ML040120768

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Draft - Section C Operating
ML040120768
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 12/08/2003
From: Christman R
Entergy Nuclear Northeast
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-286/03-303
Download: ML040120768 (89)
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Text

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR

~~

TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 1 LESSON NO.: NIA APPROXIMATE TIME FOR INSTRUCTION: 75 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide
2. Attachment 1, Simulator Exercise Summary
3. Attachment 2, Simulator Documentation Record
4. Attachment 3, Scenario Objectives
5. Attachment 4, Shift Turnover

~~~~~

~

LESSON

REFERENCES:

1.
2.

ONOP-FWC-1, Instrument Failures

3.
4.
5.
6.

POP-3.1, Plant Shutdown From 45% Power ONOP-TG-1, Excessive Load Increase or Decrease E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation E-3, Steam Generator Tube Rupture REMARKS:

SUBMITTED:

DATE:

I EXERCISE: NRC Simulator EX^ Scenario 1 SCENARIO NRC1 Total Malfunctions (5-8/scenario):

Prior to EOP Entry:

1. Rapid Load Decrease
2. Pressurizer Level Channel Failure
3. Turbine Control Valve Failure
4. Turbine Trip/Automatic Reactor Trip Failure After EOP Entry (1 -2/scenario):
1. Fail 32 MSIV Open
2. Steam Generator Tube Rupture
3. Faulted Steam Generator Abnormal Events (2-4kcenario):
1. Turbine Control Valve Fails Closed Major Transients (l-2/scenario):
1. SGTR
2. Faulted Steam Generator EOPs enteredhequiring substantive actions (1 -2/scenario):
1. E-0
2. E-2
3. E-3 EOP Contingencies requiring substantive action (0-2/scenario):

N/A Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

75 minutes EOP run time (40-70% of run time):

70%

Critical Tasks (2-3/scenario):

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ES-301 2of2 CT ##

Technical Specifications referenced during test (l/scenario):

1.

Description IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1 of2 SIMULATOR SET-UP

1.

Perform IC reset

2.

Perform Simulator Check List

3.

Initialize Simulator to 50% Power IC.

4.

Block Automatic Reactor Trip on Main Turbine Trip: RLY PPL438 2,O,D (Repeat for PPL439, 440, and 441)

5.

Insert Main Turbine Bearing Failure on #2,3, and 4 Bearings: PLP TSI12 2.5,0,O,D (#2); PLP TSI13 5.4,0,O,D (#3); PLP TSI14 6.9,0,O,D (#4)

6.

Fail 32 MSIV OPEN: AOV SGN2 4,O,D

7.

Place 31 ABFP in PULLOUT and Stop Tag IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATI'ACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

2 of2 TIMELINE AND EXAMINER ACTIONS FOR SIMULATION EVENT A

B C

D E

F INIT CUE CONSOLE ENTRY SYMPTOMS I CUES I DESCRIPTION NfA N/A Continue Plant Power Reduction per POP-3.1 Lead Evaluator Direction Lead Evaluator Direction Lead Evaluator Direction Entry Into E-0, Reactor Trip Or Safety Injection Entry Into E-3, Steam Generator Tube Rupture Controlling Pressurizer Level Channel Fails High Rapid Load Decrease (32 Turbine Control Valve Closure)

Turbine Trip/Automatic Reactor Trip Blocked SGTR (32 Steam Generator)

Failure of MSIV to Close Faulted Steam Generator (34 Steam Generator)

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of22 TIME EVENTEXPECTED OPERATOR RESPONSE:

A

1.
2.
3.
4.
5.
6.

COMMENCE POWER REDUCTION IN ACCORDANCE WITH POP-3.1 Initiate generator load decrease at the desired rate utilizing governor control.

Adjust FW Regulator manual set point to null manual-auto deviation during the load reduction When generator load is approximately 4OOMwe and 2 MBFPs are in service, then place 1 MBFP in standby per SOP-FW-000 1, Main Feedwater System Operation BORATE as necessary to maintain control banks above insertion limits MAINTAIN delta flu within the target band.

When turbine power is approximately 40%, then veri@

Power Below C-20 Lamp illuminates Instructor Note: Continue with the next event after one MBFP is shutdown, and a power reduction of 1-3% is achieved, or at the discretion of the Lead Evaluator.

SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

B

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
12.
13.

PRESSURIZER LEVEL CHANNEL FAILURE Enters ONOP-RPC-1, Instrument Failures Verify the following controls: Turbine Load, Rod Control, P U R pressure control, PRZR level control-Notices NOT normal, MBFP speed, S/G levels Takes RNO actions Perform:

Places PRZR level control system in Manual, and Controls pressurizer level Checks RCS Instrumentation-RCS Loop Temps-Normal, delta T set points-Normal, RCS Loop Flow-Normal, Pressurizer Instrumentation-NOT Normal, enters, Pressurizer Level Channel Failures Operates PRZR heaters as necessary to maintain PRZR between 2205psig and 226Opsig Ensures Charging Pump speed controller is in MAN, controls PRZR level to maintain program level.

Place L/460A, LEVEL DEFEAT switch for the failed instrument to the required position Perform:

Operates Level Defeat Switch Transfer Charging Pump speed control back to AUTO per SOP-CVCS-2, Charging Seal Water and Letdown Control Perform: Transfers charging to AUTO Reset Pressurizer Heaters, Modulating-AUTO, 1 Backup-ON, 2 Backups-AUTO Place PRZR level recorder to an unaffected loop Check redundant bistable lights for failed instrument are extinguished.

Place bistable trip switches for the failed instrument in the tripped (up) position, and verify the bistable status lights are illuminated, ensure Pressurizer High Level Channel Trip annunciator is lit Reference Tech Spec for Instrumentation failure SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 22 Lead Evaluator can move to next event once CRS recognizes a Tech Spec nee& to be referenced, a follow up question post scenario can exumine Tech Spec knowledge Comments:

IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

C

1.
2.
3.
4.
5.
6.
7.

Comments:

MAIN TURBINE CONTROLVALVE FAILS CLOSED Booth Operator: Insert Turbine Control Vdve Failure Perform actions of ONOP-TG-1Excessive Load Increase or Decrease.

Verify Reactor Power less than 100%

Check Turbine Control Stability Check Reactor Plant Stability Perform:

Places Rod Control in Manual, Verifies PORV Block Valves Open, Matches Tavenref, Places HP Steam Dumps In Pressure Mode if Steam Header Pressure is not Stable Verifies All Turbine Stop Valves Are Open Checks Turbine Control Valve Status: It is noted that 1 Control Valve has failed closed.

Perform:

Begin a power reduction to less than 35OMwe.

Ensure Requirements of Tech Spec are met Perform:

Verify TS 2.1,2.3 and 3.1.B are met or Borate or Dilute if required to restore Delta Flux in target Band INSTRUCTOR NOTE: Continue with the next event after Technical Specifications are addressed, or at the discretion of the Lead Evaluator, IN ANY EVENT, INITIATE THE NEXT EVENT BEFORE P-8 CLEARS AT 35% POWER.

SM STACRS RO BOP IP2 Sim Eval Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 22 TIME EVENTLEXPECTED OPERATOR RESPONSE:

C TURBINE TRIP/FAILURE OF AUTOMATIC REACTOR TRIP Booth Operator: Insert 21 LP Turbine Blade Failure followed by Loss of Condenser Vacuum

1.

Identifies the Main Turbine has tripped.

Checks:

Main Turbine Stop and Control Valves are CLOSED

2.

Verifies the Reactor has Tripped.

Checks:

Reactor Trip Breakers - are NOT OPEN Neutron Flux - is NOT decreasing Rod Bottom Lights - are NOT LIT Rod Position Indicators - are NOT at ZERO Performs:

MANUAL Reactor Trip is directed and performed.

3.

Transition to E-0, Reactor Trip or Safety Injection WRIFYAUTOM4TICACTIONSAS INITUTED BY THE PROTECTIONAND SAFEGUARDS SYSTEMS (CT #1)

SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP D

STEAM GENERATOR TUBE RUPTURE Booth Operator: Insert SGTR on 32 Steam Generator E-0, REACTOR TRIP OR SAFETY INJECTION

1. Verify Reactor Trip Checks:

Reactor Trip Breakers - OPEN Neutron Flux - DECEASING Rod Bottom Lights - LIT Rod Position Indicators -AT ZERO Performs:

MANUAL Reactor Trip is performed if not previously accomplished.

INSTRUCTOR NOTE: This is a Critical Step if not previously performed (CT#l)

2. Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED Turbine Control valves - CLOSED

3. Verify that all 480V Buses are energized by Offsite Power Checks:

Bus Status Comments:

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7 of 22 TIME EVENT/EXPECTED OPERATOR RESPONSE:

4.
5.
6.
7.
8.
9.

Check if SI is actuated Checks:

SI annunciator - LIT SI System pumps - RUNNING Perform:

SI is Manually initiated if not already in service based on lowering pressurizer level, and pressure.

V w

total AFW flow is greater than 365gpm, and controls feed flow to maintain S/G NR levels between 9% and 50%

Perform:

Notes 3 1 ABFP is tagged BOP Operator performs RO-1 (BOP EOP Actions)

Verify Feedwater Isolation-Both MBFPs-Tripped, MBFP Discharge Valves-Closed, Main and Bypass FRVs-Closed, S/G Blowdown Isolation Valves-Closed Verify SI Flow-Verifies RCS Pressure <165Opsig, Checks for HHSI pump flow Verifies:

Verifies SI flow adequate for pressure Veri@ Containment Spray is not required Checks: Verifies Containment Pressure is <22psig

10. Check RCP Seal Cooling Checks: Checks RCP Bearing Flow Low Alarm, and Thermal Barrier Low Flow Alarm SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 1.doc

SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

1 1. Establish Charging flow Perform: Checks RCS Pressure >325psig, verifies CCW cooling for Charging Pump, Checks HCV-142 Fully Open, CH-AOV-204B-Open, Opens CH-LCV-l12B, and Closes CH-LCV-l12C, Starts 1 Charging Pump in Manual, Raises flow to ensure RCP Seal Injection Available

12. Check RCS Tave Checks: Verifies RCS Tave is stable at or trending to 547 degrees F
13. Check if RCPs Should Be Stopped Checks: Determines RCPs should not be stopped at this time
14. Check PRZR PORVs, Safety Valves, and Spray Valves Checks: Determines all are closed and functioning properly
15. Determine if S/Gs are Faulted Checks: No Fault is Indicated
16. Determine if S/G Tubes are Ruptured Perform: Recognizes S/G Level response is not correct for 32 S/G-Transitions to E-3 Steam Generator Tube Rupture7 SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

1.
2.
3.
4.
5.

E-3, STEAM GENERATOR TUBE RUPTURE Booth Operator: Insert Steam Break Inside Containment on 34 Steam Generator INSTRUCTOR NOTE: The Steam Break will require transition to E-2 when identified from the E-3 Fold-Out Page or from step 6 with a return to E-3 after completion of E-2 Obtain correct procedure-E-3, Steam Generator Tube Rupture Check if RCPs Should be Stopped Checks:

SI pumps running RCS Subcooling <32F (73F)

Determines RCPs do not need to be stopped INSTRUCTOR NOTE: This is a continuous action step Identifl Ruptured SG(s)

Checks:

Unexpected rise in any SG narrow range level High radiation from any SG sample High radiation on and S/G Steamline Adjust ruptured SG Atmospheric steam dump controller maintain 1040 psig Perform: Controller is adjusted so ADV lifts at 1040 psig Check ruptured SG atmospheric steam dump valve -

CLOSED Checks:

SG Atmos verified closed SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 22 SM STACRS RO BOP TIME EVENTLEXPECTED OPERATOR RESPONSE:

6.

Check that 32 and 33 S/Gs are intact Performs:

Closes MS-4 1

7.

Verify blowdown is isolated fkom 32 S/G Checks: Verifies S/G blowdown isolation

8.

Dispatch NPO to locally isolate ruptured S/G Performs: CRS dispatches NPO to complete the step

9.

Ensure ruptured S/G steam line valves are closed Performs: Shuts 3 1,33,and 34 MSIVs and MSIV Bypass valves, Completes Attl, Alternate S/G Isolation Method, Uses intact S/G atmospheric dump valves to dump steam.

10. Check ruptured S/G is isolated fkom at least one intact S/G Checks: There is at least 1 S/G isolated from the ruptured S/G Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of22 TIME EVENTEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

11. Check Ruptured SG(s) Level Checks:

Narrow range level >9% (14%)

Performs:

Stops feed flow to 22 SG when NR level >9% (26%)

IDENTIFYAND ISOLATEA RUPTURED STEAM GENERATOR (CT #3)

12. Check PRZR PORVs and Blockvalves Checks:

Power available to block valves PORVs CLOSED Block Valves - OPEN INSTRUCTOR NOTE: This is a continuous action step

13.

Check if any SG is Faulted Checks:

Any SG pressure decreasing in an uncontrolled manner or completely depressurized Determination:

A transition to E-2, Faulted Steam Generator Isolation required at this step or fiom Foldout Page.

Comments:

IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 AmACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 22 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

E

1.
2.
3.
4.
5.
6.

Comments:

E-2, FAULTED STEAM GENERATOR ISOLATION Check MSIV(s) Of Affected SG(s) CLOSED Checks:

Affected S/G MSIV position Perform:

Verifies 34 S/G MSIV is closed from a previous step.

Check If Any SG Secondary Pressure Boundary Is Intact Checks:

Any S/G pressure stable or increasing-Recognizes this is met Identify Faulted SG(s)

Checks:

S/G pressures in all SGs -ANY decreasing in uncontrolled manner or completely depressurized-recognizes 34 S/G is faulted Isolate Faulted S/G Performs:

Isolates 34 S/G-Main and Bypass Feed, AFW, S/G Atmospheric Dump, S/G Blowdown, S/G sample lines, MSIV upstream traps IDENTIFYAND ISOLATEA FAULTED S T W GENERATOR (CT #2).

Check Secondary Radiation-Performs:

Steps leads to a transition back to E-3, Steam Generator Tube Rupture IP2 Sim Eva1 Scenario l.doc

1 EXERCISE: NRC EX^ Scenario 1 SCENARIO NRC1 I AlT'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 13 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

E-3, STEAM GENERATOR TUBE RUPTURE Continued from initial entry of E-3

14.

Check Intact SG Levels Checks:

Narrow Range SG level >9% (26%) or responding normally in all intact S/Gs Performs:

Controls feed flow to maintain intact S/Gs between 9%

(26%) and 52%

INSTRUCTOR NOTE: This is a continuous action step

15. Reset SI Check Steps 2-12 of RO-1 (BOP Actions) are complete Perform:

Press both SI reset buttons on panel SBF-2 Check:

SI Actuated Light Off

16.

Reset Containment Isolation Phase A and B Perform:

Place switches in close for 200A, 200B, 200C Press Phase A Reset Buttons Press Phase B Reset Buttons SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 14 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

17.
18.
19.
20.

Establish Instrument Air to Containment Checks:

Inst Air Low Press alarm clear on panel SJF Perform:

Depress Inst Air reset button 28 on SMF Open IA-PCV-1228 Determine if RHR Pumps Should be stopped Perform:

Stops Both RHR Pumps Check Ruptured Steam Generator Pressure is greater than 4OOpsig Check Ruptured S/G Pressure will be greater than 4OOpsig Initiate RCS Cool down to the RCS temperature based table in step 13 Perform:

Fully opens 3 1,33,34 S/G Atmospherics Stops cool down at the required temperature and maintains CETs less than the required temperature from step 13 COOL DOWN TO ESTABLISH RCS SUBCOOLING MARGIN WITH A SGTR (CT #4 Terminate Scenario when Cooldown completed.

Comments:

SM STACRS RO BOP IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 15 of 22 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

EMERGENCY PLAN

1.

Classifies event as an ALERT (3.1.2)

Comments:

IP2 Sim Eva1 Scenario 1,doc

EXERCISE: NRC Examination Scenario #1 ATTACHMENT 3 - SCENARIO OBJECTIVES SCENARIO NRC1 1of1 TERMINAL OBJECTIVES ENABLING OBJECTIVES IP2 Sim Eval Scenario 1.doc

ATTACHMENT 4, SHIFT TURNOVER 1of1 Watch Crew Turnover Sheet:

Datemime:

TODAY RCS Temp:

553°F RCS Press:

2235 psig PZR Level:

41%

RCS Total Leakage:

0.2 gpm RCS Unidentified 0.2 gpm Leakage:

Condition:

YO Power:

MW Gross:

River Water:

Boron Conc:

Rod Position:

Power Ops 50%

Xenon:

Equilibrium EFPD:

PZR Press Control:

Channel 1 PZR Level Control:

Channel 2 Service Water:

3 Header Ops Risk Assessment:

Daily Risk Factor:

Plant Equipment Status:

1.

3 1 ABFP Stop Tagged for ground investigation. 72 Hour LCO in effect for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

2.

Plant Shutdown is in progress in accordance with POP-3.1 to bring Unit off-line and investigate Main Turbine vibration. Turbine Bearings 2,3, and 4 are in an ALERT condition. The Operations Manager has given direction to continue the shutdown.

IP2 Sim Eval Scenario l.doc

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 2 LESSON NO.: N/A APPROXIMATE TIME FOR INSTRUCTION: 55 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide
2. Attachment 1, Simulator Exercise Summary
3. Attachment 2, Simulator Documentation Record
4. Attachment 3, Scenario Objectives
5. Attachment 4, Shift Turnover LESSON

REFERENCES:

1.

REMARKS:

SUBMITTED:

DATE:

EXERCISE: NRC Simulator Exam Scenario 2 SCENARIO: NRC2 Total Malfunctions (5-8/scenario):

Prior to EOP Entry:

1. Controlling Pressurizer Pressure Channel Fails High
2. Loss of Condenser Vacuum
3. Loss of 5A 480 Volt Bus
4. 34 RCP High Vibration.
5. 34 RCP seal Failure After EOP Entry (1-2/scenario):
1. 3 1 HHSI Pump Fails To Start Abnormal Events (24scenario):
1. High Vibration 34 RCP
2. Loss of Condenser Vacuum
3. 34 RCP Seal Failure Major Transients (1-2/scenario):
1. Small Break LOCA EOPs enteredrequirinp; substantive actions (1 -2/scenario):
1. E-0
2. E-1
3. ES-1.2 EOP Contingenclzs requiring, substantive action (0-2/scenario):

N/A Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

55 minutes EOP run time (40-70!?? of run time):

70%

Critical Tasks (2-3/scenario):

I EXERCISE: NRC EX^ Scenario 2 CT #

Technical Specifications referenced during test (l/scenario):

I SCENARIO: NRC2 Description IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario #2 SCENARIO: NRC2 ATIlACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1of1 SIMULATOR SET-UP

1.

Perform IC reset

2.

Perform Simulator Check List

3.

Sim Setup - 100% BOL

4.

Block Auto Start of 3 1 HHSI Pump

5.

Place 33 ABFP in PULLOUT and Stop tag.

6.

Fail 3 1 MBFP Alpha Speed Signal.

TIMELINE AND EXAMINER ACTIONS FOR SIMULATION EVENT INIT CUE CONSOLE ENTRY A

Instructor Directed B

C D

E Instructor Directed Instructor Directed Instructor Directed Instructor Directed SYMPTOMS / CUES / DESCRIPTION Pressurizer Pressure Master Controller fails high.

Tear in Main Condenser Boot (Dogbone)

Loss of 5A 480 Volt Bus 34 RCP High Vibration.

Small Break LOCA IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

A

1.
2.
3.
4.
5.
6.

Controlling Pressurizer Pressure Channel Fails High Perform actions of ONOP-RPC-1, Instrument Failures Verify the following controls: Turbine Load-Stable, Rod Control Stable, PRZR Pressure Control-Normal, P E R Level Control-Normal, MBFP Speed-Normal, S/G Levels-Normal Performs:

Place Master Pressure Controller in Manual, and Control to restore pressure to normal Check RCS Instrumentation: RCS Loop temperatures, RCS delta T set points, RCS coolant loop flow.

Checks:

All parameters are normal Check PRZR instnunentation: PRZR Levels, PRZR Pressures SM STACRS RO BOP Checks:

PRZR Levels and Pressures, and determines that the controlling pressurizer pressure channel has failed high -

Proceeds to Attachment 7 Ensure that the master pressure controller is in Manual and Control to maintain 2235 psig Perform:

If master pressure controller is not already in Manual, it is placed in manual and pressure is controlled at 2235 psig If PI-457 has failed, place PCV-456 in Close If PI-474 has failed, place PCV455C in Close Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 18

7. Place P/455A,Press Defeat switch for the failed instrument to the required position Performs:

Places P/455A to the required position

8. Place delta T Defeat switch for the failed instrument to the required position Performs:

Places delta T Defeat switch to the required position

9. If steam dumps are armed, then reset the steam dumps and place in temp control.

Checks:

Steam dumps should not be armed SOP-RCS-2, Pressurizer Pressure Control

10. Place PC-455K, PRZR pressure Controller in Auto per Performs:

Places PC-455K in Automatic recorder, select a functioning channel 1 1. If the failed instrument was selected to a Pressure or delta T Performs:

Selects recorders to functioning channels listed are extinguished

12. Check all redundant instrument Bistable Status Lights Checks:

Bistables listed in step 10 are extinguished Tripped (up) position

13. Place Bistable Trip Switches for the failed instrument in the Performs:

Appropriate Bistables fiom step 12 are tripped

14. Verify the following annunciators are lit: OTDT Channel Trip or Rod Stop, Pressurizer Low Press Channel Trip, Pressurizer Low Press (SI) Channel Trip Checks:

All annunciators are verified to be lit Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 18 Comments:

15. Troubleshoot and repair the channel
16. Ensure compliance with Technical Specification Table 3.3.2-1 Function 17 IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

B

1.
2.
3.
4.
5.
6.
7.
8.

Loss of Condenser Vacuum Performs actions of ONOP-C-1, Loss of Condenser Vacuum Monitor Turbine to determine if it should remain on-line:

Condenser Vacuum> 25 S, Pressure Differential Between Condensers <3Hg, Turbine Exhaust Hood remained.e 250 degrees F except for 1 time not to exceed 15 min Checks:

Monitors Parameters throughout the loss of vacuum event.

Stop any turbine accelerations or load increases.

Verify Circulating Water Pumps are operating properly.

Checks:

All CW Pumps are operating properly and screens are operating properly.

Direct NPO to verify S JAEs are operating properly Checks:

NPO reports back that the SJAEs are operating properly.

Direct NPO to verify the both MS-PCV-1132, and MS-PCV-1222 are fimctioning normally Checks:

NPO reports back that the above listed valves ARE functioning normally Direct NPO to verify that the SJAE/ Gland Seal Exhaust Condenser loop seal is intact Checks:

The SJNGSEC Loop Seal is intact Direct NPO to check that there is adequate Water Box vacuum.

Checks:

There is adequate water box vacuum.

Verify that CD-FCV-1120, and CD-FCV-1113 are operating properly.

Checks:

Checks that CD-FCV-1120, and CD-FCV-1113 are operating properly.

SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 18

9.
10.
11.
12.
13.
14.
15.

Comments:

Place Priming Jet Hoggers In Service IAW Attachment 1 Performs:

Places Priming Jet Hoggers In Service Direct NPO to verify that HD-LCV-1133 is controlling level in the Gland Steam Condenser Drain Tanks.

Checks:

NPO verifies that HD-LCV-1133 is working properly.

Direct NPO to verig that Gland Sealing Steam Regulators MS-PCV-1211 and MS-PCV-1212 are maintaining Gland Sealing Steam Pressure > 3psig.

Checks:

The Gland Sealing Steam Regulators are working properly and the pressure is > 3psig Direct an NPO to check for proper level in the Condenser Flange Seal Water Head Tank.

Performs:

Reports back that the Condenser Flange Seal Water Head Tank is empty and begins to fill the tank per the RNO actions Checks to see which source of steam is supplying the hoggers and gland sealing steam.

Performs:

Goes to next step since Main Steam is supplying the above listed components.

Directs an NPO to check Services to the MBFPs Checks:

All services are normal to the MBFPs Verify condenser vacuum status.

Performs:

Recognizes that vacuum is still lowering and commences action to reduce turbine load to stabilize condenser vacuum.

Checks:

Receives report that leak must be in the condenser boot, CT-139 is fully open and the Condenser Flange Seal Water Head Tank Level is not recovering.

Examiner Note: Begin N& Event when Turbine Load Has Been Reduced By S%, and Remove Condenser Leak IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 AJTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

C

1.
2.
3.
4.
5.
6.
7.
8.

Comments:

Loss of 5A 480 Volt Bus Performs actions of ONOP-EL-7, Loss of a 480 Volt Bus -

Above Cold Shutdown Check RCP Seal Cooling-Check if a Charging Pump is running, if not start a Charging Pump Verifies:

Charging Pump is running and seal injection is available to RCPs Check Service Water Headers >60 psig-Checks Essential and Non-Essential headers and starts SW pumps as needed Verifies:

Adequate SW pressure and starts an extra SW pump if pressure is in alarm Check Circulating Water Pump Status-Checks that all CW Pumps are running Checks:

Circulating Water is unaffected Check that the in service boric acid pump is running Checks:

In service boric acid pump is running, unaffected.

Check EDG Status-Checks 33 EDG status Checks:

33 EDG is running unloaded Check ABFP Status-Checks if any ABFP is running, maintains S/G level if necessary Checks:

No AJ3FPs are running Checks any waste release in progress-Blocks RCV-014 and Performs:

No release is in progress, and blocks RCV-014 and RCV-018 Checks Service Water Header Pressure between 60 psig and 97.5 psig in the essential and non-essential headers.

Checks:

SW header pressure is recovered since previous step started additional SW Pumps.

RCV-018 in Block SM STACRS RO BOP IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7 of 18

9.
10.
11.
12.
13.
14.
15.

Check Component Cooling Water Status-Check for system alarms, check 3 CCW Pumps running, Verify RCP thermal barrier flow established.

Performs:

31 CCW pump will be lost, a second pump will auto start, need to verify thermal barrier cooling.

Verify Seal Injection flow 6-12 gpm Verifies:

Seal Injection Flow is unaffected Check IA Header Pressure > 90 psig Checks:

IA Header pressure is unaffected Check 480 Volt Bus 5A De-energized Checks:

5A 480 Volt Bus is dead Determine 33 EDG Status-Performs:

Sends an operator to locally shutdown 33 EDG Refer to Tech Specs-3.8.1 Verifies:

Shutdown is required Inspect 33 EDG for problem and Repair 5A 480 Volt Bus Performs:

Initiates actions to repair bus Examiner Note: Begin n d event as Technical Scijkations are being referenced Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of 18 SM STACRS RO BOP TIME EVENTLEXPECTED OPERATOR RESPONSE:

D 34 RCP High Vibration.

1.

Determine Vibration amplitude and trend, Enter ONOP-RCSS, Reactor Coolant Pump Malfunctions Perform:

Implements ONOP-RCS-5

2.

Determine if the affected RCP should be shutdown: Check RCP Seal DP, Check RCP Seal Return, Check RCP Seal Inlet Temperature, Check RCP Seal Outlet Temperature, Check RCP Seal Cooling, Check RCP Vibrations, Check RCP Motor Winding Temperature, Check RCP Upper and Lower motor bearing temperatures, Check CC W supplies Checks:

Determines 34 RCP Vibrations are in Alert, but does not meet trip criteria.

Begin #l Seal Failure After Check of RCP Shufdown Triggem Comments:

IP2 Sim Eva1 Scenario 2.doc

FXERCISE:

NRC EX^ Scenario 2 I

SCENARIO: NRC2 I A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 18 TIME EVENTlEXPECTED OPERATOR RESPONSE:

E 34 RCP #l Seal Leak Response to indications of RCP seal leakage.

Check RCP Seal Return Flow < 6gpm Performs:

Recognizes Seal Return Flow is Failed High, begins RNO Actions as described below

1.
2.

Verify 34 RCP Seal Inlet Temperature is a 2 5 degrees F and Stable, and 34 RCP Seal Outlet Temperature is (235 degrees F and Stable.

Performs:

Recognizes 34 RCP Seal Temperature Parameters are rising, performs RCP Emergency Shutdown as described below.

3.

Pedorm a Manual Reactor Trip and Stop 34 RCP Performs:

Manually trips reactor, and Stops 34 RCP

4.

Close RCP Seal Returnvalve-CH-AOV-261D Performs:

Closes CH-AOV-261D, 34 RCP Seal Returnvalve Continue with E-0, Reactor Trip or Safety Injection.

5.

SM STACRS RO BOP RCP Emergency Shutdown and Isolation of RCPSeal Return. (CY'-1)

Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

F Small Break LOCA Perform actions for E-0, Reactor Trip or Safety Injection

1.

Verify Reactor Trip Checks:

Reactor Trip Breakers - OPEN Neutron Flux - DECREASING Rod Bottom Lights - LIT Rod Position Indicators -.e 20 Steps

2.

Veri@ Turbine Trip Checks:

Turbine Stop valves - CLOSED

3.

Verify 480V AC Buses-All Energized By Offsite Power Checks:

All 480V AC Buses Energized By OfTsite Power

4.

Determine If SI Is Actuated Checks:

Any SI Annunciator Lit or SI Pumps Running, At this time SI should be running, or it will be manually initiated if it is not running via RNO.

5.

Verify total AFW flow-Greater than 365 GPM Checks:

AFW flow is >365GPM Performs:

Controls AFW Flow to raise S/G level to 9% (14%)- 50%.

SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

6.

Direct BOP Operator to Perform RO BOP Actions During EOP Usage Performs:

BOP Performs RO-1

7.

Verify Feedwater Isolation-Check MBFPs tripped, and MBFP discharge valves are closed, Main and Bypass FRVs closed, S/G Blowdown and Sampling is isolated Verifies:

Verifies Feedwater is Isolated

8.

Verify SI Flow-RCS Pressure 4650 psig (2OOOpsig),

HHSI Flow indicated, RCS Pressure -325 psig (650 psig)

Verifies:

Pressure is 4650 psig, but not <325 psig. SI flow is verified. Recognizes 3 1 HHSI Pump failed to start and successfully manually starts it.

9.
10.

Take Actions For Failure Of Automatic SI Equipment (CT# 2)

Verify Containment Spray is not required-Check that Containment Pressure has remained < 22 psig Verifies:

Containment Spray is not required

11. Check RCP Seal Cooling-Verify CCW flow to RCP thermal barrier, and RCP bearings by verifying a l m s are clear for RCP cooling.

Verifies:

RCP Cooling alarms are clear Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 18 TIME EVENTIEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

12.
13.
14.
15.
16.

Check RCS Average Temperature-Verify RCS Tave is stable at or trending to 547 degrees F Verifies:

RCS Tave is lowering Performs:

Stops Dumping Steam, Throttles AFW to minimum to restore S/G level, Closes MSIVs, Checks if RCPs should be stopped-Verify at least one HHSI pump is running, Verify Subcooling 4 2 degrees F (75 degrees F), Stop all RCPs Performs:

Verifies conditions are met and stops all RCPs MOMTOR RCP OPERATION DURING EMERGENCY AND ABNORMAL CONDITIONS (CT#3)

Check Przr PORVs, Safety Valves, and Spray Valves-Checks Przr PORVs closed, Check Safety Valves Closed, Check Przr Spray Valves are Closed.

Checks:

Checks Przr PORVs, &Few, and Spray Valves Closed Determine if S/Gs are Faulted-Any S/G Pressure lowering in an uncontrolled manner or completely depressurized Checks:

S/G is currently not faulted

17. Determine is S/G Tubes are ruptured.- Checks S/G Level response, and abnormal radiation levels Checks:

Determines a S/G Tube Rupture does not exist Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 AlTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 13 of 18 SM STACRS RO BOP TIME EVENTDZXPECTED OPERATOR RESPONSE:

18.

Determine if the RCS is intact-Containment Pressure Pressure, Sump, and Radiation Levels are normal Performs:

Determines RCS is not intact, and Transfers to E-1, Loss of Reactor or Secondary Coolant Comments:

IP2 Sim Eval Scenario 2. d ~

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 14 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

G.

1.
2.
3.

Perform actions of E-1, LOSS OF REACTOR OR SECONDARY COOLANT Check if RCPs Should Be Stopped Checks:

RCS Subcooling "SI pumps running Note: This step should be performed during Eo while monitoring Foldout Page criteria. However, the critical task is met if performed at this step.

MONITOR RCP OPERAITON DURING EMERGENCY AND ABNORMAL CONDITIONS (CT#3)

Determine if S/Gs are faulted-Checks any SIG Pressure lowering in an uncontrolled manner or completely depressurized.

Checks:

Any SG pressure decreasing in an uncontrolled manner or completely depressurized has been previously isolated Check Intact SG Levels Checks:

Narrow Range SG level 9% (14%)- 50%

Performs:

Controls aux feed flow to maintain between 9% (14%) and 50%

SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 15 of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

4.
5.
6.
7.

Reset SI-Check SI Auto action verification-Steps 2-12 of RO-1, BOP Operator Actions During Use of E0Ps-Completed Checks:

RO-1 Steps 2-12 Completed by BOP Performs:

Presses Train 1 and 2 SI Reset Buttons, Checks that SI Actuated Light is Off Reset Containment Isolation Phase A and Phase B-Closes L/D Orifice Isolation Valves, Resets Phase A, and Phase B Performs:

Closes L D Orifice Isolation Valves Resets Phase A Resets Phase B Check Secondary Radiation-Check if a Seismic Event has occurred, Sample all S/Gs for activity, Conduct radiation survey on Steamlines and B/D sample lines, reset S/G Sample valves, check radiation monitors and S/G Levels for indications of a S/G Tube Rupture Checks:

Checks indications above and determines a S/G Tube Rupture is not in progress.

Check Przr PORVs and Block Valves-Check Power Available To BlockValves, Check PORVs Closed, Check PORV Block Valves Open.

Checks:

Performs above checks, PORVs and Blocks in proper position and available.

Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 16 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

8.
9.
10.
11.
12.
13.

Comments:

Establish Instrument Air To Containment-Veri@ IA Low Pressure Alarm Is Clear, Press Reset Instr Air Reset Pushbutton on Panel SMF, Open IA-PCV-1225, Inst Air To Cont Performs:

Reset Inst Air and Open IA-PCV-1225 Check RCP Seal Cooling-Veri@ Seal Injection and Thermal Barrier Cooling in Service Verifies:

Seal Injection and Thermal Barrier Cooling in Service Check CCW for Charging Pump Cooling Available-Checks:

CCW Cooling is Available to Charging Pumps Determine if Charging Flow has been established-Checks either Charging Pump Suction Open, Checks Normal Charging Isolation Valve Open, Check HCV-142 Fully Open, Check ANY Charging Pump Open.

Checks:

Charging and Flow Path Established Determine if SI Should Be Terminated-Check RCS Subcooling, Heat Sink, RCS Pressure, Pressurizer Level Checks:

Either Subcooling, RCS Pressure, or Pressurizer Level will not be met, such that SI can not be terminated.

Determine if the Containment Spray Pump Should be Stopped-Check if any Spray Pump s running.

Checks:

I No Spray Pump should be nmning, RNO sends to next step.

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 17 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

14.
15.
16.
17.

Determine if RHR Pumps Should be Stopped-Check if an RHR Pump is running, and if RCS Pressure is above 325 psig (650 psig) and stable or rising.

Checks:

RHR Pump is running, and pressure is adequate to stop RHR m p s Performs:

Stop RHR Pumps and place in Auto Check RCS and S/G Pressures-Check S/G Pressures Stable or Rising. Check RCS Pressure Stable or Lowering Checks:

Above checks are met Determine if Diesel Generators Should be Stopped-480V AC Buses are powered fi-om Offsite Power, Stop EDGs Performs:

Stops all EDGs Evaluate Plant Status-Initiate Att. 1, Plant Equipment Status Evaluation Performs:

Initiates Att. 1, Plant Equipment Status Evaluation

18. Check if RCS Cooldown and Depressurization is Required-Check RCS Pressure > 325 psig (650 psig)

Performs:

Conditions met, Implements ES-1.2, Post LOCA Cooldown and Depressurization Terminate Scenario upon Transition to ES-1.2, or at the direction of the Lead Evaluator.

Comments:

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Exam Scenario 2 SCENARIO: NRC2 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 18 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

Perform the required actions for an event requiring Emergency Plan Implementation

1.

Monitor CSFSTs SM STACRS RO BOP

2.

Check Fission Product Barriers LossPotential Loss

3.

After FPBs are reviewed check Event Based Categories

4.

Declare the Highest Classification from the Barrier or Event Based Tables Declares and ALERT (3.1.2)

5.

Initiate County, State and NRC Notification Comments:

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 ATTACHMENT 3 - SCENARIO OBJECTIVES SCENARIO: NRC2 1 of1 TERMINAL OBJECTIVES ENABLING OBJECTIVES IP2 Sim Eval Scenario 2,doc

ATTACHMENT 4, SHIFT TURNOVER 1 of1 Watch Crew Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

RCS Total Leakage:

RCS Unidentified Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

Risk Assessment:

TODAY 559°F 2235 psig 41%

0.2 gpm 0.2 gpm Equilibrium 150 Channel 1 Channel 2 3 Header Ops Condition:

Power Ops

% Power:

100%

M W Gross:

995 River Water:

63 "F Boron Conc:

800 Daily Risk Factor:

Plant Equipment Status:

1. 3 1 MBFP Alpha Speed Signal Failure. I&C investigating
2. 33 ABFP Stop Tagged for vibration investigation. 72 Hour LCO in effect for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Maintenance investigating for cause.

IP2 Sim Eval Scenario 2. d ~

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 3 (NEW)

APPROXIMATE TIME FOR INSTRUCTION:

LESSON NO.: N/A 70 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide
2. Attachment 1, Simulator Exercise Summary
3. Attachment 2, Simulator Documentation Record
4. Attachment 3, Scenario Objectives
5. Attachment 4, Shift Turnover LESSON

REFERENCES:

1.

REMARKS:

SUBMITTED:

DATE:

I EXERCISE: NRC Simulator EX=

scenario 3 I

SCENARIO: NRC 3 Total Malfunctions (5-8/scenario):

Prior to EOP Entry:

1. T hot Channel Fails High
2. Loss of the Operating Charging Pump
3. Dropped Control Rod (1 Rod)
4. Turbine Trip < P-8
5. Dropped Control Rods (2 Rods), Manual Reactor Trip
6. Failure of 480V Bus 6A M e r EOP Entry (1 -2/scenario):
1. 3 1 AFW Pump Motor Overload Abnormal Events (2-4/scenario):
1. T hot Channel Fails High
2. Loss of the Operating Charging Pump
3. Dropped Control Rod (1 Rod)
4. Turbine Trip < P-8
5. Dropped Control Rods (2 Rods)

Major Transients (1 -2/scenario):

1. Reactor Trip/ Loss of All Feedwater EOPs enteredhequiring substantive actions (1 -2/scenario):
1. E-0
2. ES-0.1 EOP Contingencies requiring substantive action (0-2/scenario):

FR-H. 1 - Loss of All Feed Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

70 minutes EOP run time (40-70% of run time]:

70%

I EXERCISE: NRC EX^ scenario 3 Critical Tasks (2-3/scenario):

CT #

Task ID Technical Specifications referenced during test (Uscenario):

SCENARIO: NRC3 Description IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Examination Scenario #3 SCENARIO: NRC3 AITACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1of1 SIMULATOR SET-UP

1.

Perform IC reset

2.

Perform Simulator Check List

3.

Sim Setup - 30% BOL

4.

32 ABFP Stop Tagged Due To Damaged Trip Throttle Valve

5.

Rod Drop (1 Rod) Set To Occur When Recovering Rods From T hot Failure

6.

Loss of Bus 6A to Occur Coincident With Manual Reactor Trip TIMELINE AND EXAMINER ACTIONS FOR SIMULATION EVENT INIT CUE A

Examiner Directed B

Examiner Directed C

Upon Rod Pull After A D

Examiner Directed E

Examiner Directed F

Examiner Directed CONSOLE ENTRY SYMPTOMS / CUES / DESCRIPTION T hot Fails High Loss of the Operating Charging Pump Rod Drop Event (1 Rod)

Turbine Trip < P-8 Rod Drop Event (2 Rods), Failure of 480V Bus 6A Loss of 3 1 ABFP on Motor Overload IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of 18 SM STACRS RO BOP EVENTACXPECTED OPERATOR RESPONSE:

A

1.
2.
3.
4.
5.
6.
7.
8.

T Hot Channel Fails High Perform actions of ONOP-RPC-1, Instrument Failures Veri@ the following controls: Turbine Load-Stable, Rod Control Stable, PRZR Pressure Control-Normal, PRZR Level Control-Normal, MBFP Speed-Normal, S/G Levels-Normal Performs:

Place Rod Control in Manual Check RCS Instrumentation: RCS Loop temperatures, RCS delta T set points, RCS coolant loop flow.

Checks:

RCS Loop Tave and T hot have failed high, goes to step 3 Performs the appropriate attachment per table Performs:

Reviews table and selects Attachment 2 Ensure Rod Control is in Manual Performs:

If not already in manual, places rod control in manual.

Match reactor power and turbine load Performs:

May slightly lower turbine load, or raise rods to balance reactor and turbine power Place charging pump speed control in Manual Performs:

Places charging pump speed control in Manual Control charging to maintain PRZR level on program Performs:

Controls charging per Graph RCS-2 Veri@ all redundant TRIP Status Lights for T hot are extinguished.

Verifies:

There are no redundant lights lit Comments:

IP2 Shn Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 18 Comments:

9. Place the Delta T Defeat switch for T hot to the defeat position for the channel Performs:

Defeats T hot for the failed channel to the required position Performs:

Defeats the Tavg Input by placing the Defeat switch into the correct position 1 1. If the Lo Power Rod Withdrawal Stop lamp is out then -

Ensure 2 minutes have elapsed, establish AUTO rod Performs:

Depending on power level the Lo Power Rod Stop may or may not be lit. Operator takes action as described in the

10. Place the T avg Defeat switch for the failed T hot channel control, ensure steam dumps are reset and in Temp Control step above.

Performs:

Returns PRZR level control to automatic in the Tripped (up) position Performs:

Appropriate Bistables fkom step 11 are tripped Verifies:

Verifies bistables are lit per table in step 12

15. Verify the following annunciators are lit-OPDT Channel Tripor Rod Stop, OTDT Channel Trip or Rod Stop, Low Tavg Verifies:

Annunciators listed above are tripped.

16. Troubleshoot and Repair the Channel
12. Restore automatic P E R level control
13. Place Bistable Trip Switches for the failed T hot instrument
14. Ensure the appropriate T hot bistable trip lights are lit IP2 Sim Eval Scenario 3.d;

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATIACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

B 1

2 3

4 5

Loss of the Operating Charging Pump Perform actions of ONOP-CVCS-1, Charging and Letdown Malfunctions Check that Charging Flow is Established-Checks flow is indicated on FI-128B Verifies:

Flow on FI-128B is 0- recognizes Response Not Obtained actions for step 1 are required.

Close Letdown Isolation Valves CH-LCV-459, and CH-LCV-460 Performs:

Closes letdown isolations, orifices should already be shut.

Check P E R level > 19%

Checks:

Pressurizer Level is > 19%

Check VCT Level > 5% and 9%

Checks:

VCT Level is > 5% and 9%

Check that CH-LCV-112B7 CH-LCV-112C7 or CH-288 are open Checks:

Charging is lined up for operation, valves are open Start 1 Charging Pump-Take Pump speed control to manual and adjust to 10-15% (32 or 33 pump), Start 32 or 33 pump, Control charging to maintain RCP seal injection 6-12 gpm Performs:

Starts 32 or 33 charging pump per the above instructions Check that there is not a charging or letdown line leak Checks:

Monitors radiation and sump levels in the Aux Bldg Check that charging flow is estabIished4hecks flow on Verifies:

Flow is indicated on FI-128B FI-128B Comments:

IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4of 18 9

10 11 12 Comments:

Determine Letdown Status-check letdown flow at Ogpm, check that orifice valves are closed, place PCV-135 in output, ensure open CH-AOV-201, CH-AOV-202, CH-LCV-459, CH-LCV-460, Check TCV-149 and CH-LCV-112A in AUTO, Open CH-AOV-200B, and verify L/D flow on FI-134 Performs:

Performs above steps in order to establish Letdown Flow Control Charging and Letdown-Adjust PCV-135 to maintain L/D pressure 225psig-275 psig, adjust TCV-130 to maintain L/D temperature 100-130 degrees F, Maintain RCP seal injection 6-12 gpm, adjust charging and letdown to return Pressurizer Level to program Performs:

Stabilizes charging and letdown as described above and restores PRZR level to program Check parameters that indicate Charging or Letdown leakage Checks:

Checks for abnormal system level or radiation trends Establish TCV-130, PCV-135, and Charging Pump Speed control in Automatic Performs:

When conditions are stable, places controllers in AUTO Examiners Note: Begin Dropped Rod when controllers are restored to automatic or 5 minutes after letdown is restored manual and 50% output, place TCV-130 in manual at 50%

IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

C DroppedRod

1.
2.
3.
4.
5.
6.
7.

Performs actions of ONOP-RC-1, Dropped or Misaligned Rod(s)

Determine if more than 1 Rod has dropped-No more than 1 Rod Bottom Light Lit, No more than 1 IRPI is -30 steps, Turbine is On-Line Verifies:

Only 1 Rod has dropped by IRPI and Rod Bottom Indication, Turbine is on-line Verify Actual Dropped Misaligned Rod by reviewing-AFD, NR-45, Tavg/Tref, QPTR, Power Range Channels, Tavg, CETs, SUR Verifies:

Sees changes in AFD,NR-45, Tavuref, QPTR, Power Range Channels, Tavg Verify Shutdown Margin Verifies:

Initiates Shutdown Margin Calculation Verify only 1 Rod is Misaligned Verifies:

Only 1 Rod is Misaligned Determine if the affected Rod is greater than 20 steps withdrawn Verifies:

Rod is fully dropped, goes to Att 2 Check Power Range rod drop protection channels RESET-Rotate Dropped Rod mode selector to Reset, Rotate switch back to normal, Verify drawer rod drop status lights out, Verify NIS Trip Bypass and NIS Rod Drop Bypass alarms are clear Performs:

Resets Power Range Rod Drop Protection as described above Verify PR channels have not deviated from the Target Flux band Verifies:

Verifies AFD limits not exceeded Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6of 18

8.
9.
10.
11.
12.
13.
14.

Performs QPTR Calculation Performs:

Performs QPTR When rod is repaired, place Rod Control Mode Select Switch to the bank with the dropped rod Performs:

Moves RMCS Switch to the bank of the dropped rod Open Lift Coil Disconnect Switches for all unaffected rods in the affected bank Performs:

Opens appropriate Lift Coil Disconnects Record positions for the affected group step counter, P/A converter reading, and IRPI Performs:

Records appropriate readings If retrieving dropped rod, reset the affected group step counter to 0 Performs:

Resets appropriate group step counter to 0 Veri@ <4 hours have elapsed, then withdraw the dropped rod Performs:

Recovers rod to previous position Reset Group step counter to previous value, Close Lift Coil Disconnects, Reset Rod Control Urgent Failure, Place Rods in Auto when Tave and Tref within 1.5 degrees F, Reset Plant Computer Bank Position Performs:

Above listed actions are performed Examiner Note: Begin NRxt Event when Rods are placed back in automatic Comments:

IP2 Sim Eval Scenario 3.doc

I EXERCISE: NRC EX=

Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

D

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.

Turbine Trip < P-8 Performs actions of ONOP-TG-$,Turbine Trip Below P-8 Veri8 Reactor Power Less Than 35% (P-8 Lit)

Verifies:

Power is less than P-8 Place Rod Control In Manual Performs:

Places rods into manual Veri8 that all MSIVs are OPEN, Steam Dumps are Available, and that a MBFP is running Verifies:

MSIVs are open, Steam Dumps are available and operating, and a MBFp is running Control Feedwater Regulating Valves Performs:

Places FRVs into manual and controls S/G level by matching feed and steam flow.

Check that Main Turbine Stop and Control Valves are closed Verifies:

Main Turbine Stop and Control valves are closed Check 345 KV Mot Oper Disc SW F1-3 is open Mot Oper Disc SW F1-3 is open Verify 6.9 KV Auto Transfer Verifies:

All 6.9KV busses have auto transferred Veri% all 480 Volt safeguards busses are energized All 480 Volt safeguards busses are energized Check Heater Drain Pumps 3 1 and 32 are tripped 31 and 32 heater drain pumps are tripped Maintain S/G Levels between 30% and 50%

Performs:

Manually controls feedwater to keep S/G levels 30%-50%

Verifies:

Verifies:

Verifies:

Comments:

IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of 18 1 1.

Verify Reactor Power is 4 2%

Performs:

Slowly inserts control rods to reduce power to 4 2 %

Verifies :

Charging and Letdown are fwnctioning normally Insert next Event when rods are being inserted, at the dkcretion of the examiner

12.

Check Charging and Letdown Comments :

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 18 SM STACRS RO BOP TIME EVENT/EXPECTED OPERATOR RESPONSE:

E

1.
2.
3.
4.

Multiple Dropped Rods/ Manual Reactor Trip/ Loss of 6A 480 Volt Bus (Bus Loss Linked To Reactor Trip)

Crew Enters E-0, Reactor Trip or Safety Injection May or May Not Enter ONOP-RC-1 Dropped or Misaligned Rods-Orders Reactor trip Due To 2 Dropped Rods Performs:

Orders Reactor Trip and E-0, Reactor Trip or Safety Injection entry.

Recognizes Conditions Requiring A Reactor Trip To Prevent Core Damage (CT#I)

Verify Reactor Trip Checks:

Reactor Trip AND Bypass Breakers - OPEN Neutron Flux - DECREASING Rod Bottom Lights - LIT Rod Position Indicators - < 20 Steps Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED Verify 480V AC Buses-All energized by offsite power Verifies:

Checks status of 480V Buses, recognizes that bus 6A is deenergized.

Performs:

Checks 345KV generator breakers 1 and 3 open Attempt to restore Bus 6A per SOP-EL-1 and SOP-EL-5, however recognizes that Bus 6A has experienced a bus fault Report to Control Room if asked to investigate bus 6A, that the bus has been damaged and will not be recovered for at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Comments:

IP2 Sim Eva1 Scenario 3.doc

1 EXERCISE: NRC EX^ scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

4.

Determine if SI is actuated, or is required per posted operator aid.

Checks:

Any SI annunciator lit SI has not actuated, and is not required per the operator aid Go to ES-O.

1, Reactor Trip Response SI pumps running

5.

SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of 18 TIME EVENTIEXPECTED OPERATOR RESPONSE:

F

1.
2.
3.
4.
5.

Reactor Trip Response/ Loss of All Feed Performs actions in ES-0.1, Reactor Trip Response, and meets requirements to transition to FR-H. 1 Check RCS Average Temperature-RCS Tave stable at or trending to 547 degrees F Checks:

RCS Tave is stable at or trending to 547 degrees F.

Check FW Status-Tave 6 4 7 degrees F, Check Main and Bypass FRVs closed, Verify total AFW flow > 365gpm, Check S/G Blowdown isolated, ensure both MBFPs tripped Checks:

The above requirements are met except AFW flow, operator raises flow from 31 ABFP to 31 and 32 S/Gs to >365 gpm Check if Emergency Boration is required-RCS temp > 500 degrees F, all control rods <20 steps Checks:

Checks the above and determines that emergency boration is not required Insert Loss of 31 ABFP Due To Motor Overload Crew recognizes loss of all feed and transitions to FR-H.1, Response to Loss of Secondary Heatsink Recognizes Loss of All Feed and Transitions To FR-H.1 (CT#2)

Determine if a Secondary Heat Sink is Required-Checks if RCS Pressure is Greater than any non-faulted S/G Pressure, and that any Hot Leg temperature is > 350 degrees F.

Checks:

Determines that heat sink is required SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

6.
7.
8.
9.
10.
11.

Comments:

Prepare to establish AFW flow-Check S/G blowdown isolated, Check CST level > 3ft., Check AFW Pp suction valves open, Checks:

S/G Blowdown is isolated, CST level is > 3&., and AFW suction valves are open Establish AFW Flow using motor driven pumps Performs:

Recognizes that both motor driven pumps are not available and transitions to Attachment 2, 32 AFW Pump Operation Determine 32 AFW Pump Status-Check if 32 AFW pump is running, Check alarm status of 32 AFW pump, transition to step 4.

Performs:

Recognizes that 32 AFW Pump is not available, and continues with Step 4 Stop all RCPs.

Performs:

Stops all RCPs Stops all RCPs To Limit Heat Input During Loss of Heat Sink(CT#3)

Check all MSIVs Closed.

Performs:

Manually closes all MSIVs Try to establish FW flow to any SIG-Verify 6900V Bus 1,2, or 4 energized, Transition to Attachment 3 Verifies:

1,2, and 4 6900V buses are energized, transitions to SM STACRS RO BOP IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 13 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

12.
13.
14.
15.
16.
17.

Check that a Low Pressure source of water is available-Checks that a Condensate pump is running, and ensures that only 1 is running.

Performs:

Stops all but 1 Condensate Pump Block Automatic SI Actuation-Check that SI has not actuated, Place SI block key switches to Defeat for Train A and Train B Performs:

Blocks SI for Train A and Train B Depressurize at least 1 S/G to less than 450 psig to establish feed flow-Manually dump steam from at least 1 S/G at the maximum rate Performs:

Utilizes S/G Atmospherics to dump steam with fully open dump valves. Should use all 4 S/Gs Dispatch NPO to MBFP Discharge valve breakers Performs:

Sends an operator to MCC-36A and MCC-36B Prepare to Align Flow path-Place FW isolation defeat key switches to Defeat.

Performs:

Places l/FWlDA and lFWlDB to defeat Reset SI-Verify SI has actuated Checks:

SI is not actuated, goes to step 7.

Comments :

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 14 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

18.
19.
20.
21.
22.
23.

SM STACRS RO BOP Establish initial feed water conditions-Ensure Bypass FW MOVs-Open, Ensure Main FW MOVs-Open, Crack Open Bypass FW FRVs, Place Main FW FRVs in Manual and Closed Performs:

Performs the above alignment Align Feed water Header-Manually Close MBFP recirc, Open MBFP discharge valves, Open MBFP discharge valve breakers.

Performs:

Performs the above alignment Place Steam Flow and Feed Flow Recorders to Narrow Performs:

Sets up recorders as described above to be able to see condensate flow to S/Gs Control Bypass feed water FRVs to rapidly restore at least 1 S/G level to greater than 9%

Establish Feed water Flow To At Least 1 S/G- (CTM)

Terminate Scenario When Flow Established To At Least I S/G Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 15 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

1.
2.
3.
4.
5.

Perform the required actions for an event requiring Emergency Plan Implementation Monitor CSFSTs Check Fission Product Barriers LossPotentid Loss After FPBs are reviewed check Event Based Categories Declare the Highest Classification fiom the Barrier or Event Based Tables Declares and Site Area Emergency Initiate County, State and NRC Notification Comments:

IP2 Sim Eval Scenario 3.doc

EXERCISE: NRC Examination Scenario #3 ATTACHMENT 3 - SCENARIO OBJECTIVES SCENARIO: NRC3 1of1 TERMINAL OBJECTIVES ENABLING OBJECTIVES IP2 Sim Eval Scenario 3.doc

I ATTACHMENT 4, SHIFT TURNOVER 1of1 Watch Crew Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

RCS Total Leakage:

RCS Unidentified Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

Risk Assessment:

TODAY 559°F 2235 psig 41%

0.2 gpm 0.2 gpm Equilibrium 150 Channel 1 Channel 2 3 Header Ops Condition:

YO Power:

MW Gross:

River Water:

Boron Conc:

Daily Risk Factor:

Power Ops 20%

19OMwe 63 "F 800 Plant Equipment Status:

1. 3 1 MBFP Alpha Speed Signal Failure. I&C investigating
2. 32 ABFP Stop Tagged for repair of damaged trip throttle valve 72 Hour LCO in effect for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

IP2 Sim Eva1 Scenario 3.doc

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 4 (NEW)

LESSON NO.: N/A APPROXIMATE TIME FOR INSTRUCTION: 70 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide
2. Attachment 1, Simulator Exercise Summary
3. Attachment 2, Simulator Documentation Record
4. Attachment 3, Scenario Objectives
5. Attachment 4, Shift Turnover LESSON

REFERENCES:

1.

REMARKS:

SUBMITTED:

DATE:

EXERCISE: NRC Simulator Exam Scenario 4 SCENARIO: NRC4 Total Malfbnctions (5-8/scenario):

Prior to EOP Entry:

1. Heater Drain Pump Trip
2. 1' Stage Turbine Pressure Channel Failure W-412A)
3. RCSLeak After EOP Entry (1 -2/scenario):
1. Large Break LOCA
2. 4 Control Rods fail to insert l l l y
3. Auto SI Failure
4. Failure of ECR (32 RHR Pump Trip)

Abnormal Events (2-4/scenario):

1. Heater Drain Pump Trip
2. lSt Stage Turbine Pressure Channel Failure (PY-412A)
3. RCS Leak Major Transients (1 -2/scenario):
1. Large Break LOCA EOPs enteredrequiring substantive actions (1 -2/scenarioj:
1. E-0
2. E-1 EOP Contingencies requiring substantive action (0-2/scenario):
1. ECA-1.1 Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

70 minutes EOP run time (40-70% of run time):

70%

Critical Tasks (2-3/scenario):

CT ##

Task ID Description

EXERCISE: NRC Exam Scenario 4 Technical Specifications referenced during test (l/scenario):

SCENARIO: NRC4 I

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Examination Scenario 4 SCENARIO: NRC4 AmACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

l o f l SIMULATOR SET-UP

1.

Perform IC reset

2.

Perform Simulator Check List

3.

Sim Setup - 100% BOL

4.

3 1 RHR Pump to Stop Tagged to Megger the Motor

5.

Auto SI Failure

6.

4 Control Rods to stick out on Reactor Trip TIMELINE AND EXAMINER ACTIONS FOR SIMULATION EVENT INIT CUE CONSOLE ENTRY SYMPTOMS / CUES / DESCRIPTION A

Examiner Directed B

Upon Rod Pull After "A" C

Examiner Directed D

Examiner Directed E

Examiner Directed Heater Drain Pump Trip 1 Stage Turbine Pressure Fails Low (ET-412A)

RCS Leak Large Break LOCA-4 Stuck Rods-Auto SI Failure Failure of ECR-32 RHR Pump Trip and Recirc Pump discharge valves 1802A and 1802 B fail IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of 18 SM STACRS RO BOP TIME EVENTlEXPECTED OPERATOR RESPONSE:

A

1.
2.
3.
4.
5.
6.

Heater Drain Pump Trip Perform actions of ONOP-FW-1, Loss of Feed water Check MBFPs-Both Running Checks:

Both MBFPs are running Verifj. The Following Controls-MBFP Speed Control, S/G Levels Verifies:

MBFP Speed Control-Stable All S/G Levels-Stable Check Conditions Normal For the Following-Both MBFPs Running, Heater Drain Pumps Running, Condensate Pumps Running Checks:

Heater Drain Pump was lost transitions to step #5 Check MBFP Suction Pressure-Check > 35Opsig Performs:

MBFP suction pressure is <35Opsig, verifies start of condensate booster pump, Verify open CD-AOV-52 1 Polisher Bypass, Ensure CD-MOV-522 is fully open, Booster Pump Discharge Refer to Attachent 1 to determine load reduction required to maintain plant operation-7OOMwe Performs:

Determines that a power reduction is required to approximately 700 Mwe, limited by MBFP suction pressure.

Reduce unit load in 100 Mwe increments to obtain-MBFP suction pressure > 35Opsig, Steam and feed flow matched, LI-1127, HDT Level 4 0 in.

Performs:

Commences Load Reduction Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 18

7. Determine cause of pump trip and initiate repair Commence N& EventAt The Examiners Cue, As Power Is Being Stabilized Comments:

~~

~~~

~

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 18 TIME EVENTBXPECTED OPERATOR RESPONSE:

B

1.
2.
3.
4.
5.
6.
7.

1 Stage Turbine Pressure Channel Failure (PT-412A)

Performs actions of ONOP-RPC-1, Instrument Failures Verify the following controls-Turbine Load and Rod Control-Stable, P E R Pressure Control and Level Control Normal, MBFP Speed and S/G Levels-Normal Verifies:

Rods are stepping in due to the T ref input fiom the failed instrument, Takes Rod Control to Manual Check Instrumentation for Failure and go to the appropriate step.

Performs:

Determines that la Stage Turbine Pressure has failed low, and transitions to Attachment 12 Transfer Steam Dumps to Press Cont.- Veri@ current set point will not open steam dumps when placed in pressure control, Veri@ Steam Dump controller output is O%, Place Steam Dump control switch to RESET, then place in Press Cont.

Performs:

Follows above listed steps to place Steam Dumps in Pressure Control.

Adjust Steam Dump set point to 1005psig.

Performs:

Sets Steam Dumps to 1 005psig Place AMSAC system in block by placing BS/2MSS400 in UP (Bypass)

If FT-412A has failed, ensure Rod Control is in Manual, Restore T ave within 1 degree F of T ref.

Perform:

Reduce Turbine Load to reduce T ave/T ref error to <1 degree F.

Refer to Tech Spec Table 3.3.2-1 Function 17 Performs:

Refers to Tech Spec Table 3.3.2-1 Function 17 SM STACRS RO BOP Comments:

IP2 Sim Eval Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4of 18

8.
9.
10.
11.
12.

Verify all redundant Bistable Status Lights for the failed instrument are extinguished.

Verifies:

All appropriate redundant bistable lights are extinguished.

Place the Bistable Trip Switches to the failed instrument to the UP position.

Performs:

Places all PT-412A Bistable Trip Switches into the UP position.

Ensure the Bistable Status Lights for the failed instrument are illuminated.

Checks:

Bistable Status Lights for the failed instrument are illuminated.

Verify High Steam Flow SI Channel Trip Annunciator is illuminated Verifies:

High Steam Flow SI Channel Trip Annunciator is illuminated Troubleshoot and Repair PT-412 A Insert Leak in RCS Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATIACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

C

1.
2.
3.
4.
5.
6.
7.

Comments:

RCS Leak Performs actions of ONOP-RCS-7,Excessive RCS Leakage Check PRZR Pressure between 2235 and 2260 psig Performs:

Operate heaters and spray as needed to restore pressurizer pressure. Ensure all heaters are on and spray valves are shut. This is a continuous action.

Monitor P E R level-greater than 19%

Verifies:

This is a continuous action, RNO actions include ensuring pressurizer heaters are off, letdown is isolated, charging pump speed is at minimum, HCV-142 is shut Check if Pressurizer level is stable or rising Performs:

Raises charging flow to maximum, reduces letdown with 45 gpm orifice, starts additional charging pumps, if these are done and letdown isolates on low level, then a Manual reactor trip and SI are called for. In addition, RCP seal injection flow must be controlled.

Monitor RCS leak rate.

Performs:

Computer trend analysis of leak rate is initiated Check CB Pressure relief system is secured Verifies:

No pressure relief evolution is in progress.

Check PORVs for leakage Checks:

No leakage indicated from PORVs based on position, PRT level and Temperature, PORV tailpipe temperatures, and acoustic monitoring Check PRZR Safety Valves for Leakage Checks:

No leakage is indicated from the P E R safeties as indicated by PRT temperature and Pressure, Safety Valve discharge temperatures and acoustic monitors SM STACRS RO BOP IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6of 18

8.
9.
10.
11.

Monitor CCW for indication of a Thermal Barrier Leak.

Checks:

There is no indication of a thermal barrier leak as evidenced by CCW surge tank levels, thermal barrier DE, R-17 A/B, associated annunciators.

Monitor S/Gs for indication of a tube leak.

Checks:

R Air ejector off gas, R S/G Blowdown, R Main Steam Line Rad-All have no indication of a S/G tube leak.

Check Incore Thimble Leak Alarm is clear Checks:

Incore Thimble Leak Alarm is Clear Determine if Leak is in the Containment Building Performs:

R-2,R-7,R-11, and R-12 are all rising, Containment sump and humidity levels are also rising-Determines leak is in Containment.

Insert Next Event When Completed Wdh Step 11 Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

D Reactor Trip! Large Break LOCA SM STACRS RO BOP Crew Enters E-0, Reactor Trip or Safety Injection Checks:

Reactor Trip AND Bypass Breakers - OPEN Neutron Flux - DECREASING Rod Bottom Lights - LIT Rod Position Indicators - < 20 Steps

1. Verify Reactor Trip
2. Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED

3. Veri@ 480V AC Buses-All energized by offsite power Verifies:

Checks status of 480V Buses, all are energized by offsite power.

4.

Determine if SI is actuated, or is required per posted operator aid.

Checks:

Any SI annunciator lit-They are not SI pumps are not running SI has not actuated Performs:

Determines SI is required

5.

Manually Actuate SI Performs:

Manually actuates SI Recognize Auto SI Failure and Manually Initiates SI (CT#I)

Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

6.
7.
8.
9.
10.

Comments:

SM STACRS RO BOP Check AFW Status Checks:

Check total AFW flow is > 365 GPM Performs:

Control feed flow to maintain S/G NR levels between 9%

(14%) and 50%

Direct BOP Operator to perform RO-1, BOP Operator Actions During Use of EOPs Performs:

Directs BOP to commence RO-1 Verify Feed water Isolation-Check MBFPs tripped, Verify MBFP Discharge Valves Closed, Veri@ Main and Bypass FW Isolated, Check S/G Blowdown valves Closed Verifies:

Checks MBFPs Tripped Verifies BFD-MOV-2-3 1 and BFD-MOV-2-32 Closed Verifies Main and Bypass FW MOVs Closed Verifies S/G Blowdown and Sample Isolation Valves are Closed Verifj. SI Flow-Checks RCS Pressure < 1650 psig (2000 psig), Checks flow on HHSI indicators, if RCS pressure is

< 325 psig then verifjr RHR flow is indicated Verifies:

"SI and RHR flow are indicated fiom available pumps (3 1 RHR Pump is out of service)

Check that Containment Spray is not required-Check if containment pressure has remained less than 22 psig, containment spray initiated if required, Phase B has initiated if required, Stop all RCPs if Phase B has initiated Checks:

Containment spray is running and Phase B has initiated Performs:

Stops all RCPs IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 18 SM STACRS RO BOP TIME EVENT/EXPECTED OPERATOR RESPONSE:

11.
12.
13.
14.
15.
16.

Recognizes Loss of RCP Cooling and Stops All RCPs (CT#2)

Check RCP Seal Cooling-Verify CCW flow to RCP thermal barriers Verifies:

RCP Bearing Low Flow alarm, and Thermal Barrier CCW Header Low Flow alarm Establish Charging Flow-Check RCS Pressure > 325 psig (650 psig), and CCW for charging pump is available, align charging flow path, place charging controller to manual, start 1 Charging Pump, adjust speed to maintain minimum required flow for Seal Injection Verifies:

Charging flow should be running in SI mode Check RCS average temperature-No RCP running, check RCS Tcold stable or trending to 547 degrees F Performs:

Tcold should be low due to blowdown and SI flow-Stops dumping steam, throttles AFW to minimum to restore S/G levels, and Shuts MSIVs Check if RCPs should be stopped Verifies:

RCPs are stopped fkom a previous step Check PRZR PORVs, Sdety Valves, and Spray Valves-Checks PORVs, P E R Safety Valves, Spray Valves, and CH-AOV-212 are all closed Verifies:

All P E R PORVs, Safety Valves, Spray Valves, and CH-AOV-212 are closed Determine if S/Gs are faulted-Checks S/G pressures lowering uncontrollably or fully depressurized Verifies:

S/Gs are not faulted Comments:

IP2 Sim Eval Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 18 TIME EVENTLEXPECTED OPERATOR RESPONSE:

17.

Determine if S/G Tubes are ruptured-Checks Air Ejector RAD levels, S/G Blowdown RAD levels, MS Line RAD levels, and S/G Level response Verifies:

Checks above listed parameters, determines no S/G tube rupture exists

18.

Determine if the RCS is intact-Checks containment pressure, containment sump level, and containment RAD levels Performs:

Determines a LOCA exists, and transitions to E-1, Loss of Reactor or Secondary Coolant Transifions to E-1, Loss of Reactor or Secondary Coolant SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 4.doc

1 EXERCISE: NRC EX^ scenario 4 SCENARIO: NRC4 I ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

E Large Break LOCA (Continued), Loss of Emergency Coolant Recirculation Capability Crew Enters E-1, Loss of Reactor or Secondary Coolant Determine if RCPs should be stopped RCPs were previously stopped

1.

Verifies:

2.

Determine if S/Gs are Faulted-Checks any S/G pressure lowering in an uncontrolled manor or completely depressurized Checks:

Determine S/Gs are not faulted, all pressures lowering together with MSrVs shut due to RCS cooling Insert Malfunctwns of 32 RHR Pump and Loss of Power to Recuc Pump Discharge Valves 1802A and 1802B with vaives unable io operate.

3.

Check Intact S/G levels-Check level response normal in all S/Gs and feed with AFW to raise level to between 9%

(14%) and 50%

Performs:

Continues with previous AFW feeding strategy-minimum AFW flow 365 gpm to raise S/G levels Reset SI-Check verification of AUTO SI actions completed, Press both SI reset buttons on panel SBF-2,

Verify SI actuated alarm has extinguished Performs:

Resets SI per the above listed directions

4.

SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

5.

Reset Containment Isolation Phase A and Phase B-Place switches for letdown orifices in close, Reset Phase A and Reset Phase B Performs:

Place switches for letdown orifices in close, Reset Phase A and Reset Phase B

6.

Check Secondary Radiation-Check that no Seismic event has occurred, Direct Chemistry and HP to survey and sample for S/G activity, Reset S/G Sample Isolation, Check R-15, R-19, and R-62A-D for trends and alarms, verify S/G level change does not support a SGTR.

Verifies:

Completes above checks and determines no SGTR is in progress

7.

Check PRZR PORVs and Block Valves-Check power available to block valves, that PORVs are closed, and that block valves are open Checks:

PORVs and Block Valves are lined up and ready for operation

8.

Establish Instnunent Air to Containment-Check that Inst.

Air Low Press alarm is clear, press Instr Air Reset Pushbutton on Panel SMF, Open IA-PCV-1228 Performs:

Restores instrument air to containment by resetting the IA isolation and opening IA-PCV-1228 Check RCP Seal Cooling-Seal injection or Thermal Barrier cooling established Checks:

RCP Seal Cooling was lost during the Phase B Performs:

RCPs previously tripped, closes Thermal Barrier CCW return valves, Isolates seal injection

9.

SM STACRS RO BOP Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 13 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

10.
11.
12.
13.
14.
15.
16.

Comments:

Check CCW for Charging Pump Cooling is available Checks:

CCW flow is available to the Charging Pumps Determine if Charghg flow has been established-Chg Pump suction valves open, normal charging isolation open, HCV-142 fully open, charging pump running Checks:

Charging is established Determine if SI should be terminated-Checks RCS Subcooling > 1 12 degrees F Verifies:

Subcooling requirements are not met to terminate SI Determine if containment spray should be terminated-Check that spray pumps are running and that all 5 FCUs are running, Reset Containment Spray, Stop CS pumps and place in Auto, Close CS Pump discharge valves-866A and 866B, Press Sodium Hyd Cancel Pushbutton, and Closed Spray additive tank discharge valves 876A and 876B Performs:

Determines that CS can be terminated since 5 FCUs are running and takes steps listed above to terminate CS.

Determine if RHR Pumps should be stopped-Check RHR is running, and if RCS pressure is >325 psig (650 psig)

Verifies:

Determines RHR can not be stopped based on low RCS pressure (Note-31 RHR Tagged, 32 RHR Just Tripped)

Determine if Diesel Generators should be stopped-Check 480 VAC buses energized from offsite sources, Dispatch NPO to stop any unloaded EDG and place in AUTO Performs:

Determines that EDGs can be stopped and sends an operator to stop the EDGs and place then in AUTO Evaluate Plant Status-Performs Attachment 1 Performs:

Steps 1,2, and 3 are performed and it is determined that there is a Loss of ECR capability. Transitions to ECA-1.1,

Loss of Emergency Coolant Recirculation IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 140f 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

17.
18.
19.
20.
21.
22.

Comments:

Identification of Loss of ECR (CT#3)

Crew Enters ECA-1.1, Loss of Emergency Coolant Recirculation Check Emergency Coolant Recirc Equipment Available-Consult TSC for availability Checks:

Confirms insufficient Coolant Recirc Equipment Exist, Consults with TSC If RWST Level is 41.5 fi then makeup to the RWST-Refers to SOP-SI-2 to fill the RWST Performs:

Initiates filling the RWST per SOP-SI-2 Check Intact S/G Levels-Checks any NR level >9%

(14%), controls feed flow to maintain 9% (14%) to 50%

Report received from TSC or Local NPO that ii appears that piece of VC test equipment fell into the 32 RHR Pump breaker cubical. There appears to be nothing eke wrong with the pump breaker and no flags have dropped A restart of the 32 RHR pump is recommended Perform:

The Crew successfully starts 32 RHR Pump and returns to E-1, Loss of Primary or Secondary Reactor Coolant Restoration of ECR Capability (CTM)

Continue with Attachment 1, Plant Equipment Evaluation Performs:

Crew has returned to the procedure and step in effect, and continues Att. 1 Check if RCS Cool down and Depressurization is required-Check RCS > 325 psig (650 psig)

Checks:

Due to size of LOCA-Determines further cool down and depressurization is not needed SM STACRS RO BOP IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 15 of 18 SM STACRS RO BOP TIME EVENTEXPECTED OPERATOR RESPONSE:

23.

Determine if Transfer to Cold Leg Recirculation is required-Check RWST < 11.5 feet Performs:

Procedure is in a ~o-~ooP awaiting transfer to Cold Leg Recirculation Requirements. Crew transfers to ES-1.3, Transfer to Cold Leg Recirculation at 11.5 feet in RWST Terminate the scenario upon transition to ES-1.3 Comments:

IP2 Sim Eva1 Scenario 4.doc

EXERCISE: NRC Exam Scenario 4 SCENARIO: NRC4 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 16 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

SM STACRS RO BOP

1.
2.
3.
4.
5.

Perform the required actions for an event requiring Emergency Plan Implementation Monitor CSFSTs Check Fission Product Barriers LossPotential Loss After FPBs are reviewed check Event Based Categories Declare the Highest Classification from the Barrier or Event Based Tables Declares an Alert Initiate County, State and NRC Notification Comments:

IP2 Sim Eval Scenario 4.doc

EXERCISE: NRC Examination Scenario ##4 SCENARIO: NRC 4 ATTACHMENT 3 - SCENARIO OBJECTIVES 1 of1 TERMINAL OBJECTIVES ENABLING OBJECTIVES IP2 Sim Eva1 Scenario 4.doc

ATTACHMENT 4, SHIFT TURNOVER 1of1 Watch Crew Turnover Sheet:

Datemime:

TODAY RCS Temp:

571OF RCS Press:

2235 psig PZR Level:

50%

RCS Total Leakage:

0.5 gpm RCS Unidentified 0.4 gpm Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

Risk Assessment:

Equilibrium 150 Channel 1 Channel 2 3 Header Ops Condition:

YO Power:

MW Gross:

River Water:

Boron Conc:

Daily Risk Factor:

Plant Equipment Status:

1. 3 1 RHR Pump is Stop Tagged For Meggering the Motor Power Ops 100%

900 Mwe 63 O F 1 OOOppm IP2 Sim Eval Scenario 4.doc

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