ML15079A329

2015 Point Beach Nuclear Plant Initial License Examination Administered Dynamic Simulator Scenarios

ML15079A329
Person / Time
Site:	Point Beach
Issue date:	03/06/2015
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:	Florida Power & Light Energy Point Beach
References
Download: ML15079A329 (82)

Text

Page 1 of 29 SIMULATOR EXERCISE GUIDE SEG SITE:

Point Beach Revision #: 0 LMS ID:

LMS Rev. Date:

SEG TITLE:

2015 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:

Jeff Baugniet SME (Technical Review)

Date Approved by:

Randy Amundson Training Supervision Date Approved by:

Tom Larson Training Program Owner (Line)

Date

2015 NRC Exam Scenario 1, Rev.0 SEG Page 2 of 29

Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)

Page 3 of 29 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. 1CV-135 Letdown Backpressure Controller failure

2. 1PT-468 'A' S/G Pressure transmitter fails High

3. Steamline break inside containment After EOP Entry:

1. 1P-28B SGFP fails to auto trip, 'B' FRV sticks 10% open, 1CS-3125 B MFIV fails open

2. First set of Reactor Trip pushbuttons do not work

3. 1W-1A1 Accident Fan fails to auto start, and 1P-14B Spray Pump fails to start Abnormal Events:

1. 1CV-135 Letdown Backpressure Controller failure

2. 1PT-468 'A' S/G Pressure transmitter fails High Major Transients:

1. 'B' S/G Steamline Break inside containment Critical Tasks:

1. CT-1 Manually trip the reactor from the control room, using the second set of push buttons prior to the containment pressure reaching 15 psig.

2. CT-17 Isolate faulted S/G before transition out of EOP-2.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 4 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 1: Shift Service Water Pumps This evolution should be pre-briefed prior to starting scenario.

Cues: (will be received during the shift)

CO0B 3.5 Unit 1 Safeguards Equipment Locked Off Communications:

When requested, local checks prior to starting P-32F Service Water Pump (oil level, personnel clear) are good.

When requested, post start indications for P-32F. P-32F looks and sounds normal on startup and post startup When requested, post stop indication for P-32B. P-32B check valve closed and the oil sightglass is empty and there was bearing noise on coast down.

If requested, shut SW-11 P-32B Discharge Isolation (Insert Trigger 24), wait 2 minutes and report back SW-11 is shut.

SM will contact Maintenance regarding P-32B, SW Pump and complete other required notifications After Tech Spec status is identified, SM will direct SRO to continue with placing the Unit 1 on-line End of evolution: Proceed to next event after Service Water Pumps shifted or at Lead Examiner discretion.

BOP SRO Per 0-SOP-SW-107 Service Water Pump Operations start P-32F and secure P-32B.

Shut discharge valve for P-32B, SW-11. - Local Operator action.

Have AO verify local indications prior to service water pump start and after securing service water pump.

May recommend going to PULLOUT on P-32B control switch.

Declare TRMAC 3.7.7.D One SW Pump Inoperable which directs declaring TSAC 3.7.8.A1 not met.

Declare P-32B Service Water Pump INOPERABLE and declare LCO 3.7.8 Service Water System NOT MET and enter TSAC 3.7.8.A Restore SW Pump to Operable within 7 days.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 5 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: Synchronize to the Grid and Raise Power Communications:

OS will request notifications be given to ATC about placing unit online and raising power. SM will acknowledge request and state that notification will be completed.

SM state Relief Crew SRO overseeing Steps 5.15.14 thru 5.16.3, 5.17 and 5.19.

Requests for the AO to take logs per Attachment D of OP-1C should be considered completed SAT when asked for step 5.14.5.b and 5.14.10. After one minute, report all readings are 0.7.

When requested, reset Unit 1 Generator Voltage Regulator cabinet 1E02 after 1 minute (OP-1C step 5.14.5.d) Trigger 18.

CREW Briefing on power ascension will be performed in classroom prior to beginning of the scenario.

Start procedure at step 5.14.3. Step 5.13 will not be signed off until reaching 15%

power.

Synchronize the Generator to the grid.

Withdraws rods and/or Dilute in addition to adjusting steam demand as needed to establish power increase.

Major Steps for Synchronizing to the Grid and Raising Power 5.14 Preparations For Bringing Unit Online 5.14.1 ENSURE one Isolated Phase Bus Duct Cooler is operating 5.14.2 ENSURE 1TG-01A-BGD, 1TG-01 TG Phase A Output Terminal Blast Gate Damper, and 1TG-01C-BGD, 1TG-01 TG Phase C Output Terminal Blast Gate Damper, are CLOSED.

5.14.3 INITIATE notification in accordance with NP 2.1.5, Electrical Communications, Switchyard Access And Work Planning, that the unit is coming on line.

5.14.4 ENSURE Generator Voltage Regulator Control Switch is in MANUAL position.

5.14.5 APPLY Generator Excitation as follows:

a. ENSURE Turbine speed is between 1750 and 1800 RPM.

b. COMPLETE Section 1.0 of Attachment D, Main Generator Fiber Optic Vibration Monitoring System Data.

c. CLOSE Unit 1 Generator Exciter Field Breaker.

d. RESET Unit 1 Voltage Regulator Panel Alarms at 1E02.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 6 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: Synchronize to the Grid and Raise Power Communications:

When requested, Maintenance or TH AO notifies the Control Room that AC Error Detector indicates 0.0 for step 5.14.9 When requested, TH AO completes Step 5.15.14.

Report back completed in 5 minutes. (not modeled)

Event 2: Synchronize to the Grid and Raise Power CREW 5.14.6 Slowly ADJUST Generator Voltage Regulator DC Adjuster to obtain a Generator Voltmeter indication of approximately 19 KV at 1800 rpm.

5.14.7 CHECK all three phases approximately 19 KV, using Unit 1 Generator Voltmeter switch:

• A

• B

• C 5.14.8 PERFORM the following for Automatic Voltage Regulation:

a. POSITION Unit 1 Generator Voltage Regulator to TEST.

b. CHECK yellow lamp is LIT.

c. ENSURE Generator Voltage Regulator Balance Meter is at approximately zero using the Generator Voltage Regulator AC Adjuster.

d. POSITION Generator Voltage Regulator to AUTO.

e. CHECK red lamp is LIT.

5.14.9 REQUEST Maintenance perform UNIT 1 Voltage Regulator Firing Card adjustments to nullify age related bias shifts such that the AC Error Detector output is 0.0 (- 0.3 to + 0.3 v) 5.14.10 COMPLETE Section 2.0 of Attachment D, Main Generator Fiber Optic Vibration Monitoring System Data.

5.14.11 POSITION Unit 1 19 KV Generator Output Breaker 1G52-TG-01 Synchroscope switch to ON.

5.14.12 ADJUST Incoming Voltmeter reading to match Running Voltmeter reading, using the Generator Voltage Regulator AC Adjuster.

5.14.13 CHECK Unit 1 Generator Exciter Field Ammeter at less than 23 amps.

5.14.14 ADJUST Turbine speed (using Reference Control raise and lower pushbuttons) as necessary to rotate the synchroscope 2 to 5 rpm in the FAST direction.

5.14.15 ENSURE 1G52-TG-01-CS, Unit 1 19 KV Generator Output Breaker Control Switch, is removed from PULLOUT.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 7 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Communications:

SM completes NP 2.1.5 communications per Steps 5.15.6 and 5.15.11.

SM informs OS, Step 5.15.10, eight minute hold time has been completed.

CREW 5.15 Closing Generator Output Breaker 5.15.1 WHEN the synchroscope is just before 12:00 o'clock, AND within the Green Band, THEN POSITION 1G52-TG-01-CS, Unit 1 19 KV Generator Output Breaker Control Switch, to CLOSE. RECORD Time: _____________

5.15.2 IF generator load is NOT 20 to 30 MWe, THEN adjust turbine load to obtain 20 to 30 MWe.

5.15.3 ENSURE Unit 1 Generator operating within limits of Figure 1 and Figure 2 5.15.4 CHECK LOAD CONTROL status lamp is LIT.

5.15.5 POSITION Synchroscope switch for 1G52-TG-01, Unit 1 19 KV Generator Output Breaker, to OFF.

5.15.6 INITIATE notification Unit 1 is on line and of intent to raise power in accordance with NP 2.1.5, Electrical Communications, Switchyard Access and Work Planning.

5.15.8 PRESS 1st STG IN pushbutton.

5.15.9 CHECK the following:

• 1st STG IN lamp is LIT. (Ref. 6.4.19)

• 1st STG OUT lamp is NOT LIT. (Ref. 6.4.19) 5.15.10 IF required, THEN HOLD Turbine load in accordance with CL 1C, Main Turbine Loading And Unloading Limitations.

5.15.11 PERFORM the following continuous action steps in accordance with NP 2.1.5, Electrical Communications, Switchyard Access and Work Planning:

• INITIATE notification of all planned and unplanned power level changes.

• INITIATE notification of changes in main generator voltage regulator position (e.g., switching from automatic to manual, or manual to automatic).

2015 NRC Exam Scenario 1, Rev.0 SEG Page 8 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: Synchronize to the Grid and Raise Power Communications:

When requested, TH AO will align cylinder heating steam per Step 5.16. Report back completed in 5 minutes.

(modeled always in and in auto)

When requested, TH AO perform Step 5.17 initiating MSR purge (Trigger 22). Insert trigger 22 and call back in 5 minutes step is complete 4th License will take the temperatures required for Step 5.20.

If asked, SM to direct performance of 5.16.4, Place Condenser Steam Dumps in AUTO End of evolution: Proceed to next event after noticeable power increase or at Lead Examiner discretion.

CREW 5.15.12 PRESS Reference control (RAISE) pushbutton to select desired value.

5.15.13 PRESS the "GO" pushbutton to initiate a controlled load increase toward 15% power. (Observe fuel conditioning guidelines of Step 3.3).

2015 NRC Exam Scenario 1, Rev.0 SEG Page 9 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 3: 1HC-135 Letdown Line Backpressure Controller failure Plant Response:

Controller failure causes letdown flow to lower raising letdown pressure causing the letdown line relief valve to lift.

Cues:

1C04 1C 1-6 Letdown Pressure High 1C04 1C 4-6 Low Pressure Letdown Relief Valve Temp High (This may not be received based on response time of the crew)

ARP-1-PPCS-004 Letdown Line Flow Insert TRIGGER 1 at the discretion of the Lead Examiner.

Communications:

If requested to look at 1CV-135 locally report everything look normal and report valve position is about 60% open (or equivalent control board position).

Communications:

SM Acknowledge request for notifications.

NOTE: AOP-24 may be utilized in addition to or prior to AOP-1D. (see next page for AOP-24 actions)

RO/SRO BOP/RO SRO RO/SRO RO SRO Crew RO identifies CV-135 pressure controller malfunction and takes controller to manual to control back pressure.

Addresses ARBs Crew may go to hold on ramp.

Enter AOP 1D to address the malfunction and verify actions taken.

1.

(CA STEP) Check RCS leak not in progress.

Reviews foldout page criteria and Notes

2.

Determine CVCS malfunction - CV-135 pressure control which directs transition to step 36.

36. Check LP Letdown Line Pressure Control Valve - Failed

37. Establish manual control of CV-135 - 250#

a. Place LP Letdown Line Pressure Controller - IN MANUAL

b. Adjust LP Letdown Line Pressure Controller - MAINTAIN LETDOWN PRESSURE AT 250 PSIG

38. Notify Duty Station Manager and I&C Duty and Call

39. Return to Procedure and Step in Effect The crew will have to keep CV-135 in manual control and discuss how this will be done.

(may review step 37 RNO)

2015 NRC Exam Scenario 1, Rev.0 SEG Page 10 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 3: 1HC-135 Letdown Line Backpressure Controller failure (cont'd)

Communications:

If asked, SM will direct maintaining normal Letdown.

End of evolution: Proceed to next event at Lead Examiner discretion.

SRO RO SRO Crew may also enter AOP-24 Response to Instrument Malfunction.

1.

Identify Failed Instrument -NO CV-135 Controller RNO: IF a controller has failed, THEN go to Step 3.

3.

Establish Manual Control as Required: - Take Manual control CV-135

4.

Return Affected Parameter(s) to Desired Value(s) - Restore Letdown Pressure to approximately 250 psig

5.

Using Attachment A, PPCS Parameters Used to Calculate Reactor Thermal Output. Verify that Failed Instrument is NOT an Input to RTO.

RNO: Reference AOP-21, PPCS MALFUNCTION while continuing with this procedure.

6.

Remove Failed Instrument Channel From Service per 0-SOP-IC-001 Routine Maintenance Procedure Removal of Safeguards or Protection Sensor From Service.

7.

Return Controls to Automatic if Desired. - Will not work

8.

Check Failure for Technical Specifications or TRM Applicability. - None applicable.

9.

Return to Procedure And Step In Effect.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 11 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH Plant Response:

1MS-2016, 1HX-1A SG HDR Atmospheric Steam Dump Control valve will open.

Cues:

1MS-2015, A SG ADV valve position indication Rising reactor power PPCS alarms Insert TRIGGER 3 at the discretion of the Lead Examiner.

Communications:

If requested, local inspection of pressure transmitter looks normal after 2 minutes.

Communications:

If SM asked, I&C was notified to troubleshoot and repair PT-468.

NOTE: Crew may initially enter either AOP-24 or AOP-2A.

BOP/SRO SRO BOP RO BOP RO Acknowledge and respond to receipt of annunciators. Realize feed control issues and S/G Atmospheric opening are due to instrument failure and place affected controllers in Manual.

The crew may go to hold on the load ramp.

Enter AOP-2A Secondary Coolant Leak

1.

(CA Step) Determine Secondary Leakage Not Hazardous to Personnel or Equipment Plant Habitability Containment Pressure less than 2 psig Safeguards bus fault Equipment operability

2.

(CA Step) Maintain Plant Within Limits Reactor power less than or equal to 100%

S/G level stable at or near 64%

SGFP suction pressure greater than 180 psig Condensate pump motor current less than 185 amps

3.

(CA Step) Maintain RCS Tavg Greater than 540°F Less than 577°F Within 7°F of program Tavg

2015 NRC Exam Scenario 1, Rev.0 SEG Page 12 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH (contd)

NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic diagrams as referenced in 0-SOP-IC-001-RED page 29.

Sheets #169, #172, #179, 0-SOP-IC-002 in its entirety, and logic sheet (#176) for 1FT-464 being OOS concurrent with 1PT-468 Communications:

If asked, SM will have OS2 prepare 0-SOP-IC-001 RED to remove 1PT-468 from service.

If requested, all steam generator safety valves are shut, after 2 minutes.

If requested, all steam generator atmospheric steam dump valves are shut, no delay is needed if asked after the steam generator safety valves.

NOTE: Intent is to NOT take the instrument out of service per 0-SOP-IC 001 RED. A package will be made up ahead of time if asked for.

NOTE: IF SRO determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary actions.

BOP SRO BOP NOTE: Steps 4 - 10 may be performed in any order.

4.

Check Containment Conditions Normal Containment relative humidity Containment sump A level Containment pressure Containment elevation 66 ft. air temperature

5.

Check No Secondary Leakage to Atmosphere:

a.

Steam generator safety valves shut

b.

Steam Generator atmospheric steam dump valves shut RNO: 1) Manually Shut valve(s)

c.

Locally check crossover steam dumps shut

d.

No visual or audible indications of secondary leakage

6.

Check Condenser Steam Dump Valves Shut Crew enters AOP-24

1.

Identify Failed Instrument - 1PT-468

2.

Check if Failed Instrument is a Controlling Channel - Yes

3.

Establish Manual Control as Required: - Take Manual control of feed and S/G Atmospheric

4.

Return Affected Parameter(s) to Desired Value(s)

5.

Use Attachment A to determine if RTO is affected - RTO not affected Channel is listed, but is redundant so RTO is not affected.

6.

Remove failed instrument from service per 0-SOP-IC-001 - RED

7.

Return controls to automatic if desired

8.

Check Failed Instrument for Technical Specification OR TRM Applicability

2015 NRC Exam Scenario 1, Rev.0 SEG Page 13 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH (contd)

Review 0-SOP-IC-002 Technical Specification LCO-Instruments Cross Reference.

Table 3.3.1-1 item 14-2 SF/FF Mismatch Table 3.3.2-1 item 1e SI-Steam Line Pressure-Low Table 3.3.2-1 item 3c CI-Safety Injection (no action)

Table 3.3.2-1 item 4d-2 SLI-Coincident with SI Table 3.3.2-1 item 4e-2 SLI-Coincident with SI Table 3.3.2-1 item 5c FI-Safety Injection (no action)

Table 3.3.2-1 item 6c AFW-Safety Injection (no action)

Table 3.3.3-1 item 17 SG Pressure (no action)

Table 3.3.5-1 item 2 CREFS Cont. Isolation (no action) 1FT-464 Table 3.3.1-1 item 14-2 SF/FF Mismatch Table 3.3.2-1 item 4d-1 SLI-High Steam Flow Table 3.3.2-1 item 4e-1 SLI-High High Steam Flow TSAC Description, Required Actions, Completion Times:

3.3.1.A & D One channel inoperable, D.1 Place channel in Trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or Be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 3.3.2.A & D One channel inoperable, D.1 Place channel in Trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or Be in Mode 3 within 7 hrs and Mode 4 in 13 hrs

2015 NRC Exam Scenario 1, Rev.0 SEG Page 14 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH (contd)

End of evolution: Proceed to next event at Lead Examiner discretion or after the crew has stabilized plant conditions, and identified the impact on Technical Specifications.

BOP NOTE: Alarm(s) will not be received, but actions could be completed based upon ARP guidance for anticipated alarms (if at a higher power level)

Actions to swap controlling channel for A S/G pressure transmitter failure.

ARP 1C03 1E2 2-2 S/G A Feedwater Flow High ARP 1C03 1E2 3-2 S/G A Feedwater Channel Alert 3.4.1 IF any of the following transmitters is failed, THEN PERFORM Steps 3.4.1.a through 3.4.1.e:

1FT-464, Steam Flow Loop A 1FT-466, Feedwater Flow Loop A 1PT-468, Steam Generator Pressure Loop A

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

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

c. PLACE S/G A Feedwater Flow Control Transfer Switch, to 467 (WHITE).

d. PLACE S/G A Steam Flow Control Transfer Switch, to "465" (WHITE).

e. PLACE 1FIC-466A, 1HX-1A Primary Flow Indicating Controller in "AUTO",

unless directed otherwise by Shift Management.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 15 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment Plant Response:

Containment pressure will rise to above 5 psig SI setpoint and continue above MSIV isolation setpoint (15 psig).

Cues:

• High Containment Humidity (ARP 1-PPCS-007)

• High Containment Pressure (ARP 1-PPCS-018)

• C01 B 1-4 Sump A Level High

• 1C04 1B 4-3 CONT PRESSURE HIGH (BLUE - SI)

Insert TRIGGER 5 at the discretion of the Lead Examiner.

Crew SRO BOP SRO RO Crew determines leak inside containment is secondary coolant leak.

Enter AOP-2A Secondary Coolant Leak

1.

(CA Step) Determine Secondary Leakage Not Hazardous to Personnel or Equipment Plant Habitability Containment Pressure less than 2 psig Safeguards bus fault Equipment operability RNO:

a. Trip Reactor (SRO may actuate SI prior to reaching auto setpoint)

b. Enter EOP Network

2.

(CA Step) Maintain Plant Within Limits Reactor power less than or equal to 100%

S/G level stable at or near 64%

SGFP suction pressure greater than 180 psig Condensate pump motor current less than 185 amps

3.

(CA Step) Maintain RCS Tavg

2015 NRC Exam Scenario 1, Rev.0 SEG Page 16 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (contd)

And Event 6: First Set of Reactor Trip Pushbuttons will not work When the crew attempts the SECOND set of reactor trip pushbuttons, insert TRIGGER 26

• CT-1 Manually Trip the Reactor using the second set of push buttons prior to the containment pressure reaching 15 psig.

Manually actuate both sets of reactor trip pushbuttons SRO RO SRO BOP EOP-0 Reactor Trip or Safety Injection

1.

Verify Reactor Trip RNO: When first set of pushbuttons fail the second set of pushbuttons will trip the reactor.

2.

Verify Turbine Trip - Yes

3.

Verify Power to AC Safeguards Buses - Yes

4.

Check if SI is Actuated (SRO may actuate SI prior to reaching auto setpoint)

Implement Foldout Page Criteria - Faulted SG Isolation Criteria:

3. IF any SG pressure trending lower in an uncontrolled manner OR Completely depressurized, THEN the following may be performed:

a. Isolate feed flow to the faulted SG

b. Maintain total feed flow greater than or equal to 230 gpm until NR level in at least one SG is greater than [51%] 32%.

5. Adverse Containment Conditions

-IF any condition listed below occurs, THEN environmentally qualified (Ea) equipment and adverse containment setpoint values in brackets, [I, shall be used:

o Containment pressure - GREATER THAN 5 PSIG

2015 NRC Exam Scenario 1, Rev.0 SEG Page 17 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 7: 'B' Train SGFP, MFRV and MFIV failures BOP After immediate actions the Crew may notice the B MFRV is still open. If the Crew does not notice EOP 0 will try to isolate the valve which will be unsuccessful thus requiring RNO actions to secure and isolate the B SGFP. (With B MFRV manual isolation accomplished per EOP-2)

5.

Verify Feedwater Isolation (1CS-3125 MFIV is failed OPEN)

RNO:

a. IF feedwater isolation valves can NOT be closed, THEN perform the following:

1) Shift 1FIC 476A feedwater regulating valve controller to manual and shut (will not work)

2) Shift 1HC 481 feedwater regulating bypass valve controller to manual and shut (will work)

IF any feedline can NOT be isolated, THEN perform the following:

1) Ensure Main Feedwater Pumps-TRIPPED (manual trip will work)

2) MFP discharge MOVs Both Shut (1CS-2189 will work)

2015 NRC Exam Scenario 1, Rev.0 SEG Page 18 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

Event 8: 1W-1A1 Accident Fan Fails to Auto Start Event 8: 1P-14B Spray Pump Fails to Auto Start BOP

6.

Verify Containment Isolation - ISOLATED

7.

Verify AFW Pumps - RUNNING

8.

Verify ECCS Pumps - RUNNING

9.

Verify Service Water Pumps - RUNNING

10. Verify Containment Accident Fans - RUNNING RNO: Manually start 1W-1A1 after SI sequence completed.

11. Verify Component Cooling Water Pumps - ONLY ONE RUNNING

12. Check if Main Steam Lines Can Remain Open

a. Any MSIV valve - OPEN RNO: Go to Step 13

13.

(CA Step) Verify Containment Spray Not Required BOP may request to manually actuate containment spray or manually start 1P-14B Spray Pump after Auto Spray signal fails to start the pump.

14.

Verify ECCS Flow - Pump Running

2015 NRC Exam Scenario 1, Rev.0 SEG Page 19 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

BOP RO BOP RO SRO

15. Verify AFW Valve Alignment - Proper Emergency Alignment

16. Verify Proper ECCS Valve Alignment - Valves are proper

17. Check RCP Seal Cooling - Not lost

18. Perform Attachment A, Automatic Action Verification, while continuing with this procedure

19. (CA Step) Check RCS Temperatures

a. Condenser Steam Dumps - AVAILABLE - NO RNO:

a. Adjust S/G Atmospheric steam dump controller to 1005 psig

b. IF temperature is less than 547ºF AND lowering, THEN perform the following:

a) Stop dumping steam b) IF cooldown continues, THEN control total feed flow:

Maintain total feed flow greater than or equal to 230 gpm until level is greater than [51%] 32 in at least one S/G.

b) IF cooldown continues, THEN isolate steam lines.

20. Check PZR PORVs and Spray Valves

a. PORVs - BOTH SHUT

b. Normal spray valves - BOTH SHUT

c. Auxiliary spray valves - SHUT

21. Check If RCPs Should Be Stopped - No

22. Check if SG are Not Faulted - No RNO: Go to EOP-2 Unit 1, Faulted Steam Generator Isolation

2015 NRC Exam Scenario 1, Rev.0 SEG Page 20 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

• CT-17 Isolate Faulted SG Isolate the faulted Steam Generator before transition out of EOP-2 SRO BOP EOP-2, Faulted Steam Generator Isolation CAUTIONS:

One SG must be maintained available for RCS cooldown.

If any faulted SG is not needed for RCS cooldown, it should remain isolated during subsequent recovery actions.

1.

Check Main Steam Isolation

a.

Any MSIV valve - OPEN

2.

Check If Any SG Is Not Faulted - Yes A S/G not faulted

3.

(CA Step) Identify Faulted SG - B S/G is faulted

4.

Isolate Faulted SG

a.

Ensure feedwater isolation valve is - SHUT o

1CS-3125 for SG B (see actions from EOP 0 step 5)

b.

Ensure MDAFW valve - SHUT o

SG B - 1AF-4074B

c.

Ensure TDAFW valve SHUT o

SG B - 1AF-4000

d.

Ensure SSG supply valve SHUT o

SG B - AF-4021

2015 NRC Exam Scenario 1, Rev.0 SEG Page 21 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

Communication:

When directed to locally shut 1P-29 AFP/RW steam isolation 1MS-237 and MS trap isolation 1MS-238, then insert trigger 20 and report valves closed after 5 minutes.

Communication:

Shift Manager maybe requested to contact Chemistry and RP to check for secondary radiation.

RO/BOP SRO RO

e.

Isolate flow from faulted SG:

1)

Ensure Atmospheric Steam Dump SHUT o 1MS-2015 for SG B

2)

Steam supply to TDAFW pump o 1MS-2019 for SG B

3)

Ensure SG Blowdown valves SHUT o SG B

• 1MS-5959

• 1MS-2045

4)

Locally shut 1P-29 AFP/Radwaste Steam isolation o 1MS-237 for SG B

5)

Locally shut Main Steam Trap isolation o 1MS-238 for SG B

5.

Check CST Level - GREATER THAN 4 FEET

6.

Check Secondary Radiation

7.

Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT EOP-1 Loss of Reactor or Secondary Coolant Foldout Page Criteria: SI Termination (same as listed below, in step 11)

1.

Check If RCPs Should Be Stopped - No

2015 NRC Exam Scenario 1, Rev.0 SEG Page 22 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

Communication:

Shift Manager maybe requested to contact Chemistry and RP to check for secondary radiation.

NOTE: Termination Criteria:

When the crew determines actions per Step 14 of EOP-1, Loss of Reactor or Secondary Coolant, or transitions to EOP-1.1, SI Termination, or at the discretion of the Lead Examiner.

BOP RO BOP RO SRO

2.

Check if SGs are NOT Faulted RNO: Check faulted S/Gs Isolated - completed in EOP 2

3.

(CA Step) Check Intact SG Levels

4.

Check Secondary Radiation

5.

(CA Step) Check Pzr PORV And Block Valves

6.

Reset SI

7.

Reset Isolation And Lockout Signals

8.

Establish Instrument Air to Containment

9.

Check Power Supply To Charging Pumps

10. Check If Charging Flow Has Been Established

11. (CA Step) Check If ECCS Flow Should Be Terminated:

a. RCS subcooling based on core exit TCs - GREATER THAN [74ºF]

35ºF

b. Secondary heat sink - Intact S/G level GREATER THAN [51%] 32%

OR Total feed flow GREATER OR EQUAL TO 230 GPM

c. RCS pressure - GREATER THAN [1850 psg] 1725 psig

d. Pzr Level - GREATER THAN [32%] 13%

Go to EOP-1.1 UNIT 1, SI TERMINATION if S/G is in a dryout condition

2015 NRC Exam Scenario 1, Rev.0 SEG Page 23 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

BOP RO BOP RO BOP

12.

(CA Step) Check if Containment Spray can be stopped

a. Containment spray pumps - ANY RUNNING

b. EOP-1.3 Unit 1, Transfer to Containment Sump Recirculation - Low Head Injection - NOT IN EFFECT

c. Containment pressure - LESS THAN 20 psig

d. Reset containment spray signal

e. Ensure containment spray pump RWST suction MOVs - OPEN

f. Stop both containment spray pumps and place in auto

g. Shut containment spray pump discharge valves and place in auto-after-shut position

h. Ensure both spray additive eductor suction valves - SHUT

13.

(CA Step) Check if RHR Pumps should be stopped

a. Check RCS pressure:

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

2) Pressure - STABLE OR RISING

b. RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST

c. Stop both RHR pumps and place in auto

14.

Check RCS and S/G Pressures If B S/G is not in a dryout condition transition is made back to Step 1.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 24 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

SRO BOP RO BOP EOP-1.1 SI Termination Foldout Page Criteria should be referenced

1.

Reset SI - previously done in EOP 1

2.

Reset Isolation and Lockout Signals - previously done in EOP 1 Containment Isolation 1B-03 and 2B-04 NON-Safeguards equipment lockouts

3.

Establish Instrument Air to Containment - previously done in EOP 1

4.

Check if Charging Flow has been Established - previously done in EOP 1

5.

Stop ECCS Pumps and Place in Pullout

a. Stop both SI pumps and place in auto

b. RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST

c. Stop both RHR pumps and place in auto

6.

Verify SI Flow not required

a. RCS subcooling based on CET - GREATER THAN [74ºF] 35ºF

b. PZR level - GREATER THAN [32%] 13%

7.

(CA Step) Check if Spray should be Stopped

2015 NRC Exam Scenario 1, Rev.0 SEG Page 25 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: 1HX-1B, B SG faults to Containment (cont'd)

Expected Communications: (EOP-0 Unit 1, Attachment A):

When directed to locally check shut RW service water valves, TV-LW-61 and 62, then report both valves are closed.

When directed to locally check CW pump house temperature

<105°F, then after five minutes report temperature is 72°F and stable.

BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification A1 Check Containment Spray NOT Actuated - Yes it is RNO:

1. Ensure all containment spray discharge MOVs are open.

2. Ensure at least one containment spray pump running.

3. IF two containment spray pumps running, THEN place one pump in pullout.

4. WHEN containment spray has been actuated for GREATER THAN two minutes, THEN ensure spray additive eductor valve is open on running train.

A2 Stop Any Boration via the Blender in Progress A3 Ensure The Auxiliary Building Filter/Exhaust Fans - OPERATING A4 Verify Service Water System Alignment A5 Check Miscellaneous Valves - SHUT A6 (CA Step) Check Control Room Ventilation A7 (CA Step) Check Cable Spreading Room Ventilation System - OPERATING A8 (CA Step) Check Computer Room Ventilation System - OPERATING A9 (CA Step) Check AFW Recirc Fans - ONE RUNNING A10 (CA Step) Check Circulating Water Pump House Temperature Less Than 105°F A11 (CA Step) Periodically Check Status of Spent Fuel Cooling Termination Criteria:

When the crew determines actions per Step 14 of EOP-1, Loss of Reactor or Secondary Coolant, or transitions to EOP-1.1, SI Termination, or at the discretion of the Lead Examiner.

• • • END OF SCENARIO ***

2015 NRC Exam Scenario 1, Rev.0 SEG Page 26 of 29 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS CT-1 Manually trip the reactor Critical Task:

Manually trip the reactor from the control room using the second set of push buttons prior to the containment pressure reaching 15 psig.

Plant Conditions:

• Reactor greater than 5% power

• High Containment Pressure should cause an automatic reactor trip but the trip breakers are failed to auto open.

• Reactor can be tripped from the control room with second set of pushbuttons only.

Cues:

• Indication and/or annunciation that Safety Injection has actuated with no reactor trip.

Performance Indicator:

Manipulation of second set of reactor trip pushbuttons o At least one set of Reactor trip and bypass breakers indicate open Feedback:

Indications of reactor trip

• Control rods at bottom of core Neutron flux decreasing Basis:

SAFETY SIGNIFICANCE - Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally it constitutes an incorrect performance that necessitates the taking compensating action which would complicated the event mitigation strategy and also demonstrates the inability of the crew to recognize a failure or an incorrect automatic actuation of an ESF system or component. The postulated event is a steam line break in containment, failure to active the ESF systems will cause a challenge to containment.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 27 of 29 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 the following is 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 MFW continues to be delivered to the faulted SG Valve position and flow rate indication that AFW continues to be delivered to the faulted SG Performance Indicator:

Manipulation of controls as required to isolate the faulted SG MSIVs indicate closed Indication of feedline isolation 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)

2015 NRC Exam Scenario 1, Rev.0 SEG Page 28 of 29 SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

8050 7500 Reactor power (%):

10%

100%

Boron concentration (ppm):

1450 ppm 1461 ppm Rod height (CBD @):

CBD @ 115 CBD @ 220 Target AFD

-0.37

-0.8 Full Power Target AFD

-3.75 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

LCO NOT Met TSAC Required Actions / Completion Time LCO 3.3.1 RPS Instrumentation TSAC 3.3.1.A One or more Functions with one or more required channels or trains inoperable TSAC 3.3.1 K One channel inoperable A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s) or train(s) -

Immediately K.1 Place channel to trip - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or K.2 Reduce THERMAL POWER to < P 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 3.0 EQUIPMENT OUT OF SERVICE:

P-38A SSG Pump for oil change G03 EDG scheduled maintenance 1LT-427 White Pressurizer Level for instrument drift 4.0 PLANNED EVOLUTIONS:

After shift turnover, start P-32F Service Water Pump and secure P-32B Service Water Pump per 0-SOP-SW-107 Service Water Pump Operations.

Continue rising power to approximately 15% at 15%/hr in accordance with OP 1C, Startup to Power Operation Unit 1, Step 5.5.3.

Place the unit online when requested by WE Power System Supervisor.

2015 NRC Exam Scenario 1, Rev.0 SEG Page 29 of 29 5.0 TURNOVER INFORMATION:

Safety Monitor is Green.

G04 EDG is aligned to 1(2) A06 4160 Safeguards Busses.

G01, G02 and G04 EDGs are guarded equipment.

1(2)P-29 TDAFW Pumps, 1(2)P-53 MDAFW Pumps and P-38 SSG Feed Pump are protected equipment.

1LT-426 and 1LT-428 Pressurizer Level Transmitters are guarded equipment.

P-32B Service Water Pump has a small oil leak and will need to be secured, isolated and danger tagged out after turnover to repair the leak.

Unit 1 is at 10% power ready for synchronization to the grid and power ascension.

Clock time is real time and you have the normal shift complement.

Page 1 of 28 SIMULATOR EXERCISE GUIDE SEG SITE:

Point Beach Revision #: 0 LMS ID:

LMS Rev. Date:

SEG TITLE:

2015 NRC Exam Scenario 2 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:

Jeff Baugniet SME (Technical Review)

Date Approved by:

Randy Amundson Training Supervision Date Approved by:

Tom Larson Training Program Owner (Line)

Date

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 2 of 28

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 3 of 28 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. TE-404A Thot fails High

2. 1P-2A Charging Pump Winding ground

3. SGTL requiring Rapid Downpower

4. LT-461 'A' S/G Level fails low After EOP Entry:

1. Several Train 'A' ESFAS sequencer relays fail

2. 1P-53 MDAFW Pump fails to start Abnormal Events:

1. TE-404A Thot fails High

2. 1P-2A Charging Pump Winding ground

3. SGTL requiring Rapid Downpower

4. LT-461 'A' S/G Level fails low Major Transients:

1. SGTR requiring plant trip Critical Tasks:

1. CT-18 Isolate ruptured S/G - based on one steam generator having a tube rupture.

2. CT-20 Depressurize RCS to E-3 SI termination criteria - based on the depressurization done to stop break flow.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 4 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 1: 1TE-404A Thot fails High Plant Response:

Control rods moving in auto with program pressurizer level maintaining full power program level.

Cues:

Rods moving in auto in the INWARD direction 1C03 1E2 4-2 Tavg Steam Dump Alert 1C04 1A 1-7 Automatic Rod Motion 1C04 1A 3-10 RCS Tavg Deviation 1C04 1A 3-11 RCS Tavg High And other annunciators Insert TRIGGER 1 at the discretion of the Lead Examiner.

NOTE: First alarm will come in approximately 2 minutes after the trigger has been activated.

Communication:

If SM is asked, I&C was notified to troubleshoot and repair TE-404A.

NOTE: Crew may elect to enter AOP-24 before/instead of AOP-6C.

RO SRO RO BOP SRO RO SRO/RO RO SRO Recognizes instrument failure for the Yellow channel Thot. Recommends placing rods to MANUAL.

SRO acknowledged recommendation and alarms.

Charging may be taken to manual. The unit will maintain pressurizer level at full power program level based on the circuit selecting auctioneered high Tavg.

Condenser Steam Dumps may be shifted to manual pressure control mode per Alarm Response Procedure actions. (1C03 1E2 4-2)

Enter AOP-6C Uncontrolled Motion of RCCAs

1.

Check Rod Motion - REQUIRED RNO ; No, place rods in Manual

2.

(CA Step) Maintain RCS Tavg

3.

Check RCS Tavg - At OR Trending to Tref RNO ; No, restore Tavg by manually withdrawing rods per SRO direction.

4.

Check Control Rods - Above Minimum Insertion Limits

5.

(CA Step) Verify AFD - WITHIN LIMITS

6.

Check Rod Motion Due to Instrument Failure

7.

Go To AOP-24, Response to Instrument Malfunctions

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 5 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 1: 1TE-404A Thot fails High (contd)

NOTE: The intent is to NOT remove the channel from service.

Communication:

If asked, the Shift Manager will have OS2 prepare the 0-SOP-IC-001 YELLOW procedure to remove the failed instrument from service.

NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic diagram as referenced in 0-SOP-IC-001-YELLOW page 12, Sheets #177,

1. 178, #179 and #180, as well as 0-SOP-IC-002 in its entirety.

NOTE: IF SRO determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary actions.

End of evolution: Proceed to next event at Lead Examiner discretion preferably after condenser steam dumps are in manual. After the next event trigger is inserted, it takes approximately 5 minutes for the Charging Pump Motor breaker to trip.

SRO RO BOP SRO RO SRO Crew will also enter AOP-24 Response to Instrument Malfunction.

1.

Identify Failed Instrument -1TE-404A Thot.

2.

Check if Failed Instrument is a Controlling Channel - Yes

3.

Establish Manual Control as Required: - Take Control Rods to Manual Rod control will be placed in MANUAL Charging may be placed in MANUAL

4.

Return Affected Parameter(s) to Desired Value(s) - Restore RCS temperature per AOP-6C.

5.

Using Attachment A, PPCS Parameters Used to Calculate Reactor Thermal Output. Verify that Failed Instrument is NOT an Input to RTO.

Channel is listed, but is redundant so RTO is not affected.

6.

Remove Failed Instrument Channel From Service per 0-SOP-IC-001 Routine Maintenance Procedure Removal of Safeguards or Protection Sensor From Service.

7.

Return Controls to Automatic if Desired.

8.

Check Failure for Technical Specifications or TRM Applicability

9.

Return to Procedure And Step In Effect.

TSAC Description, Required Actions, Completion Times:

3.3.1.A & D Table Function 5 - OTT, and Function 6 - OPT. Place channels in TRIP in 1 hr or Be in Mode 3 in 7 hrs.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 6 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 2: 1P-2A Charging Pump winding ground with subsequent breaker trip.

Plant Response:

Ground alarm for 1B03 with eventual 1P-2A breaker trip causing a lowering pressurizer level.

1P-2A Breaker trips Cues:

C02 D 3-2 1B03 480V Bus Ground 1C04 1C 3-9 Motor Breaker Trip 1C03 1D 2-1, 1P-1A or B RCP Labyr Seal P Low (possible) 1C04 1C 1-8, Charging Pump Speed Control Trouble 1-PPCS-003 PPCS Charging Flow Low Pressurizer level lowering Insert TRIGGER 3 at the discretion of the Lead Examiner.

Communication:

If requested, or if announced on Gaitronics, wait 2 minutes and report ground lights on 1B03 480 Safeguards Bus as one dim light and two bright lights.

If requested, wait 2 minutes and report back 1P-2A Charging Pump motor is hot to the touch.

If requested, wait 2 minutes and report back 1P-2A Breaker is tripped on overcurrent.

If requested, SM will notify the Duty Station Manager.

End of evolution: Proceed to next event at Lead Examiner discretion.

RO SRO RO SRO Crew identifies 1P-2A motor causing the ground alarms and breaker trip.

Enter AOP-1D, CVCS Malfunction

1.

(CA Step) Check RCS Leak - Not In Progress

2.

Determine CVCS Malfunction - 1P-2A Charging Pump has tripped so go to Step 3.

3.

Check any Charging Pump Running - one pump will be running

4.

Check Charging Flow Stable

5.

Check Charging Pump Relief - Not Lifting

6.

(CA Step) Check Charging Pump Suction Supply Adequate

7.

Check Charging System Response RNO: Crew should start the non-running charging pump and restore parameters to normal.

8.

Notify Duty Station Manager

9.

Return to Procedure and Step In Effect.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 7 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 3: B SGTL with Rapid Downpower Plant Response:

1RE-232 B Steamline in Alert then Alarm with lowering Pressurizer level (may not have an auto charging pump).

Cues:

RMSASRB CI 1RE-232, Unit 1 B Steamline Monitor RMSASRB CI 1RE-215, Condenser Air Ejector Gas Monitor ARP 1C04 1C 2-3 Pressurizer Level Setpoint Deviation Insert TRIGGER 5 at the discretion of the Lead Examiner.

Communication:

If RP is requested to perform steam line surveys, then wait 5 minutes and report:

o

'A' main steam line is at background.

o

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

If requested, SM will notify the Duty Station Manager, Chemistry and implement E-Plan.

RO BOP SRO BOP RO SRO IMPLEMENT AOP-3 Unit 1, Steam Generator Tube Leak

1.

(CA Step) Check Safety Injection Not Required

2.

(CA Step) Check Reactor Trip Not Required

3.

(CA Step) Check PZR Level - STABLE AT OR TRENDING TO PROGRAM RNO:

IF PZR level trending lower, THEN perform the following:

a. Control charging and letdown to maintain PZR level

b. IF PZR level continues to lower, THEN isolate letdown.

4.

Check PZR Pressure - STABLE AT OR TRENDING TO DESIRED PRESSURE

5.

Check Reactor Makeup Control

6.

Notify DSM, Chemistry, And Implement The Emergency Plan

7.

Identify The Leaking S/G - B

8.

Determine Leak Rate (approximately 5 gpm)

9.

Check Reactor Shutdown Required - yes

10. Determine Action Response Based on S/G Leakage:

a. Reduce Power to < 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Mode 3 in the next two hours.

Per AOP-17A, (likely 2 to 3%/minute ramp)

11. Place the Unit In MODE 3

12. Notify Chemistry Of Leak Rate And Rate Of Change

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 8 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 3: B SGTL with Rapid Downpower (contd)

Communication:

If requested, SM will direct RP to perform exposure and contamination evaluations.

NOTE: Potential for discussion about TE-404 failure and to trip the plant vice shutdown, if this occurs the SM should drive the crew to perform an AOP-3 power reduction.

Communication:

If requested, SM will have OS2 coordinate performance of steps 19 through 26.

RO SRO BOP

13. Monitor Leakage Every 15 Minutes

14. Direct RP To Perform Surveys And Contamination Evaluations

15. Check Leaking S/G - IDENTIFIED NOTE: Steps 16 through 26 may be completed in any order.

16. Adjust Affected S/G Atmospheric Steam Dump Controller To 1050 psig 1HC-478 for B S/G

17. Isolate Blowdown on Affected Steam Generator B S/G

• 1MS-5959

• 1MS-2045

18. Shut Affected Steam Generator Sample Isolation Valve 1MS-2084 for B S/G

19. Ensure Condensate Storage Tank Isolated from Condenser Hotwell

a.

Ensure condenser reject isolation valve SHUT

• 1CS-113

20. Locally Align Low Pressure Trap Header to Condenser.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 9 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 3: B SGTL with Rapid Downpower (contd)

Communication:

If requested, SM will notify Power Systems Supervisor and complete other NP 2.1.5 notifications.

NOTE: Rod Control will need to remain in manual due to earlier failure of 1TE-404A.

Communication:

When directed by crew to start 1P-99A and 1P-99B, MFP Seal Water Injection Pumps, wait 1 minute then insert Trigger 14, and report the pumps started.

End of evolution: Proceed to next event after power is reduced enough per Lead Examiner discretion.

SRO RO SRO RO BOP RO BOP SRO IMPLEMENT AOP-17A Unit 1, Rapid Power Reduction

1.

Determine Desired Power Level Or Condition To Be Met

2.

Notify PSS Of Load Reduction

3.

Check Rod Control System - IN AUTO RNO: Perform one of the following:

IF manual rod control desired, due to existing plant conditions, THEN operate control rods in manual to MAINTAIN TAVG WITHIN 5°F OF TREF.

4.

Select Rate Reduction Method And Reduce Load

5.

(CA Step) Borate To Maintain Rods Above The Low-Low Insertion Limit

6.

(CA Step) Check PZR Pressure - Stable at or Trending to 2235 psig

7.

(CA Step) Check PZR Level - Stable at or Trending to Program Level

8.

(CA Step) Check Steam Generator Level Controlling - In AUTO

9.

(CA Step) Maintain RCS Tavg

10. Check Main Feed Pump Seal Water Pump - Running

11. Determine Desired End-Point - Less Than 50% Turbine Load

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 10 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 4: 1LT-461 A Steam Generator Level Transmitter Fails Low Plant Response:

With transmitter failure indicated level for controlling channel fails low causing A FRV to open making actual S/G level rise.

Cues:

1C03 1E2 1-2, S/G A Level Setpoint Deviation/Trouble 1C03 1E2 1-3, S/G A High Level Channel Alert 1C03 1E2 2-3, S/G A Level High 1C03 1E2 4-3, S/G A Low-Low Level Channel Alert 1C03 1E2 3-2, S/G A Feedwater Channel Alert A S/G level rising Insert TRIGGER 7 at the discretion of the Lead Examiner.

NOTE: Crew may enter AOP-24 before/instead of AOP-2B.

Communication:

If requested, SM will inform OS1 I&C was notified to troubleshoot and repair 1LT-461.

NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic diagrams as referenced in 0-SOP-IC-001-RED page 21 Sheets #172, #176, and #182 and 0-SOP-IC-002 in its entirety.

Crew SRO RO BOP SRO BOP BOP SRO Acknowledge and respond to receipt of annunciators. Realize feed control issues are due to instrument failure and place affected controllers in Manual.

The crew may go to hold on the load ramp.

Crew enters AOP-2B.

1.

(CA Step) Maintain Power <100%

2.

Determine Secondary malfunction - FRV response which directs transition to Step 12.

12. Check Feed Regulating Valve Response - NORMAL RNO: a.1) Place affected controller in manual if desires, the Bypass FRV should also be placed in manual along with the FRV.

a.2) Match feed flow to steam flow a.3) Stabilize S/G level a.4) If transient due to instrument failure go to AOP-24 Crew enters AOP-24

1.

Identify Failed Instrument - 1LT-461

2.

Check if Failed Instrument is a Controlling Channel - Yes

3.

Establish Manual Control as Required: - Take Manual control of feed. The Bypass FRV should also be placed in manual along with FRV.

4.

Return Affected Parameter(s) to Desired Value(s)

5.

Use Attachment A to determine if RTO is affected - RTO not affected

6.

Remove failed instrument from service per 0-SOP-IC-001 - RED

7.

Return controls to automatic if desired

8.

Check Failed Instrument for Technical Specification OR TRM Applicability

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 11 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 4: 1LT-461 A Steam Generator Level Transmitter Fails Low (contd)

NOTE: Intent is to NOT take the instrument out of service per 0-SOP-IC 001 RED End of evolution: Proceed to next event at Lead Examiner discretion.

SRO Review 0-SOP-IC-002 Technical Specification LCO-Instruments Cross Reference.

Table 3.3.1-1 item 13 S/G Water Level Low-Low Table 3.3.2-1 item 5b FI-S/G water Level-High Table 3.3.2-1 item 6b AFW-S/G water Level-Low Low Table 3.3.3-1 item 16 S/G Water Level (NR) (not applicable)

TSAC 3.3.1.A and D, Place channel in trip (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) or be in MODE 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

TSAC 3.3.2.A and D, Place channel in trip (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) or be in MODE 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and Mode 4 in 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 12 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR Plant Response:

Rapidly lowering pressurizer level with S/G level deviations.

Available charging will not keep up with leak.

Cues:

1C04 1C 1-2 Pressurizer Pressure High or Low 1C04 1C 2-3 Pressurizer Level Deviation 1C03 1E2 1-5, B S/G Level Deviation B FRV closing B S/G level rising Insert TRIGGER 9 at the discretion of the Lead Examiner.

Communication:

If asked, wait two minutes then, PAB AO reports nothing abnormal for 1P-53 MDAFW Pump.

If asked, wait two minutes then, TH AO reports nothing abnormal for 1P-53 MDAFW Pump breaker 1A52-83.

NOTE: Expected operator action will be based on actual S/G level when this step is addressed.

NOTE: Forebay Level Low alarm on PPCS expected based on loss of power.

RO SRO SRO BOP DIRECT a Rx Trip, SI and CI if PZR Level is not within 10% of Program, RCS subcooling is not > 30 ºF, or charging suction shifts to the RWST.

IMPLEMENT EOP-0 Unit 1, Reactor Trip or Safety Injection

1. Verify Reactor Trip

2. Verify Turbine Trip

3. Verify Power to AC Safeguards Buses

4. Check if SI is Actuated Implement Foldout Page Criteria - Ruptured S/G Isolation Criteria

3. IF any S/G level rises in an uncontrolled manner OR any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than [51%]

32%, THEN feed flow may be isolated to affected S/G(s).

Isolate feed flow when B S/G level is greater than [51%] 32% (steam path isolated later)

5. Verify Feedwater Isolation

6. Verify Containment Isolation

7. Verify AFW Pumps - RUNNING (See Event 7)

RNO a.: WHEN SI sequence is complete, THEN manually start motor-driven AFW pump.

IF S/G level is greater than [51%] 32% in any S/G, THEN control feed flow to maintain S/G level.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 13 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

Communication:

If asked, wait two minutes then applicable AO should report no abnormal indications for pumps and breakers:

o 1P-10A RHR Pump 1B52-12A o

P-32F SW Pump 2B52-34B o

1W-1A Accident Fan 1B52-16B RO/BOP SRO

8. Verify ECCS Pumps - RUNNING Start 1P-10A RHR (See Event 6)

9. Verify Service Water Pumps - RUNNING Start P-32 F Service Water Pump (See Event 6)

10. Verify Containment Accident Cooling Units - RUNNING Start 1W-1A1 Accident Fan (See Event 6)

11. Verify Component Cooling Water Pumps - ONLY ONE RUNNING

12. Check If Main Steam Lines Can Remain Open

13. (CA Step) Verify Containment Spray Not Required

14. Verify ECCS Flow

15. Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT

16. Verify Proper ECCS Valve Alignment Open 1SI-852A Core Deluge (See Event 6)

17. Check RCP Seal Cooling

18. Perform Attachment A, Automatic Action Verification, while continuing with this procedure.

19. (CA Step) Check RCS Temperatures

20. Check PZR PORVs And Spray Valves

21. Check If RCPs Should Be Stopped

22. Check If S/G Are NOT Faulted

23. Check If S/G Tubes Are NOT Ruptured RNO: Go to EOP-3 Unit 1, Steam Generator Tube Rupture

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 14 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

Communication:

SM acknowledges request if RP is requested to perform steam line surveys.

SM acknowledges request if Chemistry is requested to standby for sampling.

When directed to shut 1MS-237, AFP Radwaste Steam Isolation and 1MS-238, Main Steam Trap Header Isolation, wait 5 minutes then insert Trigger 16 and report when the valves are closed.

SRO RO BOP/RO ENTER EOP-3, Unit 1 Steam Generator Tube Rupture

1.

(CA Step) Check If RCPs Should Be Stopped

2.

Identify Ruptured S/G - (B)

3.

Isolate Flow From Ruptured S/G(s)

a.

Shut ruptured S/G(s) MSIV and MSIV bypass valve:

o 1MS-2017 and 1MS-236 for S/G B

b.

Adjust ruptured S/G(s) atmospheric steam dump controller to 1050 psig o

1HC-478 for S/G B

c.

Check ruptured S/G(s) atmospheric steam dump - SHUT o

1MS-2015 for S/G B (1HC-478)

d.

SHUT steam supply from ruptured S/G to turbine-driven AFW pump o

1MS-2019 for S/G B

e.

Verify blowdown isolation valves for ruptured S/G(s) - SHUT o

S/G B 1MS-5959 1MS-2045

f.

Locally shut 1P-29 AFP/Radwaste steam isolation for ruptured S/G(s) o 1MS-237 for S/G B

g.

Locally shut main steam trap isolation for ruptured S/G(s) o 1MS-238 for S/G B

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 15 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

• CT-18 Isolate feedwater flow into and steam flow from the ruptured S/G before a transition to ECA-3.1 occurs.

BOP/RO

4.

Check Ruptured S/G(s) Level:

a.

Level - GREATER THAN [51%] 32%

RNO: a. Maintain feed flow to ruptured S/G(s) unit level is greater than [51%] 29%

WHEN ruptured S/G level is greater than [51%] 32%

THEN do step 4.b.

OBSERVE CAUTION PRIOR TO STEP 5 and continue with Step 5.

b.

Stop feed flow to ruptured S/G(s)

1) Place in manual and shut AFW supply valves:

o S/G B:

• 1AF-4074B

2) Ensure TDAFW Control valve - SHUT o S/G B:

• 1AF-4000

3) Ensure SSG supply valve - SHUT o S/G B

9. AF-4021 CAUTION: Major steam flow paths from the ruptured S/G(s) should be isolated before initiating RCS cooldown.

5.

Check Ruptured S/G(s) Pressure - GREATER THAN 590 PSIG CAUTION: If RCPs are NOT running, the following steps may cause a false Integrity Status Tree indication for the ruptured loop. Disregard the ruptured loop T-cold indication until after performing Step 28.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 16 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

NOTE: After cooldown commenced Crew should continue through Step 13.

NOTE: BOP may identify that the 1B03 lockout failed to actuate. No additional actions required.

RO/BOP RO NOTES:

RCP trip criteria in Step 1 does NOT apply after a controlled RCS cooldown is initiated.

RCS cooldown should proceed as quickly as possible and should not be limited by the 100°F/hr Technical Specification limit.

SI Should Be Blocked When Pressurizer Pressure Decreases to LESS THAN 1990 psig.

6.

Initiate RCS Cooldown:

a. Check SI signal status:

1) ANY Auto SI signal - IN

2) Reset SI

b.

Determine required core exit temperature: (based on current CET)

c.

Dump steam to condenser from intact S/G at maximum rate:

RNO: c. Manually or locally dump steam at maximum rate from intact S/G:

a) Open 1MS-2016 for S/G A (1HC-468)

d.

Check core exit TCs - LESS THAN REQUIRED TEMPERATURE RNO: d. WHEN core exit thermocouple temperatures are less than required temperature, THEN do Steps 6.e and 6.F.

Continue with Step 7.

e.

Stop RCS cooldown

f.

Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE

7.

(CA Step) Check Intact S/G Level:

a.

S/G level - GREATER THAN [51%] 32%

b.

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

8.

(CA Step) Check PZR PORVs And Block Valves

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 17 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

BOP RO BOP

9.

Check SI signal status

a.

ANY Auto SI signal - IN

b.

Reset SI

10. Reset Isolation and Lockout Signals Containment Isolation 1B-03 and 1B-04 NON-safeguards equipment lockouts

11. Reestablish Instrument Air To Containment

a.

Check IA Header pressure > 80 psig

b.

Open IA to containment isolation valves one at a time IA-3047 IA-3048

12. (CA Step) Check If RHR Pumps Should Be Stopped:

a. RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST

b. RCS pressure - GREATER THAN [450 PSIG] 325 PSIG

c. Stop both RHR pumps and place in auto

13. Establish Charging Flow

a.

Charging Pumps - AT LEAST ONE RUNNING

b.

Align charging suction to the RWST

c.

Establish maximum charging flow

14. Check If RCS Cooldown Should Be Stopped

a.

Check core exit TCs - LESS THAN REQUIRED TEMPERATURE

b.

Stop RCS cooldown

c.

Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 18 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

• CT-20 Depressurize the RCS to meet SI termination criteria to prevent steam release from the ruptured S/G beyond 30 minutes.

BOP RO SRO

15. Check Ruptured S/G Pressure Stable Or Rising

16. Check RCS Subcooling Based On core Exit Thermocouples - GREATER THAN [94ºF] 55 ºF

17. Depressurize RCS to Minimize Break Flow And Refill PZR

a.

Normal PZR spray - AVAILABLE

b.

Spray PZR with maximum spray until any of the following conditions satisfied:

o Both of the following:

1)

RCS pressure - Less than or Equal to Rutured S/G Pressure

2)

PZR level - GREATER THAN [32%] 13%

OR o

PZR level - GREATER THAN [52%] 58%

OR o

RCS subcooling based on core exit TCs - LESS THAN [74ºF]

35ºF

c.

Shut spray valves 1RC-431A 1RC-431B

d.

Secure Auxiliary Spray Valve:

1)

OPEN 1CV-1298

2)

SHUT 1CV-296

e.

OBSERVE CAUTION PRIOR TO STEP 20 and go to Step 20.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 19 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

RO BOP RO

20. Check If ECCS Flow Should Be Terminated

a. RCS subcooling based on core exit TCs - GREATER THAN [74ºF]

35ºF

b. Secondary Heat Sink:

o Intact S/G level - GREATER THAN [51%] 32%

OR o

Total feed flow to S/Gs - GREATER THAN OR EQUAL TO 230 GPM AVAILABLE

c. RCS pressure - STABLE OR RISING

d. PZR level - GREATER THAN [32%] 13%

21. Stop Both SI Pumps and Place in Auto

22. Establish Charging Flow

23. Verify SI flow Not Required:

a. Check RCS subcooling based on core exit thermocouples -

GREATER THAN [74º F] 35º F.

b. PZR level - GREATER THAN [32%] 13%

24. Check Reactor Makeup Control:

a.

Ensure MCCs - ENERGIZED 1B-31, 1B52-14C, train A B-43, 1B52-21C, Train B

b.

Makeup set for greater than 2800 ppm

c.

VCT level - GREATER THAN 17%

d.

Ensure makeup armed and in auto

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 20 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

RO

25. Check if Letdown can be established

a. PZR level - GREATER THAN [44%] 24%

b. Establish Letdown

1) Open letdown line containment isolation valves:

2) Open RCS loop B cold leg letdown isolation valve:

3) Ensure component cooling flow to non-regenerative heat exchanger - ESTABLISHED

4) Ensure charging flow - AT LEAST 20 GPM

5) Adjust backpressure as necessary and open letdown isolation valves to establish letdown flow:

26. Align Charging Pump Suction To VCT:

a.

VCT level - GREATER THAN 17%

b.

Open VCT outlet to charging pump suction MOV:

1CV-112C

c.

Shut RWST to charging pump suction MOV:

• 1CV-112B

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 21 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

BOP

27. Check If SI Accumulators Should Be Isolated:

a.

RCS pressure - LESS THAN 1075 PSIG

b.

Check the following:

RCS subcooling based on core exit thermocouples -

GREATER THAN [74º F] 35º F PZR level - GREATER THAN [32%] 13%

c. Restore power to both accumulator discharge MOVs:

1B52-324F for 1SI-841A 1B52-424F for 1SI-841B

d. Shut both accumulator discharge MOVs:

1SI-841A 1SI-841B

e. Remove power to both accumulator discharge MOVs:

1B52-324F for 1SI-841A 1B52-424F for 1SI-841B

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 22 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd)

SRO

28. (CA Step) Control RCS Pressure And Charging flow To Minimize S/G Leakage

a. Perform appropriate action(s) from table below and use ATTACHMENT B handout as desired:

PZR LEVEL RUPTURED S/G LEVEL RISING LOWERING OFF SCALE HIGH LESS THAN OR EQUAL TO [44%]

24%

Raise charging flow Depressurize RCS using Step 28.b Raise charging flow Raise charging flow Maintain RCS and ruptured S/G(s) pressures equal BETWEEN

[44%] 24%

AND 50%

Depressurize RCS using Step 28.b Turn on PZR heaters Maintain RCS and ruptured S/G(s) pressures equal BETWEEN 50% AND

[52%] 58%

Depressurize RCS using Step 28.b Reduce charging flow Turn on PZR heaters Maintain RCS and ruptured S/G(s) pressures equal GREATER THAN OR EQUAL TO

[52%] 68%

Reduce charging flow Turn on PZR heaters Maintain RCS and ruptured S/G(s) pressures equal

b.

Use normal PZR spray as necessary to depressurize RCS per table in Step 28.a:

o 1RC-431B, Loop B o

1RC-431A, Loop A

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 23 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Communications: (EOP-0 Unit 1, Attachment A):

When directed to locally check shut RW service water valves, TV-LW-61 and 62, wait two minutes then report both valves are closed.

When directed to locally check CW pump house temperature <105°F, then after five minutes report temperature is 72°F and stable.

BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification A1 Check Containment Spray NOT Actuated A2 Stop Any Boration via the Blender in Progress A3 Ensure The Auxiliary Building Filter/Exhaust Fans - OPERATING A4 Verify Service Water System Alignment (BOP may align SW valves -

see event 6 for specific valves)

A5 Check Miscellaneous Valves - SHUT A6 (CA Step) Check Control Room Ventilation A7 (CA Step) Check Cable Spreading Room Ventilation System -

OPERATING A8 (CA Step) Check Computer Room Ventilation System - OPERATING A9 (CA Step) Check AFW Recirc Fans - ONE RUNNING A10 (CA Step) Check Circulating Water Pump House Temperature Less Than 105°F A11 (CA Step) Periodically Check Status of Spent Fuel Cooling

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 24 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 6: Train A ESF Sequencer Fails to Actuate BOP Several A Train SI Sequencer Relays fail so the following components will not re-position after the SI signal. The BOP should notify the OS of the equipment failures and take the required RNO actions, if any. Action will be addressed in EOP-0 steps as well as EOP-0 Attachment A.

SI-852A Core Deluge valve will not auto open 1B03 Bus Lockout will not trip 1P-10A RHR Pump fail to auto start 1W-1A1 Accident Fan fail to auto start P-32F SW Pump fail to auto start 1SW-2907 SW Accident Fan Cooler MOV will not auto open SW-2930B, 2927A, 2816, and 2817 will fail to auto close EVENT 7: 1P-53 MDAFW Pump Fails to Auto start Communication:

If asked, wait two minutes and the PAB AO reports nothing abnormal for 1P-53 MDAFW Pump.

If asked, wait two minutes and the TH AO reports nothing abnormal for 1P-53 MDAFW Pump breaker 1A52-83.

BOP 1P-53 MDAFW Pump will not Auto Start. BOP should recognize pump did not start and manually start P-53 to supply AFW to the S/Gs.

Termination Criteria:

When the crew evaluates Step 28 of EOP-3 to determine actions for maintaining the RCS and ruptured S/G pressures equal, then verify with the Lead Evaluator and take the shift.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 25 of 28 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS CT-18 Isolate ruptured S/G Critical Task:

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

• SGTR

• Reactor trip

• SI Cues:

• Indication and/or annunciation of SGTR in one S/G Increasing S/G 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 S/G

• Main steam isolation valve position lamps indicate closed

• S/G Atmospheric dump controller set at 1050 psig

• 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 S/G

• Indication of decreasing or zero feedwater flow rate in the ruptured S/G Basis:

SAFETY SIGNIFICANCE - Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SG. The fact that the crew allows the differential pressure to dissipate and, as a result, are then forced to transition to a contingency ERG constitutes an incorrect performance that "necessitates the crew taking compensating action that would complicate the event mitigation strategy..."

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 26 of 28 CT-20 Depressurize RCS to E-3 SI termination criteria Critical Task:

Depressurize the RCS to meet the SI termination criteria in order to prevent steam release from the ruptured steam generator beyond 30 minutes.

Plant Conditions:

• SGTR

• Reactor Trip

• SI

• Ruptured S/G identified and isolated

• RCS cooldown to target temperature completed Cues:

• Indication and/or annunciation of SGTR in one S/G Increasing S/G water level Radiation AND o Indication and/or annunciation of reactor trip and SI AND o Indication that the RCS is cooled down to the target temperature Performance Indicator:

Manipulation of controls as required to depressurize the RCS

• Valve position lamps show PZR spray valve or PZR PORV open Feedback:

• Indication of RCS pressure decreasing

• Indication of PZR level increasing Basis:

SAFETY SIGNIFICANCE - Failure to stop reactor coolant leakage into a ruptured SG by depressurizing the RCS (when it is possible to do so) needlessly complicates mitigation of the event. It also constitutes a "significant reduction of safety margin beyond that irreparably introduced by the scenario".

Notes:

• 30 minutes is the FSAR assumption beyond which steam release does not occur for a design basis SGTR event. This is to meet assumptions for dose analysis. Reference FSAR 14.2.4.

• Simulator booth operator will need to monitor the position of the ruptured S/G atmospheric dump valve to ensure it remains closed >30 minutes from time of trip.

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 27 of 28 SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

10550 6500 Reactor power (%):

100%

100%

Boron concentration (ppm):

948 ppm 1461 ppm Rod height (CBD @):

CBD @ 220 CBD @ 220 Target AFD

-3.0

-.08 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

LCO NOT Met TSAC Required Actions / Completion Time LCO 3.3.1 RPS Instrumentation TSAC 3.3.1.A One or more Functions with one or more required channels or trains inoperable TSAC 3.3.1 K One channel inoperable A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s) or train(s) -

Immediately K.1 Place channel to trip - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or K.2 Reduce THERMAL POWER to < P 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 3.0 EQUIPMENT OUT OF SERVICE:

P-38A SSG Pump for oil change G03 EDG scheduled maintenance 1LT-427 White Pressurizer Level for instrument drift 4.0 PLANNED EVOLUTIONS:

None 5.0 TURNOVER INFORMATION:

2015 NRC Exam Scenario 2, Rev. 0 SEG Page 28 of 28 Safety Monitor is Green.

G04 EDG is aligned to 1(2) A06 4160 Safeguards Busses.

G01, G02 and G04 EDGs are guarded equipment.

1(2)P-29 TDAFW Pumps, 1(2)P-53 MDAFW Pumps and P-38 SSG Feed Pump are guarded equipment.

1LT-426 and 1LT-428 Pressurizer Level Transmitters are guarded equipment.

Clock time is real time and you have the normal shift complement.

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 25 SIMULATOR EXERCISE GUIDE SEG SITE:

Point Beach Revision #: 0 LMS ID:

LMS Rev. Date:

SEG TITLE:

2015 NRC Exam Scenario 3 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:

Jeff Baugniet SME (Technical Review)

Date Approved by:

Randy Amundson Training Supervision Date Approved by:

Tom Larson Training Program Owner (Line)

Date

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 2 of 25

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 3 of 25 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. High RCS Activity

2. 1N-43 Power Range Fails Low

3. 1P-11A CCW Pump Trip

4. Feed Line Rupture Inside Containment After EOP Entry:

1. 1RC-430 PORV opens

2. 1P-53 MDAFW Pump Sheared Shaft, and 1P-29 TDAFW Pump Overspeed Trip Abnormal Events:

1. High RCS Activity

2. 1P-11A CCW Pump Trip

3. 1N-43 Power Range Fails Low Major Transients:

1. 'B' S/G Feedline Break Inside Containment, with a loss of heat sink Critical Tasks:

1. CT-10 Close PRZR PORV block valve - based on closing the block valve after a pressure transient causes the PORV to open and it sticks open

2. CT-43 Establish main feedwater or condensate flow to SG(s) before bleed and feed is required.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 4 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 1: High RCS Activity Plant Response:

Fuel failure will ramp in causing multiple RMS alarms in systems associated with the RCS.

Cues:

1C20 B 1-9, Common Area Radiation Monitor High 1C20 C 1-1, Unit 1 Area Radiation Monitor High 1RE-109 RCS Hot Leg Sample line High RE-116 Demineralizer Valve Gallery High 1RE-106 Sample Room High 1RE-136 Sample Room High NOTE: Insert TRIGGER 1 as soon as the crew takes the watch, due to build in time required.

Communications:

SM will get asked to contact Chemistry for sampling per CAMP 300 or EPIP 8.4.1. Acknowledge and direct crew to continue in the procedure.

SM will get asked to notify DSM and implement E-Plan SM will get asked to notify Chemistry to determine if crud burst has occurred and notify Reactor Engineering to review chemistry data and core trends to determine if source of leakage is failed fuel.

SM will get asked to consult with Chemistry regarding placing the cation demineralizer in service.

If requested, PAB AO is standing by to perform requested actions for the Letdown Gas Stripper associated with placing a second Letdown Orifice in service Crew SRO RO SRO RO/BOP Multiple containment and PAB RMS alarms will come in. The crew will diagnose a high RCS activity and enter AOP-8A.

NOTE: Crew to continue while awaiting Chemistry results.

1.

Confirm High Reactor Coolant Activity

a.

Direct Chemistry to obtain and analyze RCS sample.

b.

Check sample results - HIGH ACTIVITY

2.

Initiate limited plant evacuation of PAB

a.

Announce message

b.

Sound evacuation alarm

c.

Repeat message

3.

Notify Duty Station Manager and implement E-Plan

4.

Perform the Following: - Notify Chemistry and Rx Eng

5.

Raise purification flow - additional orifice placed in service, skill of the craft may be used.

a.

Establish maximum allowable letdown purification flow per OP-5A, Reactor Coolant Volume Control

b.

Consult with Chemistry and place cation demineralizer in service per OP-5D Part 7, CVCS Demineralizer Operation Per OP-5A do not exceed 90 gpm flow through the mixed bed when raising purification flow.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 5 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 1: High RCS Activity (contd)

Communications:

SM will get asked to notify RP that radiation levels may increase in PAB and on area monitors.

SM will get asked if Reactor Engineering review is complete. State this review is in progress and direct crew to continue in procedure.

SM can respond to OS1 the Unit 2 OS will coordinate the completion of the Unit 2 and common actions in steps 8, 9 and 10.

NOTE: There are minimal crew actions after placing the second orifice in service.

End of evolution: Proceed to next event at Lead Examiner discretion.

SRO RO SRO

6.

Notify Radiation Protection that radiation levels may increase in PAB AND on Radiation Monitors.

7.

IF Reactor Engineering Review of chemistry data indicates failed fuel, THEN proceed as follows:

a.

Refer to Technical Specification 3.4.16

b.

Review logs for any known RCS to Secondary leakage.

8.

Check Gas Stripper status

9.

Locally shut Unit 2 Cryogenics valve 2CV-261C

10. Align Gas Decay Tanks

11. (CA STEP) Check if Reactor Shutdown Required.

12. Initiate Plant Shutdown, as Required:

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 6 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: 1N43 PR Upper Detector Fails Low Plant Response:

Outward rod motion due to power mismatch rate of change.

Cues:

• 1C04 1A 1-7, Automatic Rod Motion

• 1C04 1A 3-2, 1N-41, 42, 43, or 44 Power Range Loss of Detector Voltage

• 1C04 1A 3-3, Power Range Channel Deviation

• 1C04 1A 4-5, Power Range Rod Drop Communication:

Per Lead Examiner, if the crew hasnt started the downpower, the SM should instruct the crew to commence the downpower based upon Chemistry and Reactor Engineering analysis of chemistry results. (preferably after NI TS call)

Insert TRIGGER 3 at the discretion of the Lead Examiner.

Communication:

If SM is asked, I&C was notified to troubleshoot and repair 1N-43.

NOTE: Crew may elect to enter AOP-24 before/instead of AOP-6C.

RO/BOP SRO RO SRO Crew will diagnose the failure of N43 and place control rods to manual.

Enter AOP-6C Uncontrolled Motion of RCCAs

1.

Check Rod Motion - REQUIRED Change in Turbine Load Change in Steam Demand Tavg/Tref mismatch greater than 1.5ºF RNO ; No, place rods in Manual

2.

(CA Step) Maintain RCS Tavg Greater than 540ºF Less than 577ºF Within 7ºF of program Tavg

3.

Check RCS Tavg - At OR Trending to Tref RNO ; No, restore Tavg by moving rods per SRO direction

4.

Check Control Rods - Above Minimum Insertion Limits

5.

(CA Step) Verify AFD - WITHIN LIMITS PPCS axial flux alarm - Clear Control board meters - At Least Three Within Limits

6.

Check Rod Motion Due to Instrument Failure

7.

Go To AOP-24, Response to Instrument Malfunctions

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 7 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: 1N43 PR Upper Detector Fails Low (cont'd)

NOTE: The intent is to NOT remove the channel from service.

Communication:

If asked, the Shift Manager will have OS2 prepare the 0-SOP-IC-001 BLUE procedure to remove the failed instrument from service.

Per Lead Examiner, if the crew hasnt started the downpower, the SM should instruct the crew to commence the downpower based upon Chemistry and Reactor Engineering analysis of chemistry results. (preferably after NI TS call)

NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic diagrams as referenced in 0-SOP-IC-001-BLUE page 47. Sheets

1. 173, #174, #178, 0-SOP-IC-002 in its entirety.

SRO RO BOP SRO Crew will also enter AOP-24 Response to Instrument Malfunction.

1.

Identify Failed Instrument -N43 Power Range NI

2.

Check if Failed Instrument is a Controlling Channel - Yes

3.

Establish Manual Control as Required: - Take Control Rods to Manual

4.

Return Affected Parameter(s) to Desired Value(s) - Restore RCS temperature per AOP-6C guidance

5.

Using Attachment A, PPCS Parameters Used to Calculate Reactor Thermal Output. Verify that Failed Instrument is NOT an Input to RTO.

6.

Remove Failed Instrument Channel From Service per 0-SOP-IC-001 Routine Maintenance Procedure Removal of Safeguards or Protection Sensor From Service.

7.

Return Controls to Automatic if Desired.

8.

Check Failure for Technical Specifications or TRM Applicability

9.

Return to Procedure And Step In Effect.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 8 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: 1N43 PR Upper Detector Fails Low (cont'd)

Per Lead Examiner, if the crew hasnt started the downpower, the SM should instruct the crew to commence the downpower based upon Chemistry and Reactor Engineering analysis of chemistry results. (preferably after NI TS call)

NOTE: An RE-212 alert may come in prior to the downpower.

End of evolution: Proceed to next event at Lead Examiner discretion.

SRO IDENTIFY LCOs NOT MET (reference 0-SOP-IC-002): LCO 3.3.1 is Not Met TSAC Description, Required Actions, Completion Times:

3.3.1.A Immediately enter the table 3.3.1.D One channel inoperable. (D.1) Place channel in trip within 1 hr. OR (D.2) be in Mode 3 within 7 hrs.

Items: 2a, PR Flux High 2b, PR Flux Low 5, OTT 3.3.1.S One or more channels inoperable. (S.1) Verify interlock is in required state for existing unit conditions within 1 hr. OR (S.2) Be in Mode 2 within 7 hrs.

Items: 17b-1, PR Neutron Flux P-7 17c, PR Neutron Flux P-8 17d, PR Neutron Flux P-9 3.3.1.R One or more channel inoperable. (R.1) Verify interlock is in required state for existing unit conditions within 1 hr. OR (R.2) Be in Mode 3 within 7 hrs.

Item 17e, PR Neutron Flux P-10 SR 3.2.4.1 or 3.2.4.2 will be applicable but will be dependent on THERMAL POWER which will be based on crew actions with this failure.

Event 3: Normal Downpower to 28% at 30%/hr Crew will start downpower with Step 5.2.1.

Crew RO/BOP Briefing on downpower will be performed in classroom prior to beginning of the scenario Insert rods and/or Borate in addition to adjusting steam demand as needed to establish power decrease.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 9 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 4: Running CCW Pump Shaft Seizure with failure of Standby CCW Pump to Auto start.

Plant Response:

A CCW pump failure will cause motor breaker trip and failure of B CCW Pump to auto start will cause low flow alarms.

Cues:

• 1C03 1D 2-5 SI Pump Cooling Water Flow Low

• 1C03 1D 3-7 Motor Breaker Trip

• 1C03 1D 2-6 CCW Discharge Pressure Low Unit 1

• 1C03 1D 1-4 1P-1A RCP Cooling Water Low Flow

• 1C03 1D 1-5 1P-1B RCP Cooling Water Low Flow Insert TRIGGER 5 at the discretion of the Lead Examiner.

Communications:

If asked, the PAB AO reports the A CCW Pump inboard motor bearing is hot to the touch.

If asked, the PAB AO will report nothing unusual with the B CCW Pump discharge pressure indicator, it reads 125 psig locally.

If asked, the TH AO will report the A CCW Pump breaker has tripped on overcurrent.

If asked, SM will notify the Chemistry, DSM and implement Emergency Plan.

NOTE: Crew may elect to place 1P-11A in pullout to clear Motor Breaker Trip alarm.

End of evolution: Proceed to next event at Lead Examiner discretion.

BOP SRO BOP RO BOP/RO SRO BOP identifies the A CCW Pump failure with the B CCW Pump not auto starting. BOP requests from the SRO to start B CCW Pump manually. Crew may start pump per ARB guidance then enter AOP 9B.

Enter AOP 9B CCW malfunction

1.

Check Component Cooling Pumps - At Least One Running.

RNO: Start 'B' CCW Pump (may be previously started per ARB)

2.

Maintain Surge Tank Level

3.

(CA Step) Check Surge Tank Level - Greater Than 10%

4.

Check Component Cooling System for Inleakage

5.

Check Reactor Trip - Not Required

6.

Check RHR Status

7.

Request Chemistry Analyze CCW.

8.

Notify DSM and implement Emergency Plan.

9.

Return to Procedure And Step In Effect TSAC Description, Required Actions, Completion Times:

3.7.7.A One CC pump inoperable. Restore CC pump to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 10 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment Plant Response:

Containment humidity and pressure rising, containment sump A level rise with no increased indications of RMS to indicate there is a primary leak.

Cues:

• 1-PPCS-007 Containment Humidity alarm

• 1-PPCS-018 Containment Pressure alarm

• C01 B 1-4 Containment Sump A Level High

• 1C03 1E2 2-5, Steam Generator B feed Water Flow High Insert TRIGGER 9 at the discretion of the Lead Examiner.

Crew SRO RO BOP Crew determines leak inside containment is secondary coolant leak.

Enter AOP-2A Secondary Coolant Leak

1.

(CA Step) Determine Secondary Leakage Not Hazardous to Personnel or Equipment Plant Habitability Containment Pressure less than 2 psig Safeguards bus fault Equipment operability RNO:

a. Trip Reactor (SRO may actuate SI prior to reaching auto setpoint)

b. Enter EOP Network

2.

(CA Step) Maintain Plant Within Limits Reactor power less than or equal to 100%

S/G level stable at or near 64%

SGFP suction pressure greater than 180 psig Condensate pump motor current less than 185 amps

3.

(CA Step) Maintain RCS Tavg

4.

Check Containment Conditions Normal

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 11 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

SRO RO SRO BOP EOP-0 Reactor Trip or Safety Injection

a.

Verify Reactor Trip - Yes

b.

Verify Turbine Trip - Yes

c.

Verify Power to AC Safeguards Buses - Yes

d.

Check if SI is Actuated (SRO may actuate SI prior to reaching auto setpoint)

Implement Foldout Page Criteria - Faulted SG Isolation Criteria:

3. IF any SG pressure trending lower in an uncontrolled manner OR Completely depressurized, THEN the following may be performed:

a. Isolate feed flow to the faulted SG

b. Maintain total feed flow greater than or equal to 230 gpm until NR level in at least one SG is greater than [51%] 32%.

5. Adverse Containment Conditions

-IF any condition listed below occurs, THEN environmentally qualified (Ea) equipment and adverse containment setpoint values in brackets,

[I, shall be used:

o Containment pressure - GREATER THAN 5 PSIG

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 12 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

NOTE: ENSURE 1P-29 TDAFW PUMP WILL BE TRIPPED BY STEP 7 OF EOP-0 OR MAKE 1P-29 TRIP AT START OF STEP 7 OF EOP-0.

BOP SRO

5.

Verify Feedwater Isolation

6.

Verify Containment Isolation

7.

Verify AFW Pumps - RUNNING RNO: Perform the following:

a. WHEN SI sequence is complete, THEN manually start motor-driven AFW pump.

b. Manually open both steam supply valves to turbine-driven AFW pump.

IF AFW flow NOT established, THEN perform the following: try to start and align P-38A and P-38B.

Aligning of AFW pumps will be unsuccessful.

Transition to CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink.

Event 6: Pressurizer PORV Fails Open on Reactor Trip Cues:

1C04 1C 4-1, 1RC-430 or 431C Pressurizer PWR-Operated Relief Valve Not Shut CT-10 Close PRZR PORV block valve Crew RO 1RC-430 PORV fails OPEN upon reactor trip. After immediate actions are complete, crew can manually attempt to shut PORV. This will be unsuccessful requiring the closing of associated block valve.

EOP 0 Step 20 will also address the closing of the PORV and associated block valve.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 13 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 7: 1P-53 MDAFW Pump sheared shaft and 1P-29 TDAFW Pump Overspeed Communication:

If PAB AO contacted, wait 2 minutes and report the 1P-53 MDAFW Pump motor is spinning but pump is not.

If TH AO contacted, wait 2 minutes and report the 1P-29 TDAFW Pump Overspeed linkage is broken and on the floor in pieces.

BOP BOP Crew should notice failure of 1P-53 MDAFW Pump and investigate.

Crew should notice failure of 1P-29 TDAFW Pump and send an AO to look at resetting pump.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 14 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

CT-43 Establish feedwater flow into at least one SG before RCS bleed and feed is required.

SRO RO/BOP RO BOP CSP-H.1 Unit 1, Loss of Heat Sink

1. Check If Secondary Heat Sink Is Required:

a. RCS pressure - GREATER THAN ANY NON-FAULTED SG PRESSURE - yes

b. RCS hot leg temperature - GREATER THAN 350 ºF - yes

2. Check If RCS Bleed And Feed Is Required:

RNO: Perform the following:

1) Monitor bleed and feed conditions

2) IF any bleed and feed condition occurs, THEN do steps 2.b and 2.c

3) Observe the caution prior to Step 3 and continue with Step 3

3. Try to Establish AFW Flow to at Least One SG:

a. Check SG blowdown and sample isolation:

• SG blowdown isolations - SHUT SG A:

1MS-5958 1MS-2042 SG B:

1MS-5959 1MS-2045

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 15 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

BOP 3 a. Check SG blowdown and sample isolation (cont'd):

SG sample isolations - SHUT 1MS-2083 for SG A 1MS-2084 for SG B

b. Check control room indications for cause of AFW failure and try to restore AFW flow:

1) All AFW suction pressure trips and overspeed trips - NOT ACTUATED

2) Power supply to motor-driven AFW pump - AVAILABLE

3) Turbine-driven AFW pump steam supply valves - AT LEAST ONE OPEN

4) AFW valves - PROPERLY ALIGNED

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 16 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

BOP 3 c. Feed flow to SGs - ESTABLISHED RNO: c. Establish feed flow from the SSG pump(s) as follows:

1)

Ensure adequate power is available. Refer to AOP-22 UNIT 1, EDG LOAD MANAGEMENT for KW ratings

2)

Place selected Stripping Logic Override Switch to the OVERRIDE position

3)

Start Standby Steam Generator Feed Pump(s)

4)

Verify valve alignment:

a)

Ensure Unit 1 valve(s) - Open AF-4023, train A AF-4021, train B b)

Ensure Unit 2 valve(s) - Shut AF-4022, train A AF-4020, train B c)

Manually align valve (s) as necessary to establish flow greater than or equal to 230 gpm 1AF-4012, train A 1AF-4019, train B d)

IF feed flow greater than or equal to 230 gpm has been established, THEN return to procedure and step in effect

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 17 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

Communications:

When asked, the PAB AO waits 2 minutes and reports back 1AF-192 Unit 1 AFW Cross-Connect Valve is stuck shut.

The AO is working on freeing up the valve and will report back if successful.

BOP SRO 3 d. Check total feed flow to S/Gs - GREATER THAN OR EQUAL TO 230 GPM RNO: d. Perform the following:

IF any feed flow to at least one S/G is verified, THEN perform the following: - there is no feed flow IF any feed flow is NOT verified, THEN establish AFW from Unit 2 by performing the following:

1)

Locally open the following vlaves:

1AF-192, Unit 1 AFW Cross-Connect Valve 2AF-192, Unit 2 AFW Cross-Connect Valve

2)

Start Unit 2 motor driven AFW pump AND monitor total flow using Unit 2 indications:

2P-53

3)

Align AFW valve(s) to provide GREATER THAN 230 GPM:

1AF-4074A for S/G A 1AF-4074B for S/G B

4)

IF feed flow has been established, THEN return to procedure step in effect IF feed flow is NOT verified, THEN perform the following:

1). Dispatch operator to locally align AFW valves per ATTACHMENT B and restore AFW flow 2). OBSERVE CAUTION PRIOR TO STEP 4 and go to Step 4

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 18 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

Communications:

When asked, the TH AO waits 2 minutes and reports back all condensate and feedwater piping is intact.

If asked, the TH AO waits approximately 2 minutes and reports back there are no obvious deterrents to manually opening the FRV Bypasses.

SM, if asked for a deviation to NOT open both MFIVs, grant the deviation.

NOTE: Crew may choose to cycle valve partially open to verify availability from the control room.

RO BOP

4.

Stop Both RCPs

5.

Try to Establish Main Feedwater Flow to at least one S/G

a.

Condensate Pumps - at least one running

b.

Maintain hotwell level - Greater Than 5 inches

c.

Condensate and feedwater piping - INTACT

d.

Establish feedwater flow path:

1)

Reset SI

2)

Verify an Instrument Air Compressor running

3)

Open feedwater isolation valves

4)

Ensure feedwater regulating valve bypass controllers in manual and shut

5)

Reset feedwater regulating valve bypasses

6)

Check feedwater regulating valve bypasses - At Least One Capable of Being Opened Manually or Locally

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 19 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

BOP SRO

e.

Main feedwater pumps - At Least One Running RNO: Complete the following:

1)

Locally start main feed seal water pumps

2)

Ensure main feed AC lube oil pumps running

3)

Start one main feed pump

f.

Main feed pump discharge MOV on running pump(s) - OPEN

g.

Establish main feedwater flow:

1)

Throttle open feedwater regulating valve bypass(es)

h.

Verify feed flow to S/G(s):

Indication of main feedwater flow to at least one S/G Level in at least one S/G - RISING

6.

Check S/G levels:

a.

Level in at least one S/G - Greater Than [51%] 32%

RNO: feedwater flow is established so no action taken with RNO

b.

Return to procedure and step in effect. (EOP-0)

Event 5: B feed line ruptures inside containment (contd)

BOP These steps are being continued from EOP 0

8.

Verify ECCS Pumps - RUNNING

9.

Verify Service Water Pumps - RUNNING

10. Verify Containment Accident Fans - RUNNING

11. Verify Component Cooling Water Pumps - ONLY ONE RUNNING

12. Check if Main Steam Lines Can Remain Open

a. Any MSIV valve - OPEN

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 20 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd)

CT-10 Close PZR PORV block valve RO BOP RO BOP RO BOP/RO SRO

13. (CA Step) Verify Containment Spray Not Required

14. Verify ECCS Flow

15. Verify AFW Valve Alignment - Proper Emergency Alignment

16. Verify Proper ECCS Valve Alignment

17. Check RCP Seal Cooling

18. Perform Attachment A, Automatic Action Verification, while continuing with this procedure

19. (CA Step) Check RCS Temperatures

20. Check PZR PORVs and Spray Valves

a. PORVs - BOTH SHUT

b. Normal spray valves - BOTH SHUT

c. Auxiliary spray valves - SHUT

21. Check If RCPs Should Be Stopped

22. Check if SG are Not Faulted RNO: Go to EOP-2 Unit 1, Faulted Steam Generator Isolation

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 21 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Expected Communications: (EOP-0 Unit 1, Attachment A):

Communications: (EOP-0 Unit 1, Attachment A):

When directed to locally check shut RW service water valves, TV-LW-61 and 62, then report both valves are closed.

When directed to locally check CW pump house temperature <105°F, then after five minutes report temperature is 72°F and stable.

BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification A1 Check Containment Spray NOT Actuated A2 Stop Any Boration via the Blender in Progress A3 Ensure The Auxiliary Building Filter/Exhaust Fans - OPERATING A4 Verify Service Water System Alignment A5 Check Miscellaneous Valves - SHUT A6 Check Control Room Ventilation A7 Check Cable Spreading Room Ventilation System - OPERATING A8 Check Computer Room Ventilation System - OPERATING A9 Check AFW Recirc Fans - ONE RUNNING A10 Check Circulating Water Pump House Temperature Less Than 105°F A11 Periodically Check Status of Spent Fuel Cooling Termination Criteria:

When the crew makes the transition to EOP-2, Faulted Steam Generator with CSP-H.1 completed (the crew will have transitioned to EOP-0 upon completion of CSP-H.1), then verify with the Lead Evaluator and take the shift.

• • • END OF SCENARIO ***

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 22 of 25 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS CT-10 Close Pzr PORV Block Valve Critical Task:

Close 1RC-515, T-1 PZR RC-431C Power Operated Relief Isolation valve by completion of step 20.a RNO of EOP-0.

Plant Conditions:

A Pzr PORV that is open.

RCS pressure is less than 2335 psig.

1RC-515, T-1 PZR RC-431C Power Operated Relief Isolation valve can be manually shut.

Cues:

Valve position indication and/or annunciation that the Pzr PORV is open, even after attempts to close it manually from the control room AND Indication and/or annunciation of decreasing RCS pressure AND Indication and/or annunciation consistent with the discharge of Pzr fluid to the PRT o

PRT temperature, level, and pressure o

Tailpipe RTDs Performance Indicator:

Manipulation of controls, as required, to close the block MOV for the stuck open Pzr PORV Valve position indication that the block MOV upstream of the stuck open Pzr PORV is closed Feedback:

Valve position indication that the block MOV upstream of the stuck open Pzr PORV is closed.

Basis:

SAFETY SIGNIFICANCE - Closing the block MOV under the postulated plant conditions constitutes a task that "is essential to safety," because "its improper performance or omission by an operator will result in direct adverse consequences or significant degradation in the mitigative capability of the plant." In particular, the crew has failed to prevent "degradation of any barrier to fission product release." In this case, the RCS fission product barrier can be restored to full integrity simply by closing the block MOV. Therefore, failure to close the MOV also represents a failure by the crew to "take one or more actions that would prevent a challenge to plant safety."

Degradation of the RCS fission product barrier is not initiated by operator action. However, the crew's failure to close the block MOV results in unnecessary continuation of the degraded condition of the RCS barrier.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 23 of 25 CT-43 Establish feedwater flow to SG(s) before bleed and feed is required Critical Task:

Establish feedwater flow into at least one SG before RCS bleed and feed is required.

Plant Conditions:

Extreme (RED path) challenge to the heat sink CSF Plant conditions require SGs as heat sinks At least one SI pump is available AFW flow is not sufficient and cannot be increased Feedwater flow is available but not established from any of the following:

o Main feedwater pumps o

Condensate pumps Indication that RCS bleed and feed is not required Reactor trip and SI Cues:

Extreme (RED path) challenge to the heat sink CSF AND Indication that RCS pressure remains above the pressure of all SGs AND Indication that RCS temperature is above the temperature for placing the RHR system in service AND Indication that at least one SI pump is available AND Indication and/or annunciation that no AFW flow is available after repeated attempts to establish AND Level indication that SG dryout has not yet occurred Performance Indicator:

Manipulation of controls as required establishing feedwater flow into at least one SG Feedback:

Indication of feedwater flow into at least one SG Indication of increasing water level in at least one SG Basis:

SAFETY SIGNIFICANCE - Failure to establish feedwater flow to any SG results in the crew's having to rely upon the lower-priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that fails to prevent "degradation of any barrier to fission product release."

Thus, when the crew fails to simply establish available feedwater flow (as it could, given the postulated plant conditions) before SG dryout occurs, it "necessitates the crew taking compensatory action that would complicate the event mitigation strategy."

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 24 of 25 SHIFT TURNOVER INFORMATION 1.0 PLANT CONDITIONS:

UNIT 1 UNIT 2 Time in core life (MWD/MTU):

16050 6500 Reactor power (%):

75%

28%

Boron concentration (ppm):

120 ppm 1170 ppm Rod height (CBD @):

CBD @ 187 CBD @ 145 Target AFD 2.45

-.27 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:

LCO NOT Met TSAC Required Actions / Completion Time LCO 3.3.1 RPS Instrumentation TSAC 3.3.1.A One or more Functions with one or more required channels or trains inoperable TSAC 3.3.1 K One channel inoperable A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s) or train(s) -

Immediately K.1 Place channel to trip - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or K.2 Reduce THERMAL POWER to < P 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 3.0 EQUIPMENT OUT OF SERVICE:

P-38A SSG Pump for oil change G03 EDG scheduled maintenance 1LT-427 White Pressurizer Level for instrument drift 4.0 PLANNED EVOLUTIONS:

Normal Downpower per OP 3A Power Operation to Hot Standby Unit 1 step 5.2 at 30%/hr.

2015 NRC Exam Scenario 3, Rev. 0 SEG Page 25 of 25 5.0 TURNOVER INFORMATION:

Safety Monitor is Green.

G04 EDG is aligned to 1(2) A06 4160 Safeguards Busses.

G01, G02 and G04 EDGs are guarded equipment.

1(2)P-29 TDAFW Pumps, 1(2)P-53 MDAFW Pumps and P-38 SSG Feed Pump are guarded equipment.

1LT-426 and 1LT-428 Pressurizer Level Transmitters are guarded equipment.

Normal Downpower per OP 3A Power Operation to Hot Standby Unit 1 step 5.2 at 30%/hr.

Clock time is real time and you have the normal shift complement.