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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SIMULATOR EXERCISE GUIDE, SEG THREE COLUMN 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 2 of 31 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators ability to:

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

Enabling Evaluation Guide, no tasks are trained.

Objectives:

Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation Team C. 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 3 of 31 Evaluation Method: In accordance with NUREG 1021 Operating None Experience:

Risk Significant Control Feedwater Following a Scram Operator Actions: 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.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover 0.0 Initial Development for PDA 19-1 License exam N/A See Cover Filename: NRC Scenario 1 19-1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 31

NRC Exam Scenario #1, Rev. 0 SEG Page 4 of 31 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.22 Respond to Earthquake Condition 94.58 Respond to Loss of Reactor Recirculation Pump(s) 94.03 Respond to Power/Reactivity Abnormal Change Condition 94.18 Respond to Reactor Water/Condensate High Conductivity Condition 95.57 Perform /Q to Reduce Reactor Power or Scram the Reactor 95.06 Perform Reactor SCRAM Using Repeated Manual Scram 95.08 Insert Control Rods by Increasing CRD Cooling Flow and Pressure 95.65 Spray the Drywell with RHR Not Required for Adequate Core Cooling 96.80 Perform an Emergency Depressurization Using SRVs 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 5.22 Direct Crew Response to Earthquake Condition 5.58 Direct Crew response to Loss of Reactor Recirculation Pump(s) 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.18 Direct Crew Response to Reactor Water/Condensate High Conductivity Condition Direct Crew Response to Control RPV Injection prior to, during and subsequent to Emergency 6.52 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 TR-AA-230-1007-F13 , Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 5 of 31 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)

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

NRC Exam Scenario #1, Rev. 0 SEG Page 6 of 31

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.

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

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

NRC Exam Scenario #1, Rev. 0 SEG Page 8 of 31 EVENT TRIGGER DEFINITIONS:

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

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

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

OVERRIDES:

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

Time RF # Remote Function Title ET Delay Ramp Initial Final Value Value TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 9 of 31 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 Insert malfunction rp05g to HYDRAULIC LOCK SCRAM DISCHARGE 00:00:00 None 65.00000 VOLUME (VARIABLE)

Insert override DI-MS-072 to HS-4427A GRP 1 CHAN A1 ALL SIGNALS 00:00:00 None NORMAL OVRRD Insert override DI-MS-074 to HS-4427C GRP 1 CHAN A2 ALL SIGNALS 00:00:00 None NORMAL OVRRD Insert override DI-MS-076 to HS-4535 RX WTR LVL LO-LO TRIP OVRRD -

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

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

Create Event 5 an_1c06b(1) -desc 00:00:01 None 1C80 Trouble Create Event 7 !rpdis1run(1) -desc 00:00:01 None MODE SW out of RUN Create Event 9 rd_fi -desc All 00:00:01 None Rods Full In Create Event 11 ZDITCBPVJINCR l 00:00:01 None ZDITCBPVTSTG -desc SEP 307 Attmpt Schedule Schedule\_PDA19-00:00:02 None 1NRCScenario_1\Weather.sch TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 10 of 31 Weather.sch At Time Event Action Description 00:00:01 None Insert remote hv01 to 223 in 7200 WIND DIRECTION AT 50 meters (165 ft)

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

AMBIENT TEMPERATURE AT 10 meters (35 00:00:01 None Insert remote hv06 to 73 in 28800 ft) 00:00:01 None Insert remote hv07 to 73 in 28800 RIVER WATER TEMPERATURE Seal_Oil_Pump_Trip.sch At Time Event Action Description Create Event 20 00:00:00 None ZDIEGHS3640(4) -desc Emerg Seal Oil Pump HS Start Insert Override DO-EG-028 to HS-3641(1) MAIN SEAL OIL PUMP 1P-92 00:00:00 None OFF (GREEN)

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

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

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

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

None 20 Delete Malfunction EG08B LOSS OF SEAL OIL PUMP- RSOP None 20 Toggle Event 20 Condenser_Tube_Leak.sch At Time Event Action Description Insert malfunction mc07 to MAIN CONDENSER TUBE (1E-7A) 00:00:00 None 0.90000 LEAKAGE Modify malfunction mc07 after 180 MAIN CONDENSER TUBE (1E-7A)

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

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

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

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

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

NRC Exam Scenario #1, Rev. 0 SEG Page 12 of 31 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 13 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Alternate EHC The Crew will perform the actions of OI 693.2, Section 6.2.1 and alternate Pumps the EHC Pumps CRS If contacted to Simulator Operator Supervise the evolution verify the non- Acknowledge the request BOP running EHC

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

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

wait 2 minutes Simulator Operator

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

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

Verify all annunciators are reset for the evolution If contacted to Simulator Operator verify the B Report the B EHC Pump is running sat EHC Pump is running sat, TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 14 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Raise Power The Crew will perform rod withdrawals per IPOI 3 and the current rod with control rod sequence sheets to achieve a power level of 80% or at the discretion of the withdrawal 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.

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

NRC Exam Scenario #1, Rev. 0 SEG Page 15 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE At the direction Crew of the Lead Simulator Operator Respond to annunciator 1C05A (F-7), CRD ACCUMULATOR LO Evaluator, PRESSURE OR HI LEVEL Verify ET 3 is active TRUE This will result in an Accumulator alarm for When directed control rod 22-07. RO to investigate

Check the Full Core Display on 1C05 to determine which accumulator(s) control rod 22-Simulator Operator is/are in the trouble condition.

07 for an Acknowledge the request o Determines that the alarm is on Control Rod 22-07 accumulator alarm,

Send an Operator to the accumulators to determine the cause of the alarm Simulator Operator

Inform the CRS to comply with Technical Specification requirements for Wait 3 min. The alarm was due to low nitrogen Control Rod Scram Accumulators then report, pressure. Pressure is currently 900

Direct the Second Assistant to either drain the water from the psig. accumulator, or recharge the accumulator Simulator Operator CRS (1.02)

Wait 10 min Click KEYPAD Key 1 Will enter TS 3.1.5 Condition A to either declare the control rod slow, and then report, This will delete Malfunction RD072207 and or to declare the control rod inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , for an clear the 1C05 indication and alarm. inoperable accumulator.

Accumulator 22-07 is recharged to 1090

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

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

NRC Exam Scenario #1, Rev. 0 SEG Page 16 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event CREW Earthquake Simulator Operator

Perform the actions directed from AOP 901, Earthquake Click KEYPAD Key 2 After the CRD This will insert Malfunction ZZ03 for DBE CRS (5.22) accumulator, and at the

Direct Crew Response to an Earthquake Condition direction of the

IF the amber DESIGN BASIS EARTHQUAKE, or amber OPERATING Lead Evaluator: 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 Simulator Operator:

SBLC tank levels When Acknowledge the request

SJAE and offgas flow changes contacted as

Changes in jockey fire pump cycling any dept. in organization:

Core Spray and RHR system pressure TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 17 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If contacted as Simulator Operator CREW Duty Station Acknowledge the request.

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

Manager:

RO (94.22)

Respond to an Earthquake Condition

Monitor reactor power, pressure, and level on 1C05 If contacted as

Monitor for any Control Rod out of position HP or

Verify any heavy loads being handled (within the turbine building or Chemistry: Simulator Operator LLRWSF) are landed in safe location Acknowledge the request.

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

If contacted as o Verify all available RWS pumps will start and deliver >6000 gpm flow an NSPEO: o Using HS 4918, RIVER WATER SUPPLY LOOP SELECT switch, Simulator Operator select A CV4915 and B CV4914, one at a time, to verify RWS Acknowledge the request to perfrom makeup flow can be established with each loop ensuring RWS inside and outside plant walkdowns. piping is intact

IF ESW is in service, THEN At 1C06, isolate ESW from non-seismic Well Keep track of which operator has been Water by closing MO-2039A[B] WELL WATER TO A[B] CHILLER, and sent to what location in the plant.

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 Simulator Operator Wait 15 min. structure and system's integrity, and immediately report back any There is no damage in the areas that damage to the Control Room.

and report, you have walked down.

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

NRC Exam Scenario #1, Rev. 0 SEG Page 18 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Loss of Main H2 CREW Seal Oil Pump Determine that there is a loss of the Main H2 Seal Oil Pump and take actions Simulator Operator per ARP 1C08C (D-6),

If sent to the H2 Acknowledge the request Seal Oil Skid, CRS

Direct the start of the Emergency H2 Seal Oil Pump Simulator Operator Wait 3 minutes and then report, The Main H2 Seal Oil Pump has a sheared RO shaft.

Start the Emergency H2 Seal Oil Pump per the ARP

Secure the H2 Seal Oil Vacuum Pump per the ARP If asked for the

Send an operator to the H2 Seal Oil Skid to investigate Simulator Operator status of the Acknowledge the request, and Emergency Seal Oil Pump, If it is running, report The ESOP is running sat If the ESOP has not been started, report it is ready for start TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 19 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Hi vibrations CRS and Trip of B

Respond to B Recirc Pump Hi Vibrations ARP 1C04B (B-1)

Recirc MG

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

When CRS Simulator Operator:

contacted to

Direct the actions for Hi Vibrations on B RR Pump investigate B Acknowledge request wait 2 minutes and report

Notify System Engineering of Hi vibration condition Reactor Recirc All channels are reading 15 mils and

Direct the actions of AOP 264, Loss of Reactor Recirculation Pump Hi stable Pump(s), be performed Vibrations RO

Dispatch operator to 1C466C to investigate Hi Vibrations

At 1C21 Check Recirc Pump temperature recorder TRS 4600 for When increasing B Recirc Pump bearing temperatuers contacted to

Enter AOP 264 and perform concurrently with this ARP.

investigate B

Verify the AUTOMATIC ACTIONS have occurred:

RR pump trip,

A RECIRC MG SET MOTOR BREAKER 1A204 is OPEN.

Simulator Operator:

A GENERATOR FIELD BREAKER is OPEN.

Report that a B Recirc MG Generator

Determine the cause of the tripped Recirc Pump as follows:

Wait 2 min and Lockout has occurred. and the B

At 1C04, monitor associated alarms.

report, GENERATOR FIELD BREAKER is

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

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

If asked to investigate 1A2 Simulator Operator:

Wait 2 min and report Report that the B RECIRC MG SET MOTOR BREAKER 1A204 is OPEN TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 20 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Trip of Recirc CREW continued

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

NRC Exam Scenario #1, Rev. 0 SEG Page 21 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Trip of Recirc CREW continued

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 If contacted as PUMP DISCHARGE valve MO-4627 organization:

Simulator Operator

If core thermal power is greater than (>) 60% (1147 MWth), then insert Acknowledge the request 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 22 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the The Crew will respond to annunciator 1C06B A-1, Condensate Demin Panel actions of the 1C-80 trouble and perform the following actions; Earth Quake Simulator Operator are under Set ET 5 to TRUE RO (94.18) control, the plant is stable Verify that when 1C06B A-1, 1C-80

Send an Operator to 1C80 to investigate and / or at the trouble alarms, that ET 11 goes true

Based on the report, the crew will enter AOP 639, Reactor direction of the This will start a condenser Tube leak, and Water/Condensate High Conductivity.

Lead Evaluator, when ET 11 goes true, it will drive the crew to insert a manual scram SRO (5.18)

Direct entry in AOP 639, Reactor Water/Condensate High Conductivity When called on Simulator Operator

Review Action Levels contained in PCP 1.9RX or PCP 1.9FW to investigate Acknowledge the request PCP 1.9RX actions are on page 27.

the alarm on On the PPC monitor, call up GD 24, this

Monitor conductivity monitoring points listed in above note and refer to 1C80, will give you the condensate filter PCP 1.9RX - Attachment 10, to determine the source of high conductivity demineralizer panel. When you relay your

IF Condenser tube leak is suspected, THEN Direct Engineering &

report, give them the reading of the Maintenance to evaluate which loop is leaking Condensate influent conductivity.

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 Wait 3 min and Simulator Operator or plant startup, THEN Reduce Reactor Recirc flow to 39 Mlbm/hr per report, Report that the alarm was the Influent IPOI 4, Fast Power Reduction AND SCRAM 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 23 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Condenser Based on the report, the crew will enter AOP 639, Reactor Tube Leak Water/Condensate High Conductivity, and take the following action; When called as Simulator Operator RO chemistry, Acknowledge the request and state that

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

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

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

IF condensate demineralizer influent conductivity is greater than 0.1 If asked to them with a recommendation mho/cm, THEN maintain the filter demineralizer bypass valve MO-1708 monitor closed conductivity at Simulator Operator

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

Simulator Operator When CE1516A call the control room and report the is called up, conductivity reading TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 24 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Tube leak PCP 1.9RX actions.

continued Floor Instructor The CRS will direct and the STA and SM will perform the following actions Per a definition in PCP 1.9RX, a micro IAW PCP 1.9RX:

S/cm = micro mho/cm

Based on the tables, determine that the plant is in an Action Level 2 If asked to condition monitor other Simulator Operator o Write a CR Conductivity Acknowledge the request 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

points, Wait 3 min and Simulator Operator report, Using information from GD 24, report consistent conductivity readings TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 25 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Scram on main condenser Crew inserts a manual scram based on the condenser out let conductivity 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 TR-AA-230-1007-F13, Revision 0

NRC Exam Scenario #1, Rev. 0 SEG Page 26 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Scram and SRO ATWS

Directs the initiation of SBLC

Directs the Hydraulic ATWS RIPS (Critical) (6.08, 6.06)

Assess reactor power If directed to Simulator Operator o If reactor power is > 5%, the crew will enter power level control install Defeat (Critical)

Acknowledge the request 12, Directs to secure and prevent injection from, Condensate and Feed, HPCI, RHR, CS Wait 3 min and Inform at an RPV level of 87 perform the Simulator Operator If conditions allow RPV injection, maintain RPV level > -25 action, then Set ET 7 to TRUE. Note that there is a RO report to the 40 second time delay

Initiates SBLC control room, This will place the ATWS RPT switches in

Performs the ATWS RIPS (Critical) (95.06, 95.08) the TEST position o RIP 103,2, Increase CRD Cooling Flow and Pressure Start second CRD Call the control room and inform them Place CRD Flow Controller FC-1814 in MANUAL and run the output to that you have installed Defeat 12 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 TR-AA-230-1007-F13, Revision 0

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

NRC Exam Scenario #1, Rev. 0 SEG Page 28 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EOP 2 and lowering Torus The crew determines that Torus Level is lowering, and perform the following level. actions; When directed to the Torus SRO (6.65) area to determine Simulator Operator

Direct the following actions from EOP 2 where the leak Acknowledge the request o Obtain a round of Primary Containment Parameters is, Determine that Torus level is lowering

Direct that torus level e raised by:

Simulator Operator o Core Spray, OI 151 Wait 4 min and There is a lot of water flowing out of a * (Critical) Before 7.1 feet report, cracked pipe right at the torus. The o Perform an Emergency Depressurization cracked pipe is the A CS suction line 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.

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

NRC Exam Scenario #1, Rev. 0 SEG Page 29 of 31 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed RO EOP 2 actions continued to open the CS Simulator Operator o Attempt to raise torus water level; manual valves, With the CS system Acknowledge the request V-21-01 and 02,

Monitor CST level on 1C06

Verify that the CS outboard and inboard torus suction valves are open Simulator Operator

Unlock and open V-21-01, for A CS, and V-Wait 4 min and report, You are at the directed valve, but you 21-02, for B CS, as necessary.

cannot get the lock to work. You have to go and find a bolt cutter to get the (Critical) When the crew determines that they cannot maintain torus level chain off of the handwheel.

above 7.1 feet, and BEFORE 7.1 feet in the torus, the crew will perform an Emergency Depressurization and take the following actions; When directed Simulator Operator to go to the Acknowledge the request SRO (6.80) other CS,

Directs that ED be entered

Directs the following from ED Simulator Operator o Verify CV 4371A is overridden Wait 4 min and o Verify torus level is above 4.5 report, You attempted to open the CS valve, but it was hard to turn. While you were o Open 4 ADS SRVs BEFORE Torus level is below 7.1 (Critical) attempting to open it, there was a loud o Maintain RPV level using CS or RHR cracking sound, and now the valve handwheel spins freely RO (95.80)

Verify CV 4371A is overridden If sent to find Simulator Operator

Verify torus level is above 4.5 the bolt cutter Acknowledge the request, but you will

Open 4 ADS SRVs BEFORE Torus level is below 7.1 (Critical) for the initial never find a bolt cutter

Maintains RPV level using the directed injection system

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

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

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

Instructor,

- - END OF SCENARIO ***

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

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 2 of 28 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal This Evaluation Scenario Guide evaluates the Operators ability to:

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

Enabling Evaluation Guide, no tasks are trained Objectives:

Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator Initial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation Team C. 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 TR-AA-230-1007-F13 , Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 3 of 28 Evaluation Method: In accordance with NUREG 1021 Operating None Experience:

Risk Significant Initiate RPV Emergency Depressurization Operator Actions:

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

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Changed form number to match new industry SAT procedure 0

which superseded TR-AA-230-1003.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 4 of 28 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.16 Respond to GSW Abnormal Operation Condition 94.36 Respond to a Loss of 1A4 Perform Actions of EOP 3 for High Area Temperature, Radiation, and Water Level including 95.68 EOP 1 and ED 95.46 Perform actions of RC/P of EOP 1 95.47 Establish a Cooldown of the RPV at a Rate of <100 Degrees F/hr 95.48 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 Direct Crew Response for performance of EOP 3 for high area temperatures/radiation /water 6.67 level including EOP 1and ED 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.47 Direct Crew Response to Establish a Cooldown of the RPV at a Rate of <100 Degrees F/hr Direct Crew Response to Rapidly Depressurize the RPV via the Main Turbine Bypass 6.48 Valves 6.55 Direct Crew Response to Perform Initial ATWS Actions (/)

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 5 of 28 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.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 6 of 28 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.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 7 of 28 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.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 8 of 28 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 Final Value Value CORE SPRAY PUMP TRIP-As dir CS01a 5 sec 19 Inactive Active CORE SPRAY PUMP A TRIP 1C06A (B-04) GSW AUTO CRYWOL As dir AN1C06A(17) 10 sec 13 ON FILTER HI dP F 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 GSW PUMP 1P89A FAIL TO SW37A ACTIVE ACTIVE AUTO-ACTUATE RBCCW PUMP 1P81A FAIL TO Set up stsw01a ACTIVE ACTIVE AUTO-START MO2700 THERMAL OVERLOAD Set up cu11a INACTIVE ACTIVE BREAKER TRIPI MO2701 THERMAL OVERLOAD Set up cu11b BREAKER TRIP GROUP 5 ISOLATION Set up ms28b VALVE(S) FAIL(S) TO CLOSE- ACTIVE ACTIVE MO2701 RWCU LEAK IN HEAT 3 min 5 Set up Cu07 0 1.5 EXCHANGER ROOM (VI)

TEMPERATURE Set up Cu05 TRANSMITTERS 2742G,J,H,K 5 min 7 As Is 80 FAILURE 4.16 KV/480V BUS FAULT- BUS Set up ed08d 9 INACTIVE ACTIVE 1A4 RPS SCRAM CIRCUIT FAILURE Set up rp05a (ATWS)- AUTO SCRAM ACTIVE ACTIVE FAILURE TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 9 of 28 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value RPS SCRAM CIRCUIT FAILURE Set up rp05b (ATWS)- MANUAL SCRAM ACTIVE ACTIVE FAILURE RPS SCRAM CIRCUIT FAILURE Set up rp05d (ATWS)- RPS FUSE REMOVAL ACTIVE ACTIVE FAILURE Set up ALL INDIVIDUAL ROD SCRAM rp05e ACTIVE ACTIVE SWITCHES FAIL CONTROL ROD BLADE Set up rd020227 ACTIVE ACTIVE STUCK- ROD 02-27 TEMPERATURE As dir Cu05 TRANSMITTERS 2742G,J,H,K 5 min 23 80 43 FAILURE RE-7606B REAC BLDG MAIN As dir rm02re7606b 21 As Is 100 EXHAUST B CORE SPRAY PUMP TRIP-CS As dir CS01A 5 sec 19 Inactive PUMP A TRIP OVERRIDES Time OR No. Override Title Delay Ramp ET Initial Final Value Value BPVJINCR BYPASS VALVE TRANSI TRANSI/

Set up DI-TC-009 OPENING JACK, INCREASE /OFF OFF HS-2701 REAC WTR C/U ISOL As dir DI-CU-002 MOV-2701 11 NORM OPEN (CLOSE,NORM,OPEN)

DO-CU-003 HS-2701(1) RWCU ISOL MOV- 11 OFF OFF As dir 2701 (GREEN)

DO-CU-004 HS-2701(2) RWCU ISOL MOV- 11 ON OFF As dir 2701 (RED)

DO-CU-027 MO-2701(1) RWCU SYS ISOL 11 OFF OFF As dir VLV-OUTBD (GREEN)

As dir DO-CU-028 MO-2701(2) RWCU SYS ISOL 11 ON OFF VLV-OUTBD (RED)

Set up DI-AD-015 HS-4402 ADS PSV4402,B AUTO AUTO MSL,1130 PSI (AUTO,OPEN)

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

PB-7606B B GROUP 3 As Dir DI-RM-024 21 OFF ON INITIATION TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 10 of 28 REMOTE FUNCTIONS Time RF. No. Remote Function Title Delay Ramp ET Initial Final Value Value MAN OPER OF 'B' GSW PUMP As dir SW32 1 NORM OPEN (1P-89B BREAKER)

GSW DISCHARGE TO As dir SW10 5 min 13 100 50 COOLING TOWERS V-11-69 MANUAL OPER OF 'A' CS As dir CS03a 19 NORM CLOSE PUMP (1P-211A BREAKER)

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 11 of 28 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 TR-AA-230-1007-F13, Revision 0

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 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew The Crew will Shift Stator Water Cooling Pumps in accordance with OI 697 assumes the Stator watch, CRS

Direct RO to Swap Stator Water Cooling pumps in accordance with OI Simulator Operator 697 Generator Stator Cooling Water system When Report: V-45-13 B Stator Water BOP contacted as in Cooling Pump suction isolation valve is

Verify B Stator Cooling Pump 1P91B suction valve V-45-13 is OPEN plant operator OPEN

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

suction valve is

Annunciator 1C08C D-4 H2/Stator Cooling panel Trouble alarms due to OPEN reserve pump running

Verify both pumps are running

Stop the A Stator Cooling Pump 1P91A by placing switch to STOP position momentarily If asked to Simulator Operator

1C08C D-4 H2/Stator Cooling panel Trouble should clear report status of Report: B Stator water cooling pump Stator Water is operating normally.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 14 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE The Crew will The Crew will perform rod insertions in the reverse sequence of the rod reduce reactor movement control sheets to achieve a power level of 95% or at the power with rods discretion of the lead evaluator to achieve 95%

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.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 15 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE At the direction The Crew will respond to annunciator 1C03A, A-8, A Core Spray System of the Lead Auto Initiated.

Evaluator, Simulator Operator BOP will Set Event Trigger 19 to True

Determine that Drywell pressure is not > 2 psig This will give the A CS pump an

Determine that RPV level is not < 64 inadvertent initiation signal. The pump will

Determine that the CS pump should not have initiated.

then TRIP 5 seconds after starting.

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

Inform the CRS If contacted as Floor Evaluator CRS will (1.02) the in plant

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

Report: Breaker operator to investigate 1A3 BOP switchgear

Will place HS 2103, A Core Spray pump in the Stop position to secure room report the Core Spray Pump.

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

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 16 of 28 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 BOP Second Simulator Operator

May vent Core Spray per OI 151 Core Spray System Assistant to Acknowledge the request. o Direct an in-plant Operator to vent the Core Spray system per vent the CS Then Call up RF CS05, Manual CS A vent Section 8.1 system, valve. On THUNDERVIEW, monitor the PI

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

2106, on 1C03, panel 2_B Wait 5 min and Simulator Operator call the control You are standing by the CS vent valve, room and you have you venting rig attached, and report, are ready to vent the A CS system.

Simulator Operator When directed Set RF CS05 to OPEN. The RF box will to vent the CS close, Open it up again and AS SOON AS system, the CS Hi discharge pressure alarm, 1C03A C-9, clears SET RF CS05 to CLOSE TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 17 of 28 SBLC Leak Simulator Operator The Crew will respond to annunciator 1C05A, E-3, SBLC Tank HI/LO Level At the direction Set Event Trigger 2 to True of the Lead This will cause a leak from 1T218 to be OATC will Evaluator, developed. SBLC Storage tank level will

Determine that SBLC Tank Level is lowering lower until the Low Level alarm comes in.

Report to the CRS Tank Level and Trend

Direct an In-plant Operator to investigate the SBLC skid CRS will If directed to Simulator Operator

Direct V-26-01 to be closed when location of the leak is known investigate the The leak is downstream of V-26-01 SBLC

Determine both SBLC subsystems are INOPERABLE SBLC leak wait Storage Tank 1T218 Outlet Isolation

Enter LCO 3.1.7 Condition B restore 1 subsystem to OPERABLE within 3 minutes and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report the following Simulator Operator If directed to Wait 1 minutes then DELETE mf sl07 CLOSE V Report the following: V-26-01 is directed 01 SBLC Storage Tank 1T218 Outlet Isolation has been closed.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 18 of 28 At the direction Simulator Operator of the Lead Set ET 1 to TRUE The crew will respond to Annunciator 1C06A, B-3 and C-4 and take the Evaluator, This will trip the B GSW Pump, C following actions; RBCCW pump, and throttles closed the GSW discharge to the cooling towers.

Verify ET 13 goes true on the start of the BOP A GSW pump

IAW ARP 1C06A B-3 When ET 1 is o At 1C06, confirm Service Water Pumps Discharge Header Press low set to True call Simulator Operator on PI-4903 GSW PUMPS DISCH HDR PRESS the CR and A lightning bolt just hit in the yard near o Verify auto start of the standby pump.

report, warehouse 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 When Simulator Operator o Send and operator to the GSW strainer 1S-24 to verify high differential contacted to Acknowledge Request pressure on PDIS-4906.

investigate B o Inform the CRS that AOP 411 is referenced in the ARP GSW Breaker 1A409, Simulator Operator CRS Report that there is a ground fault flag

Direct actions of ARP 1C06A B-3, B-4, C-4, and AOP 411 (Loss of Wait 2 minutes (Relay 409-150G) on breaker 1A409. GSW). (5.16) and report, Simulator Operator When sent to Acknowledge Request investigate the auto strainer or the B GSW Simulator Operator Pump, The B GSW motor is warm to the touch but nothing else is abnormal.

The GSW strainer, 1S-24, is turning, Wait 4 min then PDIS-4906 is reading 5 psid and report lowering.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 19 of 28 GSW CREW After the report

Perform actions per ARP 1C06A B-3, B-4, C-4, and AOP 411 on the previous Simulator Operator BOP(94.16) page, wait 2 Delete Malfunction AN1C06A(17),

IF there is insufficient GSW cooling OR less than 2 GSW pumps are min and, 1C06A (B-04) GSW AUTO FILTER HI dP running THEN make every effort to achieve at least 2 pumps running.

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

Simulator Operator Turbine Lube

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

Wait 2 min, Simulator Operator

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

Insert Remote Function SW 14 and TURB INSTRUMENT PANEL 1C-20 TROUBLE is received THEN raise the current setting by increments perform the following as required:

of 3 until the LO temperature begins to

Monitor generator hydrogen, stator, and exciter cooler temperatures.

turn (should return to normal around OATC

40)

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

temperature and adjust as necessary.

Scram the reactor prior to securing both condensate or feed pumps Loss of the C RBCCW pump The Crew will respond the annunciator 1C06B D-3, RBCCW Pump Disch Header Lo Pressure alarm If sent to Simulator Operator investigate the BOP Acknowledge the request C RBCCW

Confirm the low pressure condition on PI-4821 and/or Computer Contact pump and Point M508

breaker,

Normally two pumps are in operation, confirm that A, B & C RBCCW Simulator Operator PUMPS 1P-81A, B & C are all running Wait 3 min and The C RBCCW pump breaker is warm

If any pump fails to start, attempt to start that pump ONCE using the report, and in the trip free position. The pump following control switch; seems normal, The A RBCCW pump o HS-4829 A RBCCW PUMP 1P-81A is running Sat.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 20 of 28 RWCU Hx room Simulator Operator The Crew will respond to Annunciator 1C04B B-4, Steam Leak Detection leak. Ambient High Temperature, and perform the following Actions, Set ET 5 to TRUE At the direction of the Lead This will start a leak in the RWCU Hx room Evaluator, BOP

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

Maximize plant ventilation IAW OI 734, QRC1, Maximize Plant Ventilation Lead Evaluator 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 If the crew Simulator Operator o Start the Reactor Building Supply Fans actions appear to Raise the severity of MF CU07, RWCU be keeping the Leak in Hx Room, in increments of 0.1 RWCU Hx room OATC from reaching a with a 30 second ramp.

Verify Automatic Actions Max Safe temperature, 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 If sent to attempt indication for MO 2701 is lost to reset the Simulator Operator Will report to the CRS that MO 2701 is not closed thermal overload Acknowledge the request

Prompt the CRS that this is an EOP 3 entry on 1B3219,

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

Simulator Operator Wait 2 min and report, I have reset the thermal overload for MO 2700 on breaker 1B3219.

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 21 of 28 RWCU Hx room In response to the leak in the RWCU Hx room leak continued Simulator Operator Verify that Event Trigger 11 goes True CRS (6.67)

When the Operator This will result in the loss of all indication

Enter EOP 3 and direct the following attempts to close for MO2701, and the valve will remain o Operate available coolers in the affected area MO 2701, open. o Operate available main plant supply and exhaust fans Maximize plant ventilation IAW OI 734, QRC1, Maximize Plant Simulator Operator Ventilation o Attempt to isolate the leaking system If sent to attempt Acknowledge the request to investigate Determines that RWCU will not isolate due to the thermal overload 1D42 ckt 04 for on MO 2700 MO 2701,

Direct that the thermal overload condition be reset and the Simulator Operator valve closed Determine that MO 2701 did not isolate, and send an Operator to Wait 2 min and There is an acrid odor near 1D4204, and

report, 1D4204 to investigate the breaker door is warm to the touch 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)

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 22 of 28 Reactor Scram CRS will perform the following:

ATWS

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 23 of 28 Re-entry to CRS Exits ATWS and returns to EOP 1 and directs the following actions; EOP 1 (6.45)

Per EOP 1 o Restore and maintain RPV level to 170 to 211 o Install defeat 11 Simulator Operator o Establishes an RPV pressure band of 800 psig to 1055 psig using When the Verify Event Trigger 9 goes True SRVs and MSL drains (6.47) turbine trips, o When the plant is stable, assigns a new pressure band of 500 to 700 This will result in the lock out of 1A4 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)

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NRC EXAM SCENARIO #2, Rev. 0 SEG Page 24 of 28 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 TR-AA-230-1007-F13, Revision 0

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 25 of 28 When the The Crew will respond to the rising temperatures above the TIP room and actions of AOP continue in the actions of EOP 3; 301 have been CRS Simulator Operator

Direct that the Defeat 9 be installed to maximize cooling to the reactor directed, and at the direction of Set Event Trigger 7 to TRUE building the Lead This will begin the leak above the TIP

If the temperature rise above the TIP room is identified early enough, the Evaluator, room. 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 If the Simulator Operator

When two areas exceed Max Safe, enter ED temperature in Modify Malfunction CU07 by BOP the RWCU Hx increments of 0.1 until the area has o Determine that RM 7606B REACTOR BUILDING VENT SHAFT RAD room has fallen MONITOR is failed upscale and cannot be reset preventing Defeat 9 gone above Max Safe again below Max from being installed.

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

NRC EXAM SCENARIO #2, Rev. 0 SEG Page 26 of 28 The Scenario will be complete when the RPV Simulator Operator is depressurized Place the simulator in FREEZE.

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

- - END OF SCENARIO ***

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

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

NRC Scenario 3, Rev. 0 SEG Page 2 of 24 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal This Evaluation Scenario Guide evaluates the Operators ability to:

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

Enabling Evaluation Guide, no tasks are trained Objectives:

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

References:

1. ARP 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 None Experience:

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

NRC Scenario 3, Rev. 0 SEG Page 3 of 24 Risk Significant Initiate RPV Emergency Depressurization Operator Actions:

Filename: NRC Scenario 3 19-1.docx TR-AA-230-1003-F06 Revision 0 Page 3 of 24

NRC Scenario 3, Rev. 0 SEG Page 4 of 24 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 Direct Crew Response to Well Water System Abnormal Operation 5.14 Condition 5.15 Direct Crew Response to the loss of River Water Supply Direct Crew Response to High Winds / Severe Thunderstorms / Tornado 5.24 Condition Direct Crew Response to Spray the Drywell with RHR Not Required for 6.65 Adequate Core Cooling Direct Crew Response for performance of ALC when injection systems 6.74 are lined up and available, or when no pumps are available 6.78 Direct Crew Response for performance of Emergency Depressurization Direct Crew Response to Perform an Emergency Depressurization Using 6.80 SRVs UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

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

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

NRC Scenario 3, Rev. 0 SEG Page 5 of 24 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title 94.03 Respond to Power/Reactivity Abnormal Change Condition 94.08 Respond to Loss of 4160V Non-essential Power Condition (1A1 or 1A2) 94.14 Respond to Well Water System Abnormal Operation Condition 94.15 Respond to the loss of River Water Supply 94.24 Respond to High Winds / Severe Thunderstorms / Tornado Condition 95.65 Spray the Drywell with RHR Not Required for Adequate Core Cooling 95.63 Perform DW/T leg of EOP 2 95.80 Perform an Emergency Depressurization Using SRVs 1.02 Determine Operability for Technical Specification Required Components 3.01 Implement Emergency Plan 5.03 Direct Crew Responses to Power/Reactivity Abnormal Change Condition 5.08 Direct Crew Response to Loss of 4160V Nonessential Power Condition 5.14 Direct Crew Response to Well Water System Abnormal Operation Condition 5.15 Direct Crew Response to the loss of River Water Supply 5.24 Direct Crew Response to High Winds / Severe Thunderstorms / Tornado Condition Direct Crew Response to Spray the Drywell with RHR Not Required for Adequate Core 6.65 Cooling Direct Crew Response for performance of ALC when injection systems are lined up and 6.74 available, or when no pumps are available 6.78 Direct Crew Response for performance of Emergency Depressurization 6.80 Direct Crew Response to Perform an Emergency Depressurization Using SRVs TR-AA-230-1007-F13, Revision 0

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

NRC Scenario 3, Rev. 0 SEG Page 7 of 24 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.

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

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

NRC Scenario 3, Rev. 0 SEG Page 9 of 24 EVENT TRIGGER DEFINITIONS:

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

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

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

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

WELL WATER PUMP TRIP-As dir sw21a 9 INACTIVE ACTIVE PUMP A, 1P58A As dir cu01b RWCU PUMP TRIP - PUMP B 11 INACTIVE ACTIVE RECIRC LOOP RUPT- DESIGN As dir rr15b BASES LOCA AT 100%- LOOP 4 min 13 0 1 B

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

NRC Scenario 3, Rev. 0 SEG Page 10 of 24 OVERRIDES:

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

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

NRC Scenario 3, Rev. 0 SEG Page 11 of 24 SHIFT TURNOVER INFORMATION

Day of week and shift o It is Today Dayshift

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

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

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

There are no Technical Specification Action statements in effect

No Locked in / failed annunciators and alarms

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

A RHRSW is in service with A RHRSW pump in operation A ESW is in service to support plant conditions o The Plant is a 50% power due to repairs on the B Feedwater Pump lube oil system.

4 days ago, 1P-2B, the B RFP Aux Lube Oil Pump, automatically started due to a faulty pressure switch. After the automatic start, 1P-2B catastrophically failed Power was reduced and the B Feedwater pump was removed from service The lube oil system has been repaired, the Mechanics have just signed off their post maintenance testing for the 1P-2B TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 12 of 24

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

NRC Scenario 3, Rev. 0 SEG Page 13 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 1: Crew: Secure A RHRSW and A ESW Secure A RHRSW Pump CRS and A ESW

Direct Operators to secure A RHRSW and A ESW BOP

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

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

Verify associated pump ammeter on 1C03 indicates 0 amps

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

Stop A ESW Pump by placing HS-4928A on 1C06 in the STOP position EVENT 2: Crew: Raise Reactor Power with Recirc IAW OI 264, Sec 4.2 Raise reactor power with CRS recirc

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

NRC Scenario 3, Rev. 0 SEG Page 14 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 3: Crew: Respond to ARP 1C08B (B-6) LC XFMR 1X09 Breaker 1A312, or When the Lead Simulator Operator MCC 1B21 BKR 1B2003 Trip and AOP 410, Loss of River Water Supply.

Evaluator is Verify ET 1 is active satisfied with This will activate ED08N for loss of 1B09 BOP the Power Adjustment,

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

Simulator Operator

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

1A3 switchgear Acknowledge Request to investigate, 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)

Wait 2 minutes, Simulator Operator then contact the Breaker 1A312 is tripped with indication

Start Standby Pump (B or D RWS Pump) to restore needed makeup flow control room of ground fault, all other indications are

Send an operator to the Intake Structure to verify alarms and check RWS and report, normal. pump breaker condition. (94.15)

If/When sent to Simulator Operator CRS Intake Structure Acknowledge Request

Enter AOP 410 Loss of River Water Supply (5.15) to investigate.

Comply with the Technical Specification requirements for Distribution Simulator Operator Systems-Operating (3.8.7 Condition D) and inoperable RWS After ten (10) There is no power for A side subsystem. (3.7.2 Condition A) (1.02) minutes contact equipment at the intake structure, all

Contact organization for support control room equipment appears normal and 1K-16B is and report, running and operating normally.

If necessary, Simulator Operator acknowledge SET RF AN03 to ACK annunciators at This will acknowledge 1C102 1C102, annunciators.

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

NRC Scenario 3, Rev. 0 SEG Page 15 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 4: AOP Crew: Take Actions directed by AOP 903, Severe Weather 903, lightning strike Simulator Operator CRS(5.24)

The National Weather Service has just

Enter and direct that AOP 903, Severe Weather, Section B be entered Call the control declared a Severe Thunderstorm and the necessary announcements be made to DAEC room as Warning For DAEC for the next 60

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

Enter and direct AOP 408, Loss of Well Water When BOP(94.24)

Simulator Operator contacted as ITC, Inform the control room that the grid is

Make the thunderstorm warning stable.

Request Security inform personnel working outside, who may not have been able to hear the page announcement, of the WARNING condition When called as

Monitor wind speed using SPDS display SPMET1, YR9400 MET System security Simulator Operator Recorder, Group Display "AOP903", Real Time Plot "Wind", and other personnel, Inform the control room that you will available local wind speed display notify any personnel working outside

Inform the CRS/SM to Refer to EPIP 1.1 and 1.2 for Emergency Action that may not have heard the warning Level Classification and Notification requirements

Start the C Well Water Pump Simulator Operator After the site wide Activate ET 9 announcement This will trip the A Well Water Pump is complete, TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 16 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 6: CREW: Respond to a loss of RWCU Pump B When the BOP Simulator Operator is adjusting well Activate ET11 OATC:

water, This will trip the B RWCU Pump

Will determine that the B RWCU Pump has tripped and take action IAW ARP 1C04B A-9, RWCU Pump Lo Flow Simulator Operator o Verify the running RWCU Pump has tripped Call the control room as a security o Direct an operator to verify the RWCU Beds in HOLD Guard and report that there was a o Direct an operator in investigate the pumps locally lightning strike just north of the plant o Direct an operator to reset the breaker1B3509(1B4329) o Check for fault light on the variable speed drives If sent to the A Simulator Operator o Crack open MO-2723, Cleanup Demin Bypass valve well house to Acknowledge the request

As Time permits, investigate, o If the RWCU System will remain shutdown/isolated for an extended Simulator Operator period of time, computer point B017, RWCU System Flow, may Wait 7 min and report the You are in the well house and 1C374, need to be substituted to zero to maintain accurate ACUMEN following, 480/277 VAC Power Panel is dark Periodic Reports.

o Restore RWCU to service if the BOP goes BOP Evaluator to terminal Respond to the BOP that fuse F08 CRS:

block TC1 to looks good, the Pop Up Pin is not

Determine that TRM Spec 3.3.4, RCS Conductivity Monitoring check fuse F08, popped out Instrumentation, is not met and enter Condition A

Direct Chemistry to swap to Recirc Sample Point for monitoring RCS If sent to check Simulator Operator Chemistry the newly Acknowledge the request started well water pump, Simulator Operator Wait 4 min and report, the Well is running SAT TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 17 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7: CREW: Respond to the rising in Dry Well Pressure LOCA When the CRS:

actions of the Simulator Operator

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

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

Will begin to perform the actions of AOP 573

Will monitor DW pressure and report to the CRS as necessary

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

NRC Scenario 3, Rev. 0 SEG Page 18 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 7:(cont) CREW: EOP 1 Actions Reactor Scram 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 TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 19 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 8: EOP CREW: Mitigate containment parameters in accordance with EOP 2, Primary 2 Actions Simulator Operator Containment Control When the DW Verify ET 5 goes TRUE reaches 2 psig, This will trip the B CS pump after a 3 min CRS will enter EOP 2 concurrently with EOP 1 and direct the following time delay and TRIP the HPCI Aux Oil actions; Pump after 5 seconds.

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 Simulator Operator BOP: (95.63)

Verify ET7 goes active when drywell

Sprays the Torus sprays are initiated

Install Defeat 4 This will cause the drywell leak to get

Sprays the DW (Critical) (95.65) worse to overtake all high pressure

Establishes Torus Cooling injection sources

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

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

NRC Scenario 3, Rev. 0 SEG Page 21 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT 10: CREW: Take actions directed by EOP 1/ ALC 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 TR-AA-230-1007-F13, Revision 0

NRC Scenario 3, Rev. 0 SEG Page 22 of 24 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EVENT10: CREW: Take actions directed by Emergency Depressurization (ED)

(cont) 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 Simulator Operator emergency Place the Simulator in FREEZE depressurized and RPV level is being Floor Instructor restored to the Announce that the scenario is directed band, complete, please stand by your and at the stations and do not discuss the direction of the scenario with your crew Lead Evaluator,

- - END OF SCENARIO ***

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

NRC Scenario 3, Rev. 0 SEG Page 23 of 24 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Trip of 1B09, the A RWS subsystem

2. Trip of the A Well

3. LOCA After EOP Entry:

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

2. Failure of automatic injection following ED Abnormal Events:

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

2. AOP 408 for the loss of the D Well

3. AOP 304.1 for the loss of the startup transformer

4. AOP 903 for weather related events Major Transients:

1. LOCA

2. Failure of ECCS to automatically start Critical Tasks:

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

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

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

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

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