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2015 Point Beach Nuclear Plant Initial License Examination Proposed Simulator Scenarios
	ML15070A540
Person / Time
Site:	Point Beach
Issue date:	03/06/2015
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	;
Shared Package
ML14328A661	List: ML15070A500; ML15070A522; ML15070A537; ML15070A540; ML15076A390; ML15076A507; ML15076A510; ML15076A514; ML15076A517; ML15076A521; ML15076A525; NRC-2014-0087, 2015 Point Beach Nuclear Plant Initial License Examination Proposed Examination Transmittal Letter;
References
	50-266/15-301, 50-301/15-301
	Download: ML15070A540 (64)
	v • d • e

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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 1: Shift Service Water Pumps BOP Per 0-SOP-SW-107 Service Water Pump Operations start P-32A and secure P-32B.

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

This evolution should be pre-briefed prior to starting Have AO verify local indications prior to service water pump start and after securing scenario. service water pump.

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

Cues: (will be received during the shift)

CO0B 3.5 Unit 1 Safeguards Equipment Locked Off SRO Declare P-32B Service Water Pump INOPERABLE and declare LCO 3.7.8 Service Communications: Water System NOT MET and enter TSAC 3.7.8.A Restore SW Pump to Operable within 7 days. Declare TRMAC 3.7.7.D One SW Pump Inoperable which directs

When requested, local checks prior to starting P-32F declaring TSAC 3.7.8.A1 not met.

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.

When 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 requarding 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.

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 2: Synchronize to the Grid and Raise Power CREW Briefing on power ascension will be performed in classroom prior to beginning of the scenario.

Communications:

OS will request notifications be given to ATC about Start procedure at step 5.14.3. Step 5.13 will not be signed off until reaching 15%

placing unit online and raising power. SM will power.

acknowledge request and state that notification will be completed.

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

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

Requests for the AO to take logs per Attachment D of OP-1C should be considered completed SAT when b. COMPLETE Section 1.0 of Attachment D, Main Generator Fiber Optic asked for step 5.14.5.b and 5.14.10. After one minute, Vibration Monitoring System Data.

report all readings are 0.7. c. CLOSE Unit 1 Generator Exciter Field Breaker.

When requested, reset Unit 1 Generator Voltage d. RESET Unit 1 Voltage Regulator Panel Alarms at 1E02.

Regulator cabinet 1E02 after 1 minute (OP-1C step 5.14.5.d) Trigger 18.

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 40

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

Communications: 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.

When requested, Maintenance or THAO notifies the 5.14.9 REQUEST Maintenance perform UNIT 1 Voltage Regulator Firing Card Control Room that AC Error Detector indicates 0.0 for adjustments to nullify age related bias shifts such that the AC Error step 5.14.9 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

When requested, TH AO completes Step 5.15.14. pushbuttons) as necessary to rotate the synchroscope 2 to 5 rpm in the Report back completed in 5 minutes. (no triggers not FAST direction.

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

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 2: Synchronize to the Grid and Raise Power CREW 5.15 Closing Generator Output Breaker 5.15.1 WHEN the synchroscope is just before 12:00 o'clock, AND within the Green Communications: 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.

SM completes NP 2.1.5 communications per Steps 5.15.6 and 5.15.11. 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)

SM informs OS, Step 5.15.10, No hold is required 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).

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 2: Synchronize to the Grid and Raise Power 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 Communications: 15% power. (Observe fuel conditioning guidelines of Step 3.3).

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.

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 3: 1HC-135 Letdown Line Backpressure Controller RO/SRO RO identifies CV-135 pressure controller malfunction and takes controller to manual to failure control back pressure.

BOP/RO Addresses ARBs Plant Response:

Controller failure causes letdown flow to lower raising Crew may go to hold on ramp.

letdown pressure causing the letdown line relief valve to lift. Enter AOP 1D to address the malfunction and verify actions taken.

1. (CA STEP) Check RCS leak not in progress.

Cues:

1C04 1C 1-6 Letdown Pressure High SRO Reviews foldout page criteria and Notes

1C04 1C 4-6 Low Pressure Letdown Relief Valve Temp RO/SRO 2. Determine CVCS malfunction - CV-135 pressure control which directs High (This may not be received based on response transition to step 36.

time of the crew)

36. Check LP Letdown Line Pressure Control Valve - Failed

ARP-1-PPCS-004 Letdown Line Flow RO 37. Establish manual control of CV-135 - 250#

Insert TRIGGER 1 at the discretion of the Lead Examiner. a. Place LP Letdown Line Pressure Controller - IN MANUAL

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

If requested to look at 1CV-135 locally report everything SRO 38. Notify Duty Station Manager and I&C Duty and Call look normal and report valve position is about 60% open 39. Return to Procedure and Step in Effect (or equivalent control board position).

Crew The crew will have to keep CV-135 in manual control and discuss how this will be done.

(may review step 37 RNO)

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)

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 3: 1HC-135 Letdown Line Backpressure Controller SRO Crew may also enter AOP-24 Response to Instrument Malfunction.

failure (cont'd) RO 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.

SRO 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 Communications:

If asked, SM will direct maintaining normal Letdown. 8. Check Failure for Technical Specifications or TRM Applicability. - None applicable.

9. Return to Procedure And Step In Effect.

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

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 40

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

1MS-2016, 1HX-1A SG HDR Atmospheric Steam Dump The crew may go to hold on the load ramp.

Control valve will open.

SRO Enter AOP-2A Secondary Coolant Leak Cues: BOP 1. (CA Step) Determine Secondary Leakage Not Hazardous to Personnel or

1MS-2015, A SG ADV valve position indication Equipment

Rising reactor power

Plant Habitability

PPCS alarms

Containment Pressure less than 2 psig Insert TRIGGER 3 at the discretion of the Lead Examiner.

Safeguards bus fault Communications:

Equipment operability

If requested, local inspection of pressure transmitter looks 2. (CA Step) Maintain Plant Within Limits normal after 2 minutes.

Reactor power less than or equal to 100%

RO Communications: BOP

S/G level stable at or near 64%

If SM asked, I&C was notified to troubleshoot and repair

SGFP suction pressure greater than 180 psig PT-468.

Condensate pump motor current less than 185 amps

3. (CA Step) Maintain RCS Tavg RO NOTE: Crew may initially enter either AOP-24 or AOP-

Greater than 540°F 2A.

Less than 577°F

Within 7°F of program Tavg Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 40

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

Containment relative humidity NOTE: IF asked for references, the Shift Technical

Containment sump A level Advisor will provide the following logic diagrams

Containment pressure as referenced in 0-SOP-IC-001-RED page 29.

Sheets #169, #172 and #179 and 0-SOP-IC-002

Containment elevation 66 ft. air temperature in its entirety. And logic sheet (#176) for 1FT-464 5. Check No Secondary Leakage to Atmosphere:

being OOS concurrent with 1PT-468 a. Steam generator safety valves shut Communications: b. Stem Generator atmospheric steam dump vlaves shut

If asked, SM will have OS2 prepare RNO: 1) Manually Shut valve(s) 0-SOP-IC-001 RED to remove 1PT-468 from service. c. Locally check crossover steam dumps shut NOTE: Intent is to NOT take the instrument out of d. No visual or audible indications of secondary leakage service per 0-SOP-IC 001 RED. A package will 6. Check Condenser Steam Dup Valves Shut be made up ahead of time if asked for.

SRO Crew enters AOP-24 NOTE: IF SRO determines the need to enter AOP-21 BOP 1. Identify Failed Instrument - 1PT-468 PPCS Malfunction, The Shift Manager should

2. Check if Failed Instrument is a Controlling Channel - Yes inform OS1 that OS2 will review AOP-21 and take any necessary actions. 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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH Review 0-SOP-IC-002 Technical Specification LCO-Instruments Cross Reference.

(contd)

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:

One channel inoperable, D.1 Place channel in Trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3.3.1.A & D or Be in Mode 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months One channel inoperable, D.1 Place channel in Trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3.3.2.A & D or Be in Mode 3 within 7 hrs and Mode 4 in 13 hrs Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 4: 1PT-468 A S/G Pressure transmitter fails HIGH Actions to swap controlling channel for A S/G pressure transmitter failure.

(contd) ARP 1C03 1E2 2-2 S/G A Feedwater Flow High BOP 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.

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.

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment Crew Crew determines leak inside containment is secondary coolant leak.

SRO Enter AOP-2A Secondary Coolant Leak Plant Response: BOP 7. (CA Step) Determine Secondary Leakage Not Hazardous to Personnel or Containment pressure will rise to above 5 psig SI setpoint Equipment and continue above MSIV isolation setpoint (15 psig).

Plant Habitability

Containment Pressure less than 2 psig Cues:

High Containment Humidity (ARP 1-PPCS-007)

Safeguards bus fault

High Containment Pressure (ARP 1-PPCS-018)

Equipment operability

C01 B 1-4 Sump A Level High RNO:

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

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

b. Enter EOP Network Insert TRIGGER 5 at the discretion of the Lead Examiner.

8. (CA Step) Maintain Plant Within Limits RO

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

9. (CA Step) Maintain RCS Tavg Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (contd) SRO EOP-0 Reactor Trip or Safety Injection And RO 1. Verify Reactor Trip Event 6: First Set of Reactor Trip Pushbuttons will not work

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

2. Verify Turbine Trip - Yes When the crew attempts the SECOND set of 3. Verify Power to AC Safeguards Buses - Yes reactor trip pushbuttons, insert TRIGGER 26

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

SRO Implement Foldout Page Criteria - Faulted SG Isolation Criteria:

CT-1 Manually Trip the Reactor using the second set of push BOP 3. IF any SG pressure trending lower in an uncontrolled manner OR Completely buttons prior to the containment pressure reaching 15 psig.

depressurized, THEN the following may be performed:

Manually actuate both sets of reactor trip pushbuttons

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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS 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)

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (cont'd) 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 Event 8: 1W-1A1 Accident Fan Fails to Auto Start

a. Any MSIV valve - OPEN RNO: Go to Step 13 Event 8: 1P-14B Spray Pump Fails to Auto Start

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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (cont'd) BOP 15. Verify AFW Valve Alignment - Proper Emergency Alignment

16. Verify Proper ECCS Valve Alignment - Valves are proper RO 17. Check RCP Seal Cooling - Not lost BOP 18. Perform Attachment A, Automatic Action Verification, while continuing with this procedure RO 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 SRO RNO: Go to EOP-2 Unit 1, Faulted Steam Generator Isolation Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 40

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

BOP

1. Check Main Steam Isolation

a. Any MSIV valve - OPEN

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

CT-17 Isolate Faulted SG 3. (CA Step) Identify Faulted SG - B S/G is faulted

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

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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 40

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

When directed to locally shut 1P-29 AFP/RW steam

1MS-5959 isolation 1MS-237 and MS trap isolation 1MS-238, then insert trigger 20 and report valves closed after 5 minutes.

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 Communication:

5. Check CST Level - GREATER THAN 4 FEET

Shift Manager maybe requested to contact Chemistry

6. Check Secondary Radiation and RP to check for secondary radiation.

SRO 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)

RO 1. Check If RCPs Should Be Stopped - No Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (cont'd) BOP 2. Check if SGs are NOT Faulted RNO: Check faulted S/Gs Isolated - completed in EOP 2 RO 3. (CA Step) Check Intact SG Levels Communication:

4. Check Secondary Radiation

Shift Manager maybe requested to contact Chemistry and RP to check for secondary radiation. BOP 5. (CA Step) Check Pzr PORV And Block Valves

6. Reset SI

7. Reset Isolation And Lockout Signals RO 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%

SRO Go to EOP-1.1 UNIT 1, SI TERMINATION if S/G is in a dryout condition Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (cont'd) BOP 12. (CA Step) Check if Containment Spray can be stopped

a. Containment spray pumps - ANY RUNNING RO b. EOP-1.3 Unit 1, Transfer to Containment Sump Recirculation - Low Head Injection - NOT IN EFFECT BOP 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 RO 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 BOP 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.

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 40

2015 NRC Exam Scenario 1, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR CREW EXPECTED STUDENT RESPONSE NOTES POS Event 5: 1HX-1B, B SG faults to Containment (cont'd) EOP-1.1 SI Termination SRO Foldout Page Criteria should be referenced BOP 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 RO 4. Check if Charging Flow has been Established - previously done in EOP 1 BOP 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 Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 40

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

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

2. Ensure at least one containment spray pump running.

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

When directed to locally check shut RW service water valves, TV-LW-61 and 62, then report both valves are closed. 4. WHEN containment spray has been actuated for GREATER THAN two minutes, THEN ensure spray additive eductor valve is open on running train.

When directed to locally check CW pump house temperature A2 Stop Any Boration via the Blender in Progress

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

Filename: 2015 NRC Scenario 1 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 36 of 40

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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 1: 1TE-404A Thot fails High RO Recognizes instrument failure for the Yellow channel Thot. Recommends placing rods to MANUAL.

Plant Response: SRO SRO acknowledged recommendation and alarms.

Control rods moving in auto with program pressurizer level RO Charging may be taken to manual. The unit will maintain pressurizer level at full maintaining full power program level. power program level based on the circuit selecting auctioneered high Tavg.

Cues:

BOP Condenser Steam Dumps may be shifted to manual pressure control mode per

Rods moving in auto in the INWARD direction Alarm Response Procedure actions. (1C03 1E2 4-2)

1C03 1E2 4-2 Tavg Steam Dump Alert

1C04 1A 1-7 Automatic Rod Motion SRO Enter AOP-6C Uncontrolled Motion of RCCAs

1C04 1A 3-10 RCS Tavg Deviation RO 1. Check Rod Motion - REQUIRED

1C04 1A 3-11 RCS Tavg High RNO ; No, place rods in Manual

And other annunciators SRO/RO 2. (CA Step) Maintain RCS Tavg Insert TRIGGER 1 at the discretion of the Lead Examiner. RO 3. Check RCS Tavg - At OR Trending to Tref RNO ; No, restore Tavg by manually withdrawing rods per SRO direction.

Communication:

If SM is asked, I&C was notified to troubleshoot and repair 4. Check Control Rods - Above Minimum Insertion Limits TE-404A. SRO 5. (CA Step) Verify AFD - WITHIN LIMITS

6. Check Rod Motion Due to Instrument Failure

7. Go To AOP-24, Response to Instrument Malfunctions NOTE: Crew may elect to enter AOP-24 before/instead of AOP-6C.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 1: 1TE-404A Thot fails High (contd) SRO Crew will also enter AOP-24 Response to Instrument Malfunction.

RO 1. Identify Failed Instrument -1TE-404A Thot.

NOTE: The intent is to NOT remove the channel from service. 2. Check if Failed Instrument is a Controlling Channel - Yes

3. Establish Manual Control as Required: - Take Control Rods to Manual Communication:

Rod control will be placed in MANUAL

If asked, the Shift Manager will have OS2 prepare the 0-SOP-IC-001 YELLOW procedure to remove the failed Charging may be placed in MANUAL instrument from service. 4. Return Affected Parameter(s) to Desired Value(s) - Restore RCS temperature per AOP-6C.

NOTE: IF asked for references, the Shift Technical Advisor BOP 5. Using Attachment A, PPCS Parameters Used to Calculate Reactor Thermal Output. Verify that Failed Instrument is NOT an Input to RTO.

will provide the following logic diagram as referenced in 0-SOP-IC-001-YELLOW page 12, Sheets #177, Channel is listed, but is redundant so RTO is not affected.

178, #179 and #180, as well as 0-SOP-IC-002 in its SRO 6. Remove Failed Instrument Channel From Service per entirety. 0-SOP-IC-001 Routine Maintenance Procedure Removal of Safeguards or Protection Sensor From Service.

NOTE: IF SRO determines the need to enter AOP-21 PPCS RO 7. Return Controls to Automatic if Desired.

Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary SRO 8. Check Failure for Technical Specifications or TRM Applicability actions. 9. Return to Procedure And Step In Effect.

End of evolution: Proceed to next event at Lead Examiner TSAC Description, Required Actions, Completion Times:

discretion preferably after condenser steam dumps are in 3.3.1.A & D Table Function 5 - OTT, and Function 6 - OPT. Place channels manual. After the next event trigger is inserted, it takes in TRIP in 1 hr or Be in Mode 3 in 7 hrs.

approximately 5 minutes for the Charging Pump Motor 3.3.2.A & D Table Function 4.d - Low Tavg input to SLI. Place channel in TRIP breaker to trip. in 1 hr or Mode 3 in 7 hrs and Mode 4 in 13 hrs.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 2: 1P-2A Charging Pump winding ground with RO Crew identifies 1P-2A motor causing the ground alarms and breaker trip.

subsequent breaker trip. SRO Enter AOP-1D, CVCS Malfunction RO 1. (CA Step) Check RCS Leak - Not In Progress Plant Response:

2. Determine CVCS Malfunction - 1P-2A Charging Pump has tripped so go Ground alarm for 1B03 with eventual 1P-2A breaker trip to Step 3.

causing a lowering pressurizer level.

3. Check any Charging Pump Running - one pump will be running 1P-2A Breaker trips

4. Check Charging Flow Stable Cues:

C02 D 3-2 1B03 480V Bus Ground 5. Check Charging Pump Relief - Not Lifting

1C04 1C 3-9 Motor Breaker Trip 6. (CA Step) Check Charging Pump Suction Supply Adequate

1C03 1D 2-1, 1P-1A or B RCP Labyr Seal P Low

7. Check Charging System Response

(possible) 1C04 1C 1-8, Charging Pump Speed Control Trouble RNO: Crew should start the non-running charging pump and restore

1-PPCS-003 PPCS Charging Flow Low parameters to normal.

SRO

Pressurizer level lowering 8. Notify Duty Station Manager

9. Return to Procedure and Step In Effect.

Insert TRIGGER 3 at the discretion of the Lead Examiner.

Communication:

If requested, 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.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 3: B SGTL with Rapid Downpower IMPLEMENT AOP-3 Unit 1, Steam Generator Tube Leak RO 1. (CA Step) Check Safety Injection Not Required Plant Response: 2. (CA Step) Check Reactor Trip Not Required 1RE-232 B Steamline in Alert then Alarm with lowering 3. (CA Step) Check PZR Level - STABLE AT OR TRENDING TO Pressurizer level (may not have an auto charging pump). PROGRAM Cues: RNO: IF PZR level trending lower, THEN perform the following:

RMSASRB CI 1RE-232, Unit 1 B Steamline Monitor a. Control charging and letdown to maintain PZR level

RMSASRB CI 1RE-215, Condenser Air Ejector Gas Monitor b. IF PZR level continues to lower, THEN isolate letdown.

ARP 1C04 1C 2-3 Pressurizer Level Setpoint 4. Check PZR Pressure - STABLE AT OR TRENDING TO DESIRED Deviation PRESSURE

5. Check Reactor Makeup Control Insert TRIGGER 5 at the discretion of the Lead Examiner. BOP 6. Notify DSM, Chemistry, And Implement The Emergency Plan SRO 7. Identify The Leaking S/G - B Communication:

BOP

If RP is requested to perform steam line surveys, then wait 8. Determine Leak Rate (approximately 5 gpm) 5 minutes and report: RO 9. Check Reactor Shutdown Required - yes o 'A' main steam line is at background. SRO o 'B' main steam line is 5 mrem above background. 10. Determine Action Response Based on S/G Leakage:

If requested, SM will notify the Duty Station Manager, a. Reduce Power to < 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and Mode 3 in the next two hours.

Chemistry and implement E-Plan. 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 3: B SGTL with Rapid Downpower (contd) RO 13. Monitor Leakage Every 15 Minutes SRO 14. Direct RP To Perform Surveys And Contamination Evaluations BOP 15. Check Leaking S/G - IDENTIFIED Communication:

NOTE: Steps 16 through 26 may be completed in any order.

If requested, SM will direct RP to perform exposure and contamination evaluations. 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 NOTE: Potential for discussion about TE-404 failure and to trip the plant vice shutdown, if this occurs the SM B S/G should drive the crew to perform an AOP-3 power

1MS-5959 reduction.

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 Communication: 20. Locally Align Low Pressure Trap Header to Condenser.

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

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 36

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

RO 3. Check Rod Control System - IN AUTO

If requested, SM will notify Power Systems Supervisor and complete other NP 2.1.5 notifications. RNO: Perform one of the following:

IF manual rod control desired, due to existing plant conditions, NOTE: Rod Control will need to remain in manual due to THEN operate control rods in manual to MAINTAIN TAVG earlier failure of 1TE-404A. WITHIN 5°F OF TREF.

SRO 4. Select Rate Reduction Method And Reduce Load RO 5. (CA Step) Borate To Maintain Rods Above The Low-Low Insertion Communication: Limit

When directed by crew to start 1P-99A and 1P-99B, MFP 6. (CA Step) Check PZR Pressure - Stable at or Trending to 2235 psig Seal Water Injection Pumps, wait 1 minute then insert

7. (CA Step) Check PZR Level - Stable at or Trending to Program Level Trigger 14, and report the pumps started.

BOP 8. (CA Step) Check Steam Generator Level Controlling - In AUTO RO 9. (CA Step) Maintain RCS Tavg BOP 10. Check Main Feed Pump Seal Water Pump - Running SRO 11. Determine Desired End-Point - Less Than 50% Turbine Load End of evolution: Proceed to next event after power is reduced enough per Lead Examiner discretion.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 4: 1LT-461 A Steam Generator Level Transmitter Crew Acknowledge and respond to receipt of annunciators. Realize feed control issues Fails Low are due to instrument failure and place affected controllers in Manual.

The crew may go to hold on the load ramp.

Plant Response:

With transmitter failure indicated level for controlling channel SRO Crew enters AOP-2B.

fails low causing A FRV to open making actual S/G level rise. RO 1. (CA Step) Maintain Power <100%

BOP 2. Determine Secondary malfunction - FRV response which directs Cues: transition to Step 12.

1C03 1E2 1-2, S/G A Level Setpoint Deviation/Trouble 12. Check Feed Regulating Valve Response - NORMAL

1C03 1E2 1-3, S/G A High Level Channel Alert RNO: a.1) Place affected controller in manual if desires, the Bypass FRV

1C03 1E2 2-3, S/G A Level High should also be placed in manual along with the FRV.

1C03 1E2 4-3, S/G A Low-Low Level Channel Alert a.2) Match feed flow to steam flow

1C03 1E2 3-2, S/G A Feedwater Channel Alert

A S/G level rising a.3) Stabilize S/G level SRO a.4) If transient due to instrument failure go to AOP-24 Insert TRIGGER 7 at the discretion of the Lead Examiner.

Crew enters AOP-24 NOTE: Crew may enter AOP-24 before/instead of BOP 1. Identify Failed Instrument - 1LT-461 AOP-2B. 2. Check if Failed Instrument is a Controlling Channel - Yes Communication: 3. Establish Manual Control as Required: - Take Manual control of feed. The Bypass FRV should also be placed in manual along with FRV.

If requested, SM will inform OS1 I&C was notified to troubleshoot and repair 1LT-461. 4. Return Affected Parameter(s) to Desired Value(s)

BOP 5. Use Attachment A to determine if RTO is affected - RTO not affected NOTE: IF asked for references, the Shift Technical Advisor will provide the following logic diagrams as referenced 6. Remove failed instrument from service per 0-SOP-IC-001 - RED in 0-SOP-IC-001-RED page 21 Sheets #172, #176,

7. Return controls to automatic if desired and #182 and 0-SOP-IC-002 in its entirety.

SRO 8. Check Failed Instrument for Technical Specification OR TRM Applicability Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 4: 1LT-461 A Steam Generator Level Transmitter SRO Review 0-SOP-IC-002 Technical Specification LCO-Instruments Cross Reference.

Fails Low (contd)

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 NOTE: Intent is to NOT take the instrument out of service per

Table 3.3.3-1 item 16 S/G Water Level (NR) (not applicable) 0-SOP-IC 001 RED TSAC 3.3.1.A and D, Place channel in trip (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) or be in MODE 3 in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

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

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

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 36

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

Plant Response: SRO IMPLEMENT EOP-0 Unit 1, Reactor Trip or Safety Injection Rapidly lowering pressurizer level with S/G level deviations. 1. Verify Reactor Trip Available charging will not keep up with leak.

2. Verify Turbine Trip Cues:

1C04 1C 1-2 Pressurizer Pressure High or Low 3. Verify Power to AC Safeguards Buses

1C04 1C 2-3 Pressurizer Level Deviation 4. Check if SI is Actuated

1C03 1E2 1-5, B S/G Level Deviation Implement Foldout Page Criteria - Ruptured S/G Isolation Criteria

B FRV closing

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

Insert TRIGGER 9 at the discretion of the Lead Examiner. 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)

Communication: 5. Verify Feedwater Isolation

If asked, wait two minutes then, PAB AO reports nothing 6. Verify Containment Isolation abnormal for 1P-53 MDAFW Pump. 7. Verify AFW Pumps - RUNNING (See Event 7)

If asked, wait two minutes then, TH AO reports nothing RNO a.: WHEN SI sequence is complete, THEN manually start motor-abnormal for 1P-53 MDAFW Pump breaker 1A52-83. driven AFW pump.

NOTE: Expected operator action will be based on actual S/G IF S/G level is greater than [51%] 32% in any S/G, THEN control feed flow to level when this step is addressed. maintain S/G level.

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

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 8. Verify ECCS Pumps - RUNNING

Start 1P-10A RHR (See Event 6)

9. Verify Service Water Pumps - RUNNING Communication:

Start P-32 F Service Water Pump (See Event 6)

10. Verify Containment Accident Cooling Units - RUNNING

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

Start 1W-1A1 Accident Fan (See Event 6) o 1P-10A RHR Pump 1B52-12A 11. Verify Component Cooling Water Pumps - ONLY ONE RUNNING o P-32F SW Pump 2B52-34B 12. Check If Main Steam Lines Can Remain Open o 1W-1A Accident Fan 1B52-16B 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 SRO 23. Check If S/G Tubes Are NOT Ruptured RNO: Go to EOP-3 Unit 1, Steam Generator Tube Rupture Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd) SRO ENTER EOP-3, Unit 1 Steam Generator Tube Rupture RO 1. (CA Step) Check If RCPs Should Be Stopped

2. Identify Ruptured S/G - (B)

Communication: BOP/RO 3. Isolate Flow From Ruptured S/G(s)

SM acknowledges request if RP is requested to perform a. Shut ruptured S/G(s) MSIV and MSIV bypass valve:

steam line surveys.

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

SM acknowledges request if Chemistry is requested to b. Adjust ruptured S/G(s) atmospheric steam dump controller to 1050 psig standby for sampling.

o 1HC-478 for S/G B

When directed to shut 1MS-237, AFP Radwaste Steam

c. Check ruptured S/G(s) atmospheric steam dump - SHUT Isolation and 1MS-238, Main Steam Trap Header Isolation, wait 5 minutes then insert Trigger 16 and report when the o 1MS-2015 for S/G B (1HC-478) valves are closed. 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 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%

CT-18 Isolate feedwater flow into and steam flow from THEN do step 4.b.

the ruptured S/G before a transition to ECA-3.1 occurs. 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.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 NOTES:

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

NOTE: After cooldown commenced Crew should continue

RCS cooldown should proceed as quickly as possible and should not be through Step 13. 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.

NOTE: BOP may identify that the 1B03 lockout failed to Continue with Step 7.

actuate. No additional actions required.

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%

RO 8. (CA Step) Check PZR PORVs And Block Valves Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd) 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 RO 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 BOP 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE EVENT 5: B SGTL worsens into SGTR (contd) BOP 15. Check Ruptured S/G Pressure Stable Or Rising

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

CT-20 Depressurize the RCS to meet SI termination satisfied:

criteria to prevent steam release from the ruptured S/G beyond 30 minutes. 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 SRO e. OBSERVE CAUTION PRIOR TO STEP 20 and go to Step 20.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 36

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

BOP 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 RO 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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:

RUPTURED S/G LEVEL PZR LEVEL RISING LOWERING OFF SCALE HIGH LESS THAN Raise charging flow Raise charging Raise charging flow OR EQUAL flow Depressurize RCS Maintain RCS and TO [44%] using Step 28.b ruptured S/G(s) 24% pressures equal BETWEEN Depressurize RCS Turn on PZR Maintain RCS and

[44%] 24% using Step 28.b heaters ruptured S/G(s)

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

[52%] 58% pressures equal Reduce charging flow GREATER Reduce charging Turn on PZR Maintain RCS and THAN OR flow heaters ruptured S/G(s)

EQUAL TO pressures equal

[52%] 68%

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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 36

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

When directed to locally check shut RW service water A1 Check Containment Spray NOT Actuated valves, TV-LW-61 and 62, wait two minutes then report both valves are closed. A2 Stop Any Boration via the Blender in Progress

When directed to locally check CW pump house A3 Ensure The Auxiliary Building Filter/Exhaust Fans - OPERATING temperature <105°F, then after five minutes report A4 Verify Service Water System Alignment (BOP may align SW valves -

temperature is 72°F and stable. 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 Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 36

2015 NRC Exam Scenario 2, Rev. 0 SEG 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 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.

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.

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.

Filename: 2015 NRC Scenario 2 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 36

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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 1: High RCS Activity Crew Multiple containment and PAB RMS alarms will come in. The crew will Plant Response: diagnose a high RCS activity and enter AOP-8A.

Fuel failure will ramp in causing multiple RMS alarms in NOTE: Crew to continue while awaiting Chemistry results.

systems associated with the RCS.

SRO 1. Confirm High Reactor Coolant Activity Cues: a. Direct Chemistry to obtain and analyze RCS sample.

1C20 B 1-9, Common Area Radiation Monitor High

b. Check sample results - HIGH ACTIVITY

1C20 C 1-1, Unit 1 Area Radiation Monitor High

1RE-109 RCS Hot Leg Sample line High RO 2. Initiate limited plant evacuation of PAB

RE-116 Demineralizer Valve Gallery High a. Announce message

1RE-106 Sample Room High

b. Sound evacuation alarm

1RE-136 Sample Room High

c. Repeat message NOTE: Insert trigger as soon as the crew takes the watch, due SRO 3. Notify Duty Station Manager and implement E-Plan to build in time required.

4. Perform the Following: - Notify Chemistry and Rx Eng Insert TRIGGER 1 at the discretion of the Lead Examiner. RO/BOP 5. Raise purification flow - additional orifice placed in service, skill of the craft may be used.

Communications: a. Establish maximum allowable letdown purification flow per

SM will get asked to contact Chemistry for sampling. OP-5A, Reactor Coolant Volume Control Acknowledge and direct crew to continue in the procedure. b. Consult with Chemistry and place cation demineralizer in

SM will get asked to notify DSM and implement E-Plan service per OP-5D Part 7, CVCS Demineralizer Operation

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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 1: High RCS Activity (contd) SRO 6. Notify Radiation Protection that radiation levels may increase in PAB AND on Radiation Monitors.

Communications: 7. IF Reactor Engineering Review of chemistry data indicates failed fuel, THEN proceed as follows:

SM will get asked to notify RP that radiation levels may increase in PAB and on area monitors. a. Refer to Technical Specification 3.4.16

SM will get asked if Reactor Engineering review is b. Review logs for any known RCS to Secondary leakage.

complete. State this review is in progress and direct crew to continue in procedure. RO 8. Check Gas Stripper status

SM can respond to OS1 the Unit 2 OS will coordinate the

9. Locally shut Unit 2 Cryogenics valve 2CV-261C completion of the Unit 2 and common actions in steps 8, 9 and 10. 10. Align Gas Decay Tanks SRO 11. (CA STEP) Check if Reactor Shutdown Required.

NOTE: There are minimal crew actions after placing the second orifice in service. 12. Initiate Plant Shutdown , as Required:

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

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 2: 1N43 PR Upper Detector Fails Low RO/BOP Crew will diagnose the failure of N43 and place control rods to manual.

NOTE: Events #2 and #3 should be run concurrently. The SRO Enter AOP-6C Uncontrolled Motion of RCCAs information for the downpower is contained in Event RO 1. Check Rod Motion - REQUIRED

3.

Plant Response:

Change in Turbine Load Outward rod motion due to power mismatch rate of change.

Change in Steam Demand Cues:

1C04 1A 1-7, Automatic Rod Motion

Tavg/Tref mismatch greater than 1.5ºF

1C04 1A 3-2, 1N-41, 42, 43, or 44 Power Range Loss of RNO ; No, place rods in Manual Detector Voltage 2. (CA Step) Maintain RCS Tavg

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

1C04 1A 4-5, Power Range Rod Drop

Greater than 540ºF Communication:

Less than 577ºF

If the crew hasnt started the downpower, the SM should instruct the crew to commence the downpower.

Within 7ºF of program Tavg

3. Check RCS Tavg - At OR Trending to Tref Insert TRIGGER 3 at the discretion of the Lead Examiner.

RNO ; No, restore Tavg by withdrawing rods per SRO direction Communication:

4. Check Control Rods - Above Minimum Insertion Limits SRO

If SM is asked, I&C was notified to troubleshoot and repair

5. (CA Step) Verify AFD - WITHIN LIMITS 1N-43.

PPCS axial flux alarm - Clear NOTE: Crew may elect to enter AOP-24 before/instead of

Control board meters - At Least Three Within Limits AOP-6C.

6. Check Rod Motion Due to Instrument Failure

7. Go To AOP-24, Response to Instrument Malfunctions Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG 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) SRO Crew will also enter AOP-24 Response to Instrument Malfunction.

RO 1. Identify Failed Instrument -N43 Power Range NI

2. Check if Failed Instrument is a Controlling Channel - Yes NOTE: The intent is to NOT remove the channel from service. 3. Establish Manual Control as Required: - Take Control Rods to Manual Communication: 4. Return Affected Parameter(s) to Desired Value(s) - Restore RCS

If asked, the Shift Manager will have OS2 prepare temperature per AOP-6C guidance the 0-SOP-IC-001 BLUE procedure to remove the failed BOP 5. Using Attachment A, PPCS Parameters Used to Calculate Reactor instrument from service. 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.

SRO 8. Check Failure for Technical Specifications or TRM Applicability

9. Return to Procedure And Step In Effect.

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG 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) 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 One channel inoperable. (D.1) Place channel in trip within 3.3.1.D 1 hr. OR (D.2) be in Mode 3 within 7 hrs.

Items: 2a, PR Flux High 2b, PR Flux Low 5, OTT One or more channels inoperable. (S.1) Verify interlock is 3.3.1.S 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 One or more channel inoperable. (R.1) Verify interlock is in 3.3.1.R 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 End of evolution: Proceed to next event at Lead Examiner discretion.

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 Briefing on downpower will be performed in classroom prior to beginning of the scenario Crew will start downpower with Step 5.2.1. RO/BOP Insert rods and/or Borate in addition to adjusting steam demand as needed to establish power decrease.

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG 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 BOP 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 Standby CCW Pump to Auto start.

may start pump per ARB guidance then enter AOP 9B.

Plant Response:

A CCW pump failure will cause motor breaker trip and failure of SRO Enter AOP 9B CCW malfunction B CCW Pump to auto start will cause low flow alarms. BOP 1. Check Component Cooling Pumps - At Least One Running.

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

1C03 1D 2-5 SI Pump Cooling Water Flow Low 2. Maintain Surge Tank Level

1C03 1D 3-7 Motor Breaker Trip

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

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

1C03 1D 1-4 1P-1A RCP Cooling Water Low Flow 4. Check Component Cooling System for Inleakage

1C03 1D 1-5 1P-1B RCP Cooling Water Low Flow 5. Check Reactor Trip - Not Required RO 6. Check RHR Status Insert TRIGGER 5 at the discretion of the Lead Examiner.

BOP/RO 7. Request Chemistry Analyze CCW.

Communications: SRO 8. Notify DSM and implement Emergency Plan.

If asked, the PAB AO reports the A CCW Pump inboard 9. Return to Procedure And Step In Effect motor bearing is hot to the touch.

If asked, the PAB AO will report nothing unusual with the B TSAC Description, Required Actions, Completion Times:

CCW Pump discharge pressure indicator, it reads 125 psig locally. 3.7.7.A One CC pump inoperable. Restore CC pump to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

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.

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Crew Crew determines leak inside containment is secondary coolant leak.

Event 5: B feed line ruptures inside containment SRO Enter AOP-2A Secondary Coolant Leak Plant Response: RO 1. (CA Step) Determine Secondary Leakage Not Hazardous to Containment humidity and pressure rising, containment sump Personnel or Equipment A level rise with no increased indications of RMS to indicate

Plant Habitability there is a primary leak.

Containment Pressure less than 2 psig Cues:

Safeguards bus fault

1-PPCS-007 Containment Humidity alarm

1-PPCS-018 Containment Pressure alarm

Equipment operability

C01 B 1-4 Containment Sump A Level High RNO:

1C03 1E2 2-5, Steam Generator B feed Water Flow High a. Trip Reactor (SRO may actuate SI prior to reaching auto setpoint)

Insert TRIGGER 9 at the discretion of the Lead Examiner. b. Enter EOP Network BOP 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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE SRO EOP-0 Reactor Trip or Safety Injection Event 5: B feed line ruptures inside containment (contd)

RO 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 SRO 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 BOP 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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 34

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

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.

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

Event 6: Pressurizer PORV Fails Open on Reactor Trip Crew 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.

Cues: RO EOP 0 Step 20 will also address the closing of the PORV and associated

1C04 1C 4-1, 1RC-430 or 431C Pressurizer PWR-Operated block valve.

Relief Valve Not Shut CT-10 Close PRZR PORV block valve Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE BOP Crew should notice failure of 1P-53 MDAFW Pump and investigate.

Event 7: 1P-53 MDAFW Pump sheared shaft and 1P-29 TDAFW Pump Overspeed BOP Crew should notice failure of 1P-29 TDAFW Pump and send an AO to look at resetting pump.

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.

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE SRO CSP-H.1 Unit 1, Loss of Heat Sink Event 5: B feed line ruptures inside containment (contd)

RO/BOP 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 RO 2. Check If RCS Bleed And Feed Is Required:

RNO: Perform the following:

1) Monitor bleed and feed conditions CT-43 Establish feedwater flow into at least one SG before RCS bleed and feed is required. 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 BOP 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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE BOP 3 a. Check SG blowdown and sample isolation (cont'd):

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

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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE BOP 3 c. Feed flow to SGs - ESTABLISHED Event 5: B feed line ruptures inside containment (contd)

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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG 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 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 Communications: IF any feed flow is NOT verified, THEN establish AFW from Unit 2 by performing the following:

When asked, the PAB AO waits 2 minutes and reports back

1) Locally open the following vlaves:

1AF-192 Unit 1 AFW Cross-Connect Valve is stuck shut.

The AO is working on freeing up the valve and will report

1AF-192, Unit 1 AFW Cross-Connect Valve back if successful.

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 SRO 2). OBSERVE CAUTION PRIOR TO STEP 4 and go to Step 4 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE Event 5: B feed line ruptures inside containment (contd) RO 4. Stop Both RCPs BOP 5. Try to Establish Main Feedwater Flow to at least one S/G

a. Condensate Pumps - at least one running Communications: b. Maintain hotwell level - Greater Than 5 inches

c. Condensate and feedwater piping - INTACT

When asked, the TH AO waits 2 minutes and reports back all condensate and feedwater piping is intact. d. Establish feedwater flow path:

1) Reset SI

If asked, the TH AO waits approximately 2 minutes and reports back there are no obvious deterrents to manually 2) Verify an Instrument Air Compressor running opening the FRV Bypasses. 3) Open feedwater isolation valves

SM, if asked for a deviation to NOT open both MFIVs, grant 4) Ensure feedwater regulating valve bypass controllers in the deviation. manual and shut

5) Reset feedwater regulating valve bypasses NOTE: Crew may choose to cycle valve partially open to verify 6) Check feedwater regulating valve bypasses - At Least One availability from the control room. Capable of Being Opened Manually or Locally Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE BOP e. Main feedwater pumps - At Least One Running Event 5: B feed line ruptures inside containment (contd)

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 SRO

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

These steps are being continued from EOP 0 Event 5: B feed line ruptures inside containment (contd)

BOP 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 Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 34

2015 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSE RO 13. (CA Step) Verify Containment Spray Not Required Event 5: B feed line ruptures inside containment (contd)

BOP 14. Verify ECCS Flow

15. Verify AFW Valve Alignment - Proper Emergency Alignment

16. Verify Proper ECCS Valve Alignment RO 17. Check RCP Seal Cooling BOP 18. Perform Attachment A, Automatic Action Verification, while continuing with this procedure RO 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 BOP/RO 21. Check If RCPs Should Be Stopped CT-10 Close PZR PORV block valve SRO 22. Check if SG are Not Faulted RNO: Go to EOP-2 Unit 1, Faulted Steam Generator Isolation Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 34

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

When directed to locally check shut RW service water A3 Ensure The Auxiliary Building Filter/Exhaust Fans - OPERATING valves, TV-LW-61 and 62, then report both valves are closed. A4 Verify Service Water System Alignment

When directed to locally check CW pump house temperature <105°F, then after five minutes report A5 Check Miscellaneous Valves - SHUT temperature is 72°F and stable.

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 after completing CSP-H.1, then verify with the Lead Evaluator and take the shift.

- - END OF SCENARIO ***

Filename: 2015 NRC Scenario 3 SEG.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 34

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