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Prop Sim Scenarios
	ML22136A166
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Site:	Point Beach
Issue date:	07/02/2019
From:	; NRC/RGN-III/DRS/OLB
To:	; Point Beach
	Baker R
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ML17215A929	List: ML22136A152; ML22136A161; ML22136A166; ML22136A175; ML22136A184; ML22136A194; ML22136A199; NRC 2019-0015, Letter Submitting Proposed Exam;
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SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 19E LMS Rev. Date:

SEG TITLE: 2019 NRC Exam Scenario 1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 90 minutes Developed by: Andrew Zommers Instructor/Developer Date Reviewed by: Jeff Hinze Instructor (Instructional Review) Date Validated by: Andrew Zommers SME (Technical Review) Date Approved by: Andrew Fahrenkrug Training Supervision Date Approved by: Joe Krear Training Program Owner (Line) Date TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 2 of 33 Facility: _Point Beach_____ Scenario No.: __1__________ Op-Test No.: _2019_____

Examiners: ___________________________ Operators: _____________________________

Initial Conditions: _ Reactor power is 100%. G03, EDG is out of service due to maintenance __

with G04, EDG aligned. 1P-2B, Charging pump is out of service for maintenance. 1LT-426, PZR _

Level transmitter (Red) removed from service. Only 1P-30A, Circ Water pump is running due to___

previous fish intrusion which has been cleaned up, waiting to restart 1P-30B CW pump _

Turnover:_ 10% down power per OP 2A Att. A to remove 5A, HP Feedwater Heater from service _

Per OI 36, 5A and 5B HP Feedwater Heater Alignment. __________________________________

Critical Tasks:_CT-33, Control AFW Flow to Minimize RCS Cooldown________________________

_CT-17, Isolate Faulted SG__________________________________________________________

Event Malf. No. Event Event No. Type* Description C-BOP 1 MAL1CCW002A C-SRO 1P-11A, CCW pumps seal leak requiring pump shift TS-SRO R-RO 2 N-BOP Down power N-SRO I-RO I-SRO 1PT-485 Turbine First Stage Pressure slowly fails high during 3 XMT1MSS008A down power TS-SRO C-RO 1HC-428A, 1P-2A, Auto Charging Pump Hand Controller oscillates 4 CNH1PCS004F in auto, during the load reduction, Charging Pump Hand Controller C-SRO functions normal in manual.

C-BOP 5 MAL1SGN003B 1HX-1B, SG steam leak downstream of orifice to containment C-SRO 6 VLV1SGN005B M-All Safety fails open on 1HX-1A, SG on the trip VLV1SGN012 RLY1PPL027 7 RLY1PPL025 C-BOP Both MSIVs fail to auto close, with a failed B non-return valve RLY1PPL024 RLY1PPL026 RLY1PPL069 8 RLY1PPL070 RLY1PPL071 C-RO Train A ESF Sequencer Fails to Actuate RLY1PPL072

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 3 of 33 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given specific plant conditions, the students will be able to respond to a leak in Objective: 1P-11A CCW Pump, a planned 10% downpower with failure of 1PT-485 Turbine First Stage Pressure during the load reduction, followed by a failure of 1P-2A Charging Pump hand controller, a B S/G steam leak inside containment requiring a plant trip, post trip an A S/G Safety fails open and Train A ESF Sequencer fails along with auto closure of the MSIVs. The students will respond in accordance with plant procedures and 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 WHITE, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - White Channels

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

3. OP 2A Unit 1, Normal Power Operation

4. AOP 9B Unit 1, Component Cooling Water System Malfunction

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

6. AOP-2A Unit 1, Secondary Coolant Leak

7. AOP 6C Unit 1, Uncontrolled Rod Motion

8. AOP-24, Response to Instrument Malfunctions

9. EOP-0 Unit 1, Reactor Trip Or Safety Injection

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

11. EOP-2 Unit 1, Faulted Steam Generator Isolation

12. ECA 2.1 Unit 1, Uncontrolled Depressurization of Both Steam Generators

13. CSP-H.1, Unit 1 Loss of Heat Sink

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

15. Technical Specifications Manual

16. Technical Requirements Manual Protected None Content:

Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 4 of 33 Operating None Experience:

Risk Significant Initiating Event with Core Damage Frequency:

Operator Actions: Steam Break Inside Containment (4.12E-09 CDF) (2.00E-11 LERF)

Failure to isolate AFW to the Faulted Steam Generator from T (1.41E-03)

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

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Developed for the 2019 ILT NRC 0

Exam TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 5 of 33 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Given specific plant conditions, the students will be able to respond to a leak in 1P-11A CCW Pump, a planned 10% downpower with failure of 1PT-485 Turbine First Stage Pressure during the load reduction, followed by a failure of 1P-2A Charging Pump hand controller, a B S/G steam leak inside containment requiring a plant trip, post trip an A S/G Safety fails open and Train A ESF Sequencer fails along with auto closure of the MSIVs. The students will respond in accordance with plant procedures and properly utilize Technical Specifications.

Initial plant conditions are 100% power; G03 EDG is OOS with G04 EDG aligned, 1P-2B Charging Pump OOS, 1LT-426 Pressurizer Level transmitter removed from service. 1P-30B Circulating Water Pump was secured due to a previous fish intrusion which has been resolved, waiting to restart 1P-30B. A plant downpower of 10% at 30%/hr is planned per OP 2A Normal Power Operations Attachment A in order to remove the 5A FWH from service.

Terminate the scenario when crew has exited EOP-2 Faulted S/G Isolation the second time transitioning to EOP-1 Loss of Reactor or Secondary Coolant or per Lead Evaluator.

SEQUENCE OF EVENTS Event # Description

1. 1P-11A CCW Pump leak with pump swap and isolation

1P-11A CCW Pump seal leak will have the crew enter AOP 9B CCW System Malfunction

Crew will add make up water to the CCW Surge Tank, start 1P-11B CCW Pump, secure and isolate 1P-11A

SRO will address Technical Specifications

2. Conduct a unit Downpower of 10% from 100%

Utilize OP 2A Normal Power Operations Attachment A

Downpower unit 10% at 30%/hr

3. 1PT-485 Turbine First Stage Pressure transmitter fails high

1PT-485 will fail during the downpower affecting auto rod control

The crew should stop any auto rod motion

Crew will enter AOP 6C Uncontrolled Rod Motion

SRO will address Technical Specifications

4. 1HC-428A 1P-2A Charging Pump Hand Controller failure

1HC-428A will start to oscillate in automatic affecting CVCS

Crew should stabilize the unit taking manual control

Crew will enter AOP-1D CVCS Malfunction

SRO will address Technical Specifications TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 6 of 33

5. 1HX-1B S/G Steam Leak inside containment requiring plant trip

Crew diagnoses secondary steam leak and enters AOP-2A Secondary Coolant Leak

Crew recognizes plant trip criteria and trips unit 1

Crew enters EOP-0 Reactor Trip or Safety Injection

6. 1HX-1A S/G Safety fails open post trip

Crew enters EOP 2 Faulted Steam Generator

Crew recognizes double faulted steam generators

Crew enter ECA 2.1 Double Faulted Steam Generators

7. Both MSIVs fail to automatically close with failed B Non-Return valve

Crew recognizes the MSIVs did not shut as required and takes manual action to isolated faulted steam generators

8. Train A ESF Sequencer fails to actuate

Crew recognizes safeguards equipment did not sequence on as required

Crew takes action to start required equipment per EOP network Terminate the scenario when crew has exited EOP-2 Faulted S/G Isolation the second time transitioning to EOP-1 Loss of Reactor or Secondary Coolant or per Lead Evaluator.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 7 of 33 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

Check Action

1. Reset to IC-61

2. Perform Simulator Setup Checklist

3. Open schedule Z:\2019\ILT\2019 NRC Scenario 1.sch

4. Open SBT INSIGHT files to trend parameters Z:\NRC SBT\SBT Master Points

5. Open the Alarm List program

6. Take schedule(s) to run

7. Verify required event file(s) open if required

8. Take sim to run

9. Place turnover sheets on CO1 desk

10. Place reactivity sheets on CO1 desk

11. Guard the following:

G01, G02, G04 EDGs

1P-2A and 1P-2C Charging Pumps Place the following OOS:

G03 EDG

1P 2B Charging Pump

1LT-426 Pressurizer Level

1P-30B Circ Water Pump Place red dots on the G03 alarm and PZR Level:

C02 E 2-1

C02 E 2-2

1C04 1C 3-3 Place two orifices in service and turn on Pressurizer heaters.

12. 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 TR-AA-230-1007-F14, Revision 0

SEG PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 Page 8 of 33 BOOTH OPERATOR BRIEFING:

Review the scenario sequence, event triggers and expected field communications.

Z:\2019\ILT\2019 NRC Scenario 1.sch On At Time Action Description Event 00:00:01 Event: Z:\2019\ILT\2019 NRC Scenario 1.evt CCW Leak 1 Insert Malfunction MAL1CCW002A to 1.000000 1P-11A CCW Pump seal failure 16 Insert remote LOA1CCW031 to 1.0000 in 30 1CC-773 Unit 1 CCW Surge Tank demin water makeup 18 Insert remote LOA1CCW002 after 60 to 0 in 30 1CC-723A 1P-11A Suction Valve 18 Insert remote LOA1CCW004 after 90 to 0 in 30 1CC-725A 1P-11A Discharge Valve 18 Insert remote LOA1CCW045 after 120 to 0 in 30 1CC-792B 1P-11A Recirc Isolation 1PT-485 fails high 3 Insert Malfunction XMT1MSS008A to 750.000 in 60 1PT-485 First Stage Pressure 1P-2A Charging Pump Controller failure 5 Insert Malfunction CHN1PCS004F to 100.000 in 10 1HC-428A oscillations in auto only B S/G steam leak inside containment 7 Insert Malfunction MAL1SGN003B to 315000.0 in 300 S/G B Steam Line break inside containment 9 Insert Malfunction MAL1SGN003B after 180 to 1E6 in 600 S/G B Steam Line break inside containment A S/G Safety Valve fails open 9 Insert Malfunction VLV1SGN005B to 15.000 1MS-2010 A S/G Safety seat leakage 15 Insert Malfunction VLV1SGN005B to 0 1MS-2010 A S/G Safety seat leakage ESF relay failures/MSIV failures/pre-loads 00:00:01 Insert malfunction RLY1PPL069 to Fail_As_Is 1SI-11X Train A SI Relay 00:00:02 Insert malfunction RLY1PPL070 to Fail_As_Is 1SI-12X Train A SI Relay 00:00:03 Insert malfunction RLY1PPL071 to Fail_As_Is 1SI-13X Train A SI Relay

SEG PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 Page 9 of 33 On At Time Action Description Event 00:00:04 Insert malfunction RLY1PPL072 to Fail_As_Is 1SI-14X Train A SI Relay 00:00:05 Insert VLV1SGN012 to Stuck Open 1MS-2017A Non-Return Valve 00:00:06 Insert malfunction RLY1PPL027 to Fail_As_Is 1MS-B2 B MSIV relay 00:00:07 Insert malfunction RLY1PPL025 to Fail_As_Is 1MS-A2 B MSIV relay 00:00:07 Insert malfunction RLY1PPL024 to Fail_As_Is 1MS-A1 A MSIV relay 00:00:08 Insert malfunction RLY1PPL026 to Fail_As_Is 1MS-B1 A MSIV relay 12 Insert remote LOA1CFW083 to ON 1P-99A SGFP Seal Water Pump 12 Insert remote LOACFW084 to ON 1P-99B SGFP Seal Water Pump auto trigger to close A MSIV manually 11 Insert malfunction RLY1PPL024 to n/a 1MS-A1 A MSIV relay 11 Insert malfunction RLY1PPL026 to n/a 1MS-B1 A MSIV relay auto trigger to close B MSIV manually 13 Insert malfunction RLY1PPL025 to n/a 1MS-A2 B MSIV relay 13 Insert malfunction RLY1PPL027 to n/a 1MS-B2 B MSIV relay 00:00:01 Insert Malfunction BKR1CVC006 fail cntr fuse 1P-2B Charging Pump 00:00:01 Insert Malfunction XMT1RCS007A to 51.00000 1LT_426 Pressurizer Level Event file: Trigger 9 Unit 1 Reactor Trip (JCRFTR)

Trigger 11 A MSIV to close (X13I287P==0)

Trigger 13 B MSIV to close (X13I276P==0)

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 10 of 33 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Event # 1 1P-11A CCW Pump leak with pump swap and isolation ACTION Booth: Insert TRIGGER 1 per Lead Evaluator CO3/C01 STUDENT

Acknowledge plant alarms for low CC Surge tank level 1C03 1D 3-6

RESPONSE

Review ARB for 1C03 1D 3-6 OS1

Implements AOP-9B Unit 1, CCW System Malfunction Crew

Check at least one CCW Pump operating

Maintain Surge Tank Level o Start RMW Services Pump o Ensure 1CC-17 Surge Tank Vent open o Cycle 1CC-815 Emergency Fill Valve to maintain level o Identify and isolate leak per Attachment A Step A2 System Leakage to Atmosphere Inspect system piping to identify leakage Isolate the leak - shift CCW pumps, shut suction/discharge valves, place pump to PULLOUT Return to Step 2.g o Check CCW Surge tank level - STABLE Shut 1CC-815 CCW Surge Tank Makeup Valve Secure Services RMW Pump o Check Surge Tank - GREATER THAN 10%

o Check CCW System for In-Leakage o Check Reactor Trip - NOT REQUIRED o Check RHR status o Request Chemistry analyze CCW system o Notify DSM and Implement Emergency Plan

Return to Procedure and Step in Effect

Assess Technical Specifications:

CCW LCO 3.7.7 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. One CC pump A.1 Restore CC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable pump to AND OPERABLE 144 hours0.00167 days 0.04 hours 2.380952e-4 weeks 5.4792e-5 months from discovery status.

of failure to meet the LCO TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 11 of 33 Event # 1 1P-11A CCW Pump leak with pump swap and isolation

WHEN asked, THEN wait two minutes and report there is excessive seal ROLE PLAY leakage coming from 1P-11A, CCW Pump recommending securing the pump immediately. RP is in the area helping to confine leakage.

IF an AO is directed to locally makeup to 1T-12 CC Surge Tank by cycling 1CC-773, Component Cooling Surge Tank Demin Water Inlet, THEN cycle open/close 1CC-773 to maintain tank level between 20% and 60%. (TRIGGER 16)

IF the crew directs the AO to locally isolate 1P-11A, Component Cooling Water Pump, THEN insert TRIGGER 18 and report 1CC-723A, 1P-11A Suction and 1CC-725A, 1P-11A Discharge Valves are shut plus the seal leak has subsided.

SM communications:

If OS1 asks the SM about swapping pumps or taking 1P-11A to pullout, ask the OS1 what their preference is and concur.

If needed, the SM should inform OS1 to continue with the scheduled downpower.

NOTES Continuation Criteria:

After 1P-11B, Component Cooling Water Pump has been started, 1P-11A secured/isolated and Technical Specifications addressed, or at the discretion of the Lead Examiner, continue with the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 12 of 33 Event # 2 Conduct a unit Downpower of 10% from 100%

ACTION Booth: No action needed to start evolution Crew STUDENT

Crew will pre-brief evolution prior to the scenario utilizing their reactivity turnover RESPONSE sheets and OP 2A, Normal Power Operation Attachment A starting at Step 1.2 CO1/3

Estimate the boron/rod motion needed for the desired downpower

Ensure EH Control in OPER AUTO

IF Turbine Control is on the Valve Position Limiter (VPL) THEN TRANSFER Turbine Control from the VPL NOTE: Crew should use 1st STG OUT until less than 97% power then shift to 1st STG IN

Using thumbwheel SET the desired ramp rate per Step 1.1.2 (30%/hr)

PRESS Reference Control (lower) pushbutton to set terminal load (SETTER) to the target value specified in Att A step 1.1.1 (90%)

PRESS GO pushbutton and CHECK REFERENCE display indicates a controlled load reduction at the selected rate

RECORD date/time of load change in the Narrative Log:

ENSURE controls are maintained in AUTO as practical:

o Rod Control o Blender Controls o Turbine Controls

In MODE1, with THERMAL POWER greater or equal to 15% RTP, MAINTAIN Axial Flux Difference (AFD) within limits specified in the COLR LCO 3.2.3

MAINTAIN Tavg within 1.5°F of Tref OS 1

Direct and maintain oversight of reactivity evolutions

IF AO dispatched, wait 2 minutes (insert TRIGGER 12) and THEN report ROLE PLAY 1P-99A/B Steam Generator Seal Water pumps started.

NOTES Continuation Criteria:

Per Lead Evaluator after sufficient actions and downpower has been seen, continue to the next event. Ensure control rods are in AUTO TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 13 of 33 Event # 3 1PT-485 Turbine First Stage Pressure transmitter fails high ACTION Booth: Insert TRIGGER 3 per Lead Evaluator [Ensure rods in auto]

CO1 STUDENT

Identifies outward rod motion

RESPONSE

Determines if rod motion is warranted or not

Recommends placing rod control to MANUAL once failed instrument identified

Verifies rod motion stops CO3

Works with C01 to validate automatic rod motion warranted or not

Identifies failed 1PT-485 and informs the crew

May address ARB 1C03 1E2 4-2 o Take Condenser Steam Dumps to MANUAL control OS1

Provides direction and oversight to stabilize the unit (may stop downpower)

Directs entry into AOP 6C, Uncontrolled Rod Motion Crew

Utilizes AOP 6C Unit 1, Uncontrolled Rod Motion o Check Rod Motion - REQUIRED Rod motion is NOT required, crew should take rods to MANUAL o Maintain RCS Tavg o Check RCS Tavg - At OR TRENDING TO Tref o Check Control Rods - ABOVE MINIMUM INSERTION LIMIT o Verify AFD - WITHIN LIMIT o Check Rod Motion Due to Instrument Failure o Go To AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS

Crew transitions to AOP-24 Response to Instrument Malfunction o Identify Failed Instrument - 1PT-485 o Check if Failed Instrument is a Controlling Channel o Establish Manual Control as Required - Rod control to Manual o Return affected parameter(s) to Desired Value(s) o Using Attachment A, PPCS Parameters Used to Calculate RTO, Verify That The Failed Instrument is NOT an Input to RTO o Remove Failed Instrument From Service per 0-SOP-IC-001-WHITE o Return Controls to Automatic if Desired o Check Failure for Technical Specification or TRM Applicability o Return to Procedure And Step In Effect TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 14 of 33 Event # 3 1PT-485 Turbine First Stage Pressure transmitter fails high OS1 STUDENT

Assess Technical Specifications:

RESPONSE RPS LCO 3.3.1 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. One or more A.1 Enter the Immediately Functions with Condition one or more referenced in required Table 3.3.1-1 channels or for the trains channel(s) or inoperable train(s)

S. One or more S.1 Verify interlock 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel(s) is in required inoperable state for existing unit conditions OR S.2 Be in Mode 2 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally ROLE PLAY at 1PT-485 Turbine First Stage Pressure Transmitter.

NOTES Continuation Criteria:

After actions for the failed instrument has been taken, and Technical Specifications addressed or per the Lead Examiner continue to the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 15 of 33 Event # 4 1HC-428A 1P-2A Charging Pump Hand Controller failure ACTION Booth: Insert TRIGGER 5 per Lead Evaluator CO1 STUDENT

Determines 1P-2A, Charging Pump controller oscillating

RESPONSE

Recommends placing 1P-2A, Charging Pump to manual

Verifies proper operation CO3

Works with C01 to identify failure

References ARB 1C04 1C 1-8 Charging Trouble Alarm and 1C03 1D 2-1 Lab Seal D/P OS1

Direct actions to stabilize the unit

Enters AOP-1D Unit 1, CVCS Malfunctions Crew

Utilizes AOP 1D Unit 1, CVCS Malfunctions o Check RCS Leak - NOT IN PROGRESS o Review/Monitor Foldout Page Criteria o Determine CVCS Malfunction IF any of the following is true, THEN go to Step 3.

Any charging pump controller NOT RESPONDING PROPERLY o Check Any Charging Pump - RUNNING o Check Charging Flow - STABLE Place running charging pumps - IN MANUAL o Check Charging Pump Relief - NOT LIFTED o Check Charging Pump Suction Supply - ADEQUATE o Check Charging System Response:

Control Charging in manual as desired o Notify Duty Station Manager o Return To Procedure And Step In Effect OS1

Assess Technical Requirements Manual:

CVCS TRM 3.5.1 is MET

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally ROLE PLAY at 1P-2A Charging Pump (i.e. no relief lifting, VFD looks normal, etc.)

SM communications:

If OS1 asks the SM about placing charging auto, ask the OS1 what their preference is and concur.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 16 of 33 Event # 4 1HC-428A 1P-2A Charging Pump Hand Controller failure NOTES Continuation Criteria:

After actions for the failed controller have been taken and Technical Specifications addressed or per the Lead Examiner continue to the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 17 of 33 Event # 5 1HX-1B S/G Steam Leak inside containment requiring plant trip ACTION Booth: Insert TRIGGER 7 per Lead Evaluator CO3 STUDENT

Identifies rising containment pressure and humidity

RESPONSE

Monitors containment parameters

Sends out AOs to look for secondary leaks CO1

Monitors reactor power OS1

Direct actions to monitor the unit

Enters AOP-2A Unit 1, Secondary Coolant Leak Crew

Implements AOP-2A Unit 1, Secondary Coolant Leak o Determine Secondary Leakage Not Hazardous to Personnel or Equipment Monitor Containment pressure Less Than 2 psig Trip the Reactor o Maintain Plant Within Limits Reactor Power Less Than 100%

Implement EOP 0 Unit 1,Reactor Trip or Safety Injection o Verify Reactor Trip o Verify Turbine Trip o Verify Power to AC Safeguards Busses o Check if SI Is Actuated Manual actuation of both trains of SI o Manually start non running SI and RHR pumps o Monitor Foldout Page Criteria:

Adjust AFW flow to approximately 230 GPM shared between S/Gs o Perform Attachment A of EOP 0 o Verify AFW Pumps - RUNNING o Verify RCP Seal Cooling o Check RCS Temperatures o Check PZR PORVs And Spray Valves o Check if RCPs should be stopped o Check if S/G are NOT Faulted:

Check pressures in both S/Gs NO S/G pressure lowering in an uncontrolled manner NO S/G completely depressurized TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 18 of 33 Event # 5 1HX-1B S/G Steam Leak inside containment requiring plant trip Crew STUDENT

Transition to EOP-2 UNIT 1, FAULTED STEAM GENERATOR ISOLATION

RESPONSE

o Monitor foldout page criteria o Check Main Steamline Isolation (See event 7 for details) o Check If Any S/G Is Not Faulted:

o IF both S/G pressure are lowering in an uncontrolled manner, THEN go to ECA 2.1 Unit 1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS

Implement ECA 2.1 Unit 1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS o Check Secondary Pressure Boundary Verify the MSIVs SHUT (See event 7 for details)

Verify Feed Isolations SHUT Verify S/G Atmospherics SHUT Verify S/G Blowdown Isolation Reset LOFWTT SHUT 1MS-2019 and 1MS-2020 Locally SHUT Radwaste STeam isolations and upstream MSIV trap isolations 1MS-235, 1MS-237, 1MS-228 and 1MS-238 o Control Feed Flow to Minimize RC Cooldown Check RCS Cooldown < 100°F/hr - NO Reduce feed flow to 50 gpm to each S/G Check RCS hot leg temperatures - STABLE OR LOWERING o Crew may need to make additional AFW flow adjustments to control RCS cold leg temperatures o Check If RCPs Should be Stopped: - NO o Implement Foldout Page Criteria to transition back to EOP-2 after field report comes in that the safety is reseated.

CT-33, Control AFW Flow to Minimize RCS Cooldown

Transition to EOP-2 UNIT 1, FAULTED STEAM GENERATOR ISOLATION o Monitor foldout page criteria NOTE: CSP Status Trees now apply. The STA will inform the crew that a RED status tree applies, CSP-H.1 Loss of Heat Sink, due to the lowered AFW flows.

Transition to CSP.H-1 UNIT 1, Loss of Heat Sink o The first note states that if total feed flow was due to operator action this procedure should not be performed.

Transition to EOP-2 UNIT 1, FAULTED STEAM GENERATOR ISOLATION o Check Main Steamline Isolation (Should already be isolated) o Check If Any S/G Is Not Faulted - A o Identify Faulted S/G - B TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 19 of 33 Event # 5 1HX-1B S/G Steam Leak inside containment requiring plant trip STUDENT CREW RESPONSE o Isolate Faulted S/G:

Ensure feedwater isolations valve - SHUT (1CS-3125)

Ensure MDAFW valve - SHUT (1AF-4074B)

Ensure TDAFW valve - SHUT (1AF-4000)

Ensure SSG supply valve - SHUT (AF-4021)

Ensure Atmospheric steam dump - SHUT (1MS-2015)

Shut TDAFW steam supply (1MS2019)

Ensure S/G blowdown valves - SHUT (previously done)

Ensure Radwaste and Steam Traps isolated (previously done) o Check CST Level - GREATER THAN 4 ft.

o Check Secondary Radiation CT-17, Isolate Faulted SG

Transition to EOP-1 UNIT 1, Loss of Reactor or Secondary Coolant o Monitor Foldout page criteria

Check if RCPs Should be Stopped

WHEN directed to locally check shut radwaste service water valves, wait one ROLE PLAY minute and THEN report TV-LW61 is OPEN & 62 is CLOSED.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

After TRIGGER 15 is inserted, call up as the PAB AO and report the lifting A S/G Safety Valve has reseated.

IF asked to validate the FACP Alarm on a panel outside the Control Room, THEN wait 2 minutes and numerous Unit 1 Containment smoke detectors are alarming along with their HADs.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 20 of 33 Event # 5 1HX-1B S/G Steam Leak inside containment requiring plant trip NOTES Continuation Criteria:

After actions have been taken in ECA 2.1 Step 2 to control feed flow and RCS temperature AND before Step 9, or per Lead Evaluator, booth insert TRIGGER 15 to reset the A S/G Safety Valve.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 21 of 33 Event # 6 1HX-1A S/G Safety fails open post trip ACTION Booth: Ensure TRIGGER 9 goes in at the reactor trip (JCRFTR)

Crew STUDENT

Recognize indicated steam flow on the A S/G that is not required

RESPONSE

Transitions to ECA-2.1 Uncontrolled Depressurization of Both S/Gs from EOP-2 Faulted S/G Isolation

AFTER 5 minutes post reactor trip, THEN call up as PAB AO reporting there is ROLE PLAY steam coming from the area of A S/G Safeties.

After TRIGGER 15 is inserted, call up as the PAB AO and report the lifting A S/G Safety Valve has reseated.

NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 22 of 33 Event # 7 Both MSIVs fail to automatically close with failed B Non-Return valve ACTION Booth: No action required, pre-loads only STUDENT Crew RESPONSE

While implementing EOP 0 Reactor Trip or Safety Injection Step 8 for RCS temperature control, the crew may shut the MSIVs to stop the cooldown.

While implementing EOP 0 Reactor Trip or Safety Injection Attachment A Step A7 Check If Main Steam Lines Can Remain Open: - the crew should recognize the MSIVs should have shut and take RNO actions to close the MSIVs.

While implementing ECA 2.1 Uncontrolled Depressurization of Both S/Gs Step 2 Check Secondary Pressure Boundary: - the crew should recognize the MSIVs should have shut and take RNO actions to close the MSIVs.

ROLE PLAY None NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 23 of 33 Event # 8 Train A ESF Sequencer fails to actuate ACTION Booth: No action required, pre-loads only CO3 - EOP 0 Attachment A STUDENT

Verify Feedwater Isolation

RESPONSE

Verify Containment Isolation

Verify ECCS Pumps RUNNING o Start A RHR Pump

Verify Service Water Pumps RUNNING o Start P-32 F SW Pump

Verify Containment Accident Cooling Units RUNNING o Start CFC Unit A

Verify Component Cooling Pumps - ONLY ONE RUNNING

Check if Main Steam Lines Can Remain Open:

o Any MSIV Valve - OPEN o Containment pressure - LESS THAN OR EQUAL TO 15 psig o High-high steam flow bistable lights - NOT LIT o High steam flow bistable lights - NOT LIT

Verify Containment Spray Not Required o Single up Spray

Verify ECCS Flow

Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT

Verify Proper ECCS Valve Alignment o Open 1SI-852A

Check Containment Spray NOT ACTUATED

Stop any boration via the blender in progress

Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING

Perform the Following:

o Notify STA to IMPLEMENT Status Trees and SM of any equipment malfunctions not previously noted

Verify Service Water Alignment o SW-2927A, 2930B, 4479 and 2817 need to be shut

Check Miscellaneous Valves - SHUT

Check Control Room Ventilation

Check Cable Spreading Room Ventilation

Check Computer Room Ventilation

Check AFW Recirc Fans - ONE RUNNING

Check Circulating Water Pump House Temperature Less Than 105°F

Check G03/G04 Switchgear Room Temperature Less Than 95°F

Periodically check status of spent fuel cooling OS1

Provide required direction for C03 to take actions starting equipment TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 24 of 33 Event # 8 Train A ESF Sequencer fails to actuate

WHEN directed to locally check shut radwaste service water valves, wait one ROLE PLAY minute and THEN report TV-LW61 is OPEN & 62 is CLOSED.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 25 of 33 Scenario Termination Terminate the scenario when crew has exited EOP-2 Faulted S/G Isolation the second time transitioning to EOP-1 Loss of Reactor or Secondary Coolant or per Lead Evaluator.

Freeze the simulator NOTES

Determine if the NRC has any follow up questions

Save the INSIGHT files AND Alarm List PRIOR TO RESET

Close all schedule and event files TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 26 of 33 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1P-11A CCW Pump seal leak

1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto

1PT-485 First Stage Pressure transmitter fails high

1HXB S/G steam leak inside containment After EOP Entry:

A S/G Safety Valve lifts

MSIVs fail to auto closes to auto close

Train A ESF Sequencer fails Abnormal Events:

1P-11A CCW Pump seal leak

1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto

1PT-485 First Stage Pressure transmitter fails high

1HXB S/G steam leak inside containment Major Transients:

Uncontrolled depressurization of both S/Gs Critical Tasks:

1. CT-17 Isolate faulted S/G

2. CT-33 Control AFW flow to minimize RCS cooldown Major Procedures:

AOP-9B OP-2A AOP-1DAOP-6C AOP-24 EOP-0EOP-2 ECA-2.1EOP-2 TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 27 of 33 CT-17 Isolate faulted SG Critical Task:

Isolate the faulted Steam Generator before transition out of EOP-2.

Plant Conditions:

Faulted Steam Generator Cues:

Indication and/or annunciation that both the following are occurring:

Steam pressure and flow rate indications that make it possible to identify a single SG as faulted AND

Valve position and flow rate indication that AFW continues to be delivered to the faulted SG Performance Indicator:

Manipulation of controls as required isolating the faulted SG

MSIVs indicate closed

Indication of feedline isolation o Feedwater control valves indicate closed o Feedline isolation valves indicate closed o Main feed pumps indicate tripped

Indication that AFW flow to the faulted SG is stopped o AFW flow control valves for faulted SG indicate closed Feedback:

Any depressurization of intact SGs stops

Steam flow indication from faulted SG decreases to zero

RCS cooldown stops

Main feedwater flow rate indication of zero

AFW flow rate indication to faulted SG of zero Basis:

SAFETY SIGNIFICANCE - Failure to isolate a faulted SG that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Also, depending upon plant conditions, it could constitute a failure by the crew to "demonstrate the ability to recognize a failure or an incorrect automatic actuation of an ESF system or component."

Failure to isolate a faulted SG can result in challenges to the following CSFs:

Integrity

Subcriticality

Containment (if the break is inside containment)

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 28 of 33 CT-33 Control AFW flow to minimize RCS cooldown Critical Task:

Control the AFW flow rate to not less than 50 gpm per SG in order to minimize cooldown rate before a severe ORANGE path develops in the integrity CSF Plant Conditions:

Uncontrolled depressurization of both SGs

Cooldown rate in RCS cold legs exceeds 100°F per hour

A severe ORANGE path challenge to the integrity CSF has not developed provided the critical task is performed Cues:

Indication of uncontrolled depressurization of both SGs

- Containment pressure rise due to fault

- Indication and communication SG Safety lifting AND

Indication that the RCS cold leg cooldown rate exceeds 100°F per hour

- Control board indications show cold leg cooldown AND

Valve position and flow rate indication that AFW continues to be delivered to the faulted SGs at a rate in excess of 50 gpm per S/G Performance Indicator:

Manipulation of controls as required throttling AFW flow sufficiently to prevent a severe ORANGE challenge to the integrity CSF but not less than the 50 gpm per SG

- Control board indications that AFW flow was lowered Feedback:

Indication

- RCS cooldown stops

- Severe ORANGE challenge to integrity CSF not developed Basis:

SAFETY SIGNIFICANCE - Failure to control AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the critical task increases challenges to the subcriticality and the containment CSFs beyond those irreparably introduced by the postulated plant conditions.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 29 of 33 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:

UNIT 1 Time in core life (MWD/MTU): 9500 Reactor power (%): 100%

Boron concentration (ppm): 1020 ppm Rod height, CBD @: 220 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Required Action & Completion Time U1 3.3.1.A/K RPS one channel inoperable Place channel in trip - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months EQUIPMENT OUT OF SERVICE:

G03 Emergency Diesel Generator for maintenance.

1LT-426 Pressurizer Level Transmitter.

1P-2B Charging Pump for seal leak repairs.

PLANNED EVOLUTIONS:

10% downpower per OP 2A Normal Power Operation so 5A FWH can be secured. Pressurizer heaters are on and a 2nd letdown orifice is in service for the downpower.

TURNOVER INFORMATION:

G04 Emergency Diesel Generator is aligned to both 1A06 and 2A06 4160 Safeguards Busses.

1P-30B Circulating Water Pump was secured for a previous fish intrusion and is ready to start.

On line risk is GREEN.

Today is Tuesday, day shift.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 30 of 33 Communications/responses 1P-11A CCW Pump leak with pump swap and isolation

WHEN asked, THEN wait two minutes and report there is excessive seal leakage coming from 1P-11A CCW Pump recommending securing the pump immediately. RP is in the area helping to confine leakage.

IF an AO is directed to locally makeup to 1T-12 CC Surge Tank by cycling 1CC-773, Component Cooling Surge Tank Demin Water Inlet, THEN cycle open/close 1CC-773 to maintain tank level between 20% and 60%. (TRIGGER 16)

IF the crew directs the AO to locally isolate 1P-11A, Component Cooling Water Pump, THEN insert TRIGGER 18 and report when the valves are repositioned and the seal leak has subsided.

Conduct a unit Downpower of 10% from 100%

IF AO dispatched, wait 2 minutes (insert TRIGGER 12) and THEN report 1P-99A/B Steam Generator Seal Water pumps started.

1PT-485 Turbine First Stage Pressure transmitter fails high

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally at 1PT-485 Turbine First Stage Pressure Transmitter.

1HC-428A 1P-2A Charging Pump Hand Controller failure

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally at 1P-2A Charging Pump (i.e. no relief lifting, VFD looks normal, etc.)

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 SEG Page 31 of 33 1HX-1B S/G Steam Leak inside containment requiring plant trip

WHEN directed to locally check shut radwaste service water valves, wait one minute and THEN report TV-LW61 is OPEN & 62 is CLOSED.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

After TRIGGER 15 is inserted, call up as the PAB AO and report the lifting A S/G Safety Valve has reseated.

IF asked to validate the FACP Alarm on a panel outside the Control Room, THEN wait 2 minutes and report numerous Unit 1 Containment smoke detectors are alarming along with their HADs.

1HX-1A S/G Safety fails open post trip

AFTER 5 minutes post reactor trip, THEN call up as PAB AO reporting there is steam coming from the area of A S/G Safeties.

After TRIGGER 15 is inserted, call up as the PAB AO and report the lifting A S/G Safety Valve has reseated.

Both MSIVs fail to automatically close with failed B Non-Return valve None Train A ESF Sequencer fails to actuate

WHEN directed to locally check shut radwaste service water valves, wait one minute and THEN report TV-LW61 is OPEN & 62 is CLOSED.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

TR-AA-230-1007-F14, Revision 0

Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check OP 2A AOP 1D AOP 2A AOP 6C AOP 9B AOP 24 EOP 0 EOP 1 EOP 2 ECA 2.1 CSP-H.1

11 110E018 SH. 3 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check 1C03 1D 3-6 1C03 1E2 4-2 1C04 1C 1-8 1C03 1D 2-1 TR-AA-230-1007-F14, Revision 0

Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP 2B OP 2A AOP 1D AOP 2A AOP 6C AOP 9B AOP 24 EOP 0 EOP 1 EOP 2 ECA 2.1 CSP-H.1

11 110E018 SH. 3 1st Check 2nd Check 1C03 1D 3-6 1C03 1E2 4-2 1C04 1C 1-8 1C03 1D 2-1 RESET IC N/A Booth Cleared Exam Material Magnets Replaced TR-AA-230-1007-F14, Revision 0

SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 20E LMS Rev. Date:

SEG TITLE: 2019 NRC Exam Scenario 2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 90 minutes Developed by: Andrew Zommers Instructor/Developer Date Reviewed by: Jeffrey A Hinze Instructor (Instructional Review) Date Validated by: Andrew Zommers SME (Technical Review) Date Approved by: Andrew Fahrenkrug Training Supervision Date Approved by: Joe Krear Training Program Owner (Line) Date TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 2 of 34 Facility: _Point Beach_____ Scenario No.: __2__________ Op-Test No.: _2019_____

Examiners: ___________________________ Operators: _____________________________

Initial Conditions: _ Reactor power is 75%. G03, EDG is out of service due to maintenance __

with G04, EDG aligned. 1P-2B, Charging pump is out of service for maintenance. 1LT-426, PZR _

Level transmitter (Red) removed from service. Only 1P-30A, Circ Water pump is running due to ___

previous fish intrusion which has been cleaned up, waiting to restart 1P-30B CW pump _

Turnover:_Continue to raise reactor power to 100%_______________________________________

Critical Tasks:_ CT-18, Isolate Ruptured SG ___________________________________________

_CT-20, Depressurize RCS to EOP-3 SI Termination Criteria ______________________________

Event Malf. No. Event Event No. Type* Description C-BOP C-SRO 1W-1B1, Containment Accident fan high vibration 1 MAL1CNM004B NEW TS-SRO R-RO N-BOP 1HX-1A, SG Tube Leak approximately 10 gpm (rapid down power) 2 MAL1RCS008A N-SRO Repeat 2017 TS-SRO I-RO 1HC-110, Boric Acid Flow Controller fails in auto during the down 3 CNH1CVC011E power, manual control still functions I-SRO NEW C-RO 1CV-135 Letdown Line Backpressure controller oscillations, works 4 CNH1CVC014F in manual C-SRO Repeat 2015 C-BOP 1P-30A Circulating Water Pump bearing failure 5 XMT1CWS018A C-SRO NEW M-All Steam Generator Tube Leak increases and PRZ level cannot be 6 MAL1RCS008A maintained, after trip it becomes a Tube Rupture C-BOP 1P-53, MD AFW Pump Fails to start 7 BKR1AFW003 Repeat 2015 CNH1PCS007B C-RO Spray valves fail causing use of the PORV 8 CNH1PCS008B Repeat 2017

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 3 of 34 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given specific plant conditions, the students will be able to respond to a Objective: 1W-1B1 Accident Fan high vibes, a 15 gpm SGTL on A S/G requiring a rapid downpower with the following malfunctions during the load reduction: 1HC-110 Boric Acid Flow Controller failure, 1CV-135 Letdown Line Backpressure controller oscillations and 1P-30A Circulating Water Pump bearing failure. This will be followed by increased S/G tube leakage requiring a unit trip. Post trip 1P-53 MDAFW Pump failing to start and the Pressurizer Spray valves not working. The students will respond in accordance with plant procedures and 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. OI 72, Containment Air Recirculation System

2. OP 1C Unit 1, Startup to Power Operations

3. AOP 3 Unit 1, Steam Generator Tube Leak

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

5. AOP-13A, Circulating Water System Malfunction

6. AOP-24, Response to Instrument Malfunctions

7. EOP-0 Unit 1, Reactor Trip Or Safety Injection

8. EOP-3 Unit 1, Steam Generator Tube Rupture

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

10. Technical Specifications Protected None Content:

Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021.

Operating None Experience:

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 4 of 34 Risk Significant Initiating Event with Core Damage Frequency:

Operator Actions: SGTR (1.24E-08 CDF) (1.12E-08 LERF)

Operators Fail to Restore MFW During SGTR (1.24E-03)

Operator Fails to Cooldown and Depressurize the Intact SG (SGTR)

(6.13E-05)

Ops Fail to Stop SI After SGTR (5.34E-06)

Failure to Identify and Isolate the Ruptured SG in a SGTR Event (5.34E-06)

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

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Developed for the 2019 ILT NRC 0

Exam TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 5 of 34 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Given specific plant conditions, the students will be able to respond to 1W-1B1 Accident Fan high vibes, a 15 gpm SGTL on A S/G requiring a rapid downpower with the following malfunctions during the load reduction: 1HC-110 Boric Acid Flow Controller failure, 1CV-135 Letdown Line Backpressure controller oscillations and 1P-30A Circulating Water Pump bearing failure. This will be followed by increased S/G tube leakage requiring a unit trip. Post trip 1P-53 MDAFW Pump failing to start and the Pressurizer Spray valves not working. The students will respond in accordance with plant procedures and properly utilize Technical Specifications.

Initial plant conditions are 75% power; G03 EDG is OOS with G04 EDG aligned, 1P-2B Charging Pump OOS, 1LT-426 Pressurizer Level transmitter removed from service. 1P-30B Circulating Water Pump was secured due to a previous fish intrusion which has been resolved, waiting to restart 1P-30B. A plant up power is planned at 30% per hour per OP 2D Power Operation Maneuvering.

Terminate the scenario when crew has secured SI pumps per EOP-3 Steam Generator Tube Rupture or per Lead Evaluator.

SEQUENCE OF EVENTS Event # Description

1. 1W-1B1 Containment Accident Fan high vibrations

Crew recognizes fan failure

Crew addresses ARB and shifting of fans

SRO will address Technical Specifications

2. 1HX-1A S/G tube leak of approximately 15 gpm

Crew will respond to a lowering pressurizer level and main steam line radiation

Crew will enter AOP-3 Steam Generator Tube Leak

Crew will downpower the unit per AOP-17A Rapid Downpower

SRO will address Technical Specifications

3. 1HC-110 Boric Acid Flow Controller fails in auto

1HC-110 will fail in auto during the rapid downpower

Crew should take manual control of boric acid flow and continue downpower

Crew will enter AOP-24 Response to Instrument Malfunction TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 6 of 34

4. 1HC-135 Letdown Line Backpressure Controller oscillates

1HC-135 will start to oscillate in automatic affecting CVCS

Crew should stabilize the unit taking manual control

Crew will enter AOP-1D CVCS Malfunction

5. 1P-30A Circulating Water Pump bearing failure

Crew diagnoses failing bearing on 1P-30A

Crew enters AOP-13A Circulating Water System Malfunction

Crew starts 1P-30B Circulating Water Pump

6. 1HX-1A S/G Tube Leak increases requiring plant trip

Crew diagnoses increased RCS leakage and inability to maintain pressurizer level

Crew recognizes plant trip criteria and trips unit 1

Crew enters EOP-0 Reactor Trip or Safety Injection

7. 1P-53 Motor Driven AFW Pump fails to auto start

Crew recognizes the pump failure to start

Crew manually starts 1P-53 MDAFW Pump

8. Pressurizer Spray valves fail shut

Crew recognizes spray valves fail to open

Crew utilizes the PORV(s) to depressurize the RCS in EOP-3 Terminate the scenario when crew has secured SI pumps per EOP-3 Steam Generator Tube Rupture or per Lead Evaluator.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 7 of 34 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

Check Action

1. Reset to IC-62

2. Perform Simulator Setup Checklist

3. Open schedule Z:\2019\ILT\2019 NRC Scenario 2.sch

4. Open SBT INSIGHT file for the NRC. Z:\NRC SBT\SB Master Points

5. Open the Alarm List program

6. Take schedule(s) to run

7. Verify required event file(s) open if required

8. Take sim to run

9. Place turnover sheets on CO1 desk

10. Place reactivity sheets on CO1 desk

11. Guard the following:

G01, G02, G04 EDGs

1P-2A and 1P-2C Charging Pumps Place the following OOS:

G03 EDG

1P 2B Charging Pump

1LT-426 Pressurizer Level

1P-30B Circ Water Pump Place red dots on the G03 alarm and PZR Level:

C02 E 2-1

C02 E 2-2

1C04 1C 3-3 Place two orifices in service and turn on Pressurizer heaters.

12. 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 TR-AA-230-1007-F14, Revision 0

SEG PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 Page 8 of 34 BOOTH OPERATOR BRIEFING:

Review the scenario sequence, event triggers and expected field communications.

Z:\2019\ILT\2019 NRC Scenario 2.sch On At Time Action Description Event 00:00:01 Event: Z:\2019\ILT\2019 NRC Scenario 2.evt 1W-1B1 High Vibrations 1 Insert Malfunction MAL1CNM004B 1W-1B1 high vibrations Steam Generator Tube Leak 3 Insert Malfunction MAL1RCS008A to 0.03500 A S/G Tube Rupture 1HC-110 BA Controller fails shut in auto 5 Insert Malfunction CHN1CVC011E to 100.000 in 20 1HC-110 BA Controller fails shut in auto 1CV-135 Letdown Line Pressure Controller failure 7 Insert Malfunction CHN1CVC014F to 20.000 1HC-135 oscillations in auto only 1P-30A Circulating Water Pump bearing failure 7 Insert Malfunction XMT1CWS018A to 222.00000 in 600 1TR-2000B-11 1P-30A Upper Motor Bearing fixed output 14 Insert Malfunction XMT1CWS018A to 90.00000 in 600 1TR-2000B-11 1P-30A Upper Motor Bearing fixed output Steam Generator Tube Rupture 9 Insert Malfunction MAL1SGN008A to 0.40000 A S/G Tube Rupture 1P-53 MDAFW Pump fail to start 00:00:02 Insert malfunction BKR1AFW003 to Fail_To_Auto_Close 1P-53 MDAFW Pump fails to auto start Spray Valve failures 9 Insert Malfunction CHN1PCS007B to 0 1HC-431C1 PCV431A Spray Valve controller failure 9 Insert Malfunction CHN1PCS008B to 0 1HC-431H1 PCV431B Spray Valve controller failure

SEG PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 Page 9 of 34 On At Time Action Description Event 16 Insert remote LOA1CFW083 to ON 1P-99A SGFP Seal Water Pump 16 Insert remote LOACFW084 to after 5 to ON 1P-99B SGFP Seal Water Pump 12 Insert remote LOA1SGN023 to 0 in 30 1MS-235 Radwaste Steam Isolation 00:00:01 Insert Malfunction BKR1CVC006 fail cntr fuse 1P-2B Charging Pump 00:00:01 Insert Malfunction XMT1RCS007A to 51.00000 1LT_426 Pressurizer Level Event File Trigger 14 1P-30A secured (X13O338G==1)

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 10 of 34 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Event # 1 1W-1B1 Containment Accident Fan high vibrations ACTION Booth: Insert TRIGGER 1 per Lead Evaluator CO1/C03 STUDENT

Diagnose failure of 1W-1B1 Containment Accident Fan

RESPONSE

Addresses ARB C01 B 3-3, 3-4 and 4-3 OS1

Provides direction and oversight

Directs shifting accident fans Crew

Implements OI-72 Containment Air Recirculation System 5.1 Starting Unit 1 Containment Cooling and Accident Recirc Fans 5.1.1 RECORD Service Water flow from cooler being started 5.1.2 START desired Containment accident recirc fan 5.1.3 CHECK Annunciator C01 B 3-3 Unit 1 Containment Recirc Cooler Air Flow Low is clear 5.1.4 CHECK yellow LOW FLOW indicator light associated with fan started in Step 5.1.2 is NOT illuminated 5.1.5 COORDINATE with Shift Management to determine if a Containment cooling fan will be started 5.1.6 IF directed by Shift Management, THEN START Containment cooling fan associated Containment accident recirc fan stated in Step 5.1.2 5.1.7 IF Annunciator C01 B 4-3, Unit 1 Containment Recirc Fan Vibration High is actuated, THEN ATTEMPT to RESET the alarm 5.1.8 IF Annunciator C01 B 4-3, Unit 1 Containment Recirc Fan Vibration High fails to reset, THEN NOTIFY Shift Management to assess fan operability 5.2 Stopping Unit 1 Containment Cooling and Accident Recirc Fans 5.2.1 STOP desired Containment cooling fan 5.2.2 STOP Containment accident recirc fan associated with Containment cooling fan stopped in Step 5.2.1 TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 11 of 34 Event # 1 1W-1B1 Containment Accident Fan high vibrations STUDENT OS1 RESPONSE

Assess Technical Specifications Containment Spray LCO 3.6.6 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION C. One or two C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months accident fan accident fan AND cooler unit(s) cooler unit(s) 144 hours0.00167 days 0.04 hours 2.380952e-4 weeks 5.4792e-5 months from discovery inoperable to OPERABLE of failure to meet the LCO status ROLE PLAY Shift Manager cue: If asked by OS1 about shifting accident fans or placing 1W-1B1 in pullout, ask OS1 what their preference is and concur.

NOTES Continuation Criteria:

After accident fans shifted and Technical Specifications addressed, or at the discretion of the Lead Examiner, continue with the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 12 of 34 Event # 2 1HX-1A S/G tube leak of approximately 15 gpm ACTION Booth: Insert TRIGGER 3 per Lead Evaluator CO1 STUDENT

Identifies lowering pressurizer level, increased charging pump speed and RESPONSE increased RMS

Determines SGTL rate CO3

Works with C01 to validate SGTL and rate

Addresses ARBs 1C20 C 1-2 and 2-1 OS1

Provides direction and oversight to determine SGTL rate

Directs entry into AOP 3 Unit 1 Steam Generator Tube Leak Crew

Utilizes AOP 3 Unit 1 Steam Generator Tube Leak o Check Safety Injection Not Required o Check Reactor Trip Not Required o Check PZR Level - STABLE OR TRENDING TO PROGRAM IF PZR level trending lower, THEN perform the following:

Control charging and letdown to maintain PZR level

IF PZR level continues to lower, THEN isolate letdown o Check PZR Pressure - STABLE OR TRENDING TO DESIRED PRESSURE o Check Reactor Makeup Control o Notify DSM, Chemistry, and Implement Emergency Plan o Identify leaking S/G - A o Determine Leak Rate - approximately 15 gpm o Check Reactor Shutdown Required: Yes o Determine Action Response Based On S/G Leakage:

Reduce Power to < 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and Mode 3 in the next two hours (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to get to mode 3 regardless of starting power level) o Place Unit in Mode 3 o Notify Chemistry of Leak Rate and Rate of Change NOTE: If the OS asks the Shift Manager method of and/or rate of shutdown ask what the OS1 recommendation is. If needed direct using AOP-17A Rapid Downpower Unit 1 at 1%/min ramp rate.

OS1

Directs entry into AOP 17A Unit 1 Rapid Downpower TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 13 of 34 Event # 2 1HX-1A S/G tube leak of approximately 15 gpm Crew STUDENT

Utilizes AOP 17A Unit 1 Rapid Downpower RESPONSE o Check Power - GREATER THAN 100% - No o Determine Desired Power Level or Condition to be Met - Offline 1%/min o Commence Boration as Necessary to Target Load o Select Turbine Rate and Reduce Load o Notify Power System Supervisor (PSS) of Load Reduction o Check Rod Control System - IN AUTO o Energize Pressurizer Backup Heaters o Check PZR Pressure - CONTROLLING IN AUTO o Check PZR Level - CONTROLLING IN AUTO o Check Steam Generator Level - CONTROLLING IN AUTO o Ensure Main Feed Pump Seal Water Pump - RUNNING o Maintain RCS Tavg o Check AFD - WITHIN LIMITS o Control MSR temperatures - LESS THAN 500°F o Determine Desired End-Point - LESS THAN 60% TURBINE LOAD o Establish One Train of Feed and Condensate OS1

Assess Technical Specifications:

RCS Operational Leakage LCO 3.4.13 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION B. Primary to B.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months secondary LEAKAGE not AND within limits B.2 Be in Mode 5 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

IF RP is requested to perform steam line surveys, THEN wait 5 minutes and ROLE PLAY report:

'A' main steam line is 5 mrem above background.

'B' main steam line is at background.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 14 of 34 Event # 2 1HX-1A S/G tube leak of approximately 15 gpm NOTES Continuation Criteria:

After boration started and some downpower has been seen, continue to the next event per Lead Evaluator.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 15 of 34 Event # 3 1HC-110 Boric Acid Flow Controller fails in auto ACTION Booth: Insert TRIGGER 5 per Lead Evaluator CO1/C03 STUDENT

Identifies changing boric acid flow during downpower

RESPONSE

Recommends stopping boration or shifting 1HC-110 to manual

Reference ARB 1C04 1C 2-8 BA Flow Deviation OS1

Provides direction and oversight to stop malfunction

Directs entry into AOP 24 Response to Instrument Malfunction Crew

Crew transitions to AOP-24 Response to Instrument Malfunction o Identify Failed Instrument - None, its a controller o Establish Manual Control as Required - Boric acid make up to manual o Return affected parameter(s) to Desired Value(s) o Using Attachment A, PPCS Parameters Used to Calculate RTO, Verify That The Failed Instrument is NOT an Input to RTO o Remove Failed Instrument From Service o Return Controls to Automatic if Desired o Check Failure for Technical Specification or TRM Applicability o Return to Procedure And Step In Effect NOTE: If the OS asks the Shift Manager about continuing with the downpower and failure of 1HC-110, ask what the OS1 recommendation is. If needed direct to continue the downpower as previously determined with 1HC-110 in manual.

IF asked to investigate 1CV-110 locally, THEN wait 2 minutes and report any ROLE PLAY valve position consistent with controller demand and/or everything else appears normal.

NOTES Continuation Criteria:

After actions for 1HC-110 have been taken and sufficient downpower has been observed or per the Lead Examiner continue to the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 16 of 34 Event # 4 1HC-135 Letdown Line Backpressure Controller oscillates ACTION Booth: Insert TRIGGER 7 per Lead Evaluator CO1 STUDENT

Identifies cycle letdown pressure and flow

RESPONSE

Determines 1CV-135 controller oscillating

Recommends placing letdown pressure control to manual

Verifies proper operation CO3

Works with C01 to identify failure

References ARB 1C04 1C 1-6 Letdown Pressure High OS1

Direct actions to stabilize letdown pressure/flow

Enters AOP-1D, Unit 1 CVCS Malfunctions Crew

Utilizes AOP 1D Unit 1 CVCS Malfunctions o Check RCS Leak - NOT IN PROGRESS o Review/Monitor Foldout Page Criteria o Determine CVCS Malfunction IF LP Letdown Line Pressure Control Valve Failed, THEN go to Step 36 1CV-135 o Check LP Letdown Line Pressure Control Valve - FAILED o Establish Manual Control Place LP Letdown Line Pressure Control Valve - IN MANUAL Adjust LP Letdown Line Pressure Controller - MAINTAIN LETDOWN PRESSURE AT 250 PSIG o Notify Duty Station Manager and I&C Duty and Call o Return To Procedure And Step In Effect

IF asked, wait 2 minutes, THEN report there are no abnormal indications locally ROLE PLAY at 1CV-135 LP Letdown Line Pressure Control Valve. (If asked for valve position respond back corresponding position matching control board indications)

Shift Manager cue: If needed, Step 1 of AOP-1D asks about an RCS leak, then directs you to AOP-1A RCS leak (SGTL in progress) which in turn sends you to AOP-3 SGTL (which is in progress). If needed cue OS1 that OS2 will look at AOP-1A for Unit 1 and he can continue with the unit 1 downpower.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 17 of 34 Event # 4 1HC-135 Letdown Line Backpressure Controller oscillates NOTES Continuation Criteria:

No action required, trigger inserts with previous event.

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PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 18 of 34 Event # 5 1P-30A Circulating Water Pump bearing failure ACTION Booth: No action required, trigger inserts with previous event.

CO3 STUDENT

Identify alarming point per 1C04 1C 4-8 1TR-2000A or B Temp Monitor

RESPONSE

Report back and monitor 1P-30A Circulating Water pump parameters CO1

Monitor the unit and reference ARBs OS1

Direct actions to monitor the pump conditions Crew

Implements OI 38 Circulating Water System Operation to start 1P-30B and secure 1P-30A.

IF asked to locally investigate 1P-30A CW Pump, THEN wait 2 minutes and ROLE PLAY report service water cooling is normal but the upper bearing oil is discolored and the area is hotter than normal.

IF asked to locally monitor 1P-30A CW Pump motor bearing temperatures, THEN wait 3 minutes and report that local temperatures with pyrometer are 3°F lower than seen on TR-2000A/B.

Shift Manager cue: If OS1 asks, concur as needed or direct shifting of the Circulating Water Pumps per OI-38, we want to do a controlled downpower with the SGTL vice trip the unit.

NOTES Continuation Criteria:

After actions have been taken to shift Circulating Water Pumps on Unit 1 or per Lead Evaluator, booth insert TRIGGER 9 to initiate the SGTR.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 19 of 34 Event # 6 1HX-1A S/G Tube Leak increases requiring plant trip ACTION Booth: Insert TRIGGER 9 per Lead Evaluator CO1/C03 STUDENT

Recognize increased SG tube leakage with inability to maintain RCS inventory

RESPONSE

Determine plant trip required OS1

Directs or confirms plant trip required

Enters EOP 0 Reactor Trip or Safety Injection Crew

Implement EOP 0 Reactor Trip or Safety Injection o Verify Reactor Trip o Verify Turbine Trip o Verify Power to AC Safeguards Busses o Check if SI Is Actuated o Monitor Foldout Page Criteria:

Adjust AFW flow to ruptured S/G when level >32% NR o Perform Attachment A of EOP 0 o Verify AFW Pumps - RUNNING -- No Manually start 1P-53 MDAFW Pump o Verify RCP Seal Cooling o Check RCS Temperatures o Check PZR PORVs And Spray Valves o Check if RCPs should be stopped o Check if S/Gs are NOT Faulted o Check if S/Gs Tubes are NOT ruptured:

Transition to EOP-3 UNIT 1, Steam Generator Tube Rupture

Implement EOP 3 Unit 1, Steam Generator Tube Rupture o Monitor Foldout Page Criteria o Check if RCPs should be stopped o Identify Ruptured S/G(s): - A TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 20 of 34 Event # 6 1HX-1A S/G Tube Leak increases requiring plant trip STUDENT RESPONSE o Isolate Flow From Ruptured S/G:

Ensure 1HC-468 A ADV - SET TO 1050 psig Ensure 1MS-2016 - SHUT Locally shut the following:

o 1MS-235 Radwaste Steam Isolation o 1MS-228 Main Steam Trap Isolation Ensure S/G blowdown is isolated:

o 1MS-5958 - SHUT o 1MS-2042 - SHUT Shut 1MS-2018 MSIV and 1MS-234 MSIV Bypass o Check Ruptured S/G Level:

Level - GREATER THAN 32%

Place in manual and shut 1AF-4074A Ensure 1AF-4001 TDAFW flow control vale - SHUT Ensure AF-4023 SSG supply valve - SHUT CT-18, Isolate Ruptured SG o Check Ruptured S/G Pressure - GREATER THAN 590 psig o Initiate RCS Cooldown:

Check SI signal status:

o ANY AUTO SI signal - IN (no) o Put SI signal in with bistables o Reset SI Determine required core exit temperature Start dumping steam o Check core exit thermocouple temperatures - LESS THAN REQUIRED TEMPERATURE Continue cooling down and continue in procedure Maintain core exit thermocouples temperatures - LESS THAN REQUIRED TEMPERATURE o Check Intact S/G Level S/G Level - GREATER THAN 32%

Control feed flow to maintain S/G level between 36% and 63%

o Check PZR PORVs and Block Valves o Check SI signal status:

ANY AUTO SI signal - IN Reset SI o Reset Isolation And Lockout Signals:

Containment Isolation 1B-03 and 1B-04 NON-Safeguards equipment lockouts o Establish Instrument Air to Containment TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 21 of 34 Event # 6 1HX-1A S/G Tube Leak increases requiring plant trip o Check If RHR Pumps Should Be Stopped-STUDENT Stop both RHR pumps and place in auto RESPONSE o Establish Charging Flow Establish maximum charging flow o Check if RCS Cooldown Should Be Stopped-Check core exit thermocouple temperatures - LESS THAN REQUIRED TEMPERATURE FROM STEP 6 Stop RCS cooldown Maintain core exit thermocouples temperatures - LESS THAN REQUIRED TEMPERATURE o Check Ruptured S/G Pressure: - STABLE OR RISING o Check RCS Subcooling Based on Core Exit Thermocouples -

GREATER THAN 57°F o Depressurize RCS to Minimize Break Flow and Refill PZR:

Normal Spray - AVAILABLE Spray PZR with maximum available spray until any of the following conditions satisfied:

o Crew determines PZR Spray valves do not work and per RNO moves to the next step to depressurize the RCS using a PORV o Depressurize RCS Using PZR PORV to Minimize Break Flow and Refill PZR:

At least one PZR PORV - AVAILABLE Open one PZR PORV until any of the following conditions satisfied:

o RCS pressure - LESS THAN RUPTURED S/G PRESSURE o PZR level - GREATER THAN 13%

OR o PZR Level - GREATER THAN 68%

OR o RCS subcooling based on core exit thermocouples - LESS THAN 37°F Shut PZR PORV o Check RCS Pressure - RISING o Check if ECCS Flow Should be Terminated RCS Subcooling based on core exit thermocouples - GREATER THAN 37°F Secondary heat sink: Intact S/G level - GREATER THAN 32%

RCS pressure - STABLE OR RISING PZR level - GREATER THAN 13%

o Stop Both SI Pumps and Place In Auto o Establish Charging Flow o Ensure Adequate RCS Depressurization CT-20, Depressurize RCS to EOP-3 SI Termination Criteria TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 22 of 34 Event # 6 1HX-1A S/G Tube Leak increases requiring plant trip o Verify SI Flow Not Required STUDENT o Check Reactor Makeup Control-RESPONSE Ensure MCCs - ENERGIZED 1B-31, 1B52-14C, Train A B-43, 1B52-21C, Train B Makeup set for greater than 2800 ppm VCT level - GREATER THAN 17%

Ensure Makeup armed and in auto o Check if Letdown can Be Established PZR Level - GRATER THAN 24%

Establish letdown CO3 - EOP 0 Attachment A STUDENT

Verify Feedwater Isolation

RESPONSE

Verify Containment Isolation

Verify ECCS Pumps RUNNING

Verify Service Water Pumps RUNNING

Verify Containment Accident Cooling Units RUNNING

Verify Component Cooling Pumps - ONLY ONE RUNNING

Check if Main Steam Lines Can Remain Open

Verify Containment Spray Not Required

Verify ECCS Flow

Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT

Verify Proper ECCS Valve Alignment

Check Containment Spray NOT ACTUATED

Stop any boration via the blender in progress

Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING

Perform the Following:

o Notify STA to IMPLEMENT Status Trees and SM of any equipment malfunctions not previously noted

Verify Service Water Alignment

Check Miscellaneous Valves - SHUT

Check Control Room Ventilation

Check Cable Spreading Room Ventilation

Check Computer Room Ventilation

Check AFW Recirc Fans - ONE RUNNING

Check Circulating Water Pump House Temperature Less Than 105°F

Check G03/G04 Switchgear Room Temperature Less Than 95°F

Periodically check status of spent fuel cooling TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 23 of 34 Event # 6 1HX-1A S/G Tube Leak increases requiring plant trip

WHEN directed to locally check shut radwaste service water valves, TV-LW61 ROLE PLAY

& 62, wait one minute and THEN report both valves are closed.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to shut 1MS-235, AFP Radwaste Steam Isolation and 1MS-228, Main Steam Trap Header Isolation, wait 5 minutes THEN insert Trigger 12 and report when the valves are closed.

NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 24 of 34 Event # 7 1P-53 Motor Driven AFW Pump fails to auto start ACTION Booth: No action required, pre-loads only STUDENT Crew RESPONSE

Post reactor trip immediate actions the crew may notice 1P-53 did not automatically start as designed and choose to start it.

While implementing EOP 0 Reactor Trip or Safety Injection Step 6 Verify AFW Pumps - RUNNING, crew should take RNO actions to start 1P-53.

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally ROLE PLAY at the pump or breaker.

NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 25 of 34 Event # 8 Pressurizer Spray valves fail shut ACTION Booth: No action required, pre-loads only STUDENT C01 RESPONSE

Recognize Pressurizer Spray valves do not operate OS1

Determine RNO actions for EOP-3 Step 17 and move to Step 18 depressurizing the RCS utilizing a PORV.

During remaining EOP-3 steps controlling the RCS pressure, ensure the PORV is used.

ROLE PLAY None NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 26 of 34 Scenario Termination Terminate the scenario when crew has secured SI pumps per EOP-3 Steam Generator Tube Rupture or per Lead Evaluator.

Freeze the simulator NOTES

Determine if the NRC has any follow up questions

Save the INSIGHT files AND Alarm List PRIOR TO RESET

Close all schedule and event files TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 27 of 34 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1W-1B1 Containment Accident Fan high vibrations

1HXA Steam Generator tube leak

1HC-110, Boric Acid Flow controller fails in auto

1HC-135, Letdown Line Backpressure controller oscillates in auto

1P-30A Circulating Water Pump bearing failure After EOP Entry:

1P-53 MDAFW Pump fails to auto start

Pressurizer Spray Valves fail shut Abnormal Events:

1W-1B1 Containment Accident Fan high vibrations

1HXA Steam Generator tube leak

1HC-110, Boric Acid Flow controller fails in auto

1HC-135, Letdown Line Backpressure controller oscillates in auto

1P-30A Circulating Water Pump bearing failure Major Transients:

Steam Generator Tube Rupture Critical Tasks:

1. CT-18 Isolate ruptured S/G

2. CT-20 Depressurize RCS to EOP-3 SI termination criteria Major Procedures:

AOP-24 AOP-3 AOP-1DAOP-13A EOP-0EOP-3 TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 28 of 34 CT-18 Isolate ruptured SG Critical Task:

Isolate feedwater flow into and steam flow from ruptured SG before a transition to ECA-3.1 Plant Conditions:

SGTR

Reactor trip

SI Cues:

Indication and/or annunciation of SGTR in one SG

- Increasing SG water level

- Radiation AND

Indication and/or annunciation of reactor trip AND

Indication and/or annunciation of SI Performance Indicator:

Manipulation of controls as required to isolate the ruptured SG

Main steam isolation valve position lamps indicate closed

Main steam isolation bypass valve position lamps indicate closed

Blowdown isolation valve position lamps indicate closed

Steam isolation valve to TDAFW pump position lamps indicate closed

AFW valve position lamps and/or indicators indicate closed

Feedwater isolation valve position lamps indicated closed Feedback:

Indication of stable or increasing pressure in the ruptured SG

Indication of decreasing or zero feedwater flow rate in the ruptured SG Basis:

SAFETY SIGNIFICANCE - Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SG.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 29 of 34 CT-20 Depressurize RCS to EOP-3 SI Termination Criteria Critical Task:

Depressurize RCS to EOP-3 SI termination criteria before the SG goes water solid Plant Conditions:

SGTR

SI

Ruptured SG identified and isolated

RCS cooldown to target temperature completed

RCS depressurization completed

SI termination criteria met Cues:

Indication and/or annunciation of SGTR in one SG

- Increasing SG water level

- Radiation AND

Indication and/or annunciation of reactor trip and SI AND

Indication that RCS is cooldown to the target temperature Performance Indicator:

Manipulation of controls as required to depressurize the RCS

- Control board indications show PZR spray valve or PZR PORV open Feedback:

Indication

- RCS pressure decreasing

- PZR level increasing Basis:

SAFETY SIGNIFICANCE - Failure to stop reactor coolant leakage into a ruptured SG by depressurizing the RCS needlessly complicates mitigation of the event. It also constitutes a significant reduction of safety margin beyond that irreparably introduced by the scenario.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 30 of 34 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:

UNIT 1 Time in core life (MWD/MTU): 9500 Reactor power (%): 75%

Boron concentration (ppm): 1125 ppm Rod height, CBD @: 178 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Required Action & Completion Time U1 3.3.1.A/K RPS one channel inoperable Place channel in trip - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months EQUIPMENT OUT OF SERVICE:

G03 Emergency Diesel Generator for maintenance.

1LT-426 Pressurizer Level Transmitter.

1P-2B Charging Pump for seal leakage repair.

PLANNED EVOLUTIONS:

Continue to raise reactor power to 100% per OP 1C Startup to Power Operation Step 5.36.2. Pressurizer heaters are on and a 2nd letdown orifice is in service for the downpower.

TURNOVER INFORMATION:

G04 Emergency Diesel Generator is aligned to both 1A06 and 2A06 4160 Safeguards Busses.

1P-30B Circulating Water Pump was secured for a previous fish intrusion and is ready to start.

On line risk is GREEN.

Today is Tuesday, day shift.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 31 of 34 Communications/responses 1W-1B1 High Vibrations None 1HX-1A S/G tube leak of approximately 15 gpm

IF RP is requested to perform steam line surveys, THEN wait 5 minutes and report:

'A' main steam line is 5 mrem above background.

'B' main steam line is at background.

1HC-110 Boric Acid Flow Controller fails in auto

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally.

1HC-135 Letdown Line Backpressure Controller oscillates

IF asked to investigate 1CV-110 locally, THEN wait 2 minutes and report any valve position consistent with controller demand and/or everything else appears normal.

1P-30A Circulating Water Pump bearing failure

IF asked to locally investigate 1P-30A CW Pump, THEN wait 2 minutes and report service water cooling is normal but the upper bearing oil is discolored and the area is hotter than normal.

IF asked to locally monitor 1P-30A CW Pump motor bearing temperatures, THEN wait 3 minutes and report that local temperatures with pyrometer are 3°F lower than seen on TR-2000A/B.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 20E, 2019 NRC Exam Scenario 2, Rev 0 SEG Page 32 of 34 1HX-1A S/G Tube Leak increases requiring plant trip

WHEN directed to locally check shut radwaste service water valves, TV-LW61 & 62, wait one minute and THEN report both valves are closed.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to shut 1MS-235, AFP Radwaste Steam Isolation and 1MS-228, Main Steam Trap Header Isolation, wait 5 minutes THEN insert TRIGGER 12 and report when the valves are closed.

1P-53 Motor Driven AFW Pump fails to auto start

IF asked, wait 2 minutes, THEN report there are no abnormal indication locally at the pump or breaker.

Pressurizer Spray valves fail shut None TR-AA-230-1007-F14, Revision 0

Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP 1D AOP 3 AOP 13A AOP 17A AOP 24 EOP 0 EOP 3 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check 1C04 1C 1-6 1C04 1C 2-8 1C04 1C 4-8 1C20 C 1-2 1C20 C 2-1 C01 B 3-3 C01 B 3-4 C01 B 4-3 TR-AA-230-1007-F14, Revision 0

Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP 2B AOP 1D AOP 3 AOP 13A AOP 17A AOP 24 EOP 0 EOP 3 1st Check 2nd Check 1C04 1C 1-6 1C04 1C 4-8 1C04 1C 2-8 1C20 C 1-2 1C20 C 2-1 C01 B 3-3 C01 B 3-4 CO1 B 4-3 Booth Cleared Exam Material Magnets Replaced TR-AA-230-1007-F14, Revision 0

SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 21E LMS Rev. Date:

SEG TITLE: 2019 NRC Exam Scenario 3 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:

DURATION: 90 minutes Developed by: Andrew Zommers Instructor/Developer Date Reviewed by: Jeffrey A. Hinze Instructor (Instructional Review) Date Validated by: Andrew Zommers SME (Technical Review) Date Approved by: Andrew Fahrenkrug Training Supervision Date Approved by: Joe Krear Training Program Owner (Line) Date TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 2 of 33 Facility: _Point Beach_____ Scenario No.: __3__________ Op-Test No.: _2019_____

Examiners: ___________________________ Operators: _____________________________

Initial Conditions: _ Reactor power is 60%. G03, EDG is out of service due to maintenance _

with G04, EDG aligned. 1P-2B, Charging pump is out of service for maintenance. 1LT-426, PZR _

Level transmitter (Red) removed from service. Only 1P-30A, Circ Water pump is running due to _

previous fish intrusion which has been cleaned up, waiting to restart 1P-30B CW pump _

Turnover:_P-32B Service Water pump has a small oil leak. After turnover Maintenance will be _

working P-32B, so start P-32F, and secure P-32B per 0-SOP-SW-107 Service Water Pump _

Operation. After Service Water Pumps are shifted, continue to 100% power___________________

Critical Tasks:_CT-52, Insert Negative Reactivity into the Core _____________________________

_CT-6, Establish Flow From At Least One SI Pump_________ _____________________________

Event Malf. No. Event Event No. Type* Description N-BOP N-SRO P-32B, SW pump oil leak, shift SW to P-32F 1 LOA1SWS003 Repeat 2015 TS-SRO R-RO 2 N-BOP UP Power N-SRO C-RO C-SRO Dropped Rod 3 MAL1CRF002-K9 NEW TS-SRO I-RO 1LT-112 VCT level transmitter fails HIGH 4 XMT1CVC019A I-SRO NEW MOT1CAS001 C-BOP K-2A, IA Compressor trips, K-2B, IA Compressor fail to auto start 5 BKR1CAS004 C-SRO NEW LOA1ANN004 MAL1CRF002-F8 M-All Multiple Dropped Rods caused by seismic event requiring trip, 6 MAL1CRF002-I11 MAL1RCS002A Small break LOCA occurs on the trip MAL1PPL001A C-RO Reactor Fails to Trip, requiring transition 7 MAL1PPL001B Repeat 2017 1P-15A, SI pump trips upon starting and 1P-15B, SI pump fails to 8 MOT1SIS001 BKR1SIS002 C-BOP auto start Repeat 2017

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 3 of 33 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given specific plant conditions, the students will be able to respond to an oil Objective: leak on P-32B SW Pump, normal up power from 60%, dropped control rod, LT-112 VCT level transmitter failure, K2A IA Compressor trip, more dropped rods with LOCA requiring reactor trip (which fails) along with 1P-15A SI pump tripping and 1P-15B failing to auto start. The students will respond in accordance with plant procedures and 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-SW-007 Service Water Pump Operation

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

3. AOP 6A Unit 1, Dropped Rod

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

5. AOP-5B, Loss of Instrument Air

6. AOP-24, Response to Instrument Malfunctions

7. EOP-0 Unit 1, Reactor Trip Or Safety Injection

8. EOP-1 Unit 1, Loss of Reactor or Secondary Coolant

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

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

11. Technical Specifications Manual Protected None Content:

Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021.

Operating None Experience:

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 4 of 33 Risk Significant Initiating Event with Core Damage Frequency:

Operator Actions: Small LOCA (2.42E-06 CDF) (2.00E-09 LERF)

Failure to Initiate Rapid Boration with Charging After ATWS with failure to Insert Rods (2.18E-03)

Failure to Depressurize RCS After a Small LOCA and Failure of HH SI (2.84E-02)

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

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Developed for the 2019 ILT NRC 0

Exam TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 5 of 33 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Given specific plant conditions, the students will be able to respond to an oil leak on P-32B SW Pump, normal up power from 60%, dropped control rod, LT-112 VCT level transmitter failure, K2A IA Compressor trip, more dropped rods with LOCA requiring reactor trip (which fails) along with 1P-15A SI pump tripping and 1P-15B failing to auto start. The students will respond in accordance with plant procedures and properly utilize Technical Specifications.

Initial plant conditions are 60% power; G03 EDG is OOS with G04 EDG aligned, 1P-2B Charging Pump OOS, 1LT-426 Pressurizer Level transmitter removed from service. 1P-30B Circulating Water Pump was secured due to a previous fish intrusion which has been resolved, waiting to restart 1P-30B. A plant up power from 60% at 15%/hr to 100% is planned per OP-1C Startup to Power Operation.

Terminate the scenario when crew has transitioned to EOP-1 Loss of Reactor or Secondary Coolant and taken significant actions or per Lead Evaluator.

SEQUENCE OF EVENTS Event # Description

1. P-32B SW Pump Oil Leak, shift SW pumps

Crew will shift SW pumps and isolate P-32B per 0-SOP-SW-007, Service Water Pump Operation

SRO will address Technical Specifications

2. Normal Up Power from 60%

Crew will raise power at 15%/hr per OP-1C, Startup to Power Operation

Crew will adjust RCS boron and turbine load per reactivity plan

3. Dropped Rod

Crew will recognize dropped rod and take rod control to manual

Crew will enter AOP-6A, Dropped Rod

SRO will address Technical Specifications

4. 1LT-112 VCT Level transmitter fails high

Crew will recognize VCT level failure and take action to stabilize the unit

Crew will enter AOP-1D, CVCS Malfunction

Crew will enter AOP-24, Response to Instrument Failure TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 6 of 33

5. K2A Instrument Air Compressor trip

Crew diagnoses tripped compressor

Crew enters AOP-5B Loss of Instrument Air

Crew will start idle IA Compressor

6. Multiple Dropped Rods due to seismic event

Crew recognizes plant trip criteria and attempts unit 1 reactor trip

Crew enters EOP-0 Reactor Trip or Safety Injection

7. Reactor Fails to Trip

Crew recognizes reactor trip failure

Crew enters CSP-S.1 from EOP-0

Crew trips reactor

8. 1P-15A SI Pump trips after start and 1P-15B fails to auto start

Crew recognizes failures associated with SI Pumps

Crew manually starts 1P-15B SI Pump per EOP network Terminate the scenario when crew has transitioned to EOP-1 Loss of Reactor or Secondary Coolant and taken significant actions or per Lead Evaluator.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 7 of 33 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.

Check Action

1. Reset to IC-53

2. Perform Simulator Setup Checklist

3. Open schedule Z:\2019\ILT\2019 NRC Scenario 3.sch

4. Open SBT INSIGHT files for the NRC. Z:\NRC SBT\SBT Master points

5. Open the Alarm List program

6. Take schedule(s) to run

7. Verify required event file(s) open if required

8. Take sim to run

9. Place turnover sheets on CO1 desk

10. Place reactivity sheets on CO1 desk

11. Guard the following:

G01, G02, G04 EDGs

1P-2A and 1P-2C Charging Pumps Place the following OOS:

G03 EDG

1P 2B Charging Pump

1LT-426 Pressurizer Level

1P-30B Circ Water Pump Place red dots on the G03 alarm and PZR Level:

C02 E 2-1

C02 E 2-2

1C04 1C 3-3 Place two orifices in service and turn on Pressurizer heaters.

12. 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 TR-AA-230-1007-F14, Revision 0

SEG PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 Page 8 of 33 BOOTH OPERATOR BRIEFING:

Review the scenario sequence, event triggers and expected field communications.

Z:\2019\ILT\2019 NRC Scenario 3.sch On At Time Action Description Event 00:00:01 Event: Z:\2019\ILT\2019 NRC Scenario 3.evt P-32B SW Pump 1 Insert remote LOA1SWS002 to 0 in 50 SW-11 P-32B SW Pump Discharge Valve Dropped Rod 3 Insert Malfunction MAL1CRF002-K9 Rod Drop K9 1LT-112 VCT level failed high 5 Insert Malfunction XMT1CVC019A to 100.000 in 10 1LT-112 VCT level fails high K2A IA Comp fails 7 Insert Malfunction MOT1CAS001 to Winding_Ground K2A IA Comp winding ground 00:00:10 Insert malfunction BKR1CAS004 to Fail_To_Auto_Cl K2B IA Comp fails to auto start Seismic event and dropped rods and SBLOCA 9 Insert remote LOA1ANN004 to SEIS_EVT SEI-6210 Switchgear Seismic Detector 9 Insert Malfunction MAL1CRF002-F8 Rod Drop F8 9 Insert Malfunction MAL1CRF002-I11 after 15 Rod Drop KI11 12 Insert malfunction MAL1RCS002A to 1.50000 RCS Leak Loop A Hot Leg Reactor Fails to Trip 00:00:02 Insert Malfunction MAL1PPL001A to Fails_To_Open Reactor Trip Breaker 52/RTA Failure 00:00:02 Insert Malfunction MAL1PPL001B to Fails_To_Open Reactor Trip Breaker 52/RTB Failure SI Pump failures 00:00:04 Insert malfunction MOT1SIS001 to Winding_Ground 1P-15A SI Pump Motor Ground

SEG PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 Page 9 of 33 On At Time Action Description Event 00:00:04 Insert malfunction BKR1SIS002 to Fail_To_Auto_Close 1P-15B SI Pump Breaker 00:00:01 Insert Malfunction BKR1CVC006 fail cntr fuse 1P-2B Charging Pump 00:00:01 Insert Malfunction XMT1RCS007A to 51.00000 1LT_426 Pressurizer Level Event File:

Trigger 12 Unit 1 Reactor Trip (JCRFTR)

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 10 of 33 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Event # 1 P-32B SW Pump Oil Leak, shift SW pumps ACTION Booth: Insert TRIGGER 1 per Lead Evaluator CO3/C01 STUDENT

Shift SW Pumps per 0-SOP-SW-007, Service Water Pump Operation

RESPONSE

OS1

Acknowledges reports and directs any required actions

Assess Technical Specifications:

Service Water LCO 3.7.8 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. One SW pump A.1 Restore SW 7 days inoperable. pump to AND AND OPERABLE 14 days from discovery of status.

Both units in failure to meet LCO MODES 1, 2, 3 or 4.

Service Water TRM 3.7.7 NOT MET CONDITION REQUIRED COMPLETION TIME ACTION D. One SW pump D.1 Declare LCO Within the Completion Time inoperable. 3.7.8, Required of LCO 3.7.8, Required AND Action A.1 not Action A.1.

met.

Requirements of TRM Table 3.7.7-2 not met.

WHEN asked, THEN report P-32C, SW Pump ready for start and when pump ROLE PLAY started report proper startup.

WHEN asked, THEN report P-32B, SW Pump coastdown was not right, oil dropped out of the sightglass and there was abnormal bearing noises.

NOTES Continuation Criteria:

After SW Pumps shifted and Technical Specifications addressed, or at the discretion of the Lead Examiner, continue with the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 11 of 33 Event # 2 Normal Up Power from 60%

ACTION Booth: No action needed to start this event.

CO1/C03 STUDENT

Continue in OP 1C, Startup to Power Operation

RESPONSE

OS1

Provides direction and oversight of reactivity evolutions Crew 5.36.2 WHEN Reactor Engineering activities are complete, THEN RESUME power escalation, observing any other required Reactor Engineering hold points.

5.36.3 On 1C03, ENSURE 1DTIC-2525, T-23 HDT Differential Temperature Indicator Ctlr, is selected to AUTO 5.36.4 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 in Step 5.34.1.a.

5.37 Continuous Action During Power Increase 5.37.1 MAINTAIN controls in AUTO as practicable 5.37.2 MAINTAIN Control Banks within the insertion, sequence, and overlap limits specified in the COLR. LCO 3.1.6 5.37.3 MAINTAIN Tavg within 1.5°F of Tref 5.37.4 ADJUST Power Range NIS as directed by 1-TS-RE-001, Power Level Determination Unit 1 5.37.5 MAINTAIN VARS OUT while keeping the null meter zeroed.

5.37.6 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 5.37.7 MONITOR FWH/MSR high level alarms to check the dump valves control level 5.37.8 MONITOR Ice Melt operations as necessary.

5.37.9 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.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 12 of 33 Event # 2 Normal Up Power from 60%

Crew STUDENT RESPONSE 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 4.7 ENSURE Dilution Flow Counter FUNCTIONS properly upon start 4.8 MONITOR system for proper response (including RMW flow, RCP seal inlet temp, etc.)

None ROLE PLAY NOTES Continuation Criteria:

Per Lead Evaluator, after sufficient up power has been seen, continue to the next event (preferably with rods in auto).

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 13 of 33 Event # 3 Dropped Rod ACTION Booth: Insert TRIGGER 3 per Lead Evaluator (preferably with rods in auto)

CO1/C03 STUDENT

Identifies dropped control rod

RESPONSE

Recommends taking rod control to manual

Addresses ARBs 1C04 1A 1-5, 3-3, and 4-5 OS1

Provides direction and oversight to stop rod motion

May go to Hold on the turbine and stop dilution

Directs entry into AOP 6A, Dropped Rod Crew

Implements AOP-6A, Dropped Rod o Check Only One Rod Dropped o Check Main Turbine - ON LINE o Check Tavg - TRENDING TO PROGRAM VALUE. (NO)

Restore Tavg to program value by adjusting turbine load o Maintain RCS Tavg o Place Control Rod Bank Selector Switch in - MANUAL o Notify the following personnel:

Reactor Engineer,

I&C Supervisor,

Maintenance Supervisor o Place Lift Coil Disconnect Switch for Dropped Rod in -

DISCONNECT o Check Axial Flux Difference - IN OPERATING BAND o Perform PBF-9133, Shutdown Margin for an Operating Reactor Within 1 Hour o Check Quadrant Power Tilt - LESS THAN 2%,

Perform AOP-6H, QUADRANT POWER TILT while continuing with the procedure o Reset Dropped Rod Alarms on NIS Power Range Cabinets o Reduce Reactor Power - to less than or equal to 75% within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of Dropped Rod TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 14 of 33 Event # 3 Dropped Rod OS1 STUDENT

Assess Technical Specifications:

RESPONSE Rod Group Alignment LCO 3.1.4 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. One rod not B.2.1.1 Verify SDM 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within to be within the alignment limits limits provided in the COLR.

AND B.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to

< 75% RTP.

Quadrant Power Tilt Ratio LCO 3.2.4 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. QPTR not A.1 Reduce 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each QPTR within limits. THERMAL determination POWER < 3%

from RTP for each 1% of QPTR > 1.00.

ROLE PLAY None NOTES Continuation Criteria:

After the crew determines required load reduction or per the Lead Examiner continue to the next event.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 15 of 33 Event # 4 1LT-112 VCT Level transmitter fails high ACTION Booth: Insert TRIGGER 5 per Lead Evaluator CO1 STUDENT

Identifies failed instrument

RESPONSE

Determines VCT Divert valve is open

Recommends placing Divert Valve to - VCT CO3

Works with C01 to identify failure OS1

Enters AOP-1D Unit 1, CVCS Malfunctions Crew

Utilizes AOP 1D Unit 1, CVCS Malfunctions o Check RCS Leak - NOT IN PROGRESS o Review/Monitor Foldout Page Criteria o Determine CVCS Malfunction IF VCT Level Transmitter failed, THEN go to Step 58 1LT-112 o Check 1LT-112, VCT Level Transmitter - INDICATES NORMAL Place VCT Level Control Divert Valve - TO VCT Place Makeup Control Switch - TO STOP Manually divert or makeup to maintain VCT level between 17%

and 78% using 1LT-141 Refer to TLCO 3.3.1 Notify Duty Station Manager and I&C Duty and Call Return To Procedure And Step In Effect OS1

Addresses Technical Specifications:

OS1 determines TRM TLCO 3.3.1 is MET

IF asked, wait 2 minutes, THEN report there are no abnormal indications locally ROLE PLAY at 1LT-112.

NOTES Continuation Criteria:

After the crew completes AOP-1D actions or per the Lead Examiner continue to the next event.

Note: IA Comp trip takes approximately 5 minutes when next event goes in.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 16 of 33 Event # 5 K2A Instrument Air Compressor trip ACTION Booth: Insert TRIGGER 7 per Lead Evaluator CO3 STUDENT

Identify alarms and determines ground on 1B03 480 bus

RESPONSE

Send AOs to investigate ground alarm C02 D 3-2

Diagnose eventual IA Comp trip CO1

Monitor the unit and reference ARB C01 A 1-8 and 1-9 OS1

Direct actions to monitor equipment and when required start standby IA Comp

Enters AOP-5B, Loss of Instrument Air Crew

Implements AOP-5B, Loss of Instrument Air o Monitor foldout page criteria o Check Power Available To At Least One Air Compressor o Check Instrument Air Compressors - AT LEAST ONE RUNNING Start an instrument air compressor Secure malfunctioning instrument air compressor, if necessary IF air receiver is depressurized, THEN restart per ATTACHMENT B o Check Service Air Compressors - AT LEAST ONE RUNNING o Check Instrument Air and Service Air Compressors - ANY RUNNING o Check Instrument Air Pressure - ADEQUATE o Check Instrument Air Pressure - GREATER THAN 80 psig o Check Instrument Air Pressure - GREATER THAN 85 psig o Check Instrument Air Pressure - GREATER THAN 90 psig o Locally Check Instrument Air System - NORMAL o Return To Procedure And Step In Effect

WHEN asked, wait 2 minutes, THEN report all ground light indications normal ROLE PLAY except 1B03 480 Safeguards Bus has 1 ground light out with the other 2 bright.

WHEN asked, wait 2 minutes, THEN report back as requested:

o South IA Header Flow - 200 SCFM o North IA Header Flow - 140 SCFM o Compressor cycle times are normal TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 17 of 33 Event # 5 K2A Instrument Air Compressor trip NOTES Continuation Criteria:

After actions have been taken to address the IA Comp trip or per Lead Evaluator, booth insert TRIGGER 9.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 18 of 33 Event # 6 Multiple Dropped Rods due to seismic event ACTION Booth: Insert TRIGGER 9 per Lead Evaluator CO1/C03 STUDENT

Recognize seismic event and multiple dropped rods

RESPONSE

Determine plant trip required OS1

Directs or confirms plant trip required

Enters EOP 0, Reactor Trip or Safety Injection Crew

Implement EOP 0, Reactor Trip or Safety Injection o Verify Reactor Trip Notify STA to MONITOR CSP Status Transition to CSP-S.1UNIT 1, Response to Nuclear Power Generation/ATWS

Implement CSP-S.1 UNIT 1, Response to Nuclear Power Generation/ATWS o Verify Reactor Trip Ensure positive rod insertion in manual or automatic o Verify Turbine Trip - C01 verify trip turbine or direct C03 to perform o Monitor foldout page criteria o Verify AFW Pumps - RUNNING o Initiate Emergency Boration of RCS Check a least one charging pump - RUNNING Align emergency boration flow path o Start 1P-4A or 1P-4B boric acid pump o Open 1CV-350 emergency borate valve Check PZR pressure - LESS THAN 2335 psig o Check If The Following Trips Have Occurred:

Reactor - TRIPPED o Dispatch operator to locally open reactor trip and bypass breakers in rod control room Turbine - TRIPPED CT-52, Insert negative reactivity into core o Check if Reactor is Subcritical o Check S/G Levels o Verify All Dilution Paths - ISOLATED o Check for Reactivity Insertion From Uncontrolled RCS Cooldown Go to Step 13 o Check Core Exit Thermocouple Temperature - LESS THAN 1200°F TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 19 of 33 Event # 6 Multiple Dropped Rods due to seismic event o Verify Reactor Subcritical STUDENT o Ensure Emergency Boration is Proper for Current Plant Conditions RESPONSE o Perform the following:

Notify STA to IMPLEMENT CSP Status Trees Return to Procedure and Step in Effect Transition to EOP 0, Reactor Trip or Safety Injection

Implement EOP 0, Reactor Trip or Safety Injection o Verify Turbine Trip o Verify Power to AC Safeguards Busses o Check if SI Is Actuated Manually depress SI and CI buttons due to failure of 1P-15B to start o Monitor Foldout Page Criteria:

o Perform Attachment A of EOP 0 o Verify AFW Pumps - RUNNING o Verify RCP Seal Cooling o Check RCS Temperatures o Check PZR PORVs And Spray Valves o Check if RCPs should be stopped RCPs - ANY RUNNING SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW RCS subcooling based on core exit thermocouples - LESS THAN [40°F] 31°F Stop both RCPs o Check if S/Gs are NOT Faulted o Check if S/Gs Tubes are NOT ruptured:

o Check if RCS is Intact Notify STA to MONITOR CSP Status Trees Go to EOP-1, Loss of Reactor or Secondary Coolant

Implement EOP-1, Loss of Reactor or Secondary Coolant o Check if RCPs should be stopped o Check if S/Gs are NOT Faulted o Check Intact S/G Level S/G Level - GREATER THAN [51%] 32%

Control feed flow to maintain S/G level between [51%] 32% and 63%

o Check Secondary Radiation o Check PZR PORVs And Spray Valves o Reset SI o Reset Isolation And Lockout Signals:

Containment Isolation 1B-03 and 1B-04 NON-Safeguards equipment lockouts o Establish Instrument Air to Containment TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 20 of 33 Event # 6 Multiple Dropped Rods due to seismic event o Check Power Supply to Charging Pumps STUDENT o Check if Charging Flow has Been Established RESPONSE o Check if ECCS Flow Should be Terminated - NO o Check if Containment Spray Should be Stopped o Check if RHR Pumps Should be Stopped Check RCS pressure:

o Pressure - GREATER TAHN 325 psig o Pressure - STABLE OR RISING RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST Stop both RHR pumps and place in auto:

o 1P-10A o 1P-10B TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 21 of 33 Event # 6 Multiple Dropped Rods due to seismic event CO3 - EOP 0 Attachment A STUDENT

Verify Feedwater Isolation

RESPONSE

Verify Containment Isolation

Verify ECCS Pumps RUNNING o SI Pumps - BOTH RUNNING o Start 1P-15B if not previously done

Verify Service Water Pumps RUNNING (P-32B OOS)

Verify Containment Accident Cooling Units RUNNING

Verify Component Cooling Pumps - ONLY ONE RUNNING

Check if Main Steam Lines Can Remain Open:

o Any MSIV Valve - OPEN o Containment pressure - LESS THAN OR EQUAL TO 15 psig o High-high steam flow bistable lights - NOT LIT o High steam flow bistable lights - NOT LIT

Verify Containment Spray Not Required

Verify ECCS Flow

Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT

Verify Proper ECCS Valve Alignment

Check Containment Spray NOT ACTUATED

Stop any boration via the blender in progress

Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING

Perform the Following:

o Notify STA to IMPLEMENT Status Trees and SM of any equipment malfunctions not previously noted

Verify Service Water Alignment

Check Miscellaneous Valves - SHUT

Check Control Room Ventilation

Check Cable Spreading Room Ventilation

Check Computer Room Ventilation

Check AFW Recirc Fans - ONE RUNNING

Check Circulating Water Pump House Temperature Less Than 105°F

Check G03/G04 Switchgear Room Temperature Less Than 95°F

Periodically check status of spent fuel cooling o

WHEN directed to locally check shut radwaste service water valves, TV-LW61 ROLE PLAY

& 62, wait one minute and THEN report both valves are closed.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

IF directed to investigate 1P-15A SI Pump/breaker, wait 3 minutes THEN report back pump looks fine but breaker is tripped on overcurrent.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 22 of 33 Event # 6 Multiple Dropped Rods due to seismic event NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 23 of 33 Event # 7 Reactor Fails to Trip ACTION Booth: No action required, pre-loads only STUDENT Crew RESPONSE

While implementing EOP 0 Reactor Trip or Safety Injection Step 1 Verify Reactor Trip, crew should take RNO actions and transition to CSP-S.1 Unit 1, Response to Nuclear Power Generation/ATWS

Direct an AO to trip the reactor trip breakers locally after immediate actions or per Step 8 of CSP-S.1.

IF an ATWS is announced, THEN immediately acknowledge the announcement ROLE PLAY and report you are going to the Unit 1 Rod Drive Room.

WHEN asked or ATWS is announced, wait until emergency boration is taking place by the BOP, THEN report back standing by at the Unit 1 Reactor Trip Breakers. (Booth change malfunction to open the reactor trip breakers)

CT-52, Insert negative reactivity into core NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 24 of 33 Event # 8 1P-15A SI Pump trips after start and 1P-15B fails to auto start ACTION Booth: No action required, pre-loads only STUDENT C01/C03 RESPONSE

Recognize 1P-15A, SI Pump trip and failure of 1P-15B, SI Pump to start

Recommend starting 1P-15B, SI Pump after immediate actions or per EOP-0 Attachment A

Per EOP 0 Attachment A Step A3, crew may start 1P-15B, SI Pump

Crew may attempt 1 restart of 1P-15A, SI Pump OS1

Provide direction and oversight to manually start 1P-15B, SI Pump CT-6, Establish flow from at least one pump

IF directed to investigate 1P-15A SI Pump/breaker, wait 3 minutes THEN report ROLE PLAY back pump looks fine but breaker is tripped on overcurrent.

NOTES TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 25 of 33 Scenario Termination Terminate the scenario when crew has transitioned to EOP-1 Loss of Reactor or Secondary Coolant and taken significant actions or per Lead Evaluator.

Freeze the simulator NOTES

Determine if the NRC has any follow up questions

Save the INSIGHT files AND Alarm List PRIOR TO RESET

Close all schedule and event files TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 26 of 33 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

P-32B SW Pump oil leak

Dropped Rod

1LT-112 VCT Level transmitter failure

K2A IA Compressor trip

Seismic event with multiple dropped rods After EOP Entry:

Reactor fails to trip

1P-15A SI Pump Trip and 1P-15B SI Pump fail to start Abnormal Events:

P-32B SW Pump oil leak

Dropped Rod

1LT-112 VCT Level transmitter failure

K2A IA Compressor trip

Seismic event with multiple dropped rods Major Transients:

ATWS

Small Break LOCA Critical Tasks:

1. CT-52 Insert negative reactivity into the core

2. CT-6 Establish flow from at least one pump Major Procedures:

AOP-6A AOP-24 AOP-1DAOP-5A EOP-0CSP-S.1EOP-1 TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 27 of 33 CT-52 Insert Negative Reactivity into the Core 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 Basis:

SAFETY SIGNIFICANCE - Failure to insert negative reactivity, under the postulated plant conditions, results in an unnecessary situation in which the reactor remains critical or returns to a critical condition.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 28 of 33 CT-6 Establish Flow From at Least one SI Pump 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 Basis:

SAFETY SIGNIFICANCE - Failure to manually start at least one SI pump under the postulated plant conditions constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency core cooling systems (ECCS) capacity.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 29 of 33 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:

UNIT 1 Time in core life (MWD/MTU): 9500 Reactor power (%): 60%

Boron concentration (ppm): 1049 ppm Rod height, CBD @: 157 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

TSAC Description Required Action & Completion Time U1 3.3.1.A/K RPS one channel inoperable Place channel in trip - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months EQUIPMENT OUT OF SERVICE:

G03 Emergency Diesel Generator maintenance.

1LT-426 Pressurizer Level Transmitter.

1P-2B Charging Pump for seal leakage maintenance.

PLANNED EVOLUTIONS:

Shift Service Water Pumps for FIN per 0-SOP-SW-007, Start P-32C and secure P-32B.

Continue to raise reactor power to 100% at 15%/hr per OP 1C Startup to Power Operation step 5.36.4. Pressurizer heaters are on and a 2nd letdown orifice is in service for the downpower.

TURNOVER INFORMATION:

G04 Emergency Diesel Generator is aligned to both 1A06 and 2A06 4160 Safeguards Busses.

1P-30B Circulating Water Pump was secured for a previous fish intrusion and is ready to start.

On line risk is GREEN.

Today is Tuesday, day shift.

TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 30 of 33 Communications/responses P-32B SW Pump Oil Leak, shift SW pumps

WHEN asked, THEN report SW Pump ready for start and when pumps shifted report proper coastdown of secured pump.

Normal Up Power from 60%

None Dropped Rod None 1LT-112 VCT Level transmitter fails high

IF asked, wait 2 minutes, THEN report there are no abnormal indications locally at 1LT-112.

K2A Instrument Air Compressor trip

WHEN asked, wait 2 minutes, THEN report all ground light indications normal except 1B03 480 Safeguards Bus has 1 ground light out with the other 2 bright.

WHEN asked, wait 2 minutes, THEN report back as requested:

o South IA Header Flow - 200 SCFM o North IA Header Flow - 140 SCFM o Compressor cycle times are normal TR-AA-230-1007-F14, Revision 0

PBN LOI NRC 21E, 2019 NRC Exam Scenario 3, Rev 0 SEG Page 31 of 33 Multiple Dropped Rods due to seismic event

WHEN directed to locally check shut radwaste service water valves, TV-LW61 & 62, wait one minute and THEN report both valves are closed.

WHEN directed to locally check CW pump house temperature less than 105°F, wait two minutes and THEN report temperature is 72°F and stable.

WHEN directed to check G03/G04 switchgear room temperature less than 95°F, wait two minutes and THEN report temperature is 72°F and stable.

IF directed to investigate 1P-15A SI Pump/breaker, wait 3 minutes THEN report back pump looks fine but breaker is tripped on overcurrent.

Reactor Fails to Trip

WHEN asked or ATWS is announced, wait until emergency boration is taking place by the BOP, THEN report back standing by at the Unit 1 Reactor Trip Breakers. (Booth change malfunction to open the reactor trip breakers)

IF an ATWS is announced, THEN immediately acknowledge the announcement and report you are going to the Unit 1 Rod Drive Room. (Booth change malfunction to open the reactor trip breakers) 1P-15A SI Pump trips after start and 1P-15B fails to auto start

IF directed to investigate 1P-15A SI Pump/breaker, wait 3 minutes THEN report back pump looks fine but breaker is tripped on overcurrent.

TR-AA-230-1007-F14, Revision 0

Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check OP 5B Att C AOP 1D AOP 5B AOP 6A AOP 24 EOP 0 EOP 0 Att A EOP 1 CSP-S.1 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check 1C04 1A 1-5 1C04 1A 3-3 1C04 1A 4-5 1C04 1A 4-10 C02 D 3-2 C01 D 2-2 C01 A 1-8 C01 A 1-9 TR-AA-230-1007-F14, Revision 0

Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check OP 5B Att C AOP 1D AOP 5B AOP 6A AOP 24 EOP 0 EOP 0 Att A EOP 1 CSP-S.1 1st Check 2nd Check 1C04 1A 1-5 1C04 1A 3-3 1C04 1A 4-5 1C04 1A 4-10 C02 D 3-2 C01 D 2-2 C01 A 1-8 C01 A 1-9 Booth Cleared Exam Material Magnets Replaced TR-AA-230-1007-F14, Revision 0

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