Text

2019 DAEC Ile Proposed Scenarios
	ML22144A071
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Site:	Duane Arnold
Issue date:	02/22/2019
From:	Randy Baker; NRC/RGN-III/DRS/OLB
To:	; Duane Arnold, NextEra Energy Duane Arnold
	Baker R
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ML17214A865	List: ML22144A067; ML22144A069; ML22144A071; ML22144A073; ML22144A074; ML22144A075; ML22144A076; ML22144A079; ML22145A439;
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TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE, THREE COLUMN SEG Page 1 of 31 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

NRC Exam Scenario #1, Rev. 0 SEG Page 2 of 31 TR-AA-230-1007-F13, Revision 0 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 Objectives:

Evaluation Guide, no tasks are trained.

Prerequisites:

Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator-Certification Training Training Resources:

A. Simulator B. Evaluation Team C. Operations Management Representative D. Simulator Operator E. Booth Communicator

References:

1 TS 3.1.5, Amendment 223 2

ARP 1C05A, Rev. 83 3

AOP 901, Rev. 31 4

EAL-01, Rev. 11 5

AOP 388, Rev. 21 6

TS 3.8.7, Amendment 223 7

TS 3.5.1, AMD 260 8

TS 3.4.1, Amendment 223 9

TS 3.6.1.3, Amendment 223 10 ARP 1C04B, A-1, Rev. 83 11 AOP 255.2, Rev. 46 12 AOP 264, Rev. 14 13 ARP 1C23C, Rev. 55 14 ARP 1C08C, Rev. 62 15 ARP 1C06B, Rev, 64 16 AOP 639, Rev. 36 17 EOP 1, Rev, 20 18 ATWS, Rev. 23 19 EOP 2, Rev, 18 20 RIP 103.2, Rev. 4 21 RIP 102.1, Rev. 9 22 ARP 1C14A, Rev,20 23 OI 151, Rev.71 24 OI 152, Rev, 116 25 ED, Rev, 11 Protected Content:

None

NRC Exam Scenario #1, Rev. 0 SEG Page 3 of 31 Filename: NRC Scenario 1 19-1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 31 Evaluation Method: In accordance with NUREG 1021 Operating Experience:

None Risk Significant Operator Actions:

Control Feedwater Following a Scram Initiate an Emergency Depressurization TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task #

Task Title Annotate risk significant tasks as applicable UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE 0.0 Initial Development for PDA 19-1 License exam N/A See Cover See Cover

NRC Exam Scenario #1, Rev. 0 SEG Page 4 of 31 TR-AA-230-1007-F13, Revision 0 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 6.52 Direct Crew Response to Control RPV Injection prior to, during and subsequent to Emergency Depressurization during ATWS 6.56 Direct Crew Response to Perform /Q to reduce Reactor Power / Scram the Reactor During ATWS 6.06 Direct Crew Response to Perform Reactor SCRAM using Repeated Manual Scram 6.08 Direct Crew Response to Insert Control Rods by Increasing CRD Cooling Flow and Pressure 6.80 Direct Crew Response to Perform an Emergency Depressurization Using SRVs

NRC Exam Scenario #1, Rev. 0 SEG Page 5 of 31 TR-AA-230-1007-F13, Revision 0 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.

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

2.

Raise Rx Power with 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.

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

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)

NRC Exam Scenario #1, Rev. 0 SEG Page 6 of 31 TR-AA-230-1007-F13, Revision 0

9.

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)

10.

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)

11.

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

NRC Exam Scenario #1, Rev. 0 SEG Page 7 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR SET UP INSTRUCTIONS

1. Verify the files listed below are in the scenario file

2. Load the saved IC to a SNAPSHOT

a. Reset to that SNAPSHOT

b. Place the Simulator in RUN OR

3. Reset to IC 23, place the simulator in RUN and perform the following:

a. Insert Event Triggers, Malfunctions, Overrides, and Remotes using Setup.sch or per the tables below

4. Have a second instructor verify:

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

b. Malfunctions

c. Remotes

d. Overrides

5. Place Guarded Equipment tags on: none

6. Verify cycle specific tags:

a. none

7. Place maintenance borders on the locked in annunciators

8. Mark up IPOI 3 to step 4.0 (9) and leave for the crew

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

10. Place copies of OI 856.1 Reactor Manual Control System and IPOI 3 Power Operations on ATCO desk

11. Print copies of STP 3.4.2-03 and STP 3.4.1-02 for availability if requested.

Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist

NRC Exam Scenario #1, Rev. 0 SEG Page 8 of 31 TR-AA-230-1007-F13, Revision 0 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 Value Final Value As dir RD072207 CONTROL ROD ACCUMULATOR TROUBLE-ROD 22-07 3

INACTIVE ACTIVE Set up RP05G HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 0 65 OVERRIDES:

Time OR #

Override Title ET Delay Ramp Initial Value Final Value Set up DI-MS-076 HS-4535 RX WTR LVL LO-LO TRIP OVRRD - A1 NORMAL NORMAL Set up DI-MS-077 HS-4536 RX WTR LVL LO-LO TRIP OVRRD - A2 NORMAL NORMAL Set up DI-MS-072 HS-4427A GRP 1 CHAN A1 ALL SIGNALS OVRRD NORMAL NORMAL Set up DI-MS-074 HS-4427C GRP 1 CHAN A2 ALL SIGNALS OVRRD NORMAL NORMAL REMOTE FUNCTIONS:

Time RF #

Remote Function Title ET Delay Ramp Initial Value Final Value

NRC Exam Scenario #1, Rev. 0 SEG Page 9 of 31 TR-AA-230-1007-F13, Revision 0 KEYPAD FILE:

NRC_Scenario_1.key Key Key Action 1

Delete Malfunction RD072207 2

Insert Malfunction ZZ03 3

Schedule E:\\_PDA19-1NRCScenario_1\\Seal_Oil_Pump_Trip.sch 4

Schedule E:\\_PDA19-1NRCScenario_1\\B_Recirc_Pump_VibTrip.sch 5

Toggle Event 2 6

Schedule E:\\_PDA19-1NRCScenario_1\\Condenser_Tube_Leak.sch 7

Schedule E\\_PDA19-1NRCScenario_1\\ Defeat_12_Install.sch SCHEDULE FILE(S):

SEG_Setup.sch At Time Event Action Description 00:00:00 None Insert malfunction rp05g to 65.00000 HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 00:00:00 None Insert override DI-MS-072 to NORMAL HS-4427A GRP 1 CHAN A1 ALL SIGNALS OVRRD 00:00:00 None Insert override DI-MS-074 to NORMAL HS-4427C GRP 1 CHAN A2 ALL SIGNALS OVRRD 00:00:00 None Insert override DI-MS-076 to NORMAL HS-4535 RX WTR LVL LO-LO TRIP OVRRD -

A1 00:00:00 None Insert override DI-MS-077 to NORMAL HS-4536 RX WTR LVL LO-LO TRIP OVRRD -

A2 00:00:00 None Insert malfunction rd072207 on event 3 CONTROL ROD ACCUMULATOR TROUBLE-ROD 22-07 00:00:01 None Create Event 3 rxqic >= 0.8 -desc Core Power at 80%

00:00:01 None Create Event 5 an_1c06b(1) -desc 1C80 Trouble 00:00:01 None Create Event 7 !rpdis1run(1) -desc MODE SW out of RUN 00:00:01 None Create Event 9 rd_fi -desc All Rods Full In 00:00:01 None Create Event 11 ZDITCBPVJINCR l ZDITCBPVTSTG -desc SEP 307 Attmpt 00:00:02 None Schedule Schedule\\_PDA19-1NRCScenario_1\\Weather.sch

NRC Exam Scenario #1, Rev. 0 SEG Page 10 of 31 TR-AA-230-1007-F13, Revision 0 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) 00:00:01 None Insert remote hv02 from 23 to 27 in 7200 WIND SPEED AT 50 meters (165 ft) 00:00:01 None Insert remote hv03 to 45 in 28800 DEW POINT TEMPERATURE 00:00:01 None Insert remote hv05 to 68 in 28800 AMBIENT TEMPERATURE AT 50 meters (165 ft) 00:00:01 None Insert remote hv06 to 73 in 28800 AMBIENT TEMPERATURE AT 10 meters (35 ft) 00:00:01 None Insert remote hv07 to 73 in 28800 RIVER WATER TEMPERATURE Seal_Oil_Pump_Trip.sch At Time Event Action Description 00:00:00 None Create Event 20 ZDIEGHS3640(4) -desc Emerg Seal Oil Pump HS Start 00:00:00 None Insert Override DO-EG-028 to OFF HS-3641(1) MAIN SEAL OIL PUMP 1P-92 (GREEN) 00:00:00 None Insert Override DO-EG-029 to OFF HS-3641(2) MAIN SEAL OIL PUMP 1P-92 (RED) 00:00:00 None Insert Malfunction AN1C08C(24) to ON 1C08C (D-06) HYDROGEN SEAL OIL MAIN PUMP 1P 92 AUTO TRIP 00:00:00 None Insert Override DO-EG-026 to ON HS-3640(1) EMERGENCY SEAL OIL PUMP 1P-93 (GREEN) 00:00:00 None Insert Override DO-EG-027 to OFF HS-3640(2) EMERGENCY SEAL OIL PUMP 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 None 20 Delete Override DO-EG-026 HS-3640(1) EMERGENCY SEAL OIL PUMP 1P-93 (GREEN)

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

None 20 Delete Malfunction EG08B LOSS OF SEAL OIL PUMP-RSOP None 20 Toggle Event 20 Condenser_Tube_Leak.sch At Time Event Action Description 00:00:00 None Insert malfunction mc07 to 0.90000 MAIN CONDENSER TUBE (1E-7A)

LEAKAGE None 5

Modify malfunction mc07 after 180 from 0.90000 to 2.00000 in 240 MAIN CONDENSER TUBE (1E-7A)

LEAKAGE None 7

Delete malfunction mc07 MAIN CONDENSER TUBE (1E-7A)

LEAKAGE

NRC Exam Scenario #1, Rev. 0 SEG Page 11 of 31 TR-AA-230-1007-F13, Revision 0 Defeat_12_Install.sch At Time Event Action Description 00:00:00 None Insert Remote RP02 to TEST ATWS TEST SWITCH (AKA DEFEAT 12) HS-1863A (RUN,TEST) 00:00:40 None Insert Remote RP03 to TEST ATWS TEST SWITCH (AKA DEFEAT 12) HS-1864A (RUN,TEST)

NRC Exam Scenario #1, Rev. 0 SEG Page 12 of 31 TR-AA-230-1007-F13, Revision 0 SHIFT TURNOVER INFORMATION Day of week and shift o Day shift Today Weather conditions o Cloudy, with a cold front coming in later today Approximately 75 %Pwr, and associated MWe and Core Flow Reactor coolant leakage o Normal Protected train o A o Protected Equipment Spent Fuel Cooling Pumps, Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room 1B35, 1B43, Fuel Pool Pump Breakers, 1C136, Fuel Pool Panel Technical Specification Action statements in effect o None Evolutions in progress or planned for upcoming shift o Alternate EHC Pumps o Raise Power with rods IAW the pull sheet to achieve 80% Reactor Power o Later this shift, Security will be running a force on force drill Plant PRA/PSA Status including CDF/LERF & color o Green-CDF 1.34 E-6/ ICDP to Yellow equal 1 year o Green-LERF 3.27 E-7 ILERP to Yellow equal to 1 year Existing LCOs, date of next surveillance o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o None Comments, problems, operator workarounds, etc.

o Two (2) extra Non-Licensed Operators

NRC Exam Scenario #1, Rev. 0 SEG Page 13 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Alternate EHC Pumps If contacted to verify the non-running EHC Pump is ready for start wait 2 minutes If contacted to verify the B EHC Pump is running sat, Simulator Operator Acknowledge the request Simulator Operator Report the B EHC Pump is ready for start Simulator Operator Report the B EHC Pump is running sat The Crew will perform the actions of OI 693.2, Section 6.2.1 and alternate the EHC Pumps CRS Supervise the evolution BOP Start standby EHC Pump 1P 97B by momentarily placing handswitch HS 3665B in the START position Verify annunciator EHC PUMPS 1P-97A/B BOTH RUNNING (1C07A, C-4) is activated.

Verify the Amps for both EHC Pumps have stabilized At 1C07, stop EHC Pump 1P 97A by momentarily placing handswitch HS 3665A in the STOP position.

Verify all annunciators are reset for the evolution

NRC Exam Scenario #1, Rev. 0 SEG Page 14 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Raise Power with control rod withdrawal The Crew will perform rod withdrawals per IPOI 3 and the current rod sequence sheets to achieve a power level of 80% or at the discretion of the lead evaluator CRS Perform a refocus brief for the evolution Give direction for the power manipulation per IPOI 3 Step to be performed Identification of control rod(s) to be moved Method of rod movement Insert and withdrawal limits (does not apply for rod adjustment sheets)

ATC From the Control Rod Sequence, identify the next rod to be withdrawn, and depress its corresponding Rod Select pushbutton.

Verify that the white ROD OUT permissive light above the Rod Movement Control Switch turns ON Withdraw the rod one notch Repeat as required Monitor Core Parameters as power is changed.

NRC Exam Scenario #1, Rev. 0 SEG Page 15 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE At the direction of the Lead Evaluator, When directed to investigate control rod 22-07 for an accumulator

alarm, Wait 3 min.

then report, Wait 10 min and then report, If called as the RE to see if there are any slow control

rods, Simulator Operator Verify ET 3 is active TRUE This will result in an Accumulator alarm for control rod 22-07.

Simulator Operator Acknowledge the request Simulator Operator The alarm was due to low nitrogen pressure. Pressure is currently 900 psig.

Simulator Operator Click KEYPAD Key 1 This will delete Malfunction RD072207 and clear the 1C05 indication and alarm.

Accumulator 22-07 is recharged to 1090 psig Simulator Operator Acknowledge call and inform the Operator that there are NO slow control rods.

Crew Respond to annunciator 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL RO Check the Full Core Display on 1C05 to determine which accumulator(s) is/are in the trouble condition.

o Determines that the alarm is on Control Rod 22-07 Send an Operator to the accumulators to determine the cause of the alarm Inform the CRS to comply with Technical Specification requirements for Control Rod Scram Accumulators Direct the Second Assistant to either drain the water from the accumulator, or recharge the accumulator CRS (1.02)

Will enter 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.

Call for maintenance support to correct the problem

NRC Exam Scenario #1, Rev. 0 SEG Page 16 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event Earthquake After the CRD accumulator, and at the direction of the Lead Evaluator:

When contacted as any dept. in organization:

Simulator Operator Click KEYPAD Key 2 This will insert Malfunction ZZ03 for DBE Simulator Operator:

Acknowledge the request CREW

Perform the actions directed from AOP 901, Earthquake CRS (5.22)

Direct Crew Response to an Earthquake Condition

IF the amber DESIGN BASIS EARTHQUAKE, or amber OPERATING BASIS EARTHQUAKE lights are ON, and not a malfunction, THEN 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

Changes in jockey fire pump cycling

Core Spray and RHR system pressure

NRC Exam Scenario #1, Rev. 0 SEG Page 17 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If contacted as Duty Station Manager:

If contacted as HP or Chemistry:

If contacted as an NSPEO:

Wait 15 min.

and report, Simulator Operator Acknowledge the request.

Simulator Operator Acknowledge the request.

Simulator Operator Acknowledge the request to perfrom inside and outside plant walkdowns.

Keep track of which operator has been sent to what location in the plant.

Simulator Operator There is no damage in the areas that you have walked down.

CREW Enter and carry out the actions of AOP 901, Earthquake.

RO (94.22)

Respond to an Earthquake Condition Monitor reactor power, pressure, and level on 1C05 Monitor for any Control Rod out of position Verify any heavy loads being handled (within the turbine building or LLRWSF) are landed in safe location At 1C06, verify River Water Supply system integrity by:

o Verify all available RWS pumps will start and deliver >6000 gpm flow o Using HS 4918, RIVER WATER SUPPLY LOOP SELECT switch, select A CV4915 and B CV4914, one at a time, to verify RWS makeup flow can be established with each loop ensuring RWS piping is intact IF ESW is in service, THEN At 1C06, isolate ESW from non-seismic Well Water by closing MO-2039A[B] WELL WATER TO A[B] CHILLER, and MO-2077 [2078] WELL WATER FROM A[B] CHILLER until Well Water piping is verified to be intact.

Monitor Process and Area Radiation Monitoring System channels on Panels 1C10 and 1C11 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.

NRC Exam Scenario #1, Rev. 0 SEG Page 18 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Loss of Main H2 Seal Oil Pump If sent to the H2 Seal Oil Skid, Wait 3 minutes and then report, If asked for the status of the Emergency Seal Oil Pump, Simulator Operator Acknowledge the request Simulator Operator The Main H2 Seal Oil Pump has a sheared shaft.

Simulator Operator Acknowledge the request, and If it is running, report The ESOP is running sat If the ESOP has not been started, report it is ready for start CREW Determine that there is a loss of the Main H2 Seal Oil Pump and take actions per ARP 1C08C (D-6),

CRS Direct the start of the Emergency H2 Seal Oil Pump RO Start the Emergency H2 Seal Oil Pump per the ARP Secure the H2 Seal Oil Vacuum Pump per the ARP Send an operator to the H2 Seal Oil Skid to investigate

NRC Exam Scenario #1, Rev. 0 SEG Page 19 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Hi vibrations and Trip of B Recirc MG When contacted to investigate B Reactor Recirc Pump Hi Vibrations When contacted to investigate B RR pump trip, Wait 2 min and

report, If asked to investigate 1A2 Wait 2 min and report Simulator Operator:

Acknowledge request wait 2 minutes and report All channels are reading 15 mils and stable Simulator Operator:

Report that a B Recirc MG Generator Lockout has occurred. and the B GENERATOR FIELD BREAKER is OPEN.

Simulator Operator:

Report that the B RECIRC MG SET MOTOR BREAKER 1A204 is OPEN CRS Respond to B Recirc Pump Hi Vibrations ARP 1C04B (B-1)

Respond to B Recirc pump trip per ARP 1C04B (A-1) and AOP 264, Loss of Reactor Recirculation Pump(s)

CRS Direct the actions for Hi Vibrations on B RR Pump Notify System Engineering of Hi vibration condition Direct the actions of AOP 264, Loss of Reactor Recirculation Pump(s), be performed RO Dispatch operator to 1C466C to investigate Hi Vibrations At 1C21 Check Recirc Pump temperature recorder TRS 4600 for increasing B Recirc Pump bearing temperatuers Enter AOP 264 and perform concurrently with this ARP.

Verify the AUTOMATIC ACTIONS have occurred:

A RECIRC MG SET MOTOR BREAKER 1A204 is OPEN.

A GENERATOR FIELD BREAKER is OPEN.

Determine the cause of the tripped Recirc Pump as follows:

At 1C04, monitor associated alarms.

Send an Operator to 1C113B in the MG Set Room to monitor relays.

Momentarily place A RECIRC MG SET MOTOR BREAKER 1A204 handswitch in the STOP position to achieve GREEN FLAG status.

NRC Exam Scenario #1, Rev. 0 SEG Page 20 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Trip of Recirc continued CREW Perform the actions of AOP 255.2, Power/Reactivity Abnormal Change RO (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 Verify thermal limits on the Official 3D Case When power is stabilized, plot location on the Stability Power / Flow Map 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 Direct inserting rods per IPOI 3

NRC Exam Scenario #1, Rev. 0 SEG Page 21 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Trip of Recirc continued If contacted as organization:

Simulator Operator Acknowledge the request CREW Perform the actions of AOP 264, Loss of Recirc Pump (s)

RO (94.58)

Stabilize reactor water level between 186 and 195.

For the Recirc Pump that tripped, perform the following:

Verify open A RECIRC PUMP DISCH BYP valve MO-4629.

Close A RECIRC PUMP DISCHARGE valve MO-4627.

Plot operating point on Power/Flow map.

For the Recirc Pump that tripped, after 5 minutes, reopen A RECIRC PUMP DISCHARGE valve MO-4627 If core thermal power is greater than (>) 60% (1147 MWth), then insert control rods as directed by the CRS to maintain power less than or equal to () 60.0% (1147 MWth).

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.

Direct STP 3.4.1-02 Single Loop Operation.

Direct STP 3.4.2-03 Daily Jet Pump Operability Single Loop Operation.

Contact organization for assistance

NRC Exam Scenario #1, Rev. 0 SEG Page 22 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the actions of the Earth Quake are under control, the plant is stable and / or at the direction of the Lead Evaluator, When called on to investigate the alarm on

1C80, Wait 3 min and

report, Simulator Operator Set ET 5 to TRUE Verify that when 1C06B A-1, 1C-80 trouble alarms, that ET 11 goes true This will start a condenser Tube leak, and when ET 11 goes true, it will drive the crew to insert a manual scram Simulator Operator Acknowledge the request 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.

Simulator Operator Report that the alarm was the Influent High conductivity alarm, and it is currently reading _____ from GD 24 Simulator Operator The only action of annunciator on 1C80 at power operation is to enter AOP 639, Reactor Water/Condensate High Conductivity The Crew will respond to annunciator 1C06B A-1, Condensate Demin Panel 1C-80 trouble and perform the following actions; RO (94.18)

Send an Operator to 1C80 to investigate Based on the report, the crew will enter AOP 639, Reactor Water/Condensate High Conductivity.

SRO (5.18)

Direct entry in AOP 639, Reactor Water/Condensate High Conductivity Review Action Levels contained in PCP 1.9RX or PCP 1.9FW PCP 1.9RX actions are on page 27.

Monitor conductivity monitoring points listed in above note and refer to PCP 1.9RX - Attachment 10, to determine the source of high conductivity IF Condenser tube leak is suspected, THEN Direct Engineering &

Maintenance to evaluate which loop is leaking IF a valid Condensate Demineralizer Influent Conductivity reading of greater than or equal to 1.0 mho/cm (CRS-1514 Pt 1 or 7 at 1C06 or CIT 1704 at 1C80) is received and is not due to condensate system startup or plant startup, THEN Reduce Reactor Recirc flow to 39 Mlbm/hr per IPOI 4, Fast Power Reduction AND SCRAM

NRC Exam Scenario #1, Rev. 0 SEG Page 23 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Condenser Tube Leak When called as chemistry, When contacted as the system

engineer, If asked to monitor conductivity at other places in the plant, When CE1516A is called up, Simulator Operator Acknowledge the request and state that it will take about an hour and a half to get the sample.

Simulator Operator Acknowledge the request and inform the control room that you will review the information from PI and get back to them with a recommendation Simulator Operator Acknowledge the request Call up the conductivity monitor 1514 on THUNDERVIEW from panel 1C06, and monitor point CE1516A.

Simulator Operator call the control room and report the conductivity reading Based on the report, the crew will enter AOP 639, Reactor Water/Condensate High Conductivity, and take the following action; RO Observe chart recorder CRS-2738 CLEANUP INFLUENT CONDUCTIVITY at 1C04 to determine the trend of reactor coolant conductivity Direct Plant Chemistry Department to sample as necessary, reactor water condensate, Hotwell, CSTs and makeup demin system to verify any high conductivity levels identified in Steps 1 and 3 IF a suspected loop has been identified, and it is recommended that the loop be isolated, THEN Isolate the suspected leaking Condenser Circ Water loop per OI 442 IF condensate demineralizer influent conductivity is greater than 0.1 mho/cm, THEN maintain the filter demineralizer bypass valve MO-1708 closed IF a valid Condensate Demineralizer Influent Conductivity reading of greater than or equal to 1.0 mho/cm (CRS-1514 Pt 1 or 7 at 1C06 or CIT 1704 at 1C80) is received and is not due to condensate system startup or plant startup, THEN Reduce Reactor Recirc flow to 39 Mlbm/hr per IPOI 4, Fast Power Reduction AND SCRAM

NRC Exam Scenario #1, Rev. 0 SEG Page 24 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Tube leak continued If asked to monitor other Conductivity

points, Wait 3 min and

report, Floor Instructor Per a definition in PCP 1.9RX, a micro S/cm = micro mho/cm Simulator Operator Acknowledge the request Simulator Operator Using information from GD 24, report consistent conductivity readings PCP 1.9RX actions.

The CRS will direct and the STA and SM will perform the following actions IAW PCP 1.9RX:

Based on the tables, determine that the plant is in an Action Level 2 condition o Write a CR o If not out of action level 2 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , begin a plant shutdown

NRC Exam Scenario #1, Rev. 0 SEG Page 25 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Scram on main condenser conductivity Crew inserts a manual scram based on the condenser out let conductivity being greater than 1 micro mho, and performs the following actions; RO Inserts manual scram o Reports that there is a Hydraulic ATWS o Reports Reactor Power CRS (6.56)

Enters EOP 1 and with the concurrence of the SM Transitions to ATWS Per ATWS directs the following; o Lockout ADS (Critical) o Install Defeat 15 o Directs the ATWS QRC RO (95.57)

Lockout ADS (Critical)

Install Defeat 15 Performs ATWS QRC o Reports that the ATWS QRC is complete, with the exception of SBL Control o Reports reactor power

NRC Exam Scenario #1, Rev. 0 SEG Page 26 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Scram and ATWS If directed to install Defeat 12, Wait 3 min and perform the action, then report to the control room, Simulator Operator Acknowledge the request Simulator Operator Set ET 7 to TRUE. Note that there is a 40 second time delay This will place the ATWS RPT switches in the TEST position Call the control room and inform them that you have installed Defeat 12 SRO Directs the initiation of SBLC Directs the Hydraulic ATWS RIPS (Critical) (6.08, 6.06)

Assess reactor power o

If reactor power is > 5%, the crew will enter power level control (Critical)

Directs to secure and prevent injection from, Condensate and Feed, HPCI, RHR, CS Inform at an RPV level of 87 If conditions allow RPV injection, maintain RPV level > -25 RO Initiates SBLC Performs the ATWS RIPS (Critical) (95.06, 95.08) 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 dP increase on PDI-1832A Throttle open MO-1830, DRIVE WATER P CONTROL, as necessary to maximize cooling water flow and pressure 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 (Critical) o If directed for power level control, secure and prevent injection from, Condensate and Feed, HPCI, RHR, CS.

o Inform the CRS when level reaches 87 o

If directed, maintain RPV level > -25

NRC Exam Scenario #1, Rev. 0 SEG Page 27 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When all rods are full in Crew determines that all control rods are inserted SRO 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 RO 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

NRC Exam Scenario #1, Rev. 0 SEG Page 28 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EOP 2 and lowering Torus level.

When directed to the Torus area to determine where the leak is, Wait 4 min and

report, Simulator Operator Acknowledge the request Simulator Operator There is a lot of water flowing out of a cracked pipe right at the torus. The cracked pipe is the A CS suction line The crew determines that Torus Level is lowering, and perform the following actions; SRO (6.65)

Direct the following actions from EOP 2 o Obtain a round of Primary Containment Parameters Determine that Torus level is lowering Direct that torus level e raised by:

o Core Spray, OI 151 (Critical) Before 7.1 feet o Perform an Emergency Depressurization RO Deliver a round of Primary Containment Parameters o Attempt to raise torus water level; With Core Spray IAW OI 150 Report that Torus level is lower than expected for this condition RO 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 Operating Limit.

NRC Exam Scenario #1, Rev. 0 SEG Page 29 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to open the CS manual valves, V-21-01 and 02, Wait 4 min and

report, When directed to go to the other CS, Wait 4 min and

report, If sent to find the bolt cutter for the initial

valve, Simulator Operator Acknowledge the request Simulator Operator You are at the directed valve, but you cannot get the lock to work. You have to go and find a bolt cutter to get the chain off of the handwheel.

Simulator Operator Acknowledge the request Simulator Operator You attempted to open the CS valve, but it was hard to turn. While you were attempting to open it, there was a loud cracking sound, and now the valve handwheel spins freely Simulator Operator Acknowledge the request, but you will never find a bolt cutter RO EOP 2 actions continued o Attempt to raise torus water level; With the CS system Monitor CST level on 1C06 Verify that the CS outboard and inboard torus suction valves are open Unlock and open V-21-01, for A CS, and V-21-02, for B CS, as necessary.

(Critical) When the crew determines that they cannot maintain torus level above 7.1 feet, and BEFORE 7.1 feet in the torus, the crew will perform an Emergency Depressurization and take the following actions; SRO (6.80)

Directs that ED be entered Directs the following from ED o Verify CV 4371A is overridden o Verify torus level is above 4.5 o Open 4 ADS SRVs BEFORE Torus level is below 7.1 (Critical) o Maintain RPV level using CS or RHR RO (95.80)

Verify CV 4371A is overridden 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

NRC Exam Scenario #1, Rev. 0 SEG Page 30 of 31 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the ED has been performed and RPV level is being restored to the directed band, and at the direction of the Floor Instructor, Simulator Operator Place the simulator in FREEZE.

Floor Instructor Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

- - END OF SCENARIO ***

NRC Exam Scenario #1, Rev. 0 SEG Page 31 of 31 TR-AA-230-1007-F13, Revision 0 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 3

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. Lockout ADS

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:

Manual scram signal

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 SIMULATOR EXERCISE GUIDE, THREE COLUMN SEG Page 1 of 28 SITE:

DAEC Revision #: 0 LMS ID:

NRC Exam 19-1 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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 2 of 28 TR-AA-230-1007-F13, Revision 0 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 Objectives:

Evaluation Guide, no tasks are trained Prerequisites:

Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator-Certification Training Training Resources:

A. Simulator B. Evaluation Team C. Operations Management Representative D. Simulator Operator E. Booth Communicator

References:

1. AOP 301, Rev. 73

2. AOP 411, Rev. 29

3. ARP 1C03A, Rev. 62

4. ARP 1C06A, Rev. 75

5. ARP 1C06B, Rev. 65

6. ATWS, Rev.23

7. ED, Rev. 11

8. EOP 1, Rev. 20

9. EOP 3. Rev. 22

10. IPOI 5 QRC 1, Rev. 6

11. SEP 307, Rev. 4

12. TS 3.5.1, AMD 223 Protected Content:

None

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 3 of 28 TR-AA-230-1007-F13, Revision 0 Evaluation Method: In accordance with NUREG 1021 Operating Experience:

None Risk Significant Operator Actions:

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

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE REVIEWER DATE 0

Changed form number to match new industry SAT procedure which superseded TR-AA-230-1003.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 4 of 28 TR-AA-230-1007-F13, Revision 0 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 95.68 Perform Actions of EOP 3 for High Area Temperature, Radiation, and Water Level including 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 95.48 Rapidly Depressurize the RPV via the Main Turbine Bypass Valves 95.55 Perform initial ATWS actions (/)

95.95 Initiate ATWS/ARI 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 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 6.67 Direct Crew Response for performance of EOP 3 for high area temperatures/radiation /water 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 6.48 Direct Crew Response to Rapidly Depressurize the RPV via the Main Turbine Bypass Valves 6.55 Direct Crew Response to Perform Initial ATWS Actions (/)

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 5 of 28 TR-AA-230-1007-F13, Revision 0 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.

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

2.

Reduce Rx Power with Rods IAW LLA to 95% RTP

3.

After the completion of the power adjustment, the A Core Spray pump will receive an inadvertent start signal.

When the crew investigates, they will determine that relay E21-K12A has failed resulting in the Core Spray pump start.

When the Core Spray HS is taken to STOP, the Amber disagreement light will light, indicating that the A Core Spray pump will not automatically start if an initiation signal were to come in.

4.

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.

5.

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

6.

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.

7.

A lightning strike in the DAEC yard will result in the following; A trip of the B GSW pump.

A trip of the C RBCCW pump.

8.

On 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.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 6 of 28 TR-AA-230-1007-F13, Revision 0 The Crew will also enter AOP 411 GSW Abnormal Operation.

9.

On the trip of the C RBCCW pump, the Crew will momentarily 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.

10.

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.

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)

11.

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.

12.

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.

13.

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.

14.

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)

15.

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

16.

The Scenario will be completed when the plant has been depressurized and RPV level is being restored to the directed band.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 7 of 28 TR-AA-230-1007-F13, Revision 0 SIMULATOR SET UP INSTRUCTIONS General Instructions

a.

Reset to IC (1) This IC was derived from IC 20, 100% power..

(2) The attached malfunctions, remote functions overrides and Event triggers were inserted

b.

Actuate event triggers, malfunctions, overrides, remote functions, local operator actions, simulator lesson files, etc. as needed for setup as listed below.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 8 of 28 TR-AA-230-1007-F13, Revision 0 EVENT TRIGGER DEFINITIONS:

Trigger No.

Trigger Logic Statement Trigger Word Description 1, 2, 5, 7,19 Manually Activated Manually Activated 9

zlotctrip Turbine Trip Light ON 11 zdicuhs2701(1)

MO 2701 taken Closed 13 zdiswhs4904a(4)== 1 A GSW pump to start 21 Rd_fi All Rods In 23 zloadhs4406(2)

Red light on psv 4406 on 25 zdicshs2103(1)

A CS HS taken to stop MALFUNCTIONS Time Malf. No.

Malfunction Title Delay Ramp ET Initial Value Final Value As dir CS01a CORE SPRAY PUMP TRIP-CORE SPRAY PUMP A TRIP 5 sec 19 Inactive Active As dir AN1C06A(17) 1C06A (B-04) GSW AUTO FILTER HI dP 10 sec 13 CRYWOL F

ON As dir sw10c RBCCW PUMP TRIP-PUMP C 1

INACTIVE ACTIVE As dir Sl07 SBLC TANK 1T218 LEAK 2 min 2

0 100 Set up SW37A GSW PUMP 1P89A FAIL TO AUTO-ACTUATE ACTIVE ACTIVE Set up stsw01a RBCCW PUMP 1P81A FAIL TO AUTO-START ACTIVE ACTIVE Set up cu11a MO2700 THERMAL OVERLOAD BREAKER TRIPI INACTIVE ACTIVE Set up cu11b MO2701 THERMAL OVERLOAD BREAKER TRIP Set up ms28b GROUP 5 ISOLATION VALVE(S) FAIL(S) TO CLOSE-MO2701 ACTIVE ACTIVE Set up Cu07 RWCU LEAK IN HEAT EXCHANGER ROOM (VI) 3 min 5

0 1.5 Set up Cu05 TEMPERATURE TRANSMITTERS 2742G,J,H,K FAILURE 5 min 7

As Is 80 Set up ed08d 4.16 KV/480V BUS FAULT-BUS 1A4 9

INACTIVE ACTIVE Set up rp05a RPS SCRAM CIRCUIT FAILURE (ATWS)- AUTO SCRAM FAILURE ACTIVE ACTIVE

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 9 of 28 TR-AA-230-1007-F13, Revision 0 Time Malf. No.

Malfunction Title Delay Ramp ET Initial Value Final Value Set up rp05b RPS SCRAM CIRCUIT FAILURE (ATWS)- MANUAL SCRAM FAILURE ACTIVE ACTIVE Set up rp05d RPS SCRAM CIRCUIT FAILURE (ATWS)- RPS FUSE REMOVAL FAILURE ACTIVE ACTIVE Set up rp05e ALL INDIVIDUAL ROD SCRAM SWITCHES FAIL ACTIVE ACTIVE Set up rd020227 CONTROL ROD BLADE STUCK-ROD 02-27 ACTIVE ACTIVE As dir Cu05 TEMPERATURE TRANSMITTERS 2742G,J,H,K FAILURE 5 min 23 80 43 As dir rm02re7606b RE-7606B REAC BLDG MAIN EXHAUST B 21 As Is 100 As dir CS01A CORE SPRAY PUMP TRIP-CS PUMP A TRIP 5 sec 19 Inactive OVERRIDES Time OR No.

Override Title Delay Ramp ET Initial Value Final Value Set up DI-TC-009 BPVJINCR BYPASS VALVE OPENING JACK, INCREASE TRANSI

/OFF TRANSI/

OFF As dir DI-CU-002 HS-2701 REAC WTR C/U ISOL MOV-2701 (CLOSE,NORM,OPEN) 11 NORM OPEN As dir DO-CU-003 HS-2701(1) RWCU ISOL MOV-2701 (GREEN) 11 OFF OFF As dir DO-CU-004 HS-2701(2) RWCU ISOL MOV-2701 (RED) 11 ON OFF As dir DO-CU-027 MO-2701(1) RWCU SYS ISOL VLV-OUTBD (GREEN) 11 OFF OFF As dir DO-CU-028 MO-2701(2) RWCU SYS ISOL VLV-OUTBD (RED) 11 ON OFF Set up DI-AD-015 HS-4402 ADS PSV4402,B MSL,1130 PSI (AUTO,OPEN)

AUTO AUTO Set up DI-AD-017 HS-4405 ADS PSV4405,C MSL,1140 PSI (AUTO,OPEN)

AUTO AUTO As Dir DI-RM-024 PB-7606B B GROUP 3 INITIATION 21 OFF ON

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 10 of 28 TR-AA-230-1007-F13, Revision 0 REMOTE FUNCTIONS Time RF. No.

Remote Function Title Delay Ramp ET Initial Value Final Value As dir SW32 MAN OPER OF 'B' GSW PUMP (1P-89B BREAKER) 1 NORM OPEN As dir SW10 GSW DISCHARGE TO COOLING TOWERS V-11-69 5 min 13 100 50 As dir CS03a MANUAL OPER OF 'A' CS PUMP (1P-211A BREAKER) 19 NORM CLOSE

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 11 of 28 TR-AA-230-1007-F13, Revision 0 SHIFT TURNOVER INFORMATION Day of week and shift o Day Shift Today Weather conditions o Cloudy, with a cold front coming in later today Approximately 100% reactor power with the associated MWE and Core Flow Reactor Coolant Leakage:

o Normal Protected train o A o Protected 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.

o Time to 200° F is 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months .

Technical Specification Action statements in effect o None Evolutions in progress or planned for upcoming shift 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.

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 None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o None Comments, problems, operator workarounds, etc.

o Two (2) extra Non-Licensed Operators

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 12 of 28 TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 13 of 28 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew assumes the

watch, When contacted as in plant operator to verify Stator Cooling Pump suction valve is OPEN If asked to report status of Stator Water Cooling pump Simulator Operator Report: V-45-13 B Stator Water Cooling Pump suction isolation valve is OPEN Simulator Operator Report: B Stator water cooling pump is operating normally.

The Crew will Shift Stator Water Cooling Pumps in accordance with OI 697 Stator CRS Direct RO to Swap Stator Water Cooling pumps in accordance with OI 697 Generator Stator Cooling Water system BOP Verify B Stator Cooling Pump 1P91B suction valve V-45-13 is OPEN Start B Stator Cooling Pump 1P91B by momentarily placing its Handswitch to RUN on 1C08.

Annunciator 1C08C D-4 H2/Stator Cooling panel Trouble alarms due to reserve pump running Verify both pumps are running Stop the A Stator Cooling Pump 1P91A by placing switch to STOP position momentarily 1C08C D-4 H2/Stator Cooling panel Trouble should clear

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 14 of 28 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE The Crew will reduce reactor power with rods to achieve 95%

The Crew will perform rod insertions in the reverse sequence of the rod movement control sheets to achieve a power level of 95% or at the discretion of the lead evaluator CRS Perform a refocus brief for the evolution Give direction for the power manipulation per IPOI 3 Step to be performed Identification of control rod(s) to be moved Method of rod movement Insert and withdrawal limits (does not apply for rod adjustment sheets)

OATC From the Control Rod Sequence, identify the next rod to be inserted, and depress its corresponding Rod Select pushbutton.

Verify that the white ROD OUT permissive light above the Rod Movement Control Switch turns ON Withdraw the rod one notch Repeat as required Monitor Core Parameters as power is changed.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 15 of 28 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE At the direction of the Lead Evaluator, If contacted as the in plant operator to investigate 1A3 switchgear room report Simulator Operator Set Event Trigger 19 to True This will give the A CS pump an inadvertent initiation signal. The pump will then TRIP 5 seconds after starting.

Floor Evaluator Report: Breaker The Crew will respond to annunciator 1C03A, A-8, A Core Spray System Auto Initiated.

BOP will Determine that Drywell pressure is not > 2 psig Determine that RPV level is not < 64 Determine that the CS pump should not have initiated.

May go to 1C43 to investigate the status of the 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 place HS 2103, A Core Spray pump in the Stop position to secure the Core Spray Pump.

Identify that the Core Spray Amber Disagreement light is still lit.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 16 of 28 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE TS and Risk for the Inoperable Core Spray Pump.

If called as the Second Assistant to vent the CS

system, Wait 5 min and call the control room and

report, When directed to vent the CS

system, Simulator Operator Acknowledge the request.

Then Call up RF CS05, Manual CS A vent valve. On THUNDERVIEW, monitor the PI 2106, on 1C03, panel 2_B Simulator Operator You are standing by the CS vent valve, you have you venting rig attached, and are ready to vent the A CS system.

Simulator Operator Set RF CS05 to OPEN. The RF box will close, Open it up again and AS SOON AS the CS Hi discharge pressure alarm, 1C03A C-9, clears SET RF CS05 to CLOSE BOP May vent Core Spray per OI 151 Core Spray System o Direct an in-plant Operator to vent the Core Spray system per Section 8.1 Identify that the Core Spray Amber Disagreement light is still lit.

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 17 of 28 TR-AA-230-1007-F13, Revision 0 SBLC Leak At the direction of the Lead Evaluator, If directed to investigate the SBLC leak wait 3 minutes and report the following If directed to CLOSE V 01 Simulator Operator Set Event Trigger 2 to True This will cause a leak from 1T218 to be developed. SBLC Storage tank level will lower until the Low Level alarm comes in.

Simulator Operator The leak is downstream of V-26-01 SBLC Storage Tank 1T218 Outlet Isolation Simulator Operator Wait 1 minutes then DELETE mf sl07 Report the following: V-26-01 is directed SBLC Storage Tank 1T218 Outlet Isolation has been closed.

The Crew will respond to annunciator 1C05A, E-3, SBLC Tank HI/LO Level OATC will Determine that SBLC Tank Level is lowering Report to the CRS Tank Level and Trend Direct an In-plant Operator to investigate the SBLC skid CRS will Direct V-26-01 to be closed when location of the leak is known Determine both SBLC subsystems are INOPERABLE Enter LCO 3.1.7 Condition B restore 1 subsystem to OPERABLE within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 18 of 28 TR-AA-230-1007-F13, Revision 0 At the direction of the Lead Evaluator, When ET 1 is set to True call the CR and

report, When contacted to investigate B GSW Breaker

1A409, Wait 2 minutes and report, When sent to investigate the auto strainer or the B GSW

Pump, Wait 4 min then report Simulator Operator Set ET 1 to TRUE This will trip the B GSW Pump, C RBCCW pump, and throttles closed the GSW discharge to the cooling towers.

Verify ET 13 goes true on the start of the A GSW pump Simulator Operator A lightning bolt just hit in the yard near warehouse Simulator Operator Acknowledge Request Simulator Operator Report that there is a ground fault flag (Relay 409-150G) on breaker 1A409.

Simulator Operator Acknowledge Request Simulator Operator The B GSW motor is warm to the touch but nothing else is abnormal.

The GSW strainer, 1S-24, is turning, PDIS-4906 is reading 5 psid and lowering.

The crew will respond to Annunciator 1C06A, B-3 and C-4 and take the following actions; BOP IAW ARP 1C06A B-3 o At 1C06, confirm Service Water Pumps Discharge Header Press low on PI-4903 GSW PUMPS DISCH HDR PRESS o Verify auto start of the standby pump.

Determine that the A GSW pump did not automatically start.

Start the A GSW pump o Shortly after the start of the A GSW pump, the crew will respond to annunciator 1C06A B-4, GSW AUTO FILTER HIGH P o Send and operator to the GSW strainer 1S-24 to verify high differential pressure on PDIS-4906.

o Inform the CRS that AOP 411 is referenced in the ARP CRS Direct actions of ARP 1C06A B-3, B-4, C-4, and AOP 411 (Loss of GSW). (5.16)

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 19 of 28 TR-AA-230-1007-F13, Revision 0 GSW After the report on the previous page, wait 2 min and, If sent to adjust Turbine Lube

Oil, Wait 2 min, Simulator Operator Delete Malfunction AN1C06A(17),

1C06A (B-04) GSW AUTO FILTER HI dP Simulator Operator Acknowledge the request Simulator Operator Insert Remote Function SW 14 and raise the current setting by increments of 3 until the LO temperature begins to turn (should return to normal around

40)

Keep monitoring the Turbine Lube Oil temperature and adjust as necessary.

CREW Perform actions per ARP 1C06A B-3, B-4, C-4, and AOP 411 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.

OATC 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 Loss of the C RBCCW pump If sent to investigate the C RBCCW pump and

breaker, Wait 3 min and

report, Simulator Operator Acknowledge the request Simulator Operator The C RBCCW pump breaker is warm and in the trip free position. The pump seems normal, The A RBCCW pump is running Sat.

The Crew will respond the annunciator 1C06B D-3, RBCCW Pump Disch Header Lo Pressure alarm BOP Confirm the low pressure condition on PI-4821 and/or Computer Contact Point M508 Normally two pumps are in operation, confirm that A, B & C RBCCW PUMPS 1P-81A, B & C are all running If any pump fails to start, attempt to start that pump ONCE using the following control switch; o HS-4829 A RBCCW PUMP 1P-81A

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 20 of 28 TR-AA-230-1007-F13, Revision 0 RWCU Hx room leak.

At the direction of the Lead Evaluator, If the crew actions appear to be keeping the RWCU Hx room from reaching a Max Safe temperature, If sent to attempt to reset the thermal overload on 1B3219, Wait 2 min and

report, Simulator Operator Set ET 5 to TRUE This will start a leak in the RWCU Hx room Lead Evaluator Simulator Operator Raise the severity of MF CU07, RWCU Leak in Hx Room, in increments of 0.1 with a 30 second ramp.

Simulator Operator Acknowledge the request Simulator Operator I have reset the thermal overload for MO 2700 on breaker 1B3219.

The Crew will respond to Annunciator 1C04B B-4, Steam Leak Detection Ambient High Temperature, and perform the following Actions, BOP

Go to 1C21 and determine that the leak is from RWCU Hx room

Maximize plant ventilation IAW OI 734, QRC1, Maximize Plant Ventilation o Start 1V-EF-1, 1V-EF-2, and 1V-EF-3 MAIN PLANT EXHAUST FANS and verify their respective dampers indicate OPEN o Start the Reactor Building Exhaust Fans o Start the Reactor Building Supply Fans OATC

Verify Automatic Actions o Determine that MO 2700, the RWCU Inboard Isolation Valve did not close, and has a thermal overload on the breaker Send someone to 1B3219 to attempt to reset the thermal overload o Determine that MO 2701 did not close and attempt to close the valve When the HS for MO 2701 is taken to the close position, all indication for MO 2701 is lost Will report to the CRS that MO 2701 is not closed

Prompt the CRS that this is an EOP 3 entry

Insert a manual reactor scram prior to reaching a Max Safe Operating Temperature Limit in the RWCU Hx room. (Critical)

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 21 of 28 TR-AA-230-1007-F13, Revision 0 RWCU Hx room leak continued When the Operator attempts to close MO 2701, If sent to attempt to investigate 1D42 ckt 04 for MO 2701, Wait 2 min and

report, Simulator Operator Verify that Event Trigger 11 goes True This will result in the loss of all indication for MO2701, and the valve will remain open.

Simulator Operator Acknowledge the request Simulator Operator There is an acrid odor near 1D4204, and the breaker door is warm to the touch In response to the leak in the RWCU Hx room CRS (6.67)

Enter EOP 3 and direct the following o Operate available coolers in the affected area o Operate available main plant supply and exhaust fans Maximize plant ventilation IAW OI 734, QRC1, Maximize Plant Ventilation o Attempt to isolate the leaking system Determines that RWCU will not isolate due to the thermal overload on MO 2700 Direct that the thermal overload condition be reset and the valve closed Determine that MO 2701 did not isolate, and send an Operator to 1D4204 to investigate o Determine that a pressure reduction will decrease leakage into secondary containment 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 reactor scram o Insert a reactor scram prior to reaching a Max Safe Operation Limit in the RWCU Hx room. (Critical)

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 22 of 28 TR-AA-230-1007-F13, Revision 0 Reactor Scram ATWS CRS will perform the following:

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 The ROs will perform the following: (95.55)

Lock out ADS Install Defeat 15 Per the ATWS QRC o Verify the MODE Switch is in SD o FW Master Controller in Auto and set at 158.5 o HSS-4450 in 1 element o Recirc run back to minimum o Initiate ARI (critical) (95.95) o Verify Recirc Pumps trip 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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 23 of 28 TR-AA-230-1007-F13, Revision 0 Re-entry to EOP 1 When the turbine trips, Simulator Operator Verify Event Trigger 9 goes True This will result in the lock out of 1A4 CRS Exits ATWS and returns to EOP 1 and directs the following actions; (6.45)

Per EOP 1 o Restore and maintain RPV level to 170 to 211 o Install defeat 11 o Establishes an RPV pressure band of 800 psig to 1055 psig 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 RO will perform the following actions; (95.46)

Trip the main turbine Install defeat 11 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. (95.47)

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 24 of 28 TR-AA-230-1007-F13, Revision 0 Loss of 1A4 The crew will respond to the lock out of 1A4,and perform the actions of AOP 301, Loss of Essential Electrical Power CRS will direct the performance of AOP 301 for the loss of 1A4 (5.36)

The BOP will perform the following actions of AOP 301, Loss of Essential Electrical Power (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.

Prompt CRS to enter AOP 358 to restore RPS Send an operator to investigate 1A4 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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 25 of 28 TR-AA-230-1007-F13, Revision 0 When the actions of AOP 301 have been directed, and at the direction of the Lead Evaluator, If the temperature in the RWCU Hx room has fallen below Max

Safe, Simulator Operator Set Event Trigger 7 to TRUE This will begin the leak above the TIP room.

Simulator Operator Modify Malfunction CU07 by increments of 0.1 until the area has gone above Max Safe again The Crew will respond to the rising temperatures above the TIP room and continue in the actions of EOP 3; CRS

Direct that the Defeat 9 be installed to maximize cooling to the reactor building

If the temperature rise above the TIP room is identified early enough, the CRS will direct the crew to anticipate Emergency Depressurization o

Direct the performance of SEP 307, Rapid Depressurization with Bypass Valves. This will be unsuccessful as the Turbine Bypass Valve Jack will not engage.(6.48)

Wait until two areas exceed Max Safe

When two areas exceed Max Safe, enter ED BOP o

Determine that RM 7606B REACTOR BUILDING VENT SHAFT RAD MONITOR is failed upscale and cannot be reset preventing Defeat 9 from being installed.

o Verify torus level is > 4.5 ft o

Open 4 ADS SRVs (Critical)

Receive the report from 1C03, that 3 ADS SRVs opened, and 1 LLS SRV has opened OATC o

Maintain RPV level using Condensate and Feed, CS or RHR during the ED o

Restore RPV level to 170 to 211 BOP (95.68)

Install Defeat 9 to maximize reactor building ventilation (UNSUCCESSFUL)

Perform SEP 307, Rapid Depressurization with Bypass Valves.

(UNSUCCESSFUL)

Report Torus level Report to the CRS that 3 ADS SRVs opened, and 1 LLS SRV opened.

Place Torus Cooling in service

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 26 of 28 TR-AA-230-1007-F13, Revision 0 The Scenario will be complete when the RPV is depressurized and RPV level is being restored, and at the direction of the Lead Evaluator Simulator Operator Place the simulator in FREEZE.

Floor Instructor Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

- - END OF SCENARIO ***

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 27 of 28 TR-AA-230-1007-F13, Revision 0 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 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. 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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 28 of 28 TR-AA-230-1007-F13, Revision 0 CREW GRADING ATTACHMENT ESG ______ Rev. __0____

Date ________________

Operator Name Position Evaluator CRS ATC BOP Management Representative/Lead Evaluator ______________/________________

Crew Critical Tasks Task Statement SAT UNSAT

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. 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 SIMULATOR EXERCISE GUIDE, THREE COLUMN SEG Page 1 of 24 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

NRC Scenario 3, Rev. 0 SEG Page 2 of 24 TR-AA-230-1007-F13, Revision 0 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 Objectives:

Evaluation Guide, no tasks are trained Prerequisites:

Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator-Certification Training Training Resources:

A. Simulator B. Evaluation Team C. Simulator Operator D. Booth Communicator

References:

1. ARP 1C08A, Rev. 98

2. AOP 410, Rev. 30

3. TS 3.8.7, AMD 223

4. TS 3.7.2, AMD 223

5. AOP 903, Rev, 59

6. ARP 1C04A, Rev. 64

7. ARP 1C23C, Rev. 55

8. AOP 408, Rev. 32

9. AOP 255.2, Rev. 48

10. AOP 304.1, Rev.60

11. EOP 1, Rev, 20

12. EOP 2, Rev, 18

13. OI 644 QRC 1, Rev. 8

14. ED Rev. 11 Protected Content:

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

None

NRC Scenario 3, Rev. 0 SEG Page 3 of 24 Filename: NRC Scenario 3 19-1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 24 Risk Significant Operator Actions:

Initiate RPV Emergency Depressurization

NRC Scenario 3, Rev. 0 SEG Page 4 of 24 TR-AA-230-1007-F13, Revision 0 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 6.65 Direct Crew Response to Spray the Drywell with RHR Not Required for Adequate Core Cooling 6.74 Direct Crew Response for performance of ALC when injection systems are lined up and 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 UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

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

See cover See cover

NRC Scenario 3, Rev. 0 SEG Page 5 of 24 TR-AA-230-1007-F13, Revision 0 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 6.65 Direct Crew Response to Spray the Drywell with RHR Not Required for Adequate Core Cooling 6.74 Direct Crew Response for performance of ALC when injection systems are lined up and 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

NRC Scenario 3, Rev. 0 SEG Page 6 of 24 TR-AA-230-1007-F13, Revision 0 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.

5.

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.

6.

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

NRC Scenario 3, Rev. 0 SEG Page 7 of 24 TR-AA-230-1007-F13, Revision 0 Trouble.

The Control Room Supervisor will enter TRM Spec 3.3.4 for online chemistry monitoring is not met with RWCU OOS.

7.

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.

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)

8.

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

9.

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.

10.

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)

11.

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

NRC Scenario 3, Rev. 0 SEG Page 8 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR SET UP INSTRUCTIONS

1. General Instructions

2. Verify the files listed below are in the exam directory

a. Load the saved IC and to a SNAPSHOT

b. Reset to that SNAPSHOT

c. Place the Simulator in RUN OR

d. Reset to IC 13, place the simulator in RUN and insert the listed malfunctions and event triggers per the SEG (1) Place in service A RWS Pump

3. Have a second instructor verify:

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

b. Malfunctions

c. Remotes

d. Overrides

4. Place Guarded Equipment tags on: None

5. Align EOOS to reflect the simulator initial conditions with B Condensate Pump OOS

6. Mark up IPOI 3 to step 4.0 (9) and leave for the crew

7. Ensure BOL pull sheets are in the 1C05B hanging file Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist

NRC Scenario 3, Rev. 0 SEG Page 9 of 24 TR-AA-230-1007-F13, Revision 0 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 7

ZDIRHH2001(2) l ZDIRHHS1903(2)

Drywell Sprays Initiated 9, 11, 13 Manually activated MALFUNCTIONS:

Time Malf. No. Malfunction Title Delay Ramp ET Initial Value Final Value SETUP stcs01 CORE SPRAY INJECTION VALVE FAILS TO OPEN - MO-2117 INACTIVE ACTIVE SETUP cs05a CORE SPRAY PUMP A -

FAILURE TO AUTO-INITIATE INACTIVE ACTIVE SETUP strh01 LPCI A INJECT VALVE FAILS TO AUTO OPEN - MO-2003 INACTIVE ACTIVE SETUP strh02 LPCI B INJECT VALVE FAILS TO AUTO OPEN - MO-1905 INACTIVE ACTIVE As dir ed08m 4.16 KV/480V BUS FAULT-BUS 1B09 1

INACTIVE ACTIVE As dir ed06c STARTUP TRANSFORMER LOSS 3

ACTIVE ACTIVE As dir cs01b CORE SPRAY PUMP TRIP-CORE SPRAY PUMP B TRIP 3 min 5

INACTIVE ACTIVE As dir hp12 HPCI Aux Oil Pump Trips 5 sec 5

ACTIVE ACTIVE As dir rr15b RECIRC LOOP RUPT-DESIGN BASES LOCA AT 100%- LOOP B

20 min 7

1 3

As dir sw21a WELL WATER PUMP TRIP-PUMP A, 1P58A 9

INACTIVE ACTIVE As dir cu01b RWCU PUMP TRIP - PUMP B 11 INACTIVE ACTIVE As dir rr15b RECIRC LOOP RUPT-DESIGN BASES LOCA AT 100%- LOOP B

4 min 13 0

1

NRC Scenario 3, Rev. 0 SEG Page 10 of 24 TR-AA-230-1007-F13, Revision 0 OVERRIDES:

Time OR No.

Override Title Delay Ramp ET Initial Value Final Value REMOTE FUNCTIONS:

Time RF. No.

Remote Function Title Delay Ramp ET Initial Value Final Value SCHEDULE FILE(S): NONE Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist

NRC Scenario 3, Rev. 0 SEG Page 11 of 24 TR-AA-230-1007-F13, Revision 0 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

NRC Scenario 3, Rev. 0 SEG Page 12 of 24 TR-AA-230-1007-F13, Revision 0 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 While you raise power to between 55% and 60% power, the JITT will be going on in the simulator, and the WCC will develop the prejob brief for the start of the second Feedwater pump When the Feedwater System is started, 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 extra RO o 3 Extra NSPEO

NRC Scenario 3, Rev. 0 SEG Page 13 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1:

Secure A RHRSW Pump and A ESW Crew: Secure A RHRSW and A ESW CRS 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 EVENT 2:

Raise reactor power with recirc Crew: Raise Reactor Power with Recirc IAW OI 264, Sec 4.2 CRS Direct the OATC to raise reactor power to 55-60% with recirc Supervise the manipulation of the Recirculation System OATC Raise Recirc Flow with SIC-9245A, A Recirc MG Set Speed Control, and SIC-9245B, B Recirc MG Set Speed Control.

Monitor Parameters IAW OI 264 Sec. 4.2

NRC Scenario 3, Rev. 0 SEG Page 14 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3:

When the Lead Evaluator is satisfied with the Power Adjustment, If/When sent to 1A3 switchgear to investigate, Wait 2 minutes, then contact the control room and report, If/When sent to Intake Structure to investigate.

After ten (10) minutes contact control room and report, If necessary, acknowledge annunciators at

1C102, Simulator Operator Verify ET 1 is active This will activate ED08N for loss of 1B09 Simulator Operator Acknowledge Request Simulator Operator Breaker 1A312 is tripped with indication of ground fault, all other indications are normal.

Simulator Operator Acknowledge Request Simulator Operator There is no power for A side equipment at the intake structure, all equipment appears normal and 1K-16B is running and operating normally.

Simulator Operator SET RF AN03 to ACK This will acknowledge 1C102 annunciators.

Crew: Respond to ARP 1C08B (B-6) LC XFMR 1X09 Breaker 1A312, or MCC 1B21 BKR 1B2003 Trip and AOP 410, Loss of River Water Supply.

BOP Send an Operator to the Intake Structure to verify 1K-16B is maintaining system air pressure and supplying both Intake Structure Instrument Air headers.

Start River Water Supply Pumps 1P-117B and D as required per OI 410 (River Water Supply System) and perform the following:

o Monitor Circ Water Pit level on Computer Point F092 and Cooling Tower Basin levels on LI-4231 and LI-4232 o Be prepared to perform AOP 410 (Loss of River Water Supply)

Start Standby Pump (B or D RWS Pump) to restore needed makeup flow Send an operator to the Intake Structure to verify alarms and check RWS pump breaker condition. (94.15)

CRS Enter AOP 410 Loss of River Water Supply (5.15)

Comply with the Technical Specification requirements for Distribution Systems-Operating (3.8.7 Condition D) and inoperable RWS subsystem. (3.7.2 Condition A) (1.02)

Contact organization for support

NRC Scenario 3, Rev. 0 SEG Page 15 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4: AOP 903, lightning strike Call the control room as Security and

report, When contacted as

ITC, When called as security personnel, After the site wide announcement is complete, Simulator Operator The National Weather Service has just declared a Severe Thunderstorm Warning For DAEC for the next 60 minutes Simulator Operator Inform the control room that the grid is stable.

Simulator Operator Inform the control room that you will notify any personnel working outside that may not have heard the warning Simulator Operator Activate ET 9 This will trip the A Well Water Pump Crew: Take Actions directed by AOP 903, Severe Weather CRS(5.24)

Enter and direct that AOP 903, Severe Weather, Section B be entered and the necessary announcements be made to DAEC Will call ITC to determine the status of the grid and inform the ITC Real Time Desk of the severe storm warning Enter and direct AOP 408, Loss of Well Water BOP(94.24)

Make the thunderstorm warning Request Security inform personnel working outside, who may not have been able to hear the page announcement, of the WARNING condition Monitor wind speed using SPDS display SPMET1, YR9400 MET System Recorder, Group Display "AOP903", Real Time Plot "Wind", and other available local wind speed display Inform the CRS/SM to Refer to EPIP 1.1 and 1.2 for Emergency Action Level Classification and Notification requirements Start the C Well Water Pump

NRC Scenario 3, Rev. 0 SEG Page 16 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6:

When the BOP is adjusting well

water, If sent to the A well house to investigate, Wait 7 min and report the following, if the BOP goes to terminal block TC1 to check fuse F08, If sent to check the newly started well water pump, Wait 4 min and

report, Simulator Operator Activate ET11 This will trip the B RWCU Pump Simulator Operator Call the control room as a security Guard and report that there was a lightning strike just north of the plant Simulator Operator Acknowledge the request Simulator Operator You are in the well house and 1C374, 480/277 VAC Power Panel is dark BOP Evaluator Respond to the BOP that fuse F08 looks good, the Pop Up Pin is not popped out Simulator Operator Acknowledge the request Simulator Operator the Well is running SAT CREW: Respond to a loss of RWCU Pump B OATC:

Will determine that the B RWCU Pump has tripped and take action IAW ARP 1C04B A-9, RWCU Pump Lo Flow o Verify the running RWCU Pump has tripped o Direct an operator to verify the RWCU Beds in HOLD o Direct an operator in investigate the pumps locally o Direct an operator to reset the breaker1B3509(1B4329) o Check for fault light on the variable speed drives o Crack open MO-2723, Cleanup Demin Bypass valve As Time permits, o If the RWCU System will remain shutdown/isolated for an extended period of time, computer point B017, RWCU System Flow, may need to be substituted to zero to maintain accurate ACUMEN Periodic Reports.

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

NRC Scenario 3, Rev. 0 SEG Page 17 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7:

LOCA When the actions of the lightning strikes are under control and at the directions of the Lead Evaluator, Simulator Operator Activate ET 13 This will begin the LOCA CREW: Respond to the rising in Dry Well Pressure CRS:

Enter and direct AOP 573, Primary Containment Abnormal Set a Critical Parameter on DW pressure, and place a line in the sand to insert a manual scram at 1.8 psig BOP Will begin to perform the actions of AOP 573 Will monitor DW pressure and report to the CRS as necessary Will insert a reactor scram prior to DW pressure reaching 2 psig

NRC Scenario 3, Rev. 0 SEG Page 18 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7:(cont)

Reactor Scram CREW: EOP 1 Actions 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 OATC:

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

NRC Scenario 3, Rev. 0 SEG Page 19 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: EOP 2 Actions When the DW reaches 2 psig, Simulator Operator Verify ET 5 goes TRUE This will trip the B CS pump after a 3 min time delay and TRIP the HPCI Aux Oil Pump after 5 seconds.

Simulator Operator Verify ET7 goes active when drywell sprays are initiated This will cause the drywell leak to get worse to overtake all high pressure injection sources CREW: Mitigate containment parameters in accordance with EOP 2, Primary Containment Control CRS will enter EOP 2 concurrently with EOP 1 and direct the following actions; Provides the crew with an update the EOP 2 is being entered Obtains a round of Primary Containment parameters Per PC/P o When the torus pressure is above 2 psig and below 11 psig, direct to Spray the Torus Per DW/T o Verifies torus level < 13.5 feet o Plots DW temp vs DW pressure on the DWSIL curve o Verifies Recirc pumps Tripped o Directs spraying the DW prior to DW air temperature reaching 280°F (Critical) (6.65)

Per TT o Maximize Torus Cooling BOP: (95.63)

Sprays the Torus Install Defeat 4 Sprays the DW (Critical) (95.65)

Establishes Torus Cooling Determines that the B CS pump has tripped, and reports the issue to the CRS 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

NRC Scenario 3, Rev. 0 SEG Page 20 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 9: On the Turbine Trip CREW: Loss of Non-Essential Power CRS: (5.08)

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

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

Verify two Well Water Pumps are in service Verify Well Water Pump 1P-58D secured. In AUTO, verify FC-44 demand is zero. In HAND, verify speed adjust at 1C373 is zero Verify GSW Pumps 1P-89A and B in service Place BUS 1A1 TRANSFER switch in MANUAL Place BUS 1A2 TRANSFER switch in MANUAL

NRC Scenario 3, Rev. 0 SEG Page 21 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 10:

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)

OATC: (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

NRC Scenario 3, Rev. 0 SEG Page 22 of 24 TR-AA-230-1007-F13, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT10:

(cont) ED 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)

Recognizes that at a reactor pressure of 450 psig, that MO-1905, LPCI Inject did not open and MO-2117, Core Spray Injection Valve failed to open, and manually opens both injection valves (Critical)

Establishes injection into the RPV with low pressure systems Restores RPV level to 170 to 211 When the plant has been emergency depressurized and RPV level is being restored to the directed band, and at the direction of the Lead Evaluator, Simulator Operator Place the Simulator in FREEZE Floor Instructor Announce that the scenario is complete, please stand by your stations and do not discuss the scenario with your crew

- - END OF SCENARIO ***

NRC Scenario 3, Rev. 0 SEG Page 23 of 24 TR-AA-230-1007-F13, Revision 0 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

NRC Scenario 3, Rev. 0 SEG Page 24 of 24 TR-AA-230-1007-F13, Revision 0 CREW GRADING ATTACHMENT ESG ______ Rev. __0____

Date ________________

Operator Name Position Evaluator CRS 1C05 1C03 Management Representative/Lead Evaluator ______________/________________

Crew Critical Tasks Task Statement SAT UNSAT

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

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