Water Pump at the direction of the Lead Evaluator, EVALUATOR NOTE: This first event was developed for the BOP Operator for the loss of Well Water. Ensure that the BOP Operator is in the vicinity of 1C07 and the well water system controls. The next event was developed for the ATC Operator for the loss of RWCU system.

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NRC Scenario 3, Rev. 0 SEG Page 18 of 19 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4: AOP CREW: Respond to a loss of RWCU Pump B and the following 903, lightning annunciators:

strike

1C04B A-9 RWCU PUMP LO FLOW

1C04B B-9 RWCU FILTER/DEMIN TROUBLE SIMULATOR OPERATOR When the BOP ATC:

Activate ET11 is adjusting well

Will determine that the B RWCU Pump has tripped and take action IAW water at 1C23, This will trip the B RWCU Pump ARP 1C04B A-9, RWCU Pump Lo Flow

Verify the running RWCU Pump has tripped SIMULATOR OPERATOR

Direct an operator to verify the RWCU Beds in HOLD Call the control room as a security

Direct an operator in investigate the pumps locally Guard and report that there was a

Direct an operator to reset the breaker1B3509(1B4329) lightning strike just north of the plant

Check for fault light on the variable speed drives

Crack open MO-2723, Cleanup Demin Bypass valve BOOTH COMMUNICATOR

As Time permits, If contacted to o If the RWCU System will remain shutdown/isolated for an extended ACKNOWLEDGE the request, WAIT 3 investigate period of time, computer point B017, RWCU System Flow, may minutes and REPORT, B RWCU TRIP of B need to be substituted to zero to maintain accurate ACUMEN pump is warm to the touch. A RWCU RWCU pump Periodic Reports.

pump is normal. Both RWCU Demin Beds are in HOLD. o Restore RWCU to service CRS:

Determine that TRM Spec 3.3.4, RCS Conductivity Monitoring Instrumentation, is not met and enter Condition A

Direct Chemistry to swap to Recirc Sample Point for monitoring RCS Chemistry EVALUATOR NOTE: The next event will be a Loss of Coolant Accident and the follow-on events will be automatically inserted based on Operator actions. The leak rate will take approximately 2 minutes before control room annunciators will alert the Operating crew of the primary leak into containment.

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NRC Scenario 3, Rev. 0 SEG Page 19 of 20 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5: CREW: Respond to the rising in Dry Well Pressure LOCA When the CRS:

actions of the SIMULATOR OPERATOR

Enter and direct AOP 573, Primary Containment Abnormal lightning strikes are under ACTIVATE ET 13

Set a Critical Parameter on DW pressure, and place a line in the sand to control and at This will begin the LOCA insert a manual scram at 1.8 psig the directions of the Lead BOP:

Evaluator,

Will begin to perform the actions of AOP 573

Will monitor DW pressure and report to the CRS as necessary ATC:

Will insert a reactor scram prior to DW pressure reaching 2 psig TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 20 of 21 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 5: CREW: Perform actions directed by EOP 1 LOCA and EOP 1 CRS:

Enter and Direct EOP 1, RPV Control

Restore and maintain RPV level to 170 to 211 with high pressure sources

Install Defeat 11

Maintain RPV pressure 800 psig to 1055 psig using EHC and MSL drains

When plant conditions are stable, Directs that a pressure band of 500 psig to 700 psig be established using the SRVs to take the head off of the leak ATC:

Insert a manual reactor scram

Will provide the crew with the scram report:

o All Rods fully inserted o Will provide an RPV level and that a there is an EOP entry condition o Will provide a reactor pressure

Maintain RPV level 170 to 211 using Main Feedwater

Will maintain RPV pressure 800 psig to 1055 psig using EHC

Utilize MSL drains and SRVs to lower reactor pressure to the desired band

Will operate available high pressure systems to maintain RPV level in the directed band BOP:

Install Defeat 11 TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 21 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6: Hi CREW: Mitigate containment parameters in accordance with EOP 2 DW Pressure SCRAM, ECCS CRS:

failures SIMULATOR OPERATOR

Enter EOP 2, Primary Containment Control VERIFY ET 5 goes TRUE

Obtains a round of Primary Containment parameters When the DW reaches 2 psig, This will trip the B CS pump after a 3 min

Per PC/P time delay and TRIP the HPCI Aux Oil

When the torus pressure is above 2 psig and below 11 psig, direct to Pump after 5 seconds Spray the Torus

Per DW/T

Verifies torus level < 13.5 feet BOOTH COMMUNICATOR If contacted to

Plots DW temp vs DW pressure on the DWSIL curve ACKNOWLEDGE request WAIT 3

Verifies Recirc pumps Tripped investigate minutes and REPORT 1D41-13 is

Directs spraying the DW prior to DW air temperature reaching 280°F HPCI Aux Oil TRIPPED. There is no indication of (Critical) (6.65)

Pump Breaker smoke or fire.

Per TT o Maximize Torus Cooling If contacted to ACKNOWLEDGE request WAIT 3 ATC:

investigate minutes and REPORT The HPCI Aux HPCI Aux Oil

TRIP the A Reactor Recirc pump when directed prior to spraying the Oil Pump has catastrophically failed Pump DW and there are pieces lying about.

BOP: (95.63)

Sprays the Torus

Install Defeat 4 SIMULATOR OPERATOR

Sprays the DW (Critical) (95.65)

VERIFY ET7 goes ACTIVE

Establishes Torus Cooling When drywell sprays are initiated, the

Determines that the B CS pump has tripped, and reports the issue to drywell leak to get worse to overtake all the CRS available high pressure injection sources

Determines that the ACS pump did not automatically start and start the CS pump and report it to the CRS (Critical)

Determines that the HPCI Aux Oil Pump does not restart after HPCI turbine trip TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 22 of 23 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7: CREW: Loss of Non-Essential Power Startup Transformer CRS: (5.08)

Lockout

Enter and direct AOP 304.1, Loss of 4160V Non-Essential Electrical Power ATC:

Start RCIC to maintain reactor water level in the directed band BOP:

o Verify two Well Water Pumps are in service o Verify Well Water Pump 1P-58D secured. In AUTO, verify FC-4414 demand is zero. In HAND, verify speed adjust at 1C373 is zero o Verify GSW Pumps 1P-89A and B in service o Place BUS 1A1 TRANSFER switch in MANUAL o Place BUS 1A2 TRANSFER switch in MANUAL TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 23 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: ALC CREW: Take actions directed by EOP 1/ ALC CRS: (6.74, 6.78)

Enter into the ALC leg of EOP 1

Secures the cooldown if still in progress

Directs ADS locked out

Maximize injection with CRD IAW AIP 407

Inject with SBLC pumps IAW AIP 406

Ensures that there are low pressure ECCS systems available to inject into the RPV

Waits for RPV level to lower to +15 inches

After RPV level lowers to below +15 inches and prior to RPV level lowering to -25, implements the mitigation strategy of Emergency Depressurization (Critical)

ATC: (95.80)

Inform the CRS that RPV level cannot be maintained

Maximize injection with CRD IAW AIP 407

Inject with SBLC pumps IAW AIP 406

Monitor RPV level and reports to Control Room Supervisor BOP:

Reports that the A CS pump had to be manually started

Lockout ADS timers TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 24 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: ALC CREW: Take actions directed by Emergency Depressurization (ED)

CRS: (6.80)

When RPV level has dropped to +15, enter ED

Verify torus level is > 4.5 ft

Open 4 ADS SRVs (Critical)

Directs maximizing injection with low pressure systems

Restore RPV level to 170 to 211 BOP:

Report torus level

Open 4 ADS SRVs (Critical)

EVALUTOR NOTE:

Recognizes that at a reactor pressure of 450 psig, that MO-1905, LPCI The following valves shall be manually Inject did not open and MO-2117, Core Spray Injection Valve failed to opened at or before reactor pressure open, and manually opens both injection valves (Critical) lowers to their respective specified shutoff head pressure values identified in EOP 1.

They are:

Core Spray (MO-2117) at 330 psig

LPCI (MO-1905) at 260 psig

Establishes injection into the RPV with low pressure systems

Restores RPV level to 170 to 211 TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 25 of 26 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the plant has been SIMULATOR OPERATOR emergency Place the Simulator in FREEZE and depressurized Announce that the scenario is and RPV level complete, please stand by your is being stations and do not discuss the restored to the scenario with your crew directed band, and at the direction of the Lead Evaluator,

- - END OF SCENARIO ***

TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 26 of 27 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Trip of 1B09, the A RWS subsystem

2. Trip of the A Well

3. LOCA After EOP Entry:

1. Loss of Condensate and Feed due to the loss of the non-essential busses

2. Failure of automatic injection following ED Abnormal Events:

1. AOP 410 for the loss of 1 subset of River Water Supply

2. AOP 408 for the loss of the D Well

3. AOP 304.1 for the loss of the startup transformer

4. AOP 903 for weather related events Major Transients:

1. LOCA

2. Failure of ECCS to automatically start Critical Tasks:

1. IF the reactor is shutdown under all conditions and RPV level drops to +15, THEN perform Emergency RPV Depressurization before RPV level reaches -25".

2. IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39")

3. BEFORE drywell temperature reaches 280°F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 27 of 28 Facility: Duane Arnold Energy Center Scenario No.: ___3_____ Op-Test No.: 19-1 NRC Examiners: Operators: _____________________________

Initial Conditions/Turnover:

Reactor Power is 50%.

Guarded Equipment: Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room, 1C136 Fuel Pool Cooling Panel, 1B3507 A Fuel Pool Cooling Pump Breaker, 1B4327 B Fuel Pool Cooling Pump Breaker.

Severe weather is expected to enter the area during the shift.

Evolutions in progress or planned for upcoming shift

Complete securing of A RHRSW pump and A side ESW

Raise Power with Recirc to 55%-60% in preparation of putting the B RFP in service Plant PRA/PSA Status including CDF/LERF & color

CDF GREEN - 1.47E-6/ Cumulative Core Damage Probability (CCDP) No Limit

LERF GREEN - 3.92 E-7/ Cumulative Large/Early Release Probability (CLERP) No Limit 2 Reactor Operators are in the Training Center 3 Extra Non Licensed Personnel Available in Work Control Event Malf. Event Event No. No. Type* Description 1 N-BOP Complete securing of A RHRSW pump and A side ESW None N-SRO 2 R-ATC Raise Power with Recirc to 55%-60% from an initial power of 50%

None R-SRO 3 Breaker 1A312, feeder breaker to 1B09 opens on ground fault.

C-BOP Subsequently, a loss of A side RWS occurs. The crew will start 1P-C-SRO ed08m 117B(D) IAW ARP 1C08A, B-6 and AOP 410 Loss of River Water Supply TS-SRO Tech Spec 3.8.7, Condition D 3.7.2 Condition A TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 28 of 28 4 Shortly after the crew enters AOP 903, a lightning strike will result in:

sw21d C-ATC

The Tripping of the A well AOP 408 rr37a C-BOP rr37b C-SRO An additional lightning strike will result in:

cu01a/b TS-SRO

Reactor Water Cleanup Pump Trip TRM 3.3.4 5 A LOCA will develop. The crew will insert a manual scram prior to the DW rr15b M-All reaching 2 psig. The crew will enter EOP 1 on the scram, and when the DW reaches 2 psig, the crew will re-enter EOP 1 and enter EOP 2.

6 On the 2 psig signal; The B CS pump will start and trip.

cs01b C-BOP The A CS pump will fail to automatically start. The A CS pump can be cs05a C-SRO started manually by taking the CS pump HS to the start position.

hp12 The HPCI Aux Oil Pump Feeder Breaker will trip on start and prevent HPCI from injecting 7 On the turbine trip the startup transformer will lockout. The crew will perform the applicable actions of AOP 304.1, Loss of 4160V Non-Essential C-All fw02b Electrical Power.

This will result in a loss of all Condensate and Feed 8 The primary leak will worsen and the crew will perform actions directed by Alternate Level Control and prepare for an Emergency Depressurization.

When RPV level reaches +15, the crew will; C-BOP

Open 4 ADS SRVs

When RPV pressure lowers to 450 psig, the crew will determine that the selected RHR and A CS inject valves did not automatically open, and operator actions are taken to manually open the valves TR-AA-230-1007-F13, Revision 0

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