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2017 Point Beach Nuclear Plant Initial License Examination Administered Simulator Scenarios
	ML17205A475
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Site:	Point Beach
Issue date:	05/23/2017
From:	; Point Beach
To:	; NRC/RGN-III/DRS/OLB
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SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 15E LMS Rev. Date:

SEG TITLE: 2017 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 Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _1___________ Op-Test No.: _2017____

Examiners: ___________________________ Operators: _____________________________

Initial Conditions: _Unit 1 is at approximately 100%. Unit 2 is on ice melt. 1PT-950, Loop B Containment Pressure has been removed from service. Repairs are expected to be complete during the upcoming refueling outage. 1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure. ____

Turnover: Normal Shift routine. Lower power utilizing OP 3A, Power Operation to Hot Standby at _

30%/hr in preparation for refueling outage _______________________________________________

Event Malf. No. Event Event No. Type* Description I-BOP 1 XMT1CNM014A I-SRO 1PT-947, Loop A Containment Pressure Transmitter fails low TS-SRO I-BOP 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller 2 CNH1CFW003F I-SRO oscillates in automatic 3 XMT1AFW005A TS-SRO 0LT-4040, T-24A CST Level Transmitter fails low R-RO 4 ANN-C02D-A09 N-BOP 1X01, Main Transformer loss of cooling (rapid down power)

R-SRO C-RO 5 CNH1PCS004F 1P-2A, Auto Charging Pump controller oscillation failure C-SRO 6 MAL1RCS001 M-ALL Large Break LOCA BKR1RHR001 C-BOP 1P-10A, RHR pump fails to start in Auto 7 MOT1RHR002 1P-10B, RHR pump trips upon starting RLY1PPL020 8 RLY1PPL021 C-BOP Containment Spray fails to actuate, manual alignment required.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to the failures listed below in accordance with plant procedures:

1. 1PT-947, Loop B Containment Pressure Transmitter failing low / removing from service

2. 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillating in automatic only

3. 0LT-4040 Condensate Storage Tank Level transmitter fails low

4. 1X-01, Main Transformer loss of cooling

5. Auto charging pump controller oscillating in automatic only

6. Instantaneous Large Break LOCA

7. RHR pump failures

a. 1P-10A, RHR pump failing to auto start

b. 1P-10B, RHR pump tripping

8. Containment Spray failing to actuate Embedded within these events is the expectation to properly utilize Technical Specifications.

Enabling None Objectives:

Prerequisites: 1. Simulator available

2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator

3. Communicator

4. NRC Evaluators

References:

1. 0-SOP-IC-001 BLUE, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels

2. 0-SOP-IC-002, Technical Specifications LCO - Instrument Cross Reference

3. AOP-1D Unit 1, Chemical And Volume Control System Malfunction

4. AOP-2B Unit 1, Feedwater System Malfunction

5. AOP-17A Unit 1, Rapid Power Reduction

6. AOP-24, Response to Instrument Malfunctions

7. ARP C02 D 1-9, 1X-01 Main Trans Loss Of Cooling

8. ARP C01 A 2-9, T-24A or B Condensate Storage Tanks - Level High or Low

9. CSP-P.1 Unit 1, Response To Imminent Pressurized Thermal Shock Condition

10. EOP-0 Unit 1, Reactor Trip Or Safety Injection Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG

11. EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant

12. EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation, Low Head Injection

13. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients

14. OP-3A Unit 1, Power Operation To Hot Standby Unit 1

15. RMS Alarm Setpoint And Response Book

16. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021.

Operating N/A Experience:

Risk Significant HEP-RHR-EOP13-LL, OPS FAIL TO ALIGN SI FLOR LOW CONT SUMP Operator Actions: RECIRC (LLOCA/MLOCA), FV: 4.46E-03 Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 35

PBN LOI 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Unit 1 is at approximately 100% EOL, Unit 2 is on ice melt.

1PT-950, Loop B Containment Pressure has been removed from service.

Repairs are expected to be complete during the upcoming refueling outage.

1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.

Normal Shift routine will be to lower power at 30%/hr utilizing OP-3A Unit 1, Power Operation To Hot Standby Unit 1.

Events:

1PT-947, Loop A Containment Pressure Transmitter fails low 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040 Condensate Storage Tank Level transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto Large Break LOCA RHR pump malfunctions 1P-10A, RHR Pump fails to auto start 1P-10B, RHR Pump trips Containment Spray fails to actuate Terminate the scenario when crew has completed Step 21 of EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation - Low Head Injection and is waiting for RWST level to lower to 34%.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SEQUENCE OF EVENTS Event # Description

1. 1PT-947, Loop A Containment Pressure Transmitter fails low Once the crew has taken the shift, 1PT-947, Loop A Containment Pressure Transmitter fails low.

The crew should implement AOP-24, Response to Instrument Malfunctions and take the channel out of service in accordance with 0-SOP-IC-001 BLUE, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE.

Address Technical Specifications.

2. 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic After identifying the malfunction, the crew may shift 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller to manual to mitigate the transient per OM 3.7, AOP and EOP Procedure Usage for Response to Plant Transients The crew should implement AOP-2B Unit 1, Feedwater System Malfunction and lower turbine load to maintain reactor power less than 100% in accordance with AOP-17A Unit 1, Rapid Power Reduction if required.

The crew may reference and or implement AOP-24, Response to Instrument Malfunctions.

3. 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low The crew should reference ARP C01 A 2-9 and ARB C01 A 3-9 for the failed level transmitter and determine the applicable Technical Specifications Required Actions.

4. 1-X01, Main Transformer loss of cooling Unit 1, 1X-01, Main Transformer B phase incurs a loss of cooling as indicated by annunciator C02 D 1-9, 1X-01 Main Trans Loss of Cooling.

The crew should implement ARP C02 D1-9, 1X-01 Main Trans Loss of Cooling and based on field reports, begin ramping the unit off-line in accordance with AOP-17A Unit 1, Rapid Power Reduction.

5. 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto During the load reduction, 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto.

The should take manual control of 1HC-428A, 1P-2A Charging Pump Hand Controller and implement AOP-1D Unit 1, Chemical and Volume Control System Malfunction.

The crew may implement/reference AOP-24, Response to Instrument Malfunctions (not required).

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG

6. Large Break LOCA The crew should implement EOP-0 Unit 1, Reactor Trip or Safety Injection, EOP-1 Unit 1, Loss of Reactor or Secondary Coolant and EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation, Low Head Injection.

7. RHR pump malfunctions: 1P-10A, RHR Pump fails to auto start and 1P-10B, RHR Pump trips The crew should address the failures by starting 1P-10A, RHR Pump:

After EOP-0 Unit 1 Immediate Actions are complete in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients OR EOP-0 Unit 1, ATTACHMENT A, AUTOMATIC ACTION VERIFICATION Step A3.b.RNO.

8. Containment Spray fails to actuate The crew should address the failures by aligning the Containment Spray System:

After EOP-0 Unit 1 Immediate Actions are complete in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients OR EOP-0 Unit 1, ATTACHMENT A, AUTOMATIC ACTION VERIFICATION Step A12.a.RNO.

STOP Terminate the scenario when crew has completed Step 21 of EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation - Low Head Injection and is waiting for RWST level to lower to 34%.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

General Instructions Simulator Setup Instructions:

Load IC-3 and go to run Open the saved Event and Schedule files from the secure drive:

Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)

Reposition bistable switches for: 1PT-950, Loop B Containment Pressure Transmitter Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:

Load saved IC and go to run Open the saved Event and Schedule files:

Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:

Setup: 1PT-950, Loop B Containment Pressure Transmitter is out of service / 1W-3B, CTL Rod Drive Shroud Fan MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT950 LOOP B CONT XMT1CNM017A PRESSURE 00 :00 :00 - 90 Preload XMTR FIXED OUTPUT Simulator Setup:

1. Place OOS magnet at PT-950, Containment Pressure

2. Place a RED dot on C01 B 1-5, U1 Containment Pressure Channel Alert

3. Place 1W-3B CS in pull-out, install OOS magnet.

4. Install an orange Guarded magnet at 1W-3A.

SIMULATOR MALFUNCTIONS:

Event 1: / 1P-947, Loop A Containment Pressure Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT947 LOOP A CONT XMT1CNM014A PRESSURE 00 :00 :00 00 :00 :00 1 00 :00 :00 - -6 SETUP XMTR FIXED OUTPUT Expected field communications:

1. None Event 2: 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PC2273 FW HTR EMER CNH1CFW003F BYPASS VLV 00 :00 :00 00 :01 :00 5 00 :00 :00 - 90 PLE CNTRL OSC AUTO ONLY Expected field communications:

1. IF directed to locally monitor Feedwater Heater level, THEN report #2 Feedwater Heater level is (was) low and that the level control system is responding in automatic to restore level.

With the controller in automatic:

IF an operator is dispatched to locally investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two minutes report that the valve is cycling open and close in response to the air signal being supplied.

With the controller in manual:

IF an operator is dispatched to locally investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two minutes report that the valve is stable (matching the control rooms indication).

If directed to investigate Hydrogen Pannel alarm, report alarm is due to low pressure, caused by the secondary temperature transient.

Reset the local alarm using LOA1MGA001 Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 3: 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 0-LT4040 COND STOR TK T24A 00 : 00 XMT1AFW005A 00 :00 :00 00 :00 :03 11 - 0 PLE LEVEL FIXED :00 OUTPUT Expected Communications:

1. IF an AO is sent to locally investigate 0LT-4040, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally.

Event 4: 1X-01, Main Transformer loss of cooling MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE MAIN TRANS ANN-C02D-A09 1X01 LOSS OF 00 :00 :00 - 9 00 :00 :00 - ON PLE COOLING 1-P99A SGFP SEAL WATER LOA1CFW083 00 :01 :00 - 11 00 :00 :00 - ON PLE INJECT PUMP C.S.

1-P99B SGFP SEAL WATER LOA1CFW084 00 :01 :10 - 11 00 :00 00 - ON PLE INJECT PUMP C.S.

Expected field communications:

1. IF an AO is directed to locally investigate 1X-01, Main Transformer; wait two minutes and THEN report breaker 8MN in the Cooler Control Cabinet for phase B is in the tripped condition and none of the cooling units are running.

2. IF an AO is directed to locally start 1P-99A and 1P-99B, Main Feed Pump Seal Water Pumps; insert Trigger 11 and THEN report when they are running.

3. WHEN the AO is directed to monitor transformer temperatures THEN report as follows:

Phase B initial temperatures: Oil = 35°C, Winding = 55°C Phase B Temperatures rise about 1°C every 5 minutes Phase A and C temperatures are stable, same initial temperature as B.

Event 5: 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-HC428A P-2A CHARGE PUMP CNH1PCS004F SPEED HAND 00 :00 :00 00 :00 :10 13 00 :00 :00 - 100 PLE CTLR OSC AUTO ONLY Expected field communications:

1. IF the PAB AO is directed to check that there are no charging pump relief valves lifting on unit 1; wait two minutes and THEN report that no charging pump relief valves on are lifting Unit 1.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 6: Large Break LOCA MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE HOT MAL1RCS001 DBA LOCA 00 :00 :00 00 :00 :00 15 00 :00 :00 - PLE LEG A 0-SW-322 1HX-12A CC LOA1SWS048 00 :04 :00 00 :00 :30 17 00 :00 :00 - 0.4 When directed by crew HTEXCH OUTLET 1-CC-744B BA EVAP HX-8A LOA1CCW018 00 :07 :00 00 :00 :30 17 00 :00 :00 - 0 When directed by crew RETURN STOP VALVE 1-CC-740A NON-REGEN LOA1CCW016 00 :01 :00 00 :00 :30 17 00 :00 :00 - 0 When directed by crew HX-3A&B INLET VALVE 1-CC-750A LOA1CCW021 SEAL STR HX-5 00 :02 :30 00 :00 :30 17 00 :00 :00 - 0 When directed by crew INLET VALVE 1-SI-897A LOA1SIS030 HANDWHEEL 00 :01 :00 00 :00 :30 19 00 :00 :00 - 0 When directed by crew GAG 1-SI-897B LOA1SIS031 HANDWHEEL 00 :02 :00 00 :00 :30 19 00 :00 :00 - 0 When directed by crew GAG Expected field communications:

1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.

2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.

3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.

4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.

5. WHEN directed to perform Attachment A of EOP-1.3; insert trigger 17, wait for the valves to finish stroking and THEN report that the CCW alignment is complete.

6. WHEN directed to locally shut 1SI-897A and B, SI Test Line Return Isolation AOVs; insert trigger 19, wait for the valves to finish stroking, and THEN report the valves are closed.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 7: RHR pump malfunctions: 1P-10A, RHR Pump fails to auto start and 1P-10B, RHR Pump trips MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-B5212A P-10A FAIL BKR1RHR001 RH REMOVAL 00 :00 :00 - - 00 :00 :00 - AUTO PRELOAD PUMP CKTBKR CL P-10B RH RESIDUAL WINDING MOT1RHR002 00 :00 :00 - - 00 :00 :00 - GROUND PRELOAD HEAT REMOVAL PUMP Expected field communications:

1. IF the PAB AO is directed to check 1P-10B, RHR Pump; wait two minutes and THEN report that the motor is not running, discolored, hot to the touch and smells acrid. IF asked; THEN report that there is no fire.

2. IF an AO is directed to locally investigate breaker 1B52-21A on 1B-04 for 1P-10B, RHR Pump; wait two minutes and THEN report that breaker has tripped on overcurrent.

Event 8: Containment Spray fails to actuate MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-CS-10X TRAIN A CONT FAIL AS RLY1PPL020 00 :00 :00 - - 00 :00 :00 - PRELOAD SPRAY IS AUXILIARY 1-CS-20X TRAIN B CONT FAIL RLY1PPL021 00 :00 :00 - - 00 :00 :00 - PRELOAD SPRAY AS IS AUXILIARY Expected field communications:

1. None Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.

Crew Shift Turnover Information: See Attached Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Crew takes the Normal Shift routine will be to lower power CREW Implements OP-3A Unit 1, Power Operation To Hot Standby Unit 1, utilizing OP-3A Unit 1, Power Operation To Hot starting at Step 5.1.9.

watch: ________ Standby Unit 1.

Event 1: Trigger 1 [XMT1CNM017A, 1-PT-947 LOOP A BOP The crew responds to the containment pressure alarm and diagnoses that 1PT-947, Loop A CONT PRESSURE XMTR FIXED alarm being due to an instrument failure.

Containment OUTPUT, Value = -6, Ramp = 0 sec]

Pressure OS Implements AOP-24, Response to Instrument Malfunctions Transmitter fails After completion of crew turnover and the BOP 1. Identify Failed Instrument low examinees have assumed the watch, insert Trigger 2 Check If Failed Instrument Is A Controlling Channel 1 to cause 1PT-947, Loop A Containment Pressure 3. Establish Manual Control As Required Transmitter to fail low. 4. Return Affected Parameter(s) To Desired Value(s)

Start: _________ 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE Plant Response: REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is 1PT-947, Loop A Containment Pressure Transmitter NOT An Input To RTO fails low bringing in a containment pressure PPCS 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, Alarm. ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE Cues: 7. Return Controls To Automatic If Desired 1C20 D 2-1, PPCS Priority Alarm 8. Check Failure For Technical Specification Or TRM Applicability Containment Pressure PPCS Alarm 9. Return To Procedure And Step In Effect Expected Communications: OS Implements 0-SOP-IC-001 BLUE, ROUTINE MAINTENANCE None BOP PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE Instructor Note: If the crew decides to NOT 1. In cabinet C-115, place the following bistable trip switches in the remove the failed containment pressure TRIP position (toggle switch up) and check expected response channel from service, have the Shift Manager SAFEGUARD ACTUATION (P/947) provide a cue directing the crew to take action CONTAINMENT SPRAY LOGIC (P/947) to remove it from service. 2. Remove from scan PPCS point ID PT947, CNMT LR PRESS BLU.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: Reference Technical Specifications Once the crew has completed taking the channel Technical Specifications:

out of service per 0-SOP-IC-001 BLUE and has OS Reference 0-SOP-IC-002:

addressed Technical Specifications, or at the Table 3.3.2-1 D. One channel D.1 Place channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months discretion of the Lead Examiner, proceed with the inoperable trip Item 1c next event.

item 2c OR item 3c D.2.1 Be on MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months item 4d-2 AND item 4e-2 D.2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months item 5c item 6c Table 3.3.5-1 item 2 Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 2: Trigger 5 [CHN1CFW003F, 1-PC2273 FW HTR BOP Identifies 1PC-2273, Feedwater Heater Emergency Bypass Valve 1PC-2273, EMER BYPASS VLV CNTRL OSC Controller malfunction by indicated 1PC-2273, Feedwater Heater Feedwater Heater AUTO ONLY = 90; Ramp = 00:01:00] Emergency Bypass Valve Controller output oscillating (90% of scale),

Emergency 1CS-2273, Feedwater Heater Emergency Bypass Valve indication Bypass Valve Insert Trigger 5 to cause 1PC-2273, Feedwater showing intermediate (Red and Green lights lit), rise in reactor power, Controller Heater Emergency Bypass Valve Controller to SG A and B level deviations with corresponding annunciators for SG A oscillates in oscillate in automatic. and B level deviations. May take manual control of 1PC-2273, automatic Feedwater Heater Emergency Bypass Valve Controller to mitigate the Plant Response: transient.

1PC-2273, Feedwater Heater Emergency Bypass Start: __________ Valve Controller output oscillates (90% of scale), OS1 Implements AOP-2B Unit 1, Feedwater System Malfunction 1CS-2273, Feedwater Heater Emergency Bypass Monitor Foldout Page Valve indication shows intermediate (Red and OATC 1. Maintain Reactor Power Less Than or Equal to 100%

Green lights lit, rise in reactor power, SG A and B RNO: Reduce power per AOP-17A Unit 1, Rapid Power Reduction level deviations with corresponding annunciators for as necessary to maintain reactor power less than or equal SG A and B level deviations. to 100%.

2. Determine the Secondary System Malfunction AND go to the Cues: appropriate step (16) 1PC-2273, Feedwater Heater Emergency Bypass 16. Perform the following:

Valve Controller output oscillates (90% of scale) BOP a. Check Main Feed Pump Suction Pressure - GREATER THAN 1CS-2273, Feedwater Heater Emergency Bypass 190 PSIG Valve indication shows intermediate (Red and b. Check LP Feedwater Heater Bypass Valve - SHUT Green lights lit) RNO: Perform the following:

Reactor power rises 1) IF 1CS-2273 open due to controller malfunction, SG A and B level deviated from normal program THEN perform the following:

band a) Ensure LP feedwater heater bypass Annunciators: controller set at 25 psig below main feed 1C03 1E2 1-2, Steam Generator A Level pump suction pressure in auto Setpoint Deviation/Trouble 1PC-2273 1C03 1E2 1-5, Steam Generator B Level b) IF controller will NOT operate in auto, THEN Setpoint Deviation/Trouble place controller in manual and place LP 1C03 1F 3-1, LP Feedwater Heater 1, 2, or 3 feedwater heater bypass valve in desired Level Low position.

c. Return to Step 2

3. Check Plant Conditions - STABLE

4. Check Secondary System Alignment - NORMAL

5. Check Change in Reactor Power - LESS THAN 15% IN ANY ONE HOUR

6. Notify the DSM Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE The crew should implement AOP-2B Unit 1, OS Feedwater System Malfunction, and lower turbine 7. Return to Procedure and Step in Effect load to maintain reactor power less than 100%. OS Implements AOP-17A Unit 1, Rapid Power Reduction (if necessary)

Prompt action by the crew to take manual control of 1CS-2273 may eliminate the need to take action to OATC 1. Check Power - GREATER THAN 100%

reduce turbine load. 2. Reduce Load - LESS THAN 100%

a. Manually insert control rods 10 steps to initially lower RCS If the overpower condition is recognized before the temperature.

crew has diagnosed the secondary malfunction, the b. WHEN control rod movement has started, THEN reduce turbine crew may enter AOP-17A first to address the load.

overpower condition. 1) Select Turbine Manual.

BOP 2) Reduce turbine load by 2% by pulsing GV Down IF the crew discusses returning to full power, THEN pushbutton.

monitor for proper reactivity control implementation OATC/BOP c. Commence Boration per shiftly reactivity brief.

and supervisor oversight. Set quantity on boric acid flow counter, YIC-110A Set flow rate on boric acid flow controller, HC-110 Expected Communications: Place reactor makeup mode selector in BORATE IF directed to locally monitor Feedwater Heater OATC Place reactor makeup control switch to START level, THEN report #2 Feedwater Heater level OATC d. IF NI power is still greater 100%, THEN reduce turbine load in is (was) low and that the level control system is 1% increments and adjust rods as necessary until less than responding in automatic to restore level. 100%.

With the controller in automatic: e. Return control rods to auto.

IF an operator is dispatched to locally f. IF less than 100% AND additional load reduction is required, investigate 1CS-2273, Feedwater Heater THEN Go to Step 3.

Emergency Bypass Valve, THEN after two RNO Perform the following:

minutes report that the valve is cycling open and 1) Restore Tavg-Tref differential to <1°F using rod close in response to the air signal being control in manual.

supplied. 2) Return affected controls to automatic per Shift With the controller in manual: Management.

Turbine controls IF an operator is dispatched to locally Rod Control investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two 2) Go to Procedure and Step In Effect.

minutes report that the valve is stable (matching the control rooms indication).

Continuation Criteria:

After the crew has addressed the 1CS-2273 failure per AOP-2B Unit 1, or at the discretion of the Lead Examiner, continue on with the next event.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 7 [XMT1AFW005A, 0-LT4040 COND BOP CO Identifies the failed level channel for T-24A Condensate Storage Tank, 0LT-4040 STOR TK T24A LEVEL FIXED dispatches an AO to investigate and references ARP C01 A 2-9, T-Condensate OUTPUT, VALUE = 0, RAMP = 3 sec] 24A or B Condensate Storage Tanks - Level High or Low and ARB Storage Tank T- C01 A 3-9, T-24A or B Condensate Storage Tanks Level Low-Low.

24A Level Insert Trigger 7 to cause 0LT-4040 Condensate Transmitter fails Storage Tank T-24A Level Transmitter to fail low. OS Reference Technical Specifications low Plant Response: Technical Specifications:

Start: _________ Indicated tank level goes to 0%. 3.3.3 Post Accident Monitoring (PAM) Instrumentation is not met (2 required channels).

Cues:

CONDITION REQUIRED ACTION COMPLETION C01 A 2-9, T-24A or B Condensate Storage TIME Tanks - Level High or Low C01 A 3-9, T-24A or B Condensate Storage A. One or more A.1 Restore 30 days Tanks Level Low-Low Functions with required PPCS: L-4040 CST LVL A low one required channel to channel OPERABLE Expected Communications: inoperable. status.

IF an AO is sent to locally investigate 0LT-4040 T-24A Condensate Storage Tank Level Transmitter, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally.

Continuation Criteria:

One the crew has addressed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 9 [ANN-C02D-A09, MAIN TRANS 1X01 LOSS BOP Acknowledge the alarm and refer to Alarm Response Procedure for 1-X01, Main OF COOLING = ON] C02 D 1-9, 1X-01 Main Tran Loss of Cooling.

Transformer loss of cooling Insert Trigger 9 to override on the annunciator for OS Implements ARP C02 D 1-9, 1X-01 Main Tran Loss of Cooling C02 D 1-9, 1X-01 Main Tran Loss of Cooling. 3.1 DISPATCH AO to validate alarm for the affected Main Start: _________ Transformer(s) and PERFORM the following:

Plant Response: CHECK cooler fan operation Annunciator only. CHECK oil cooler operation CHECK local alarm panel Cues: 3.2 INSTRUCT AO to perform the following for affected transformer(s):

C02 D 1-9, 1X-01 Main Tran Loss of Cooling 3.2.1 Continuously MONITOR Winding and Oil temperature indicators and REPORT temperature changes to Control Outside air temperature for this scenario is 24°F (- Room.

4.44°C). Per the table using a conservative 3.2.2 CONTINUE attempts to restore cooling at each affected temperature of 0°C, time to get the unit off-line transformer using the flowing steps as applicable:

should be 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . a. CHECK affected Transformer Phase Cooling Control Cabinet(s) for alarms Expected Communications: b. OPEN affected Cooling Control Cabinet(s) and CHECK WHEN an AO is directed to locally investigate 1X-01, for tripped Main Power Supply breaker 8MN.

Main Transformer; wait two minutes and THEN report h. IF no cooling banks can be started, THEN immediately breaker 8MN in the Cooler Control Cabinet for phase TAKE Main Generator OFF-LINE AND DE-ENERGIZE B is in the tripped condition and none of the cooling Main Transformer based on loading and ambient units are running. Breaker 8MN will not reset if temperature as follows:

attempted. 1. REFER to AOP-17A Unit 1, Rapid Power Reduction AND REDUCE power at a rate WHEN the AO is directed to monitor transformer determined by Shift Management temperatures THEN report as follows:

Phase B initial temperatures: Oil = 35°C, Winding = 55°C Phase B Temperatures rise about 1°C every 5 minutes Phase A and C temperatures are stable, same initial temperature as B.

SM Cue: If asked, recommend a 1%/min ramp rate.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS Implements AOP-17A Unit 1, Rapid Power Reduction Continuation Criteria:

When the crew begins reducing load per AOP-17A, OATC/BOP 1. Check Power - GREATER THAN 100%

Rapid Power Reduction, or at the discretion of the 3. Determine Desired Power Level Or Condition To Be Met Lead Examiner, continue with the next event. Control Room Supervisor announce desired power level or condition using less than or equal to 3%/min ramp rate.

4. Commence Boration As Necessary to Target Load

a. Set boric acid flow totalizer to desired quantity

b. Set boric acid flow controller to desired flow rate

c. If desired, start second boric acid transfer pump

d. Place Reactor Makeup Mode Selector Switch to Borate.

e. Place Reactor Makeup Control Switch to Start

5. Select Turbine Rate And Reduce Load o Operator Automatic Load Rate Control

a. Ensure EH controls are set for Operator Auto

b. Ensure First Stage In is selected

c. IF first stage pressure is unavailable, THEN select First Stage Out OS d. Ensure the appropriate load rate is selected on load rate thumb-wheel

e. Select target end-point on reference control OATC/BOP f. WHEN temperature reduction of at least 0.5°F is observed on Tavg-Tref indicator, THEN depress GO push-button

g. Continue with next step Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS 6. Notify Power System Supervisor (PSS) Of Load Reduction Expected Communications: 7. Check Rod Control System - IN AUTO IF an AO is directed to locally start 1P-99A and 1P- OATC/BOP 8. Energize Pressurizer Backup Heaters 99B, Main Feed Pump Seal Water Pumps; insert 9. Check PZR Pressure - CONTROLLING IN AUTO Trigger 11 and THEN report when they are running. 10. Check PZR Level - CONTROLLING IN AUTO

11. Check Steam Generator Level - CONTROLLING IN AUTO

12. Ensure Main Feed Pump Seal Water Pump - RUNNING o 1P-99A o 1P-99B

13. Maintain RCS Tavg:

Greater than 540°F Less than 577°F Within 7°F of program Tavg

14. Check AFD - WITHIN LIMITS:

o PPCS Screen AFD PLOT o ROD 1.2, HFP EQUIL DELTA FLUX

15. Control MSR temperatures - LESS THAN 500°F o HC-2085

16. Determine Desired End-Point - LESS THAN 60% TURBINE LOAD Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5: Trigger 13: [CNH1PCS004F, P-2A CHARGE PUMP SPEED HAND CTLR OSC AUTO OATC Acknowledges the annunciator and identifies 1HSC-428A, 1P-2A 1HC-428A, 1P-2A, Charging Pump Speed Hand Controller output oscillating between 0 Charging Pump ONLY, Value = 100]

and 100% output and takes manual control to stabilize pump speed Hand Controller and pressurizer level.

oscillates in auto Insert Trigger 13 to cause 1P-2A, Charging Pump Speed to oscillate between minimum and maximum OS Implements AOP-1D Unit 1, Chemical and Volume Control System flow while in automatic. OATC Malfunctions Start: __________ 1. Check RCS Leak - NOT IN PROGRESS Plant Response: 2. Determine CVCS Malfunction:

1P-2A, Charging Pump Speed will oscillate between IF any of the following is true, THEN go to Step 3 minimum and maximum flow while in automatic.

Any charging pump - TRIPPED Cues: OR Any charging pump - NOT OPERATING PROPERLY 1C04 1C 1-8, Charging Pump Speed Control OR Trouble Any charging pump controller - Not RESPONDING 1C03 1D 2-1, 1P-1A or B RCP LABYR Seal dP PROPERLY Low 3. Check Any Charging Pump - RUNNING 1HSC-428A, 1P-2A Charging Pump Speed Hand 4. Check Charging Flow - STABLE Controller output oscillating between 0 and 100% RNO: Perform the following:

output. a. Place running charging pumps - IN MANUAL

b. IF charging flow NOT stable, THEN stop all charging Expected Communications: pumps and go to Step 10 IF the PAB AO is directed to check that there are 5. Check Charging Pump Relief - NOT LIFTED no charging pump relief valves lifting on Unit 1; 6. Check Charging Pump Suction Supply - ADEQUATE wait two minutes and THEN report that Unit 1 7. Check Charging System Response:

charging pump relief valves are NOT lifting. Desired Charging Pumps - RUNNING Labyrinth seal P - GREATER THAN 20 INCHES Letdown line pressure - STABLE PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL

8. Notify Duty Station Manager

9. Return to Procedure And Step In Effect Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS May implement AOP-24, Response to Instrument Malfunctions When the crew has addressed the failure per AOP- OATC 1. Identify Failed Instrument 1D Unit 1 or AOP-24, and is pursuing returning the RNO: IF a controller has failed, THEN go to Step 3 system to automatic, or at the discretion of the Lead 3. Establish Manual Control as Required:

Examiner, continue with the next event. o Place affected controller in manual OR o Place any affected equipment controls in manual

4. Return Affected Parameter(s) To Desired Value(s)

BOP 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO.

6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFGUARDS OR PROTECTION SENSOR FROM SERVICE RNO: IF failed instrument channel can NOT be removed from service OR is NOT addressed in 0-SOP-IC-001, THEN perform the following:

a. IF failed channel can NOT be removed from service, THEN inform SM of failed channel status.

7. Return Controls To Automatic If Desired

8. Check Failure For Technical Specification Or TRM Applicability

9. Return To Procedure And Step In Effect Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 6: Trigger 15: [MAL1RCS001, DBA LOCA HOT LEG OATC DIAGNOSE a large break LOCA event.

Large Break A]

LOCA OS Implements EOP-0, Unit 1 Reactor Trip or Safety Injection Insert Trigger 15 to cause a Large Break LOCA. OATC 1. Verify Reactor Trip Start: _________ 1P-10A, RHR Pump fails to auto start and 1P-10B, 2. Verify Turbine Trip RHR Pump trips. 3. Verify Power to AC Safeguards Buses

4. Check if SI is Actuated Plant Response: a. Any SI annunciators LIT Rapid depressurization of RCS, automatic SI b. Both trains of SI - Actuated actuation. RNO: Manually actuate both trains of SI and CI Cues: BOP Rapid drop in RCS pressure Auto SI Event 7: Preloads: [BKR1RHR001, 1-B5212A P-10A RH BOP NOTE: Following immediate actions, CREW may manually RHR pump Removal Pump CKTBKR, Fail Auto start RHR and realign the Containment Spray system malfunctions: 1P- Close] in accordance with OM 3.7, AOP And EOP Procedure 10A, RHR Pump [MOT1RHR002, P-10B RH Removal Usage For Response To Plant Transients.

fails to auto start Pump, Winding Ground]

and 1P-10B, RHR Pump trips Event 8:

Preloads: [RLY1PPL020, 1-CS-10X TRAIN A Containment CONT SPRAY AUXILIARY, Fail As Is]

Spray fails to [RLY1PPL021, 1-CS-20X TRAIN B actuate CONT SPRAY AUXILIARY, Fail As Is]

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: OATC EOP-0 continued ...

IF the PAB AO is directed to check 1P-10B, RHR Monitor Foldout Page Criteria: RCP Trip Criteria Pump; wait two minutes and THEN report that the IF both conditions listed below occur, THEN trip both RCPs:

motor is not running, discolored, hot to the touch and RCS subcooling - LESS THAN [36 ºF] 26 ºF smells acrid. IF asked; THEN report that there is no fire. SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF IF an AO is directed to locally investigate breaker 1B52- DELIVERING FLOW 21A on 1B-04 for 1P-10B, RHR Pump; wait two minutes and THEN report that breaker has tripped on BOP 5. Perform ATTACHMENT A, Automatic Action Verification while overcurrent. continuing with this procedure OATC 6. Verify AFW pumps - Running

7. Check RCP Seal Cooling

8. Check RCS Temperatures

9. Check PZR PORVs and Spray Valves

10. Check if RCPs should be stopped

11. Check if SGs are NOT Faulted

12. Check if SG Tubes are NOT Ruptured

13. Check if RCS is Intact RNO: Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT The LOCA / SI injection will result in meeting a IF an INTEGRITY Critical Safety Function RED path is identified and Critical Safety Function INTEGRITY RED path reported to the OS prior to the crew implementing EOP-1.3, THEN the condition. Depending on when this condition is crew should implement CSP-P.1, Response to Imminent identified, the crew may enter, then immediately exit Pressurized Thermal Shock Condition.

CSP-P.1, Response to Imminent Pressurized 1. Check RCS pressure - GREATER THAN [450 PSIG] 325 PSIG.

Thermal Shock Condition, at Step 1. RNO: IF RHR flow is greater than 550 gpm, THEN return to procedure and step in effect.

STA CUE: Identify and report the INTEGRITY Critical Safety Function RED path when appropriate.

Status tree monitoring to commence following completion of Step A14 of EOP-0 Attachment A.

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service Water valves, LW-61 and 62, THEN report both

CT-5, Manually start at least one Low-Head ECCS Pump valves are closed.

WHEN directed to locally check CW pump house A3 Verify ECCS Pumps RUNNING temperature <105 ºF, wait 3 minutes and THEN a. SI Pumps - BOTH RUNNING report the temperature is 72 ºF and stable. b. RHR Pumps - BOTH RUNNING WHEN directed to locally check G03/G04 RNO WHEN SI sequence is complete, THEN manually Switchgear Room temperature <95 ºF, wait 3 start RHR pumps minutes and THEN report the temperature is 75 ºF A4 Verify Service Water Pumps RUNNING and stable. A5 Verify Containment Accident Cooling Units RUNNING IF directed to periodically check the status of A6 Verify Component Cooling Water Pumps - ONLY ONE spent fuel cooling, wait 5 minutes and THEN RUNNING A7 Check If Main Steam Lines Can Remain Open report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable. A8 Verify Containment Spray Not required

a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig RNO Perform the following:

1) Check containment spray actuated:

Annunciator {C01 B 2-6}, CONTAINMENT SPRAY, lit IF containment spray has NOT actuated, THEN manually actuate containment spray.

A9 Verify ECCS Flow A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 Verify Proper ECCS Valve Alignment Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP *CT-3, Manually actuate containment cooling A12 Check Containment Spray NOT ACTUATED RNO Check containment spray alignment

1. Ensure all containment spray pump discharge MOVs are open

2. Ensure at least one containment spray pump is running

3. IF two containment spray pumps are running, THEN place one containment spray pump in pull out

4. WHEN containment spray has been actuated for GREATER THAN two minutes, THEN ensure spray additive educator suction valve is open on running train A13 Stop any boration via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS Implements EOP-1, Loss of Reactor or Secondary Coolant Monitor Foldout Page criteria:

Containment Sump Recirculation Switchover Criteria IF either condition below is satisfied, THEN Go to EOP-1.3, TRANSFER TO CONTAINMENT SUMP RECIRCULATION - LOW HEAD INJECTION RWST level - LESS THAN 60%

OR RCS pressure less than [450 psig] 325 psig AND RHR flow greater than 550 gpm Expected Communications: OS Implements EOP-1.3 Unit 1, Transfer to Containment Sump Recirculation - Low Head Injection WHEN directed to perform Attachment A of EOP-1.3; 1 Reset SI insert trigger 17, wait for the valves to finish stroking BOP and THEN report that the CCW alignment is complete. OATC 2 Check RCS Break Size 3 Align CCW per ATTACHMENT A, LOCAL ALIGNMENT OF COMPONENT COOLING WATER While Continuing With The Procedure BOP 4 Direct Unnecessary Personnel To Evacuate The PAB 5 Check if Containment Sump pH Must Be Adjusted 6 Check if Train 'A' SI Flow Should Be Stopped

a. Check Train 'B; RHR injection flow - GREATER THAN 550 GPM

a. RNO Go to Step 7 7 Check if Train 'B' SI Flow Should Be Stopped

a. Check Train 'A; RHR injection flow - GREATER THAN 550 GPM

b. Stop train B SI pump and place in pull out

c. Stop train B RHR pump and place in pull out 8 Monitor Core Cooling

a. Maintain core exit thermocouple temperatures - LESS THAN 700º F 9 Evaluate Control Room Conditions:

a. Check Control Room RMS high alarms - CLEAR 1RE-101 1RE-235 Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: BOP 10 Isolate Component Cooling Flow To Containment

a. Check RCPs - BOTH STOPPED WHEN directed to locally shut 1SI-897A and B, SI Test b. Shut containment equipment CC supply header isolation Line Return Isolation AOVs; insert trigger 19, wait for the valves to finish stroking, and THEN report the valves valve:

are closed. 1CC-719 11 Isolate Component Cooling Flow to Non-Regenerative Heat Exchanger 12 Check Service Water Pumps - SIX RUNNING 13 Check Service Water Ring Header - CONTINUOUS FLOWPATH ESTABLISHED 14 Establish Component Cooling Flow To RHR Heat Exchangers:

a. Ensure component cooling pumps - AT LEAST ONE RUNNING

b. Open only one RHR heat exchanger shell side inlet valve:

1CC-738A 1CC-738B

c. Start second component cooling pump

d. Open second RHR heat exchanger shell side inlet valve:

1CC-738A 1CC-738B 15 Ensure RV Injection MOVs - BOTH OPEN 16 Align SI Test Lines For Recirculation

a. Check containment spray discharge valves - AT LEAST ONE OPEN IN EACH TRAIN Train A o 1SI-860A o 1SI-860B (preferred)

Train B o 1SI-860C o 1SI-860D (preferred)

b. Locally shut both SI test line return isolation AOVs:

1SI-897A 1SI-897B Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Termination Criteria: BOP 17 Align RHR Sump Suction Valves Terminate the scenario when crew has completed a. Open train A RHR pump suction from containment sump B Step 21 of EOP-1.3 Unit 1, Transfer To isolation valve:

Containment Sump Recirculation - Low Head 1SI-850A Injection and is waiting for RWST level to lower to b. Open train B RHR pump suction from containment sump B 34% or at the discretion of the Lead Examiner. isolation valve 1SI-850B 18 Check Train 'A' - READY FOR RECIRCULATION 19 Check Train 'B' - READY FOR RECIRCULATION 20 Check Battery Chargers Supplying DC Buses - ENERGIZED 21 Check RHR Trains - At Least One Ready For Recirculation Train A OR Train B 22 Check RWST Level - LESS THAN OR EQUAL TO 34%

RNO: Perform the following:

a. WHEN RWST level is less than or equal to 34%, THEN immediately return to this procedure and continue with Step 23.

b. Implement Critical Safety Procedures and continue with Procedure And Step In Effect.

- - END OF SCENARIO ***

Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)

Malfunctions:

Before EOP Entry:

1PT-947, Loop A Containment Pressure Transmitter fails high 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040, Condensate Tank T-24A Level Transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto After EOP Entry:

RHR pump malfunctions 1P-10A, RHR Pump fails to auto start 1P-10B, RHR Pump trips Containment Spray fails to actuate Abnormal Events:

1PT-947, Loop A Containment Pressure Transmitter fails high 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040, Condensate Tank T-24A Level Transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto Major Transients:

Large Break LOCA Critical Tasks:

1. CT-3 Manually actuate containment cooling

2. CT-5 Manually Start at Least One Low-Head ECCS Pump Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG CT-3 Manually actuate containment cooling Applicable ERG LP Version Applicable ERG E-0, ECA-0.2, FR-Z.1 Critical Task:

Manually actuate at least one Containment Spray pump before an extreme (RED path) challenge develops to the containment CSF.

Plant Conditions:

Containment cooling is required but the minimum required complement of containment cooling equipment is not automatically actuated (instrument failure is not the cause of the requirement for containment cooling)

The minimum required complement of containment cooling equipment can be manually actuate from the control room Cues:

Indication and/or annunciation that containment cooling is required (containment pressure > 25 psig)

Indication and/or annunciation that Containment Spray is not actuated Performance Indicator:

Manipulation of controls as required to actuate at least one Containment Spray Pump Feedback:

Indication and/or annunciation that at least one Containment Spray pump is running Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 35

PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG CT-5 Manually Start at Least One Low-Head ECCS Pump Applicable ERG HP, LP Version Applicable ERG E-0, ECA-0.2 Critical Task:

Manually start at least one low-head ECCS pump before transition out of EOP-0 Plant Conditions:

Large-break LOCA Reactor trip SI RCS pressure below the shutoff head of the low-head ECCS pumps Both low-head ECCS pumps fail to automatically start upon SI At least one low-head ECCS pump can be started provided that manual action is taken as necessary Cues:

Indication and/or annunciation that low-head ECCS pumped injection is required

- SI actuation

- RCS pressure below the shutoff head of the low-head ECCS pumps AND Indication and/or annunciation that no low-head ECCS pump is injecting into the core

- Control switch indication that the circuit breakers or contactors for both low-head ECCS pumps are open

- All low-head ECCS pump discharge pressure indicators read zero

- All flow rate indicators for low-head pumped injection read zero Performance Indicator:

Manipulation of controls as required to start at least one low-head ECCS pump

- Control switch indication that the circuit breaker for at least one low-head ECCS pump is closed Feedback:

Indication and/or annunciation that at least one low-head ECCS pump is injecting

- Flow rate indication of injection from at least one low-head ECCS pump Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 35

TURNOVER INFORMATION SEG 1.0 Plant Conditions:

Unit 1 Unit 2 Time in Core Life (MWD/MTU): 19,400 Reactor Power: 100%

Boron Concentration: 11 ppm Rod Height: CBD @ 220 2.0 Equipment Out of Service:

1PT-950, U1C High Range Pressure Transmitter 1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.

3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:

LCO NOT Met TSAC Required Actions Completion Time 3.3.2 A. One or more Functions with one A.1 Enter the Condition referenced in Immediately or more channels or trains Table 3.3.2-1 for the channel(s) or inoperable. train(s).

D. One channel inoperable D.1 Place channel in trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR D.2.1 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 4.0 Planned Evolutions:

Normal Shift routine will be to lower power at 30%/hr utilizing OP-3A Unit 1, Power Operation To Hot Standby Unit 1.

5.0 Common

Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.

Unit 2 is on ice melt Filename: NRC Scenario 1 final.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 35

SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 16E LMS Rev. Date:

SEG TITLE: 2017 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 Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _2___________ Op-Test No.: _2017____

Examiners: ___________________________ Operators: _____________________________

Initial Conditions: _Unit 1 is in OP 1C, Startup to Power Operation, at approximately 29% post _

chemistry hold coming out of a forced outage. At Chemistrys request B Train of Main Feed and _

Condensate have been running for 5 minutes for iron flushing. 1W-3B, Control Rod Shroud Fan _

is OOS due to imminent motor failure. 1PT-950, Loop B Containment Pressure has been removed _

from service. Repairs are expected to be complete during the upcoming refueling outage.__________

Turnover: Secure 1P-28B, SGFP and 1P-25B, Condensate Pump. Raise power to 50%. _________

Event Malf. No. Event Event No. Type* Description N-BOP 1 Secure SG Feed Pump and Condensate Pump N-SRO R-RO 2 N-BOP Raise power to 50%

R-SRO I-BOP 3 XMT1SGN001A I-SRO 1FI-464, SG Steam Flow fails slowly high TS-SRO I-BOP 4 XMT1MSS009A I-SRO 1PT-486, Turbine First Stage Pressure fails low TS-SRO C-RO 1P-1B, RCP Seal leak develops, which degrades requiring reactor 5 MAL1RCP001B C-SRO trip 6 MAL1RCS003F M-ALL Small Break LOCA from RTD Bypass Line occurs on reactor trip MAL1PPL001A C-RO Reactor fails to trip 7 MAL1PPL001B (CSP-S.1, Response to Nuclear Power Generation/ATWS)

MOT1SIS001 C-BOP 1P-15A, SI Pump trips upon starting 8 BKR1SIS002 1P-15B, SI Pump fails to start in Auto

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to the failures listed below in accordance with plant procedures:

1FT-464, SG Steam Flow Transmitter fails high (no auto shift to single element)

PT-486, Turbine First Stage Pressure fails low 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria Small Break LOCA Reactor fails to trip (ATWS)

Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Embedded within these events is the expectation to properly utilize Technical Specifications.

Enabling None Objectives:

Prerequisites: 1. Simulator available

2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator

3. Communicator

4. NRC Evaluators

References:

1. 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels

2. 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Red Channels

3. 0-SOP-IC-002, Technical Specifications LCO - Instrument Cross Reference

4. OP 1C, Startup to Power Operation Unit 1

5. AOP-1B Unit 1, Reactor Coolant Pump Malfunction

6. AOP-2B, Feedwater System Malfunction

7. AOP-24, Response to Instrument Malfunctions

8. ARP 1C03 1E2 3-2, Steam Generator A Feed Water Flow Channel Alert

9. ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert

10. CSP-S.1 Unit 1, Response to Nuclear Power Generation / ATWS

11. EOP-0 Unit 1, Reactor Trip Or Safety Injection Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG

12. EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant

13. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients

14. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021.

Operating N/A Experience:

Risk Significant HEP-ODA-EOP12-05, FAILURE TO COOLDOWN AN DEPRESSURIZE Operator Actions: RS FO LONG TERM COOLING BY SECONDARY STEA, FV: 3.86E-02 Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Unit 1 is in OP 1C Unit 1, Startup to Power Operation Unit 1 at approximately 28%

post chemistry hold coming out of a forced outage. At Chemistrys request, B Train of main feed and condensate pumps have been running for 5 minutes for iron flushing.

Secure 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump.

Raise power to 50% in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.

OOS Equipment 1PT-950, Loop B Containment Pressure has been removed from service.

Repairs are expected to be complete during the upcoming refueling outage.

1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.

Events 1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element) 1PT-486, Turbine First Stage pressure transmitter fails low 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria Small Break LOCA Reactor fails to trip (ATWS)

Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Terminate the scenario when crew has completed Step 13 of EOP-1 Unit 1, Loss of Reactor or Secondary Coolant.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description

1. Secure 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump

2. Raise power to 50% (or per Lead Examiner) in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.

3. 1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element)

The crew should respond by taking 1FIC-466A, 1 HX-1A Primary Flow Indicating Controller to manual and controlling steam generator level.

The crew should implement AOP-24, Response to Instrument Malfunctions and 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Red Channels to shift to a new controlling channel and take the flow transmitter out of service.

The crew may implement ARP 1C03 1E2 2-2, Steam Generator A Feed Water Flow High to shift to a new controlling channel.

4. 1PT-486, Turbine First Stage Pressure Transmitter fails low The crew should implement :

ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert and realign the condenser steam dump system for continued operation.

AOP-24, Response to Instrument Malfunction and 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service -

Blue Channels to take the transmitter out of service Technical Specifications for the failed channel

5. 1P-1B, Reactor Coolant Pump seal leak develops, then degrades requiring a reactor trip Unit conditions degrade such that AOP-1B Unit 1, Foldout Page criteria are met and a transition to Step 18 to trip the unit and secure the pump is warranted.

6. Small Break LOCA from RTD bypass line Will result in a Safety Injection signal Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG

7. Reactor fails to trip (ATWS)

Upon failure of the reactor to trip from the control room, the crew should transition from AOP-1B Unit 1/EOP-0 Unit 1, Reactor Trip or Safety injection to CSP-S.1 Unit 1, Response to Power Generation / ATWS.

After completing the actions in CSP-S.1 Unit 1, the crew should transition back to EOP-0 Unit 1, Step 1 RNO.

Concurrent with the implementation of EOP-0 Unit 1, the crew should complete the remainder of AOP-1B Unit 1 Step 18 which was suspended when entering CSP-S.1Unit 1.

The crew should complete the actions of EOP-0 Unit 1 and transition to EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant and then to EOP-1.2 Unit 1, Post LOCA Cooldown and Depressurization to address the Small Break LOCA.

8. Safety Injection Pump failures: 1P-15A, Safety Injection pump trips upon starting and 1P-15B, Safety Injection pump fails to auto start Following immediate actions of EOP-0 Unit 1, The crew may manually start a Safety Injection Pump in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients, otherwise pump start is addressed in EOP-0 Unit 1, Attachment A, Step A3.a.RNO .

STOP Terminate the scenario when crew has completed Step 9 of EOP-1 Unit 1, Loss of Reactor or Secondary Coolant.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

General Instructions Simulator Setup Instructions:

Load IC-7 and go to run Open the saved Event and Schedule files from the secure drive:

Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)

Reposition bistable switches for: 1PT-950, Loop B Containment Pressure Transmitter Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:

Load saved IC and go to run Open the saved Event and Schedule files:

Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:

Setup: 1PT-950, Loop B Containment Pressure Transmitter is out of service MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT950 LOOP B CONT XMT1CNM017A PRESSURE 00 :00 :00 - 90 Preload XMTR FIXED OUTPUT Simulator Setup:

1. Place OOS magnet at PT-950, Containment Pressure

2. Place a RED dot on C01 B 1-5, U1 Containment Pressure Channel Alert

3. Place 1W-3B CS in pull-out, install OOS magnet.

4. Install an orange Guarded magnet at 1W-3A.

SIMULATOR MALFUNCTIONS:

Event 1: Secure 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump.

Event 2: Raise power to 50% in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.

MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-P73A 1P-28B LOA1CFW079 SGFP AC LUBE - - 11 `- - ON Directed from Crew OIL PUMP CS Expected field communications:

1. [5.31.17.c] 1P-73A-CS, P-73A SGFP AC Lube Oil Pump Local Stl Station is ON. (Trigger 11)

2. [5.31.17.c.3)] Lowering suction flow at 1FI-2188, 1P-28B SGFP Suction Flow Indicator.

3. [5.31.17.d.2)] 1P-25B, Condensate pump is stopped and not rotating backwards.

Event 3: 1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element)

MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-FT464 LOOP A XMT1SGN001A STEAM FLOW 00 :00 :00 00 :00 :45 1 00 :00 :00 - 2.0 PLE FIXED OUTPUT Expected field communications:

1. None Event 4: 1PT-486, Turbine First Stage Pressure Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT486 FIRST STAGE XMT1MSS009A PRESSURE 00 :00 :00 00 :00 :05 3 00 :00 :00 - 0 PLE XMTR FIXED OUTPUT Expected field communications:

1. IF and AO is dispatched to locally investigate 1PT-486, Turbine First Stage Pressure Transmitter, wait two minutes and THEN report that locally there doesnt seem to anything out of normal.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Event 5: 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE RCP #1 SEAL MAL1RCP001B FAILURE PUMP 00 :00 :00 00 :05 :00 5 00 :00 :00 - 5 PLE B

1-CV-300B P-1B Per When directed by the LOA1CVC048 RCP SEAL INJ 00 :00 :00 00 :00:00 - 00 :00 :00 - Crew Crew THROTTLE Direct.

RCP #1 SEAL MAL1RCP001B FAILURE PUMP 00 :00 :00 00 :01 :00 7 00 :00 :00 5 300 PLE B

Expected field communications:

1. IF the PAB AO is dispatched to monitor Unit 1 Reactor Coolant Drain Tank level; call up Instructor Station Drawing 1WPS1 and THEN report as indicated. The change in RCDT level should indicate a <1% change in 5 minutes.

2. IF the PAB AO is directed to throttle 1CV-300B, 1P-1B RCP Seal Injection Throttle Valve; coordinate with the Control Room and THEN make adjustments using LOA1CVC048, 1-CV-300B P-1B RCP SEAL INJ THROTTLE as directed.

Event 6: Small Break LOCA MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE RTD BYPASS 1C04 Trip pushbuttons LINE LEAK 9 MAL1RCS003F 00 :00 :00 00 :00 :30 75 [X14I055A == 1 l X14I057A ==

LOOP B Cond 1]

COMMON Expected field communications:

1. None Event 7: Reactor fails to trip (ATWS)

MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE REACTOR TRIP Fails to MAL1PPL001A BREAKER 00 :00 :00 - - 00 :00 00 - PRELOAD Open 52/RTA FAILURE REACTOR TRIP Fails to MAL1PPL001B BREAKER 00 :00 :00 - - 00 :00 :00 - PRELOAD Open 52/RTB FAILURE Expected field communications:

1. FOLLOWING the PA announcement for ATWS or when directed to locally open the reactor trip breakers, allow 2 minutes for travel to the Rod Drive Room and THEN report to the control room. WHEN directed to open the Unit 1 reactor trip breakers change MAL1PPL001A and MAL1PPL001B to Trip and THEN report the reactor trip breakers are open Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Event 8: Safety Injection Pump failures: 1P-15A, Safety Injection pump trips upon starting and 1P-15B, Safety Injection pump fails to auto start MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-P15A SAFETY Winding MOT1SIS001 INJECTION 00 :00 :00 - - 00 :00 :00 - PRELOAD Ground PUMP 1-A5285 P-15B Failauto BKR1SIS002 SAFETY INJ 00 :00 :00 - - 00 :00 :00 - PRELOAD cl PUMP CKTBKR Expected field communications:

1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.

2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.

3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.

4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.

5. IF an AO is dispatched to locally investigate 1P-15A, Safety Injection pump, wait 2 minutes and THEN report that the motor is hot to the touch and there is a faint acrid smell in the area. There is no fire.

6. IF an AO is dispatched to locally investigate breaker 1A52-59, Pwr to 1P-15A, Safety Injection Pump, wait 2 minutes and THEN report the breaker has tripped.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.

Crew Shift Turnover Information: See Attached Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 1: Unit 1 is in OP 1C, Startup to Power Operation CREW Implements OP 1C Unit 1, Startup to Power Operation Unit 1 Secure 1P-28B, Unit 1, at approximately 28% post chemistry 5.31.17 WHEN a minimum of 5 minutes of flushing is obtained on the train Main Feedwater hold coming out of a forced outage. At of main feed and condensate, THEN DETERMINE main feed and Pump and 1P-25B, Chemistrys request, train B main feedwater condensate train to be secured as follows:

Condensate and condensate pumps have been run for 5 a. ENSURE 1PC-2273, Low Pressure Heater Bypass Pressure Pump. minutes for iron flushing. Controller, SET to 190 psig

b. N/A Start: ________ Expected Communications: c. IF 1P-28B, Steam Generator Feed Pump, will be STOPPED,

[5.31.17.c] 1P-73A-CS, P-73A SGFP AC Lube THEN PERFORM the following:

Oil Pump Local Stl Station is ON. (Trigger 11) 1) POSITION 1P-73A,-CS, P-73A SGFP AC Lube Oil

[5.31.17.c.3)] Lowering suction flow at 1FI-2188, Pump Local Ctl Station, to ON.

1P-28B SGFP Suction Flow Indicator. 2) SHUT 1CS-2189, 1P-28B SGFP Discharge MOV by

[5.31.17.c..6] MFP coastdown SAT positioning 1CS2189-CS, 1P-28B SGFP Discharge

[5.31.17.d.2)] 1P-25B, Condensate pump is MOV control switch, to CLOSE.

stopped and not rotating backwards. 3) MONITOR 1CS-2189 closure and decreasing suction flow at 1FI-2188, 1P-28B SGFP Suction Flow Indicator.

4) BEFORE 1CS-2189 reaches fully SHUT, THEN HOLD 1CS-2189-CS in CLOSE position.

5) ENSURE 1CS-2188, 1P-28B SGFP Mini Recirc Flow Control, begins modulating OPEN

6) STOP 1P-28B by positioning 1P-28B-CS, 1P-28B Steam Generator Feed Pump Control Switch, to STOP.

7) RELEASE 1CS-2189-CS.

8) OBSERVE 1CS-2188 goes fully SHUT, THEN POSITION 1P-28B-CS to PULLOUT.

d. STOP a Condensate Pump

1) POSITION selected condensate pump control switch in PULLOUT. Remaining pump control switch may be marked N/A:

2) Locally ENSURE pump selected in STEP 5.3.17.d.1) has stopped (NOT rotating backwards)

3) RETURN condensate pump control switch in PULLOUT, to AUTO. Remaining pump control switch may be marked N/A:

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE 5.31.18 NOTIFY Chemistry MFP / Cond pump bump is complete.

5.32 WHEN directed by Shift Management, THEN PLACE an additional feed train in service as follows:

Deferred to 50% - 60% power Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE 5.33 Restriction For Continued Load Escalation Event 2: Raise power to 50% in accordance with OP 1C 5.33.1 IF Step 5.27 was performed, THEN BEFORE continued load Raise power to Unit 1, Startup to Power Operation Unit 1. escalation, PERFORM the following:

50% in a. DETERMINE magnitude and rate of continued load accordance with escalation and RECORD below: (15%/hr)

OP 1C Unit 1, Expected Communication: SM b. INITIATE notification of continued load escalation in Startup to Power If necessary, prompt the crew to continue accordance with NP 2.1.5, Electrical Communications, Operation Unit 1. with the power ascension. Switchyard Access and Work Planning.

If requested, report that NP 2.1.5 5.33.2 WHEN power is approximately 35%, THEN CHECK the following Start: ________ notifications have been completed. indications:

5.34 Load Escalation Continuation Criteria: 5.34.1 NOTIFY Turbine Hall Operator to monitor the following:

Once the crew has raised reactor power about 3% 5.34.2 NOTIFY Primary Auxiliary Building (PAB) Operator, to PERFORM to 5%. Or at the discretion of the Lead Examiner, the following:

continue to the next event. 5.34.3 IF determined necessary by Operations Shift Management, THEN LOWER the PPCS constants for SG Blowdown Flow by 5 KLBS/hr.

5.34.4 IF required, THEN PLACE an additional Letdown Orifice in service.

5.35.1 IF Step 5.32 was performed, THEN ENSURE one hour has elapsed beyond the time recorded in Step 5.32.2.

5.35.2 WHEN Reactor Engineering activities are complete, THEN RESUME power escalation, observing any other required Reactor Engineering hold points.

5.35.3 On 1C03, ENSURE 1DTIC-2525, T-23 HDT Differential Temperature Indicator Ctlr, is selected to AUTO 5.35.4 CONTINUE load escalation as follows:

a. ENSURE Governor Valves are off Valve Positon Limiter (VPL)

b. MOVE Valve Position Limiter (VPL) to its desired position (e.g., 100% value)

c. SELECT the desired EH Control System mode of Operation and MARK mode NOT selected N/A:

d. SHIFT to the selected rate recorded ins Step 5.33.1.a.

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PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE 5.36 Continuous Action During Power Increase 5.36.1 MAINTAIN controls in AUTO as practicable 5.36.2 MAINTAIN Control Banks within the insertion, sequence, and overlap limits specified in the COLR. LCO 3.1.6 5.36.3 MAINTAIN Tavg within 1.5°F of Tref 5.36.4 ADJUST Power Range NIS as directed by 1-TS-RE-001, Power Level Determination Unit 1 5.36.5 MAINTAIN VARS OUT while keeping the null meter zeroed.

5.36.6 MAINTAIN the controller setpoint for the LP Feed Water Heater Bypass Valve (1CS-2273, LP FWH Bypass Press Controller) at 25 psig below SG Feed Pump suction pressure 5.36.7 MONITOR FWH/MSR high level alarms to check the dump valves control level 5.36.8 MONITOR Ice Melt operations as necessary.

5.36.9 IF required, THEN CONTINUE OPENING MSR Control Valves using manual operation of controller 1HX-2085 at the rate of less than or equal to 25°F per 30 minutes.

5.36.10 WHEN power is approximately 35%, THEN CHECK the following:

OP 5B Blender Operation / Dilution / Boration, Attachment C, Alternate Dilution 4.1 ESTIMATE the amount of water addition 4.2 SET desired quantity on YIC-111A, Reactor Makeup Water Flow Counter 4.3 SET desired flow rate on HC-111, Reactor Makeup Water Flow Controller 4.4 IF desired to place all dilution flow to the charging pump suction, THEN CLOSE CV-110C, Z-1 BA Blender to VCT FCV.

4.5 PLACE Reactor Makeup Mode Selector Switch in ALT DIL 4.6 PLACE Reactor Makeup Control Switch to START.

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PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 1 [XMT1SG001A, 1-FT464 LOOP A BOP Acknowledges alarms, identifies 1FT-464, 1HX-1A SG Steam Flow 1FT-464, 1HX-1A STEAM FLOW FIXED OUTPUT, RAMP Transmitter has failed to a higher value and references the ARPs.

SG Steam Flow = 00 :00 :20, VALUE = 2.0]

Transmitter fails Implements AOP-24, Response to Instrument Malfunctions high (no auto shift Insert Trigger 1 to cause 1FT-464, 1HX-1A SF 1. Identify Failed Instrument to single element) Steam Flow Transmitter to fail high (no auto shift to 2 Check If Failed Instrument Is A Controlling Channel single element. 3. Establish Manual Control As Required Start: _________ OS1 4. Return Affected Parameter(s) To Desired Value(s)

Plant Response: BOP 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE 1HX-1A Steam Generator level deviates bringing in REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is alarms for 1C03 1E2 1-2, Steam Generator A Level NOT An Input To RTO Setpoint Deviation / Trouble and 1C03 1E2 2-2, 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, Steam Generator A Feed Water Flow High. The ROUTINE MAINTENANCE PROCEDURE REMOVAL OF Steam Generator Water Level Control System - SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE level dominant system response then drives 7. Return Controls To Automatic If Desired affected steam generator level back to normal level. 8. Check Failure For Technical Specification Or TRM Applicability

9. Return To Procedure And Step In Effect Cues:

1C03 1E2 1-2, Steam Generator A Level Setpoint May implement AOP-2B, Feedwater System Malfunction Deviation / Trouble 1. Maintain Reactor Power Less Than Or Equal To 100%

1C03 1E2 3-2, Steam Generator A Feed Water 2. Determine The Secondary System Malfunction And Go To the Flow Channel Alert Appropriate Step 1FI-464 increasing to 2E6 PPH. OS1 12. Perform The Following For Feed Regulating Valves:

a. Check Feed Regulating Valve Response - NORMAL Expected Communications: RNO None BOP a. Perform the following:

1) Place the affected feedwater regulating valve controller to The crew may elect to exercise the ARP to switch manual or single element control.

controlling channels prior to implementing 0-SOP- 2) Match feed flow to steam flow IC-001 Red, Routine Maintenance Procedure 3) Stabilize steam generator level.

Removal Of Safeguards Or Protection Sensor From 4) IF transient caused by instrument failure, THEN defeat failed Service - Red Channels. instrument per AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP Implements 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Red Channels Remove from Service NOTE: Steps 1 through 4 may be N/Ad if both transfer switches are already in WHITE.

1. PLACE Feedwater Regulating Valve in MANUAL:

FIC-466A, HX-1A Primary Flow Indicating Controller NOTE: Controlling channel will be FT-465.

2. PLACE SG A Steam Flow Control Transfer Switch to 465 (WHITE).

NOTE: Controlling change will be FT-467.

3. PLACE SG A Feedwater Flow Control Transfer Switch to 467 (WHITE).

4. PLACE Feedwater Regulating Valve Controller in AUTO unless directed otherwise by Shift Management:

FIC-466A, HX-1A Primary Flow Indicating Controller

5. In cabinet C-112, PLACE the following bistable trip switches in the TRIP positon (toggle switch up) and CHECK expected response.

BISTABLE BISTABLE ANNUNCIATOR SWITCHES TO TRIP PROVING LAMP LAMP LIT LIT CABINET C-112 HI STM FLO HIGH TRIP (F/464) (Note 1) NONE LINE A FC464A HI HI STM FLO HI HI TRIP (F/464) Lit Unless Failed High 1CO3 1D 3-10 LINE A FC464B LIT Unless Indicated Feed SF<FWF (F/466) Flow is .8x106 Greater NONE 1CO3 1E2 2-2 than Steam Flow LIT Unless Indicated Feed STM FW FLOW SF>FWF (F/466) Flow is .8x106 Greater 1CO3 1E2 3-2 DAE FC466C than Feed Flow NOTE 1: Proving lamp will be lit IF indicated steam flow is BELOW the High Stream Flow per STPT 2.2 section 1.2.1.

6. REMOVE from scan PPCS point ID FT466V, SA A-1 SF RED.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS Reference Technical Specifications Technical Specifications:

A. One or more A.1 Enter the condition Immediately functions with one referenced in Table or more required 3.3.1-1 for the channels or trains channel(s) or train(s) inoperable.

Table 3.3.1-1 D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months item 14-2 inoperable OR SF/FF Mismatch D.2 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Table 3.3.2-1 D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months item 4d-1 SLI- inoperable OR High Steam Flow D.2.1 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND D2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months Table 3.3.2-1 D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months item 4e-1 SLI- inoperable OR High Steam Flow D.2.1 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND D2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS1 Implement ARP 1C03 1E2 3-2, Steam Generator A Feed Water Flow Once the crew has Channel Alert Switched controlling channels BOP 3.4 IF alarm is due to an instrument failure, THEN PERFORM the Placed the FRV in auto, AND following to select an operable control channel unless directed Addressed technical specifications otherwise by Shift Management:

or at the discretion of the Lead Examiner, continue 3.4.1 IF an of the following transmitters is failed, THEN with the next event. PERFORM Steps 3.4.1.a through 3.4.1.e:

1FT-464, Steam Flow Loop A

a. IF 1PT-468, Steam Generator Pressure Loop A has failed, THEN ENSURE 1HC-468, SG A Atmospheric Steam Dump Controller in MANUAL.

b. PLACE 1FIC-466A, 1HX-1A Primary Flow Indicating Controller in MANUAL.

c. PLACE SG A Feedwater Flow Control Transfer Switch, to 467 (WHITE).

d. PLACE SG A Steam Flow Control Transfer Switch, to 465 (WHITE).

e. PLACE 1FIC-466A, 1HX-1A Primary Flow Indicating Controller in AUTO unless directed otherwise by Shift Management.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 3 [XMT1MSS009A, 1-PT486 FIRST BOP Acknowledges alarm and references ARP 1C03 1E2 4-2, Tavg Steam 1PT-486, Turbine STAGE PRESSURE XMTR FIXED Dump Channel Alert.

First Stage OUTPUT, VALUE = 0, RAMP = 5 sec]

Pressure Implements ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert Transmitter fails Insert Trigger 3 to cause 1PT-486, Turbine First 3.1 CHECK condition of steam dump system low Stage Pressure Transmitter to fail low. 3.2 CHECK to see if steam dump required, TavgTref with turbine runback or trip.

Plant Response: 3.3 IF the alarm is due to an instrument failure, AND it is desired to defeat Arms condenser steam dumps and alarms the failed channel, THEN PERFORM the following unless directed Start: __________ annunciator 1C03 1E2 4-2, Tavg Steam Dump otherwise by shift management:

Channel Alert. 3.3.1 PLACE the Condenser Steam Dump Controller 1HFC-484 in MANUAL, AND ENSURE controller output is ZERO on C03.

Cues: 3.3.2 PLACE the Steam Dump Mode Selector Switch in MANUAL 1C03 E2 4-2, Tavg Steam Dump Channel Alert on C03.

1PI-486, Turbine First Stage (STM DUMP) 3.3.3 PLACE the Condenser Steam Dump controller 1HFC-484 on Pressure Indicator reads 0 psig C03 in AUTO as follows, unless directed by Shift Management:

Expected Communications: a. LOWER the controller AUTO set point to 50 psig above IF and AO is dispatched to locally investigate the current Main Steam header pressure.

1PT-486, Turbine First Stage Pressure b. PLACE the controller in AUTO.

Transmitter, wait two minutes and THEN report c. RETURN the controller to the original AUTO set point.

that locally there doesnt seem to anything out of 3.4 REFERENCE AOP-6C, Uncontrolled Motion of RCCAs normal.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS1 Implements AOP-24, Response to Instrument Malfunctions Once the crew has taken action per ARP and /or BOP 1. Identify Failed Instrument AOP-24 to address CSDs and addressed Technical 2 Check If Failed Instrument Is A Controlling Channel Specifications, or at the discretion of the Lead 3. Establish Manual Control As Required Examiner, continue with the next event. 4. Return Affected Parameter(s) To Desired Value(s)

5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO

6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE

7. Return Controls To Automatic If Desired

8. Check Failure For Technical Specification Or TRM Applicability

9. Return To Procedure And Step In Effect OS1 Reference Technical Specifications Technical Specifications:

RPS LCO 3.3.1 is not met (3.3.1 item 17b-2)

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Enter the Condition Immediately Functions with one referenced in Table or more required 3.3.1-1 for the channels or trains channel(s) or inoperable. train(s).

S. One or more S.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel(s) required state for inoperable. existing conditions.

OR S.2 Be in MODE 2 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5: Trigger 5 [MAL1RCP001B, RCP#1 SEAL OATC Acknowledges alarms and identifies that 1P-1B, RCP is the affected 1P-1B, Reactor FAILURE PUMP B, RAMP = 00 :05 :00, pump based on alarms and available indications.

Coolant Pump VALUE = 5]

seal leak develops OS1 Implements AOP-1B, Reactor Coolant Pump Malfunction After the crew has stabilized the plant and has exited the applicable AOPs, insert Trigger 5 to OATC/BOP Monitors Fold out Page Start: __________ ramp in a ~5 gpm #1 seal leak on 1P-1B, Reactor 1. Check Annunciator P-1A&B RP VIBRATION ALARM - CLEAR Coolant Pump. 1C04 1C 1-5

2. Check Annunciator 1TR-2001 TEMPERATURE MONITOR ALARM Plant Response: - CLEAR Leak off flow will increase. Alarms for RCP No. 1 1C04 1C 3-10 Seal Water Flow High or Low, Lab Seal P Low, 3. Check Annunciator 1P-1A OER B RCP UPPER OR LOWER SUMP RCP Lab Seal Water or Bearing Temperature High OIL LEVEL HIGH OR LOW - CLEAR and RCP #1 RCP Seal Water Outlet Temperature 1C04 1D 3-11 High. The affected RCP seal and bearing 4. Check RCP No. 1 Seal Leakage - GREATER THAN 0.8 gpm temperatures increase. The seal outlet 5. Check RCP No. 1 Seal Leakage - LESS THAN 6 gpm temperatures increase. The seal P lowers or is 1FR-177 negative. RNO IF seal outlet temperature is rising, THEN go to Step 18.

o 1TI-182 for RCP B Cues: IF RCP No. 2 seal leakage greater than 2 gpm, THEN go to 1C03 1D 2-1, 1P-1A or B RCP Labyr Seal Delta Step 18.

P low o RCDT level change greater than 2% in 3 1/2 minutes.

1C03 1D 3-3, 1P-1B RCP No. 1 Seal Water Flow o Standpipe level high alarm High or Low o 1C03 1D 1-3 for RCP B

6. Verify RCP Seal Cooling:

a. Labyrinth seal P - GREATER THAN 20 inches 1PI-124 for RCP B RNO Perform the following:

1) Adjust seal injection throttle valves and charging flow control valve as necessary to establish a positive labyrinth seal P o 1CV-300B for RCP B o 1HC-142

2) IF positive labyrinth seal P can NOT be established AND component cooling water can NOT be maintained greater than 21 gpm, THEN go to Step 18.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: BOP b. Component cooling RCP thermal barrier - NORMAL IF the PAB AO is dispatched to monitor Unit 1 1) Thermal barrier outlet AOV - OPEN Reactor Coolant Drain Tank level; call up Instructor 1CC-761B for RCP B Station Drawing 1WPS1 and THEN report as 2) RCP Cooling water flow low alarm - CLEAR indicated. The change in RCDT level should 1C03 1D 1-5 for RCP B indicate a <1% change in 5 minutes. c. RCP component cooling return temperature alarm - CLEAR 1C03 1D 2-4 IF the PAB AO is directed to throttle 1CV-300B,

7. Check RCP Related Firework Panel Alarms - CLEAR 1P-1B RCP Seal Injection Throttle Valve;

8. Check RCP No 2 Seal Indications - NORMAL coordinate with the Control Room and THEN make Annunciator 1P-1B RCP STANDPIPE LEVEL HIGH - CLEAR adjustments using LOA1CVC048, 1-CV-300B P-1B RCP SEAL INJ THROTTLE as directed. 1C03 1D 1-3 RCP No. 2 seal leakage - LESS THAN OR EQUAL TO 0.5 Continuation Criteria: gpm When the crew has completed Step 9 of AOP-1B RCP No. 1 seal leakage flow has remained stable Unit 1, Reactor Coolant Pump Malfunction, or at the o 1FR-175 discretion of the Lead Examiner continue with the o 1FR-177 next event. 9. Check RCP Seal Injection Temperatures - NORMAL Annunciator VCT TEMPERATURE HIGH - CLEAR 1C04 1C 3-7 VCT outlet temperature - LESS THAN 130°F 1TI-140

10. Determine RCP Seal Status:

RCP No. 1 and No. 2 combined seal leakage - BETWEEN 0.8 gpm AND 6 gpm RCP No. 2 seal leakage - LESS THAN 1.1 gpm RNO Perform the following

a. Shutdown per OP-3A, POWER OPERATION TO HOT STANDBY Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5a: Trigger 7 [MAL1RCP001B, RCP#1 SEAL OATC/OS1 Recognizes degrading plant conditions and AOP-1B Unit 1, Foldout 1P-1B, Reactor FAILURE PUMP B, RAMP = 00 :05 :00, Page RCP trip criteria and goes to Step 18.

Coolant Pump seal VALUE = 300] o RCP No. 1 Seal leakage leak degrades o Greater than 6 gpm with seal water outlet temperature rising requiring a reactor Trigger 9 [MAL1RCS003F, RTD BYPASS LINE LEAK o Less than 0.8 gpm with seal water outlet temperature rising trip LOOP B COMMON, Value = 75]

OATC 18. Secure Affected RCP Start: _________ After the crew has completed Step 9 of AOP-1B a. Trip the reactor Unit 1, Reactor Coolant Pump Malfunction, insert Trigger 7 such that the seal leak degrades requiring NOTE: The pending ATWS will interrupt performance of Step 18 Event 6: Small a reactor trip. Trigger 9 will insert a RTD Bypass and should not be completed until exit of CSP-S.1 Unit 1, Break LOCA line leak (Small Break LOCA) when the reactor trip Response to Nuclear Power Generation / ATWS and return pushbuttons are depressed. to EOP-0 Unit 1, Reactor Trip or Safety Injection.

Plant Response: OATC/BOP b. Stabilize the plant using EOPs while continuing with this The affected RCP seal and bearing temperatures procedure increase. The seal outlet temperatures increase. c. Trip affected RCP The seal P lowers or is negative. Pressurizer d. Check at least one RCP running pressure and level begin to lower. e. Shut associated PZR normal spray valve Cues: o 1RC-431B for RCP B 1C03 1D 1-1, 1P-1A or B RCP Labyr Seal Water f. Check affected RCP has been tripped for 3 minutes Inlet or Bearing Temp High g. Shut affected RCP No. 1 seal water return MOV 1C03 1D 3-1, 1P-1A or B RCP No. 1 Seal Water o 1CV-270B for RCP B Outlet Temperature High h. Check RCP seal water bypass control valve shut 1C03 1D 4-1, 1P-1B RCP No. 1 Seal Delta P 1CV-386 Low 19. Return to Procedure And Step In Effect Rising 1P-1B, RCP seal inlet, outlet and bearing temperatures as indicated on 1TI-125 and 1TI-182.

Indications of a Small Break LOCA Expected Communications:

None Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE PRELOAD: [MAL1PPL001A, REACTOR TRIP Event 7: OS1 DIRECT a reactor trip BREAKER 52/RTA FAILURE, VALUE =

IMPLEMENTS EOP-0 Unit 1, Reactor Trip or Safety Injection Fails to Open]

Reactor fails to OATC 1. Verify Reactor Trip trip (ATWS) [MAL1PPL001B, REACTOR TRIP RNO: Manually trip reactor:

BREAKER 52/RTB FAILURE, VALUE = Train A Start: __________ Fails to Open]

Train B IF reactor power is greater than or equal to 5% OR Plant Response:

intermediate range SUR is positive, THEN Go to CSP-S.1 The reactor will not trip from the control room. The UNIT 1, RESPONSE TO NUCLEAR POWER GENERATION crew will have to take actions IAW CSP-S.1,

/ ATWS.

Subcriticality procedure and open the RTBs locally.

OS1 ENTER CSP-S.1, Response to Nuclear Power Generation / ATWS Cues:

RTBs NOT open OATC CT-52 Insert negative reactivity into the core PR NIs greater than 5%

1. Verify Reactor Trip Expected Communications: RNO: Manually trip reactor FOLLOWING the PA announcement for ATWS or IF reactor will NOT trip, THEN allow control rods to insert when directed to locally open the reactor trip automatically until rod speed is less than 36 breakers, allow 2 minutes for travel to the Rod Drive STEPS/MINUTE, THEN manually insert control rods Room and THEN report to the control room. WHEN 2. Verify Turbine Trip directed to open the Unit 1 reactor trip breakers change MAL1PPL001A and MAL1PPL001B to Trip Monitor Foldout Page Criteria:

and THEN report the reactor trip breakers are open.

3. Verify AFW Pumps - RUNNING NOTE: If necessary, delay reporting the AO is in the a. Motor-Driven Pump - RUNNING Rod Drive Room to allow the crew to initiate RNO: WHEN SI sequence is complete, THEN manually start emergency boration. motor-driven AFW pump.

b. Turbine-Driven Pump - RUNNING RNO: Open both steam supply valves to turbine-driven AFW pump 1MS-2020 1MS-2019 Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP 4. Initiate Emergency Boration of RCS:

5. Check if the Following Trips have Occurred:

a. Reactor - TRIPPED RNO: Dispatch operator to locally open trip and bypass breakers in rod control room.

b. Turbine - TRIPPED

6. Check If Reactor is Subcritical:

a. Power range channels - Less than 5%;

RNO: OBSERVE CAUTIONS PRIOR TO STEP 7. Go to Step 7

b. Intermediate range channels - NEGATIVE STARTUP RATE RNO: OBSERVE CAUTIONS PRIOR TO STEP 7. Go to Step 7

c. OBSERVE CAUTION PRIOR TO STEP 15. Go to Step 15 CAUTION: Boration should continue to obtain adequate OATC shutdown margin during subsequent actions.

15. Ensure Emergency Boration Is Proper For Current Plant Conditions

16. Return To Procedure And Step In Effect BOP Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 8: PRELOAD: [MOT1SIS001, 1-P15A SAFETY OS1 Implements EOP-0, Unit 1 Reactor Trip or Safety Injection Safety Injection INJECTION PUMP, Winding Ground] OATC 1. Verify Reactor Trip Pump failures: [BKR1SIS002, 1-A5285 P-15B 2. Verify Turbine Trip 1P-15A, Safety SAFETY INJ PUMP CKTBKR, 3. Verify Power to AC Safeguards Buses Injection pump Failautocl] 4. Check if SI is Actuated trips upon a. Any SI annunciators LIT starting and 1P- b. Both trains of SI - Actuated 15B, Safety Expected Communications: RNO: Manually actuate both trains of SI and CI Injection pump IF an AO is dispatched to locally investigate 1P- BOP fails to auto start 15A, Safety Injection pump, wait 2 minutes and NOTE: Following immediate actions, CREW may manually start a THEN report that the motor is hot to the touch Safety Injection Pump in accordance with OM 3.7, AOP and there is a faint acrid smell in the area. There And EOP Procedure Usage For Response To Plant is no fire. Transients.

IF an AO is dispatched to locally investigate NOTE: The ATWS interrupted performance of AOP-1B Unit 1.

breaker 1A52-59, Pwr to 1P-15A, Safety Step 18 and should now be completed upon the return to Injection Pump, wait 2 minutes and THEN report EOP-0 Unit 1, Reactor Trip or Safety Injection.

the breaker has tripped.

Monitor Foldout Page Criteria: RCP Trip Criteria IF both conditions listed below occur, THEN trip both RCPs:

RCS subcooling - LESS THAN [40 ºF] 31 ºF SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW BOP 5. Perform ATTACHMENT A, Automatic Action Verification while OATC continuing with this procedure

6. Verify AFW pumps - Running

7. Check RCP Seal Cooling

8. Check RCS Temperatures

9. Check PZR PORVs and Spray Valves

10. Check if RCPs should be stopped

11. Check if SGs are NOT Faulted

12. Check if SG Tubes are NOT Ruptured

13. Check if RCS is Intact RNO: Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service Water valves, LW-61 and 62, THEN report both CT-6, Establish flow from at least one high-head SI pump valves are closed.

WHEN directed to locally check CW pump house A3 Verify ECCS Pumps RUNNING temperature <105 ºF, wait 3 minutes and THEN a. SI Pumps - BOTH RUNNING report the temperature is 72 ºF and stable. RNO WHEN SI sequence is complete, THEN manually start WHEN directed to locally check G03/G04 SI pumps Switchgear Room temperature <95 ºF, wait 3 b. RHR Pumps - BOTH RUNNING minutes and THEN report the temperature is 75 ºF A4 Verify Service Water Pumps RUNNING and stable. A5 Verify Containment Accident Cooling Units RUNNING IF directed to periodically check the status of A6 Verify Component Cooling Water Pumps - ONLY ONE RUNNING spent fuel cooling, wait 5 minutes and THEN A7 Check If Main Steam Lines Can Remain Open A8 Verify Containment Spray Not required report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable. a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig A9 Verify ECCS Flow A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 Verify Proper ECCS Valve Alignment A12 Check Containment Spray NOT ACTUATED A13 Stop any boration via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS1 Implements EOP-1 Unit 1, Loss of Reactor or Secondary Coolant BOP 1. Check If RCPs Should Be Stopped Termination Criteria: 2. Check If SGs Are NOT Faulted Terminate the scenario when crew has completed 3. Check Intact SG Level Step 13 of EOP-1 Unit 1, Loss of Reactor or 4. Check Secondary Radiation Secondary Coolant or at the discretion of the Lead 5. Check PZR PORV and Block Valves Examiner. 6. Reset SI

7. Reset Isolation and Lockout Signals

8. Establish Instrument Air to Containment

a. Check instrument air header pressure - GREATER THAN 80 PSIG

b. Open instrument air containment isolation valves one at a time 1IA-3047 1IA-3048

9. Check Power Supply To Charging Pumps

10. Check If Charging Flow Has Been Established

11. Check If ECCS Flow Should Be Terminated RNO: Go to Step 12.

12. Check If Containment Spray Should Be Stopped

13. Check If RHR Pumps Should Be Stopped

a. Check RCS pressure

1) Pressure - GREATER THAN [450 PSIG] 325 PSIG

2) Pressure - STABLE OR RISING RNO: Go to Step 14

- - END OF SCENARIO ***

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)

Malfunctions:

Before EOP Entry:

1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element)

1PT-486, Turbine First Stage Pressure Transmitter fails low

1P-1A, Reactor Coolant Pump seal leak After EOP Entry:

Small Break LOCA from RTD By-pass Line Reactor fails to trip (ATWS)

Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Abnormal Events:

1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element)

1PT-486, Turbine First Stage Pressure Transmitter fails low

1P-1A, Reactor Coolant Pump seal leak Major Transients:

Small Break LOCA ATWS Critical Tasks:

1. CT-6 Establish flow from at least one high-head SI pump

2. CT-52 Insert negative reactivity into the core Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG CT-6 Establish flow from at least one high-head SI pump Applicable ERG LP Version Applicable ERG E-0, ECA-0.2 Critical Task:

Establish flow from at least one Safety Injection pump before transition out of E-0 Plant Conditions:

Reactor trip SI Small-break LOCA RCS pressure below high-head ECCS pumps shutoff head LP Plants:

- Both Safety Injection pumps fail to start automatically

- At least one SI pump can be started provided that manual action is taken as necessary Cues:

Indication and/or annunciation that SI pump injection is required

- SI actuation

- RCS pressure below the shutoff head of the SI pump AND Indication and/or annunciation that no SI pump is injecting into the core

- Control switch indication that the circuit breaker or contactors for both SI pumps are open

- All SI pump discharge pressure reads zero

- All flow rate indicators for SI pump injection read zero Performance Indicator:

Manipulation of controls as required to establish flow from at least one SI pump Control switch indication that the circuit breaker or contactor for at least one SI pump Flow rate indication of injection from at least one SI pump Feedback:

Indication and/or annunciation that at least one SI pump is injecting Flow rate indication of injection from at least one SI pump Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG CT-52 Insert negative reactivity into the core Applicable ERG LP Version Applicable ERG FR-S.1 Critical Task:

Insert negative reactivity into the core by inserting control rods prior to completion of immediate actions.

Plant Conditions:

ATWS (Indication exists that the reactor is not tripped and that a manual reactor trip is not effective.)

Cues:

Indication of ATWS AND Indication that the reactor is not tripped and that a manual reactor trip is not effective Performance Indicator:

Manipulation of controls in the control room as required to initiate the insertion of negative reactivity into the core For scenarios in which it is possible for the crew to insert control rods:

- Group and individual rod position indication systems show control rods moving inward

- Control rod banks sequentially reach core bottom (unless RTBs opened locally)

Feedback:

Indication of a negative SUR on the intermediate range of the excore NIS Indication of less than 5% power on the power range of the excore NIS Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 35

TURNOVER INFORMATION SEG 1.0 Plant Conditions:

Unit 1 Unit 2 Time in Core Life (MWD/MTU): 1005 Reactor Power: 28%

Boron Concentration: 1874 ppm Rod Height: CBD @ 152 2.0 Equipment Out of Service:

1PT-950, Loop B Containment Pressure has been removed from service. Repairs are expected to be complete during the upcoming refueling outage.

1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.

3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:

LCO NOT Met TSAC Required Actions Completion Time 3.3.2 A. One or more Functions with one A.1 Enter the Condition referenced in Immediately or more channels or trains Table 3.3.2-1 for the channel(s) or inoperable. train(s).

D. One channel inoperable D.1 Place channel in trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR D.2.1 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 4.0 Planned Evolutions:

Secure Train B main feed and condensate pumps.

Raise power to 50% utilizing OP-1C Unit 1, Startup to Power Operation Unit 1.

5.0 Common

Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.

Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 35

SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 16E LMS Rev. Date:

SEG TITLE: 2017 NRC Exam Scenario 2 Note: modified to reflect "as-run" test conditions during session #2 of this scenario on 5/10/17.

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 Filename: NRC Scenario 2 final.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 35

PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _2_(Session #2)___ Op-Test No.: _2017____