Text

Final As-Administered Scenarios for the Prairie Island Initial Examination - August 2005
	ML053010262
Person / Time
Site:	Prairie Island
Issue date:	08/08/2005
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	; Nuclear Management Co
References
	50-282/05-301, 50-306/05-301
	Download: ML053010262 (116)
	v • d • e

QF-1030-19 Rev. 4 (FP-T-SAT-30)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # 2005 NRC SCENARIO 1 RPI FAILURE/TURB LOAD CYCLING/

LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK SEG TITLE: IN CONTAINMENT #: SCEN 1 REV. # 0 PROGRAM: INITIAL LICENSED OPERATOR #: P8100 COURSE: INITIAL LICENSED OPERATOR #: P8100 TOTAL TIME: 2 HOURS Developed by: Travis Ouret 3/16/05 Instructor Date Reviewed by:

Instructor Date Validated by:

Validation Lead Instructor Date Approved by:

Training Supervision Date Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 Guide Requirements During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of Training: the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Diagnose and take corrective actions for a failed RPI per C47, Learning SP1319, and C5 AOP5 Objectives: 2. Diagnose and take corrective actions for cycling turbine load per C23 AOP2

3. Respond to a Loss of Cooling Water Header pressure per C47.

4. Diagnose and take corrective actions for a Cooling Water Valve Closure per C47 and 1E-0.

5. Diagnose and take corrective actions for a steam line break inside containment per 1E-0, 1E-2, 1E-1, and 1ES-0.2.

None Prerequisites:

1. Full Scope Simulator Training 2. Operations Management Representative Resources: 3. Lead Evaluator

4. Human Performance Evaluator

5. Comment Recorder

6. Booth Operator (Primary Communicator)

7. Backup Communicator

1. C47013:0407

References:

2. C47013:0507

3. C5AOP4

4. C5 AOP5

5. C23 AOP2

6. C47020-0204

7. C47020-0106

8. C47020-0304

9. 1E-0

10. FRZ.1

11. 1E-2

12. 1E-1

13. 1ES-0.2

14. F3-2 Page 2 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 None Commitments:

This is an evaluation scenario for the 2005 ILT NRC Exam, this Evaluation scenario is based on P9160S-002 Evaluation #24.

Method:

None - Evaluation Scenario Operating Experience:

Initiating Event with Core Damage Frequency:

Related PRA Normal transient (4%)

Information:

Important Components:

11 and 12 AFW pumps 11 and 12 SI pumps Important Operator Actions with Task Number:

None Page 3 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Failed IRPI

2. Turbine CVs Cycling

3. Loss of 11 Cooling Water Pump

4. Turbine Building Cooling Water Valve Closure After EOP Entry:

1. 12 AFW pump auto start failure

2. Steam line break inside containment

3. SI system fails to respond to S signal

4. MSIV auto closure failure Abnormal Events:

1. C5 AOP5; Misaligned Rod, Stuck Rod, RPI Failure

2. C23 AOP2; Malfunction of the EH Control System Major Transients:

1. Loss Cooling Water to Turbine Building Components

2. Steam line break inside containment Critical Tasks:

1. Manually start a SI pump prior to transitioning out of E-0.

2. Establish and maintain minimum required FW flow to the SGs prior to transitioning out of E-0.

3. Isolate the faulted steam generator prior to transitioning out of E-2.

Page 4 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This evaluation can be run from IC-32 (IC-A).

Reactor Power is 100%, BOC

RCS Boron Concentration 1283 ppm.

Adding 10 Gallons Reactor Makeup 3-4 times per shift.

2. The following additional equipment is OOS:

11 TD AFW Pump

Breaker 16-10 SEQUENCE OF EVENTS:

Event 1: Failed rod position indicator

Rod G-7 RPI fails to 0 steps causing a rod at bottom alarm.

Reactor power and Tavg remain normal.

The RPI is declared inoperable.

Action is taken to verify position of the affected rod.

Event 2: Turbine CV cycling

As the CVs cycle, turbine load fluctuatescausing primary and secondary system perturbations.

Action to take manual control of the turbine to stop the fluctuations.

Event 3: Loss of 11 Cooling Water Pump

12, 22 and 121 fail to Auto Start

Action to manually start 121 Cooling Water Pump Event 4: Turbine Building Cooling Water Valve Closure

The Cooling Water Supply Valve to the Turbine Building Closes

Action is taken to Trip the Reactor and Turbine

Action to manually STOP equipment cooled by Cooling Water Event 5: Steam line break inside containment

When the crew trips the reactor a break develops in the steam line from 12 SG.

The only available AFW pump fails to auto start. A manual start is required.

Page 5 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0

Low pressure in 12 SG results in more AFW flow to that SG. This also results in low AFW pump discharge pressure. Throttling of AFW to 12 SG is required to ensure AFW reaches 11 SG and to prevent tripping the pump.

Containment humidity, temperature, and pressure increase.

SG pressure decrease and containment pressure increase cause a S signal.

The SI system does not respond to the S signal. SI pumps must be manually started.

12 SG must be isolated by the crew.

TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

This is an evaluation scenario and as such, tasks are not credited for training and therefore not listed here.

Page 6 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 NOTE:

SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC-32):

Standard IC- A

Mode: 1

Exposure: BOC

Power: 100%

Boron: (CB): 1283 ppm

Temperature: 560°F

Pressure: 2235 psig

Xenon: At Equilibrium

Rods: Bank D step counters at 218, all others at 228

Generator: 561 Mwe Page 7 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

1. SIMULATOR SET UP

a. Perform set up per the Simulator Setup Checklist for IC-A, including entering actions items per the Simulator Input Summary.

b. Perform set up attached to this guide

2. SIMULATOR SET UP

a. Reset the simulator to IC-32.

b. Place the simulator in RUN.

c. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary, to cause the following pre-existing conditions (Relative Order 0):

1) 12 MDAFW pump auto start fails

2) 11 and 12 SI pumps fail to auto start

3) MSIVs fail to auto close

3. COMPLETE TURNOVER:

a. UNIT 1 LPEO / PEO TURNOVER LOG

1) Use Standard IC-A Turnover sheet

b. Verify crew performs walk down of control boards and the reviews turnover checklists.

Page 8 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1 4. WHEN the crew has assumed the duty and at the LEAD / C47013:0407 ROD AT BOTTOM discretion of the Lead Evaluator, enter the failed RO

Refer to C5 AOP4 (May go directly to C5 RPI for rod G-7 (Relative Order of 1, Trigger 1). AOP5)

LEAD / C47013:0507 ROD DEVIATION/SEQUENCING

a. IF directed to perform a flux map per SP-1319, THEN reply that you will get started right RO

Verify cause using ERCS RODS away.

Initiate SP-1319 RO 1C5AOP4 Dropped Rod

b. Allow the crew to hold a brief.

Confirm rod NOT dropped and refer to 1C5AOP5 1C5 AOP5, Misaligned Rod, Stuck Rod, and/or RPI Failure SS

Notify Ops Manager and NRC Resident Inspector

Diagnose the symptoms are indicative of a failed RPI.

SS

Refer to T.S.3.1.7 Condition A (Verify rod position once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months )

Direct SP-1319 to be performed.

Event 2 5. After the crew has adequately addressed Technical C23 AOP2 Malfunction of EH Control System Specifications for the failed RPI and initiated action LEAD

Place turbine in MANUAL to verify rod position, and at the discretion of the SS

Notify System Engineer and/or WIN Team Lead Evaluator, enter the Turbine Load cycling malfunction. (Relative Order of 2, Trigger 2). RO

Maintain Tave at Tref and power <100%

Page 9 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3 6. After the Crew has placed the Turbine in Manual LEAD C47020-0204, Loop A Cooling Water LO Press and at the discretion of the Lead Evaluator, ENTER C47020-0205, Loop B Cooling Water LO Press the malfunction to trip 11 Cooling Water Pump.

Verify Pressure low (Relative Order 3, Trigger 3)

a. If asked to investigate Loss of 11 Cooling

Start available pumps as necessary Water pump, report breaker 13-8 has a 50-G o Crew may start any pump flag.

b. If asked to check the low pressure auto start C47020-0106 11 Cooling Water Pump Locked Out setpoints of the 11 and 22 diesel cooling water LEAD pumps, report both low pressure auto start

Verify Cooling Water Header Pressure restored to setpoints were found set at 52 psig. Normal

c. NOTE: The low pressure auto start of the

Start 12 Diesel Driven CL Pump pumps is 70 psig.

OR

Start 121 CL Pump

d. IF the turbine CV cycling has not resulted in a sufficient reactivity change for RO evaluation, THEN the crew should be SS Tech Specs allowed to initiate a power reduction prior

Enter LCO 3.7.8 Condition A due to failure of the to continuing to the next event. The SM can low pressure auto start of 11 and 22 diesel direct the SS to initiate the power reduction cooling water pumps at 70 psig.

per 3.0.3 if required.

Enter LCO 3.0.3, there is not a condition describing both cooling water pumps failing to

1) If a power reduction is directed or at the auto start.

discretion of the Lead Evaluator, provide a reactivity prediction to the If the crew elects to investigate the low pressure Crew as the Nuclear Engineer. setpoint this action may be delayed until the report is received.

Page 10 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4 7. When the crew has adequately addressed C47, LEAD C47007-0303 Hydrogen and Seal Oil Local Alarm and at the discretion of the Lead Evaluator, ENTER

Dispatch an Operator to investigate.

the closure of the Turbine Cooling Water Header Motor Valve. (Relative Order of 4, Trigger 4).

a. If asked to locally investigate MV-32031, report LEAD C47007-0101 Bus Duct Cooler Cooling Water LO the valve is closed there is no apparent reason Flow for the valve closing.

Dispatch an Operator to investigate.

Monitor bus duct temperature on ERCS C47020-0304 Turbine Cooling Water Header MV-LEAD 32031 CLOSED

Verify position lights on CS-46038, 1 Turbine BLDG CLG WTR SPLY HDR LEAD /

RO

Trip the Reactor and Initiate 1E-0 LEAD

The Reactor Trip breakers fail to open

Actuate AMSAC/DSS to trip Reactor

Stop the Feedwater Pumps LEAD

Place Standby Condensate Pump in Manual

Stop the running Condensate pumps

Place the Standby Heater Drain Pump in Manual

Stop the running Heater Drain Pump

Place EH Oil Pump switches in PULLOUT Page 11 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5 8. WHEN the reactor is tripped, THEN verify that the RO/LRO 1E-0, Reactor Trip or Safety Injection Steam line break has automatically entered. Crew

Perform Immediate actions from memory.

a. If not, ENTER the Steam line break (Relative LRO

The Reactor Trip breakers fail to open Order 0, Trigger 13)

Actuate AMSAC/DSS to trip Reactor

9. During 1E-0:

Verify immediate actions.

Crew

Verify component alignment per Attachment L.

a. If requested to locally open the Reactor Trip Breakers, wait two minutes and report the - Manually start SI pump(s) (Critical Task)1 breakers are both stuck in the closed position. - Manually start AFW Pump (Critical Task)2

b. If requested, report that all category 1 vent

Check AFW status and RCS temperature (steps 6 doors are closed. & 7)

c. If requested, report all Turbine Building roof

Maintain >200 gpm total AFW flow, but throttle exhausters are stopped. as necessary to limit cooldown.

RO

d. If requested to isolate Unit 1 MSRs per Attachment J, perform the following:

Maintain AFW discharge pressure > 900 psig

1) Bring up the CAEP Window

Close both MSIVs due to RCS cooldown

2) Click on OPEN File

May also be done by lead during performance of

3) Click on Attachment J-E0 .cae Attachment L.

4) Click on Run button CREW

Trip RCPs if trip criteria is met.

5) After 12.5 minutes, Report that Unit 1 MSRs are isolated per 1E-0 Attachment J.

Diagnose a Faulted SG and transition to E-2.3

e. IF the LEAD is performing Attachment L, THEN it may be turned over when step 7 of 1. Manually start at least one SI pump prior to attachment is complete. IF an extra operator is transitioning out of E-0.

performing attachment L, THEN it may NOT be 2. Establish and maintain minimum required FW turned over. flow to the SGs prior to transitioning out of E-0.

An orange path in containment may exist,requiring transition to FR-Z.1.

Page 12 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

10. IF containment conditions exist, crew may have to Crew FRZ.1, Response to High Containment Pressure transition to FR-Z.1

Verify CI valves closed

Verify CS running

Check CFCUs running in SLOW to the Dome

Check CL pressure both loops >65 psig.

Verify MSIVs closed

Identify 12 SG as faulted.

Isolate Feed flow to 12 SG

Transition to 1E-2.

11. Allow crew to complete actions of 1E-2 as Crew 1E-2: Faulted Steam Generator Isolation1 necessary.

Close/verify 12 MSIV is closed

Verify 11 SG NOT faulted

Isolate AFW to 12 SG (Critical Task) 2

Verify steam supply to TDAFP from 12 SG closed

Transition to E-1

1. If transition to FR-Z.1 was required, THEN generator would have been isolated in that procedure.

2. To fulfill Critical Task requirements, SG must be isolated prior to transition out of E-2.

Page 13 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

12. Allow crew to complete actions of 1E-1 as 1E-1: Loss of Reactor or Secondary Coolant necessary.

Maintain 11 SG AFW > 200 GPM until SG level >5%

NR [50% WR], then maintain level 5 -50% NR [50 -

59% WR].

Reset SI

Reset CI

Establish IA to containment.

Check if SI can be terminated, if so transition to ES-0.2.3,4

Check if SG is still blowing down

3. SI termination is listed on the information page of E-1.

4. The scenario may be terminated when SI is verified as not required.

Page 14 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

13. Allow crew to complete actions of ES-0.2 as 1ES-0.2: SI Termination necessary.

Place AMSAC in Pull to Lock

Rest AMSAC

Verify if charging flow is established.

Stop RHR and SI pumps

14. WHEN the crew verifies SI is not required and / or Crew Assemble near fire detection panel while evaluators at the discretion of the Lead Evaluator, place the consult simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented

15. The Classification will be performed by the SS after the conclusion of the Scenario.

a. The EAL for this Scenario is NUE on 7A.

Page 15 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 0 SIMFW08 Malfunction FW34B 12 MDAFW pump auto start fails 0 SIMRP02 Malfunction SI05A 11 SI pumps fail to auto start 0 SIMRP02 Malfunction SI05B 12 SI pumps fail to auto start 0 SIMRP02 Malfunction RP06 MSIVs fail to auto close 0 SIMMS01A Malfunction MS01B 40 13 12 SG steam line break 0 EVENT EVENT Rdc0001a<20 13 Enter trigger 13 when RPI for TRIGGER ACTION E3 <20 steps 0 Malfunction RP07 Reactor Trip Breakers fail to Open 1 SIMRD02 Malfunction RD0916 1 G7 RPI fails to 0 2 SIMTC01 Malfunction TC03 20 2 120 Ramp Turbine CV Cycling 3 Malfunction CL01A 3 Trip 11 CL Pump 3 Malfunction CL03 3 121 CL Pump fails to Auto Start Page 16 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 3 Malfunction CL02A 3 12 CLPump fails to Auto Start 3 Malfunction CL02B 3 22 CL Pump fails to Auto Start 4 Override DI DI-46038C ON 4 Close MV-32031 Close 4 Override DI DI-46038O OFF 4 Close MV-32031 Open 4 Override DO LO-46038B ON 4 MV-32031 Blue Light ON Page 17 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 SIMULATOR SETUP CHECKLIST Before Training

_____ Setup Simulator per Standard IC-A Checklist

_____ Protected equipment label placed on 12 AFW Pump

_____ Procedures to be used during scenario are cleaned of any place keeping marks C47013-0407 C47013-0507 C5AOP4 C5 AOP5 C23 AOP2 C47007-0101 C47007-0303 C47020-0106 C47020-0304 C47020-0204 LCO 3.7.8 LCO 3.0.3 1E-0 FRZ.1 1E-2 1E-1 1ES-0.2 F3-2

_____ Shift Manager procedures are cleaned of any place keeping marks 1E-0 1E-1 1E-2 1ES-0.2 FR-Z.1 LCO 3.7.8 LCO 3.0.3 Page 18 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 1, RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT, REV. 0 After Training for the Day

_____ Headsets turned off and put away

_____ Procedures cleaned off and put away

_____ Simulator Reset to IC-10 or next IC to be used

_____ Simulator placed in DORT if simulator will not be used again that day

_____ Protected equipment tag removed

_____ Information Tags removed and put away

_____ If last scenario of the day, ensure all exam material removed from simulator and stand down from exam security per form PITC-220, if NRC exam.

Page 19 of 20

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 64 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS 11 TD AFW Pump is OOS as of 1200 yesterday for trip throttle valve replacement PROTECTED EQUIPMENT 12 MD AFW Pump RAD MONITORS OOS ANNUNCIATORS OOS None None OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS None None OTHER EQUIPMENT OOS / STATUS Breaker 16-10, the cubicle is damaged and the breaker is removed.

12 BATP is OOS for seal replacement CFCU's are on Cooling Water MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE None OPERATIONAL PLANS FOR COMING SHIFT Dilute with 10 gal RMU 1 to 2 times per shift for temperature control NEW PROCEDURES / INSTRUCTIONS None WATCHSTANDERS LPEO: OURET, TRAVIS PEO: KEMPKES, JOHN LPEO Relieved By: Time: Date:

PEO Relieved By: Time: Date:

CB WALKDOWN LPEO: Time:

PEO: Time:

Page 20 of 20

QF-1030-19 Rev. 4 (FP-T-SAT-30)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # 2005 NRC SCENARIO 2 PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SEG TITLE: SHAFT SHEAR/LOSS OF FW #: SCEN 2 REV. # 0 PROGRAM: INITIAL LICENSED OPERATOR #: P8100 COURSE: INITIAL LICENSED OPERATOR #: P8100 TOTAL TIME: 2 HOURS Developed by: J. Kempkes 5/5/05 Instructor Date Reviewed by:

Instructor Date Validated by:

Validation Lead Instructor Date Approved by:

Training Supervision Date Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 Guide Requirements During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of Training: the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Swap running Charging pumps per 1C12.1.

Learning

2. Diagnose and perform corrective actions for a pressurizer level Objectives:

channel failure high per 1C51.

3. Diagnose and perform corrective action for an imminent loss of 10 Bank Transformer per 1C20.3 AOP7 and 1C20.5.

4. Diagnose and perform corrective action for RCP hi vibration per C47 and C1.4/C1.4 AOP1.

5. Diagnose and perform corrective action for a RCP shaft shear with automatic turbine trip failure per 1E-0.

6. Diagnose and perform corrective action for a loss of secondary heat sink per C28.1 and FR-H.1.

Prerequisites: None

1. Full Scope Simulator Training 2. Operations Management Representative Resources: 3. Lead Evaluator

4. Human Performance Evaluator

5. Comment Recorder

6. Booth Operator (Primary Communicator)

7. Backup Communicator

1. 1C51

References:

2. C47

3. C12.1 AOP3

4. C1.4/C1.4 AOP1

5. 1E-0

6. 1C12.1 None Commitments:

Page 2 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 Evaluation This is an evaluation scenario for the 2005 ILT NRC Exam, this Method: scenario is based on P9160S-002 Evaluation #27.

Operating None - Evaluation Scenario Experience:

Initiating Event with Core Damage Frequency:

Related PRA Loss of secondary heat removal, which contributes 2% to the CDF.

Information:

Important Components:

AFW pumps Important Operator Actions with Task Number:

None Page 3 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Pressurizer Level Instrument failure.

2. Imminent failure of 10 bank transformer.

3. RCP high vibration and shaft shear.

After EOP Entry:

1. Bus 12 M to R auto transfer failure.

2. Turbine Trip failure

3. AFW pump trip.

Abnormal Events:

1. C20.3 AOP7 Electric Power System Operating Restrictions and Limitations Loss of 10 Transformer.

Major Transients:

1. RCP Shaft Shear/Turbine Trip Failure

2. Loss of Heat Sink Critical Tasks:

1. Manually trip the turbine prior to reaching a RED path on Pressurized Thermal Shock.

2. Establish feedwater flow to at least 1 SG before RCS bleed and feed is required.

Page 4 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This Evaluation can be run from the following Requalification Exam Scenario Standard (Specific) IC sets:

IC-A 100% power

2. The following equipment is OOS:

Breaker 16-10, Bus Tie to Bus 26

11 AFW Pump SEQUENCE OF EVENTS:

Normal Operation: Swap Running Charging Pumps

Per report from the field, Crew swaps running Charging pumps from 12 to 13 per 1C12.1 Event 1: Pressurizer level controlling channel failure low

The charging pump in AUTO goes to maximum speed.

Letdown is isolated and heaters deenergized

A new controlling channel is selected.

Charging pump speed is returned to automatic

Letdown is restored using excess letdown.

Event 2: 10 Bank Transformer Oil Leak

The Unit 2 Turbine Building Operators report a large leak from a crack at the base of 10 Transformer.

Bus 15 is transferred from the 1RY to the CT11 source in anticipation of the loss of the transformer.

Event 3: 12 RCP high vibrations, #1 seal failure and shaft shear

A vibration of 10.5 mils requires a controlled shutdown.

The crew starts a power reduction per 1C1.4 or 1C1.4 AOP1.

The RCP shaft shears causing a loss of RCS flow.

The turbine fails to trip automatically, thus requiring closure of the control valves OR MSIV isolation.

Page 5 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 Event 4: Loss of Secondary Heat Sink

11 MFW pump trips because of the turbine trip.

12 MFW pump trips because Bus 12 fails to auto transfer 30 seconds after the trip.

12 AFW pump locks out causing a loss of secondary heat sink.

21 AFW pump cannot be cross-connected.

Main feedwater or condensate flow can be used to restore feedwater flow to the steam generators per FR-H.1.

TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

This is an evaluation scenario and as such, tasks are not credited for training and therefore are not listed here.

Page 6 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC):

Standard IC-A (IC sim setup per standard IC guide)

Mode: 1

Exposure: BOC

Power: 100%

Boron: (CB): 1283 ppm

Temperature: 560

Pressure: 2235

Xenon: Stable

Rods: CBD@228

Generator: 570 Mwe

1. SIMULATOR SET UP

a. Reset the simulator to IC-32.

b. Place the simulator in RUN.

2. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary, to cause the following pre-existing conditions (Relative Order 0):

a. Turbine Auto Trip Failure

b. MSIV Auto Trip Failure

c. MD AFW Pump Trip on Start

d. Bus 12 Auto Transfer Failure

e. Turbine Stop Valve Fails to Close

3. Complete the Simulator Setup Checklist.

4. COMPLETE TURNOVER: CREW Review the Unit 1 LPEO / PEO Turnover log

a. UNIT 1 LPEO / PEO TURNOVER LOG

b. Verify crew performs walk down of control Walk down the control boards and ask questions as boards and the reviews turnover checklists. appropriate.

Page 7 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 0 5. When the crew has assumed the duty and at the RO 1C12.1, Section 5.4.1 discretion of the Lead Evaluator report as the Aux

Verify desurger pressurized.

Building Operator, 12 Charging pump belt is frayed

Transfer 11 Charging Pump to MANUAL.

and recommend swapping from 12 to 13 charging

Verify 13 Charging Pump in MANUAL/minimum.

pump.

Reduce 11 Chg speed to get ~6.5 gpm seal inj

a. If asked, report the desurger has been

Verify chg pressure <2400 psig verified pressurized per section 5.13.

Start 13 Chg Pump

Adjust seal inj to ~9.5 gpm, <2550 psig charging Note: The crew may start 13 Charging pump then

Stop 12 Chg Pump secure 12 Charging pump, or stop 12 Charging

Adjust seal injection back to 8.0 gpm pump then start 13 Charging pump. Either action is satisfactory.

Transfer 11 Charging Pump to AUTOMATIC OR 1C12.1, Section 5.4.2

Verify desurger pressurized.

Transfer 11 Charging Pump to MANUAL.

Verify 13 Charging Pump in MANUAL/minimum.

Adjust 12 Chg speed to get ~9.5 gpm seal inj

Stop 12 Chg Pump

Adjust seal injection to 6.0 gpm

Verify Charging pump header < 2400 psig

Start 13 Chg Pump

Adjust seal injection back to 8.0 gpm

Transfer 11 Charging Pump to AUTOMATIC

Page 8 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1 6. When 13 charging pump is running and at the RO 47012-0607, Pressurizer Lo-Lo level discretion of the Lead Evaluator, enter the

Verify all pressurizer heaters deenergized malfunction to cause the controlling channel of pressurizer level to fail low. (Relative Order 1,

Verify letdown is isolated Trigger 1) Lead/ 47012-0507

7. If desired by evaluators, trip the bistable on request. RO

Verify level low on 1L-428 only (Relative Order 2, Trigger 2)

Verify heaters ON

Take manual control of the charging pump speed to maintain level at program.

Refer to C51 C51.3 Pressurizer Level 1L-428 - low Lead/

Operate heaters manually if desired.

RO

Take manual control of the charging pump speed to maintain level at program.

Select position 2-1 on pressurizer level control selector switch.

Restore pressurizer heaters for normal operation.

Return charging pump back to auto.

Switch pressurizer level recorder to another channel.

Refer to T.S.3.3.1 Condition A and Table 3.3.1-1 Function SS 9 (6 hr LCO for B/S tripping).

Lead Trip bistable 1LC-428A.

Initiate work order on the failed channel.

Make appropriate log entries.

Page 9 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2 8. When letdown is in service and charging is restored SS Direct entry to C20.3 AOP7 based on imminent loss of 10 and at the discretion of the Lead Evaluator, give the Transformer.

Lead Crew an Update as the Unit 2 SS, : C20.3 AOP7 "An oil leak is in progress from 10 bank transformer,

Verifies auto actions have NOT occurred as through a crack at the base on the north side. transformer has not locked out yet.

About fifty gallons of oil is already on the ground."

Contacts Transmission System Operator (TSO) to report oil leak.

SS

Contacts Technical Engineering for assistance.

9. IF the Shift Supervisor enters D14.3 AOP1 OIL Lead

Verify/transfer Unit 2 safeguard buses to 2RY.

SPILL, as the Shift Manager direct "Unit 2 will

Transfer Bus 15 to CT11 per 1C20.5 section 5.15.

complete D14.3 AOP1." o Bkr 15-7 to MANUAL o Sync scope to CT11

10. IF TSO or Engineering is contacted, recommend o Verify voltages matched and synchronized isolation of the transformer from the System Control o Announce transfer/stand clear Bus 15 Center once plant loads are shifted to alternate o Close breaker 15-7 CT11 source and trip sources using plant procedures. breaker 15-3 1RY source within 5 seconds NOTE: IF C20.3 AOP7 is not entered based on the o Verify bus voltage on meter and mimic light imminent loss, transfer of Bus 15 to CT11 per o Sync scope to OFF normal procedures is adequate. o Bkr 15-7 to AUTO Lead

Place 1RY source breakers to buses 15/16 in MANUAL and PULLOUT

11. WHEN realignment of Unit 2 buses is addressed, reply "Bus 25 is already on 2RY and Unit 2 SS Technical Specifications operators will transfer Bus 26 to 2RY per 2C20.5."

3.8.1 Condition A (7 days, plus perform SP 1118 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter)

12. WHEN 1RY source breakers to Bus 15 are in PULLOUT and the evaluators concur, continue with the next event.

Page 10 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3 13. WHEN 1RY source breakers to Bus 15 are in RO 47012-0203 PULLOUT and at the discretion of the Lead

Determine RCP vibration using ERCS GRPDIS Evaluator Enter the 12 RCP Vibration Alarm and "RCPVIBES" ERCS overrides (Relative Order 3, Trigger #3)

Determine shaft vibration requires a controlled shutdown.

14. WHEN directed, report "12 RCP shaft vibration is SS Unit Power Reduction (option selected by SS) 10.5 mils and stable."

Lead/ 1C1.4 Power Operation option

Determine nuclear engineering notification is not

15. IF asked for direction on rate of load decrease or RO required as BOC, >400 ppm boron and no load follow chosen rate is 1%/min or less or if directed by the history.

Lead Examiner, reply as the RCP System Engineer,

Predict reactivity for power change using C1 Figures "12 RCP should be shutdown within the next hour and Curves for reactivity balance, or Figure C1-32.

based on current vibration."

Conduct prejob brief.

Notify the Duty Chemist of the load decrease.

Pressurizer heaters to ON

Set desired load rate and final load on EH controls.

Borate or insert rods to cause Tavg decrease.

Start turbine load reduction in AUTO.

Borate and move rods to maintain Tavg/Tref within 1.5°F, Delta I within band, and rods above the RIL.

C1.4 AOP1 Option

Verify control systems in AUTO

Reduce turbine load in AUTO o Select desired load rate o Verify in IMP IN o Set desired load on setter o Depress GO

Borate the RCS to maintain rods above the RIL and Delta I within limits Page 11 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4 16. WHEN 5% power reduction has been achieved and SS

Direct entry to 1E-0 at the discretion of the Lead Evaluator, Enter the 12 RO

Verify reactor trip RCP Shaft Shear (Relative Order 4, Trigger #4). o Trip/bypass breakers OPEN Then DELETE Relative Order 3 RCP vibration o Flux decreasing alarms. (Relative Order #3a) o RPIs at 0 NOTE: It is expected that the turbine trip will occur o Rod bottom lights LIT Lead

Verify Turbine Trip (critical task) before SI actuates on excessive cooldown. IF SI o Note: turbine will not automatically trip and actuates, additional steps are included in the expected when manually tripped the left stop valves will student responses for E-0 actions until transition to FR- not close. The MSIV's will not auto close.

H.1 is directed. o Manually trip turbine using CB pushbutton Lead Manually close CV's NOTE: If SG WR level is >50% in either SG when RO IF NOT, manually close MSIV's AFW status is checked, E-0 actions will continue until

Verify both safeguards buses energized decay heat causes sufficient inventory loss to reach

Verify SI not actuated or required RED path criteria for heat sink. o Both SG pressures >530 psig SS o Pzr Press >1830 psig

17. During 1E-0: o Containment pressure <3.5 psig

a. If requested, report that all category 1 vent

Transition to 1ES-0.1 Reactor Trip Recovery doors are closed.

IF Red Path exists on CSF for Heat Sink, Transition to

b. If requested, report all Turbine Building roof 1FR-H.1.

IF SI has actuated:

exhausters are stopped.

Lead 1. Perform E-0 Att. L (see attached procedure section)

c. If requested to isolate Unit 1 MSRs per RO 2. Check AFW Status Attachment J, perform the following: o Total AFW flow <200 gpm

1) Bring up the CAEP Window o Attempt/verify 12 AFW start (allowable per

2) Click on OPEN File ARP if SG pressure is <700 psig, but will lock

3) Click on Attachment J-E0 .cae out on restart. If SG pressure high will not be

4) Click on Run button allowed to start.)

d. After 12.5 minutes, Report that Unit 1 MSRs SS o IF wide range level is <50% on both SGs, are isolated per 1E-0 Attachment J. transition to FR-H.1.

Page 12 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5 18. During Loss of Heat Sink (1FR-H.1) RO

Verify RCS pressure >SG pressure

Verify hot leg temperature >350°F

19. IF asked to check breaker 16-3, report a 51A

Verify secondary heat sink exists overcurrent flag is present. o Either WR SG level >9%

o Pzr Pressure <2335 psig

20. IF asked to cross connect 21 AFW pump to Unit 1, Lead

Attempt to restore AFW flow wait 5 minutes and report 21 AFW pump failed to o Close SG Blowdown Isolation valves o Determine 12 AFWP locked out start.

o Attempt to restore AFW flow 47010-0107 12 AFWP LOCKED OUT o IF SG pressures both >700 psig:

Dispatch operator to breaker 16-3

Notify electrical department

Notify SS that 12 AFWP cannot be started.

o IF NOT,

Verify CST level >5000 gal

Close 12 AFWP discharge valves to 11/12 SGs

12 AFWP to MANUAL

CS-46425 to TRIP to reset the lockout (verify alarm clears)

CS-46425 to START (will immediately lock out)

Perform actions above for both >700 psig o Verify AFW flow <200 gpm o Dispatch operator to locally restore AFW o Stop 11 RCP Page 13 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS (cont) 21. Loss of Heat Sink (cont) Lead

Attempt to restore MFW flow (critical task) o Reset SI NOTE: Critical task is met if MFW or Condensate flow o Verify/Start one condensate pump is restored prior to Bleed and Feed cooling required per o Verify FW Containment Isolation valves open FR-H.1 Step 2.

IF NOT, reset CI, verify FRV/BFRV in MANUAL/CLOSED and open valves o Establish MFW flow

22. IF directed, locally open MFWP discharge isolation:

Reset FW bypass isolation

a. For 11 FWP enter (Relative Order 5,

Start either MFWP Trigger 5)

Manually open at least one bypass FRV

b. For 12 FWP enter (Relative Order 6, to establish flow >200 gpm on Trigger 6) ERCS/clear heat sink RED path

Check SG levels o Check SG NR levels >5% in either SG OR verify feed flow to at least one SG o Return to procedure/step in effect (ES-0.1 or E-SS 0, for No SI/SI)

Lead

IF MFW not established, establish Condensate Flow (critical task)

RO o IF SI pumps running, depressurize RCS to

<1950 psig and block automatic SI Lead o Depressurize at least one SG to <400 psig

Verify Condensate System in service

Dump steam to condenser or use SG PORV at maximum rate

Locally open one MFWP discharge isolation valve

Control flow with FW bypass valve o Repeat above step for checking SG level Page 14 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 23. Reactor Trip Recovery 1ES-0.1 SS

Verify reactor trip has been announced 6a Lead

Steam dump to STM PRESS mode or (MSIVs closed)

NOTE: IF Safety Injection has actuated, perform tasks SG PORVs to 71.8%

of Event 6b instead RO

Check RCS cold leg temperatures stable/trending to 547°F NOTE: WHEN cold leg temperatures are under control o IF NOT, stop dumping steam, verify SGB and evaluator concurs, terminate the scenario. isolation valves closed, and reduce feed flow to just above 200 gpm until NR SG level is >5% in one SG o IF cooldown continues, close MSIVs/Bypass valves and reduce SG PORV setpoints to 71.8%

Event 24. Reactor Trip or Safety Injection (Cont) and SI SS

Return to procedure/step in effect (1E-0 Step 7) 6b Termination LEAD

Check RCS cold leg temperatures stable/trending to 547°F NOTE: Only performed if SI is actuated during o IF NOT, stop dumping steam, verify SGB previous events. isolation valves closed, and reduce feed flow to just above 200 gpm until NR SG level is >5% in one SG o IF cooldown continues, close MSIVs/Bypass valves and reduce SG PORV setpoints to 71.8%

Check PORVs and Spray Valves CLOSED

Verify RCP's stopped

Check SGs not faulted (none depressurizing uncontrollably)

Check SGs not ruptured (radiation monitors normal)

Check RCS intact (containment radiation/pressure/

Sump B level normal)

Verify SI can be terminated Page 15 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS o Subcooling >20°F o Total FW flow >200 gpm OR >5% NR SG level o RCS pressure >2000 psig, stable/increasing o Pressurizer level >7%

SS

Transition to 1ES-0.2 SI Termination 1ES-0.2 SI TERMINATION Lead

Reset SI, CI

Verify instrument air to containment

Block/reset AMSAC/DSS

Establish at least one charging pump running per RO 1C12.1

Stop SI and RHR pumps Lead

25. WHEN both SI Pumps are turned off and / or at the Crew Assemble near fire detection panel while evaluators discretion of the Lead Evaluator, place the simulator in consult freeze.

a. Do not reset the simulator until the Lead Evaluator has consented

26. The Classification will be performed by the SS after the conclusion of the Scenario.

a. The EAL for this Scenario is NUE on 20A.

Page 16 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 0 MFS TC06 Turbine Auto Trip Failure 0 SIMS01A MFS RP06 MSIV Auto Closure Failure 0 SIMS01B MFS TC01A CV-31182 Left Turbine Stop Valve Fails to Close 0 SIMFW08 MALF FW32 MD AFW pump trip on start 0 SIMED07 MALF ED02B Bus 12 1R transformer breaker 12-1 fails to close 1 SIMRP03A SYS OVRD RX206 0 1 PRZR level (charging pump speed) controller 24043 (LT-428) 2 Remote RP119 Trip 2 Trip LC-428A 3 C1-C2 ANN MALF M47012:0203W CRY 3 Delay 200 sec 11 or 12 RCP high vibration WOLF alarm Page 17 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 3 ERCS PT CP-1Y0771A 9.0 3 Start Value 5 12 RCP frame vibration OVRD Ramp 300 sec monitor (horizontal) 3 ERCS PT CP-1Y0772A 7.5 3 Start Value 5 12 RCP frame vibration OVRD Ramp 300 sec monitor (vertical) 3 ERCS PT CP-1Y0773A 10.5 3 Start Value 8 12 RCP shaft vibration OVRD Ramp 300 sec monitor (horizontal) 3 ERCS PT CP-1Y0774A 8.1 3 Start Value 5 12 RCP shaft vibration OVRD Ramp 300 sec monitor (vertical) 3a C1-C2 ANN MALF M47012:0203W DELETE 11 or 12 RCP high vibration alarm 3a ERCS PT CP-1Y0771A DELETE 12 RCP frame vibration OVRD monitor (horizontal) 3a ERCS PT CP-1Y0772A DELETE 12 RCP frame vibration OVRD monitor (vertical) 3a ERCS PT CP-1Y0773A DELETE 12 RCP shaft vibration OVRD monitor (horizontal) 3a ERCS PT CP-1Y0774A DELETE 12 RCP shaft vibration OVRD monitor (vertical)

Page 18 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 4 SIMRC05B MALF RC03B 4 Delay 12 RCP shaft shear (free wheel impeller) 7 Seconds TC-14C 4 4 CV-3 Fails as is FW27B 4 4 FCV 476 Fails Closed on Trip FW126 Local 5 RF 5 11 FWP Discharge Valve Control Switch FW129 Open 5 RF 5 11 FWP Discharge Valve Open Pushbutton FW127 Local 6 RF 6 12 FWP Discharge Valve Control Switch FW131 Open 6 RF 6 12 FWP Discharge Valve Open Pushbutton Page 19 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

NRC EXAM SCENARIO 2, PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP SHAFT SHEAR/LOSS OF FW, Rev 0 SIMULATOR SETUP CHECKLIST Standard IC-A Before Training

_____ Simulator Setup Checklist for IC-A completed

_____ Procedures to be used during scenario are cleaned of any place keeping marks

C47012-0203, 11 or 12 RCP Hi Vibration

C47012-0507, PRZR Level Deviation

C47012-0607, PRZR Lo-Lo Level Heater Off and Letdown Secured

1C12.1, Letdown, Charging, and Seal Water Injection - Unit 1

1C51.3, Pressurizer Level IL-428 - Low

1E-0, Reactor Trip or Safety Injection

1FR-H.1, Response to Loss of Secondary Heat Sink

F3-2, Classifications of Emergencies

T.S. LCO 3.3.1 Condition A, and Table 3.3.1-1 Function 9

T.S. LCO 3.4.14

T.S. LCO 3.8.1 Condition A

C20.3 AOP7

1C1.4

1C1.4 AOP1

C51.3

1ES-0.1

C47010-0107 After Training for the Day

_____ Information Tags removed and put away

_____ Signs/placards removed and put away unless normal simulator configuration

_____ Instructor station returned to normal with all books, paper, and etc. put away

_____ Headsets turned off and put away

_____ Simulator reset to IC-10 unless another IC will be used for further training

_____ Simulator placed in DORT if simulator will not be used again that day Page 20 of 21

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 64 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS 11 TD AFW Pump is OOS as of 1200 yesterday for trip throttle valve replacement PROTECTED EQUIPMENT 12 MD AFW Pump RAD MONITORS OOS ANNUNCIATORS OOS None None OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS None None OTHER EQUIPMENT OOS / STATUS Breaker 16-10, the cubicle is damaged and the breaker is removed.

12 BATP is OOS for seal replacement MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE None OPERATIONAL PLANS FOR COMING SHIFT Dilute with 10 gal RMU 1 to 2 times per shift for temperature control NEW PROCEDURES / INSTRUCTIONS None WATCHSTANDERS LPEO: OURET, TRAVIS PEO: KEMPKES, JOHN LPEO Relieved By: Time: Date:

PEO Relieved By: Time: Date:

CB WALKDOWN LPEO: Time:

PEO: Time:

Page 21 of 21

QF-1030-19 Rev. 4 (FP-T-SAT-30)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # 2005 NRC EXAM SCENARIO 4 HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PRESSURIZER PORV LEAKAGE, LETDOWN HX LEAK, SEG TITLE: LOSS OF ALL AC POWER #: SCEN 4 REV. # 0 PROGRAM: INITIAL LICENSED OPERATOR #: P8100 COURSE: INITIAL LICENSED OPERATOR #: P8100 TOTAL TIME: 2 HOURS Developed by: Travis Ouret 3/9/05 Instructor Date Reviewed by:

Instructor Date (See page 10, Simulator Development Checklist.)

Validated by:

Validation Lead Instructor Date (See page 11, Simulator Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 Guide Requirements During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of Training: the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Respond to Heater Drain Tank Level Transmitter Failure (Low)

Learning per C47.

Objectives: 2. Diagnose and respond to a leak in the Letdown Heat Exchanger to Component Cooling per 1C4 AOP1 and 1C14 AOP2.

3. Diagnose and respond to a Pressurizer PORV Leaking per C47 and Tech Specs.

4. Restore safeguards power to Bus 15 via the Bus Tie Breakers from Bus 25 per ECA-0.0.

Prerequisites: None

1. Full Scope Simulator Training 2. Operations Management Representative Resources: 3. Lead Evaluator

4. Human Performance Evaluator

5. Comment Recorder

6. Booth Operator (Primary Communicator)

7. Backup Communicator

1. C47003-0503

References:

2. C47022-0109

3. C47047-1R-39

4. 1C14 AOP2

5. 1C12.1 AOP3

6. LCO 3.4.14

7. C47012-0506

8. LCO 3.4.11

9. 1E-0

10. 1ECA-0.0

11. 1ECA-0.1

12. 1ECA-0.2 Page 2 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 None Commitments:

This is an evaluation scenario for the 2005 ILT NRC Exam, this Evaluation scenario is based on the 2000 SRO NRC EXAM EVALUATION D, Method: ATT SRO-00-D. It has been modified for use as 2005 NRC EXAM SCENARIO 4 Operating None - Evaluation Scenario Experience:

Initiating Event with Core Damage Frequency:

Related PRA Loss of Power with SBO (23.9%)

Information:

Important Components:

11 AFW pump D1 and D2 Emergency Diesel Generators 4169V Busses 15 and 16 Important Operator Actions with Task Number:

None Other Page 3 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Heater Drain Tank Level Transmitter Fails Low

2. Letdown Heat Exchanger to Component Cooling Leak

3. Pressurizer PORV Leakage After EOP Entry:

1. Loss of All AC Power, restore Safeguards Bus Tie Breakers

2. Failure of Safeguards Bus Tie Breaker to Close

3. LOCA via RCP Seals in 1ECA0.0 Abnormal Events:

1. Pressurizer PORV Leakage

2. 1C14 AOP2 Letdown Heat Exchanger to Component Cooling Leak Major Transients:

1. 1E-0, Reactor Trip or Safety Injection

2. 1ECA-0.0, Loss of All Safeguards AC Power

3. 1ECA-0.2, Loss of all Safeguards AC Power Recovery with SI Required

4. 1ECA-0.1, Loss of all Safeguards AC Power Recovery without SI Required Critical Tasks:

1. Maintain / return power to within license limits during secondary transient.

2. Determine LCO 3.4.11 Condition A cannot be satisfied in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and enter / discuss Condition D shutdown requirement.

Page 4 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This evaluation can be run from IC-10.

Reactor Power is 100%, MOC

RCS Boron Concentration 721 ppm.

Adding 10 Gallons RMU 3-4 times per shift for Temperature Control.

2. The following additional equipment is OOS:

D1 OOS for fuel injector replacement, estimated return to service is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SEQUENCE OF EVENTS:

Event 1: Heater Drain Tank Level Transmitter Fails Low

A failure of the HDT Level transmitter results in MW decreasing and Reactor Power to Increasing.

The HDT pump running in AUTO will go to minimum speed.

The Crew will respond per C47.

Event 2: RCS Leakage in the Letdown Heat Exchanger to Component Cooling

CC Surge Tank level increases and 1R-39 alarms on inleakage.

The Crew will respond per C47, 1C4 AOP1 and 1C14 AOP2.

Letdown Heat Exchanger is isolates and excess Letdown placed in service.

The leak exceeds Tech Spec limits for RCS Leakage requiring isolation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Event 3: Pressurizer PORV leakage.

Determine which PORV is leaking.

Attempt to isolate the PORV by closing the associated Block Valve.

The Block valve will not close.

Enter Tech Spec 3.4.11 Condition D, requiring a Unit shutdown to Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Event 4: Loss of All AC Power on Unit 1 with Cross-Tie Recovery

Offsite power is lost.

D1 is OOS and Bus 16 locks out.

The Unit 2 to Unit 1 Bus Tie Breaker has an internal fault, resulting in the breaker tripping open if the breaker is closed.

Plant Electricians will repair the breaker and power is restored on the Unit 2 bus tie to Bus 15.

Page 5 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

This is an evaluation scenario and as such, tasks are not credited for training and therefore are not listed here.

Page 6 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC-10):

Standard IC-10

Mode: 1

Exposure: MOC

Power: 100%

Boron: (CB): 721 ppm

Temperature: 560°F

Pressure: 2235 psig

Xenon: At Equilibrium

Rods: Bank D step counters at 218, all others at 228

Generator: 561 Mwe

1. SIMULATOR SET UP

a. Reset the simulator to IC-10.

b. Place the simulator in RUN.

2. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary, to cause the following pre-existing conditions (Relative Order 0):

a. D1 OOS Annunciators

b. Breaker 25-17 closure failure

3. Remove D1 from service

a. Place CS-46935, D1 Diesel Generator Control Switch in Pullout, and attach a HOLD Card

b. Place CS-46950, BUS15 SOURCE FROM D1 DSL GEN, Control Switch in Pullout, and attach a HOLD Card

c. Place CS-46948, BKR 15-2 MAN / AUTO Page 7 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CLOSURE SEL SW, in Manual, and attach a HOLD Card.

d. Hang D1 Out of Service signs on Control Board.

4. Complete the Simulator Setup Checklist.

5. COMPLETE TURNOVER: CREW Review the Unit 1 LPEO / PEO Turnover log

a. UNIT 1 LPEO / PEO TURNOVER LOG

b. Verify crew performs walk down of control Walk down the control boards and ask questions as boards and the reviews turnover checklists. appropriate.

Event 1 6. When the crew has the duty and at the discretion of C47003-0503, Heater Drain Tank High Level the Lead Evaluator, ENTER the malfunction to cause the Heater Drain Tank Level Transmitter to

Verify High level fail Low. (Relative Order 1, Trigger 1). LEAD

a. If asked to investigate as the Turbine Building RO

Reduce Reactor power to maintain Tave and Tref Operator, report, All local indications of the (CRITICAL TASK 1)

HDT pumps are normal.

Note: The HDT pump in AUTO will go to minimum speed, eventually the Hi level alarm will come in. The event may be noticed by Increase in Reactor Power and decrease in MW.

Page 8 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2 7. When the Crew has diagnosed the level transmitter LEAD Observe Increasing CC Surge Tank Level failure and/ or at the discretion of the lead evaluator, ENTER the leak in the Letdown Heat C47022-0109 Hi Radiation Train A Panel Alarm Exchanger. (Relative Order 2, Trigger 2). LEAD

a. When directed to CLOSE CC-12-4 and CC

Determine 1R-39 in Alarm by observing Rad 3, then DELETE Malfunction VC08, (Relative Monitor panel.

order 2a) C47047-1R-39 LEAD

Verify 11 CC Surge Tank Vent valve, MV-Note: The leakage is approximately 30 gpm which 32088, CLOSES is greater than Tech Spec limits.

Refer to 1C14 AOP2, Leakage into the CREW Component Cooling System.

NOTE: THIS EVENT WAS NOT USED DURING THE EXAMINATION. CREW

When leaking HX is found, leave it isolated.

1C14 AOP2, Leakage into the Component Cooling System

Check 1R-39 for High Radiation LEAD

Check RCP CC outlet flow and temperatures o Flows and Temps Normal

Refer to Table 1.

Remove Letdown from service per 1C12.1 RO RO

Isolate Letdown HX by CLOSING the following valves:

o CV-31203, LTDN PRESS CONT, using 1HC-125A o CC-12-4, 11 LTDN HX CC INLT Page 9 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS o CC-12-3, 11 LTDN HX CC OUTLT

Notify Rad Protection of potential radioactive LEAD/ contamination of the CC system.

SS 1C12.1 AOP3, Loss of Letdown Flow to the VCT RO

Close the Letdown Orifice Isolation Valves are CLOSED.

o CV-31325, LETDOWN ORFICE ISOL 40 GPM using CS-46170 o CV-31326, LETDOWN ORFICE ISOL 40 GPM using CS-46171 o CV-31327, LETDOWN ORFICE ISOL 80 GPM using CS-46174 RO

CLOSE the letdown isolation valves.

o CV-31226, LETDOWN LINE ISOL using CS-46165 o CV-31255, LETDOWN LINE ISOL using CS-46133 RO

Place operating Charging pumps in MANUAL RO

If 2 Charging pumps are running then STOP one pump as follows:

o Reduce Speed of one Charging pump while Closing 1HC-142, CHG LINE FLOW CONT, and maintaining seal injection 6-10 gpm to each RCP.

Page 10 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS o Adjust 1HC-142, CHG LINE FLOW CONT until seal injection flow approx 9.5 gpm.

o STOP the Charging pump.

Adjust speed of inservice charging pump and RO 1HC-142 to maintain seal injection flow 6-10 gpm. Continue until 1HC-142 is closed.

RO

Place 1HC-135A, LTDN PRESS CONT in MANUAL and OPEN to about 50%

Initiate CC flow through Excess Letdown Heat RO Exchanger by OPENING MV-32095, 11 Excess LTDN HX CC INLT/OUTL RO

Position CV-31333, EXCESS LTDN DIVERT TO RCDT, to the V.C. TK position, using CS-46169

OPEN CV-31330, EXCESS LTDN HX INLT

Slowly OPEN CV-31210, EXCESS LTDN FLOW CONT RO

Monitor Pressurizer Level and adjust Excess Letdown flow as necessary LEAD

Notify Duty RP Tech to implement radiation surveys per PINGP 1483, Special Survey Checklist - Mixed Bed OOS.

Page 11 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SS TECH SPECS

LCO 3.4.14, RCS Leakage Condition A Action to reduce Leakage to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Identify Leakage within 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months .

Event 3 8. When the Crew has isolated the Letdown Heat C47012-0506, PRZR Power Relief Line Hi Temp Exchanger and addressed the Tech Spec and / or RO

Determine PORV PCV-430 is leaking based on:

at the discretion of the Lead Evaluator, ENTER the

Relief line temperatures malfunction to cause Pressurizer PORV leakage.

(Relative Order 3, Trigger 3). RO

Acoustic Monitors

a. If directed to prepare a team to enter

Close Block Valve for PCV-430 Containment, REPORT a team will be assembled and briefed in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

TECH SPECS SS

LCO 3.4.11, Each PORV and associated Block valve shall be OPERABLE.

Determine Condition A is not met and close block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Determine Condition D is not met; acknowledge a Unit shutdown is required within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(CRITICAL TASK 2)

Page 12 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4 9. When the Crew has stabilized Reactor power and/ 1E-0 Reactor Trip or Safety Injection or at the discretion of the lead evaluator, ENTER CREW

Perform immediate actions from memory.

the Loss of All AC Power and Bus 16 Lockout.

RO

Verify Reactor Trip (Relative Order 4, Trigger 4).

LEAD

Verify Turbine tripped, both stop valves closed.

NOTE: THIS EVENT WAS NOT USED DURING THE

Verify Safeguards busses energized EXAMINATION. LEAD

Bus 15 and Bus 16 are deenergized

a. LOOP and Bus 16 will not be repaired.

Transition to 1ECA-0.0. Loss of All Safeguards

b. If asked, report Unit 2 is at 100%, SI is NOT AC Power actuated.

c. If directed to cross connect 21 AFW pump to Unit 1 per 1C28.1, ENTER (Relative Order 5, 1ECA-0.0, Loss of All Safeguards AC Power Trigger 5). To: LEAD

Check if RCS is isolated:

1) CLOSE MV-32381, 12 MD AFWP to 11 o PRZR PORVS - Closed STM GEN o Close Isolation Valves CV-31255 and CV-

2) CLOSE MV-32382, 12 MD AFWP to 12 31266 STM GEN o Close Excess Letdown isolation valve CV-

3) CLOSE AF-13-4, 12 MD AFWP Discharge 31330 Valve

4) OPEN AF-13-1 and 2AF-13-1 LEAD

Verify AFW Flow - Greater than 200 GPM

5) Start 21 MD AFW pump. o Verify TD AFW pump running

6) Report 21 MD AFP Pump is running o Dispatch personnel to locally start pump.

available for Unit 1 use.

Perform Notifications

d. If asked the status of Bus 16, report an 86 SS o Announce Unit 1 Reactor Trip Lockout with 50-G flags.

1) The bus will not be restored. o Notify Shift Manager and SEC

e. If requested to Investigate breaker 25-17, LEAD

Check Cooling Water Header Pressures report the breaker is stuck between open and Page 13 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS closed. The Electricians are investigating. o Both Greater than 25 psig.

f. If asked to locally isolate the RCP seals,

Check if Safeguards busses are available for LEAD ENTER (Relative Order 6, Trigger 6) and loading:

Report RCP seals are isolated.

o Bus 16 - Available.

g. If asked to place PNL EM1-5, Circuit 4, Containment lighting to OFF, report PNL EM1- o Load rejection lights LIT 5, Circuit 4, Containment lighting is OFF o Lockout annunciator C47024-0104 OFF

h. If asked to open Foxboro instrument rack Annunciator is ON doors, report Foxboro instrument rack doors o Bus 15 - Available are Open.

i. If asked to as Engineering to transfer 480V o Load rejection lights LIT MCCs to Unit 2, report an Evaluation is o Lockout annunciator C47024-0101 OFF underway.

Attempt to Restore Power to any Safeguards Bus

j. After the Crew Has placed bus 15 loads in LEAD From Unit 1 Source pullout and / or at the discretion of the Lead o Energize available bus with Diesel Evaluator, DELETE DI-46943C, BKR 25-17 Generator Control Switch malfunction. Then REPORT o Determine no Unit 1 Source is available Breaker 25-17 has been swapped out and is ready to be Closed.

Attempt to Restore Power to any Safeguards Bus

k. The Crew may transition to either 1ECA-0.1 or LEAD From Unit 2 Source 1ECA-0.2 o Check bus tie breakers for either bus -

1) If the Crew transitions to 1ECA-0.1 and when AVAILABLE SI Flow is verified to not be required and/ or at o Unit 1 SI Actuated annunciator 47014-0604 the discretion of the Lead Evaluator, place the

- OFF Simulator in FREEZE.

2) IF the Crew transitions to 1ECA-0.2 and when Reset SI 11 SI Pump is running and/ or at the discretion o Unit 2 SI pumps - Both OFF of the Lead Evaluator, place the Simulator in o Bus 25 Energized FREEZE.

Page 14 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS o Place the following in PULLOUT 1R Source CT11 Source D1 DG Source o Check Unit 1 SI pump Breaker OPEN Manually OPEN Breakers o Close 4KV bus tie breakers for available bus:

Unit 2 bus tie breaker

Bus Tie Breaker fails to close

Locally Isolate RCP Seals LEAD

Place the following in PULLOUT LEAD o MD AFW pump o Group A & B PRZR heaters o RHR pumps o SI Pumps o CS Pumps o Containment FCU - OFF o CC Pumps o Control Room Chillers o 121 and 122 Air Compressors

Attempt to restore power from Unit 1 - No Source LEAD is available Page 15 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS LEAD

Attempt to restore power from Unit 2 - Bus Tie is Available LEAD

Energize bus 15 from Unit 2 Bus 25

Check is at Least One Safeguards Bus Energized o Bus 15 should be restored using the Bus tie Breakers

Verify the following loaded on Safeguards Bus o Bus 111 and 112 o Battery Charger o Instrument busses 111 and 113 o Start one Air Compressor CREW

Transition to 1ECA-0.2, Loss of all Safeguards AC Power Recovery with SI Required

OR

Transition to 1ECA-0.1, Loss of all Safeguards AC Power Recovery with SI Not Required 1ECA-0.1, Loss of all Safeguards AC Power Recovery with SI NOT Required

Check RCP Seal Isolated LEAD

Check Containment Isolation - NOT Actuated

Establish Instrument Air to Containment

Start one Air Compressor Page 16 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS LEAD

Start one CC Pump RO

Start one Charging pump LEAD

Start Containment FCUs

Start Control Room Chiller and fans

Check Cooling Water Pressure greater than 75 psig RO

Establish 30 GPM Charging Flow

Verify SI Not required o Subcooling greater than 20F o Pressurizer level greater than 7%

1ECA-0.2, Loss of all Safeguards AC Power Recovery with SI Required RO

Reset SI

Check RWST Greater THAN 33%

Verify SI Valve Alignment

RCP Thermal Barrier CC status o Previously Closed

Manually Start the Following LEAD o 11 SI Pump RO o 11 CC Pump Page 17 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 0 Annun M47024:1003W CW D1 Loss of Voltage 0 Annun M47024:1103W CW D1 Local Control 0 DI DI-46943C OFF BKR 25-17 Control Switch to OFF 1 Malfunction FW30 1 Heater Drain Tank Level Transmitter Fails LOW 2 Malfunction VC08 2 Letdown Heat Exchanger Tube Rupture into CC System 2a Malfunction VC08 DELETE Letdown Heat Exchanger Tube Rupture into CC System 3 Malfunction RC22A 50 3 Ramp 10 Min PORV PCV-430 Leakage 3 Override DI DI-46264C Close OFF 3 PORV Block Valve Switch 4 Malfunction ED14 4 Loss of all Offsite Power 4 Malfunction ED09F 4 60 Seconds Loss of 4160V Bus 16 Page 18 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 5 Remote FW136 0 5 Close MV-32381 5 Remote FW137 0 5 Close MV-32382 5 Remote FW157 CLOSE 5 120 Seconds Close AF-13-4 5 Remote FW156 OPEN 5 130 Seconds Open AF-13-1 and 2AF-13-1 5 Remote FW133 START 5 140 Seconds Start 21 MDAFW Pump 6 Remote VC120 0 6 Locally CLOSE MV-32166. Seal Return Isol Valvew 6 Remote VC100 0 6 Close VC-14-1, 11 RCP Seal Injection Throttle Valve 6 Remote VC101 0 6 Close VC-14-2, 12 RCP Seal Injection Throttle Valve 6 Remote CC106 0 6 Close CC-16-3, 11 RCP Bearing Cooling Water Return 6 Remote CC107 0 6 Close CC-16-2, 12 RCP Bearing Cooling Water Return Page 19 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

5. The scenario contains objectives for the desired tasks and relevant Yes No human performance tools.

1. The scenario content adequately addresses the desired tasks, through Yes No simulator performance, instructor-led training freezes, or both.

2. Plant PRA initiating events, important equipment, and important tasks Yes No are identified.

3. Turnover information includes a Daily At Power Risk Assessment Yes No provided by the PRA group.

4. The scenario contains procedurally driven success paths. Procedural Yes No discrepancies are identified and corrected before training is given.

5. The scenario guide includes responses for all communications to Yes No simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

6. The scenario includes related industry experience. Yes No

7. Training elements and specific human performance elements are Yes No addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Page 20 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 Simulator Exercise Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved. Yes No

2. All malfunctions and other instructor interface items were functional and Yes No responded to support the simulator scenario.

3. All malfunctions and other instructor interface items were initiated in the Yes No same sequence described within the simulator scenario.

4. All applicable acceptance criteria were met for procedures that were Yes No used to support the simulator scenario.

5. During the simulator scenario, observed changes corresponded to Yes No expected plant response.

6. Did the scenario satisfy the learning or examination objectives without Yes No any significant simulator performance issues, or deviations from the approved scenario sequence?

7. Evaluation: The simulator is capable of being used to satisfy learning Yes No or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Discrepancies noted (Check none or list items found) X None DR = Discrepancy Report DR: DR: DR: DR:

Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Page 21 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 SIMULATOR SETUP CHECKLIST Before Training

_____ Simulator in "Training Load"

_____ Step counters "ON"

_____ Alarm sound "ON"

_____ Recorder power "ON"

_____ Simulator Reset to correct IC (malfunctions, remotes, and overrides for Relative Order 0 conditions and conditions actuated by event triggers entered per "Simulator Input Summary")

_____ High Flux at Shutdown alarm placards updated to: 5000 cps

_____ Control Valve position placard on Turbine Panel updated to: CV-1 @ 35, CV-2 @ 100, CV-3 @ 100, and CV-4 @ 100

_____ Feedwater Reg Valve placard updated to: A @ 72/73, B @ 72/73

_____ MOC I sheet displayed on C panel

_____ Boric Acid/RMU integrators set to: BA: 3, RMU: 30, and reset

_____ Placard on CVCS Letdown panel updated: boron: 721

_____ Turbine reference/setter positions: 850/850

_____ Reactivity Guidance placard updated to: BA: 3 gal, RMU: 67 gal

_____ Chart recorders operating and forwarded (Paperless 'messages' not flashing red)

_____ ERCS driven recorders are on-scale

_____ All ERCS terminals operating

_____ ERCS alarm screen up and reset

_____ ERCS Group Displays update rate entered (5 seconds)

_____ ERCS TPM screen displayed, CALM and Auto selected

_____ I displayed on ERCS single point display #1 (1U1613A)

_____ Pens/Paper/Markers available on the simulator

_____ Turnover sheet/LCO log/PRA sheet/Protected Equipment sheet available

_____ Procedures to be used during scenario are cleaned of any place keeping marks

C47003-0503

C47022-0109

C47047-1R-39

1C14 AOP2

1C12.1

1C12.1 AOP3

LCO 3.4.14, RCS Leakage Condition A

C47012-0506

LCO 3.4.11, Condition A and D Page 22 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0

1E-0

1ECA-0.0

1ECA-0.1

1ECA-0.2

_____ Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

_____ Magnetic placards in place:

11 BA TANK "Lined Up For Service"

11 BA PUMP "Lined Up To 11 BA Tank"

CC TO SFP MV-32115 "In Service"

Blowdown 46470 "SGB To CDSR"

Protected equipment signs on:

o 12 AFW Pump o 12 RHR Pump o 12 SI Pump o 12 CS Pump o 12 CC Pump o 122 CR Chiller o 122 Air Compressor o 22 DD CL Pump o D2 Page 23 of 25

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC EXAM SCENARIO 4, HEATER DRAIN TANK LEVEL TRANSMITTER FAILURE, PZR PORV LEAKAGE, LETDOWN HX LEAK, LOSS OF ALL AC POWER, Rev. 0 After Training for the Day

_____ Information Tags removed and put away

_____ Signs/placards removed and put away unless normal simulator configuration

_____ Floor PCs logged off

_____ All books, note pads, and calculators put away

_____ Instructor station returned to normal with all books, paper, and etc. put away

_____ Headsets turned off and put away

_____ Simulator reset to IC-10 unless another IC will be used for further training

_____ ERCS computer restored to normal

_____ Simulator placed in DORT if simulator will not be used again that day

_____ Recorder power "OFF" Page 24 of 25

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 64 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS D1 OOS for fuel injector replacement, estimated return to service is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

PROTECTED EQUIPMENT 12 AFW Pump 12 RHR Pump 12 SI Pump 12 CS Pump 12 CC Pump 122 CR Chiller 122 Air Compressor 22 DD CL Pump D2 RAD MONITORS OOS ANNUNCIATORS OOS None None OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS None None OTHER EQUIPMENT OOS / STATUS 12 BATP OOS, seal replacement.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE OPERATIONAL PLANS FOR COMING SHIFT Adding 10 gallons of RMU 3-4 times per shift for Temperature Control NEW PROCEDURES / INSTRUCTIONS None WATCHSTANDERS LPEO: OURET, TRAVIS PEO: KEMPKES, JOHN LPEO Relieved By: Time: Date:

PEO Relieved By: Time: Date:

CB WALKDOWN LPEO: Time:

PEO: Time:

QF-1030-19 Rev. 4 (FP-T-SAT-30)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # 2005 NRC SCENARIO 6 LOSS OF REGEN HX/ STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS SEG TITLE: LEAK/LBLOCA WITH RHR FAILURE #: SCEN 6 REV. # 0 PROGRAM: INITIAL LICENSED OPERATOR #: P8100 COURSE: INITIAL LICENSED OPERATOR #: P8100 TOTAL TIME: 2 HOURS Developed by: J. Kempkes 3/11/05 Instructor Date Reviewed by:

Instructor Date Validated by:

Validation Lead Instructor Date Approved by:

Training Supervision Date Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 Guide Requirements During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of Training: the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Raise reactor power from 2% to 6% in preparation for turbine Learning roll per 1C1.2.

Objectives: 2. Respond to a regenerative heat exchanger outlet valve failing CLOSED per 1C12.1 AOP2, Loss of Charging Flow to the Regen HX.

3. Diagnose and Respond to a Steam Line Header Pressure Instrument failure.

4. Respond to a fire in the vicinity of the RHR pits per C47, F5 App D and F5 App A.

5. Respond to an RCS leak in containment per 1C4 AOP1.

6. Respond to a Large Break LOCA from the Pressurizer Surge Line per 1E-0 and 1E-1.

7. (If necessary) Respond to a Containment High Pressure condition per 1FR-Z.1.

Prerequisites: None

1. Full Scope Simulator Training 2. Operations Management Representative Resources: 3. Lead Evaluator

4. Human Performance Evaluator

5. Comment Recorder

6. Booth Operator (Primary Communicator)

7. Backup Communicator

1. 1C1.2 Startup Operation

References:

2. 1C12.1 AOP2, Loss of Charging Flow to the Regen HX

3. F5 Appendix A Fire Strategies

4. F5 Appendix D Effect of Fire Outside the Control Room

5. 1C4 AOP1 RCS Leak

6. 1E-0 Reactor Trip or Safety Injection

7. 1E-1 Loss of Reactor or Secondary Coolant Page 2 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 None Commitments:

Evaluation This is an evaluation scenario for the 2005 ILT NRC Exam, this is a Method: new scenario.

Operating None - Evaluation Scenario Experience:

Initiating Event with Core Damage Frequency:

Related PRA Large Break LOCA 1.2%

Information:

Important Components:

12 AFWP RHR Pumps Page 3 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Loss of Charging to Regen HX

2. Steam Header Pressure Fails Low

3. RCS Leak After EOP Entry:

1. 12 RHR Pump Start Failure/11 RHR Pump Lockout on Start Abnormal Events:

1. Regen HX Outlet Valve Fails Closed

2. Fire in Aux Building

3. RCS Leak Major Transients:

1. Large Break LOCA Critical Tasks:

1. Direct a power reduction to MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of determining RCS leakage is in excess of 10 gpm.

2. Start at least one RHR pump prior to reaching a RED condition on the Core Cooling CSF.

Page 4 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. Conditions based on IC-6, except reactor power is reduced to between .5 and 2%

(IC starts at 6% prior to turbine roll). Procedure 1C1.2 is in progress with the step 5.12 SM Hold having just been signed off.

2. 11 and 22 Component Cooling pumps are in service.

SEQUENCE OF EVENTS:

Event 1: Raise Reactor Power to approximately 6%

1. Rods are withdrawn to raise Tavg and increase steam flow through the steam dumps.

Event 2: Regen HX Charging Line Outlet CV fails CLOSED

CV-31328 fails CLOSED, causing greatly reduced charging flow and high charging pressure/charging relief lift.

Letdown is isolated and excess letdown placed in service per 1C12.1 AOP2.

Event 3: Steam Header Pressure fails low

Action to place Steam Dumps in Manual or reduce the setpoint of the PORVs

Reactivity transient will occur Event 4: Fire in the Auxiliary Building

Fire Detection Zone 8 alarms (695' Aux Building)

Fire is in the vicinity of Unit 1 RHR Pits.

12 CC pump is started and 12 AFWP placed in LOCAL per F5 App D.

Page 5 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 Event 5: RCS Leak

An 11 gpm (approx) RCS leak develops on the Pressurizer Surge Line.

Previous malfunctions prevent start of additional charging pumps, so excess letdown flow is reduced or stopped.

Leak is NOT isolable and is determined to be located in containment.

Technical Specifications require unit shutdown.

Event 6: Large Break LOCA

The pressurizer surge line shears causing a LBLOCA.

Neither RHR pump autostarts on the SI.

Page 6 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

This is an evaluation scenario and as such, tasks are not credited for training and therefore are not listed here.

Page 7 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC): (RO/LO

1. Initialize simulator to IC-6 (or exam IC) and allow /SRO)

ERCS to come up.

a. IF using IC-6, perform the following:

1) Insert rods to reduce reactor power to between 0.5 and 2% and stable.

2) Enter malfunctions and triggers.

Mode: 2

Exposure: ZBC

Power: 2%

Boron: (CB): 1850 ppm

Temperature: 552

Pressure: 2235

Xenon: Zero

Rods: As required

Generator: Offline

2. SIMULATOR SET UP

a. Reset the simulator to IC-6.

b. Place the simulator in RUN.

3. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary, to cause the following pre-existing conditions (Relative Order 0):

a. 11 RHR pump locks out

b. 12 RHR pump fails to Auto Start

4. Pull out 1C1.2 and sign through step 5.12 SM Hold.

5. Complete the Simulator Setup Checklist.

Page 8 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

6. COMPLETE TURNOVER: CREW Review the following with the offgoing operator:

a. UNIT 1 LPEO / PEO TURNOVER LOG

Unit 1 LPEO / PEO Turnover log (should be provided with the scenario IC)

b. Verify crew performs walk down of control Walk down the control boards and ask questions as boards and the reviews turnover checklists. appropriate.

Page 9 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1 7. Increase reactor power to 6% for turbine roll. Per 1C1.2 section 5.12:

8. If asked, to complete 1C1.2 Step 5.12.4, A,B,C, wait 2 Lead Log entry to MODE 1 when above 5% power.

minutes and report 1C1.2 Step 5.12.4, A,B,C are complete. RO Withdraw control rods to raise power to 6% while monitoring SG level (in auto) and steam dump (in auto)

Event 2 9. WHEN the crew has increased power to 6% and/ CREW Diagnose failure of outlet valve.

or at the discretion of the Lead Evaluator, enter the RO NOTE: One charging pump may be stopped, letdown failure of the Regen HX Outlet Valve CLOSED isolated and charging reduced to minimum as part of plant (Relative Order 2, Trigger 2) stabilization efforts at any time.

47015-0205 Charging Line High Pressure Verify charging pressure high at 1PI-133 Verify proper operation of 1HC-142, 11 CHG LINE FLOW CONTROL Check for charging pump speed control problem (none exists) 47015-0408 Letdown Flow Hi Temp Verify 1TCV-145 diverted to VCT Verify CC flow to letdown HX Verify charging/flow balance Verify CV-31203 Letdown Pressure Control is controlling.

47015-0509 Regen HX Letdown Line Hi Temp Verify temperature high Balance letdown and charging LEAD/ 1C12.1 AOP2 Loss of Charging Flow to the Regen HX RO Verify seal injection flow has not been lost.

Verify RMU controller in AUTO Page 10 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS IF VCT<17%, verify auto makeup has initiated.

CLOSE letdown orifice isolation valves.

CLOSE letdown isolation valves Place charging pumps in MANUAL speed control.

Place Excess letdown in service.

Page 11 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3 10. WHEN the crew has placed Excess Letdown in service Crew Plant Stabilization Actions and / or at the discretion of the Lead Evaluator, enter LEAD Control the Steam Dump in Manual the Steam Header Pressure PT-484 Instrument failure low. (Relative Order 3, Trigger 3) OR

a. If asked as I&C to trouble shoot the failed LEAD Adjust the PORV setpoint to 1005 psig Instrument, report an I&C Technician will be in the RO Control Reactor Power Control Room in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . RO Control Tave NOTE: There are no alarms associated with this malfunction. The operators will see the Steam Dumps close, RCS Temp increasing and Reactor power decreasing.

Event 4 11. WHEN the crew has stabilized Reactor Power and Tave LEAD 47022-0601 FIRE ALARM and / or at the discretion of the Lead Evaluator, enter Determine fire alarm is in ZONE 8 Aux Bldg 695' the Zone 8 Fire Alarm (Relative Order 4, Trigger 4)

Page Aux Building Operator WHEN called as Aux Building Operator, wait 2 minutes then Actuate the fire alarm call back and report a fire in progress on the north end of 11 Announce the fire and simulate fire brigade auto paging RHR pit, involving consumables and staged equipment, and could not be extinguished with one portable extinguisher. Notify the Red Wing Fire Department Establish radio communication with the Fire Brigade Chief Two minutes after the Fire page, come up on the radio as SS Consult Att A of ARP the Fire Brigade Chief and receive a turnover on the fire report. Lead Start 12 CC pump per F5 App D Direct local control of 12 AFWP per F5 App D Inform the SS that "Unit 2 will perform classification and Reset fire panel notification."

Verify auto starts of fire pumps When directed to open breakers per C47022-0611 Notify Security of RWFD arrival Attachment A for Zone 8, enter (Relative Order 4c, Trigger Notify Fire Protection/Industrial Safety 10), then report the breakers are open.

Consult Technical Specifications for inoperability of 12 Page 12 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SS AFWP while in LOCAL (3.7.5 Cond B, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

WHEN directed, place 12 AFWP in LOCAL (Relative Order 4a, Trigger 5)

WHEN 12 CC pump is started AND local control of 12 AFWP is completed, report "Fire is OUT and damage is limited to material in storage area."

As the Unit 2 SS report, Unit 2 will take over the actions for the fire.

One minute later, DELETE the fire alarm malfunction (Relative Order 4b)

Page 13 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5 12. WHEN the crew has assumed the Tech Spec for RO Note lowering pressurizer level and adjust charging 12 AFW pump and / or at the discretion of the Lead or excess letdown flow to stabilize.

Evaluator, enter the 11 gpm RCS Leak (Relative 47012-0508 Pressurizer Hi/Lo Pressure Order 5, Trigger 6)

Check pressure low.

Note: The high radiation alarm takes 5 minutes to come Verify all pressurizer heaters ON in. Verify both pressurizer PORVs closed

13. When the Crew has entered LCO 3.4.14 Condition Verify aux spray valve closed A, report as the Event Team Leader, a Verify pressurizer pressure control operating in Containment Entry has been made and the leak is SS AUTO coming from a crack on the Pressurizer Surge Line. Refer to TS 3.4.1 (DNB) if <2190 psig RCS pressure LEAD/

SS Initiate RCS leakrate using ERCS 'LEAK' program LEAD 47022-0108 Train B High Radiation Determine alarm is 1R-11/1R-12 1C4 AOP1 RCS LEAK RO

Continuous action* Verify RCS inventory can be maintained by available charging flow. IF NOT, trip the reactor, initiate SI and exit C4 AOP1.

LEAD Determine location of leak using Figure 1.

(Containment radiation monitors and humidity will change)

Remove excess letdown from service and recalculate leakrate.

Close CV-31198 Charging FCV and recalculate leakrate Page 14 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Isolate charging to the RCP seals:

Verify both RCP TBHX CC valves open LEAD

Stop the running charging pump and recalculate leakrate

Restore seal injection by restarting charging pump once determined leak not isolated SS

When the leak location is unidentified:

o Refer to LCO 3.4.14 Condition A for total leakage not within limit of 10 gpm.

o Action to reduce leakage less than 10 gpm within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

When the leak location is identified:

o Refer to LCO 3.4.14 Condition D o Action to direct/recognize a power reduction to Mode 3 is required within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

o (CRITICAL TASK)

Notify Operations Manager and Resident Inspector of entry to C4 AOP1 Page 15 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6 14. WHEN the crew has addressed the Tech Spec for SS 1E-0 Reactor Trip or Safety Injection RCS leak and / or at the discretion of the Lead RO

Direct entry to 1E-0 Evaluator, enter the Large Break LOCA (increase

Verify reactor trip RC10 severity to 100%) (Relative Order 6). o Trip/bypass breakers OPEN

15. 1E-0 Implementation o Flux decreasing

a. If requested, report that all category 1 vent o RPIs at 0 doors are closed. Lead o Rod bottom lights LIT

b. If requested, report all Turbine Building roof Lead

Verify Turbine Trip exhausters are stopped. RO

Verify both safeguards buses energized

c. If requested to isolate Unit 1 MSRs per Attachment J, perform the following:

Verify SI actuated

1) Bring up the CAEP Window Lead Note: RCP trip criteria should be checked and

2) Click on OPEN File RCP's stopped. For a LBLOCA, this is not a

3) Click on Attachment J-E0 .cae RO critical task.

4) Click on Run button

Perform E-0 Att. L (see attached procedure

16. After 12.5 minutes, Report that Unit 1 MSRs are section) isolated per 1E-0 Attachment J o Start 12 RHR pump (Critical Task) o Manually actuate Containment Spray if >23 NOTE: IF directed to investigate, report 11 RHR pump psig has a 51A overcurrent flag and an 86 lockout flag.

Check AFW Status (>200 gpm and >900 psig)

NOTE: IF directed to repair, report after 30 minutes the o Locally start 12 AFWP if necessary motor failed its megger and must be replaced, ETR

Check RCS Cold Leg Temp 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . o Verify no steam dump in progress NOTE: IF directed to locally start 12 AFWP, wait 2 o Throttle AFW flow to just above 200 gpm minutes and enter DI-5151802 START (Relative unless either SG is >50% WR, then it may Order 7, Trigger 7) be throttled further or stopped o Verify both MSIV's closed (ctmt press auto close)

Check Pzr PORVs and spray valves closed Page 16 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS (E-0 continued) RO

Check/verify RCP's stopped

Check SG's not faulted o RO should use steam tables, SS may use ERCS plot 'SGTEMP'

Check SG's not ruptured o R-15, R-19, R-51, R-52 normal

Check RCS intact o Containment radiation R-2, 7, 11, 12 high o Containment pressure abnormal SS

Transition to 1E-1

17. E-1 Loss of Reactor or Secondary Coolant RO

Verify RCP's stopped

18. If asked as Unit 2, report Unit 2 will unload diesel Lead

Verify SGs not faulted generators as required.

Control AFW flow to maintain 50-59% WR SG RO

Check secondary radiation NORMAL

Check Pzr PORV's/blocks closed Lead

Reset SI

Reset CI

Open Instrument Air to Ctmt valves

Verify offsite power to safeguards buses RO

Establish at least 1 charging pump running

Verify SI cannot be terminated

Verify SI pump cannot be stopped

Verify RCS and SG pressures stable (no loop)

SS

Stop unloaded DG's (D1/D2) NOTE: May be done by Unit 2 operators Page 17 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

19. WHEN the crew verifies SI can not be stopped and Crew Assemble near fire detection panel while evaluators

/or at the discretion of the Lead Evaluator, place consult the simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented

20. The Classification will be performed by the SS after the conclusion of the Scenario.

a. The EAL for this Scenario is SAE on 2C.

Page 18 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SIMULATOR INPUT

SUMMARY

Relative System Or Order Panel Severity Event Drawing Type Code Or Value Trigger Timing Description 0 SIMRH01 MALF RH01A 11 RHR pump lockout on start 0 SIMRH01 MALF RH02B 12 RHR pump fails to start in AUTO 2 C1-C26 OVRD DI DI-46296O OFF 2 Regen HX outlet valve CV-OPEN 31328 fails CLOSED 3 D1-D5 REMOTE RX225 1 3 Steam Header Pressure Fails LOW (PT-484) 4 FDP-4 REMOTE CH121 8 4 Zone 8 Fire Alarm 4a SIMFW08 OVRD DI DI-51517 ON 5 12 AFWP local control LOCAL 4b FDP-4 REMOTE CH121 DELETE Zone 8 Fire Alarm 4c OVRD DO LO-46203R OFF 10 MV-32 breaker OFF Page 19 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SIMULATOR INPUT

SUMMARY

Relative System Or Order Panel Severity Event Drawing Type Code Or Value Trigger Timing Description 4c OVRD DO LO-46027G OFF 10 MV-32 breaker OFF 4c OVRD DO LO-46027R OFF 10 MV-32 breaker OFF 4c OVRD DO LO-46204G OFF 10 MV-32 breaker OFF 4c OVRD DO LO-46205G OFF 10 MV-32 breaker OFF 4c OVRD DO LO-46316R OFF 10 MV-32 breaker OFF 4c OVRD DO LO-46317R OFF 10 MV-32 breaker OFF 5 SIMRC03 MALF RC10 0.011 6 RCS Leak 11 GPM- Surge Line 6 SIMRC03 MALF RC10 100 Pzr Surge Line Shear 7 SIMFW08 OVRD DI DI-5151802 ON 7 Local start 12 AFWP START Page 20 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 SIMULATOR SETUP CHECKLIST Before Training

_____ Simulator in "Training Load"

_____ Step counters "ON"

_____ Alarm sound "ON"

_____ Recorder power "ON"

_____ Simulator Reset to correct IC (malfunctions, remotes, and overrides for Relative Order 0 conditions and conditions actuated by event triggers entered per "Simulator Input Summary")

_____ High Flux at Shutdown alarm placards updated to: 5000 cps

_____ Control Valve position placard on Turbine Panel updated to: CV-1 @ 0, CV-2 @ 0, CV-3

@ 0, and CV-4 @ 0

_____ Feedwater Reg Valve placard updated to: A @ 0/0, B @ 0/0

_____ ZBC I sheet displayed on C panel

_____ Boric Acid/RMU integrators set to: BA: 3, RMU: 10, and reset

_____ Placard on CVCS Letdown panel updated: boron: 1850

_____ Turbine reference/setter positions: 0/0

_____ Reactivity Guidance placard updated to: BA: 3 gal, RMU: 67 gal

_____ Chart recorders operating and forwarded (Paperless 'messages' not flashing red)

_____ ERCS driven recorders are on-scale

_____ All ERCS terminals operating

_____ ERCS alarm screen up and reset

_____ ERCS Group Displays update rate entered (5 seconds)

_____ ERCS TPM screen displayed, NIS selected

_____ I displayed on ERCS single point display #1 (1U1613A)

_____ Pens/Paper/Markers available on the simulator

_____ Turnover sheet/LCO log/PRA sheet/Protected Equipment sheet available

_____ Procedures to be used during scenario are cleaned of any place keeping marks 47015-0205 47015-0408 47015-0509 47022-0601 Tech Spec 3.7.5 Condition B Tech Spec 3.4.14 47022-0611 47012-0508 Page 21 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 6, LOSS OF REGEN HX/STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS LEAK/LBLOCA WITH RHR FAILURE, REV 0 47022-0108 1C1.2 Startup Operation 1C12.1 AOP2, Loss of Charging Flow to the Regen HX F5 Appendix A Fire Strategies F5 Appendix D Effect of Fire Outside the Control Room 1C4 AOP1 RCS Leak 1E-0 Reactor Trip or Safety Injection 1E-1 Loss of Reactor or Secondary Coolant

_____ Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

_____ Magnetic placards in place:

11 BA TANK "Lined Up For Service"

11 BA PUMP "Lined Up To 11 BA Tank"

CC TO SFP MV-32115 "In Service"

Blowdown 46470 "SGB To CDSR" After Training for the Day

_____ Information Tags removed and put away

_____ Signs/placards removed and put away unless normal simulator configuration

_____ Floor PCs logged off

_____ All books, note pads, and calculators put away

_____ Instructor station returned to normal with all books, paper, and etc. put away

_____ Headsets turned off and put away

_____ Simulator reset to IC-10 unless another IC will be used for further training

_____ ERCS computer restored to normal

_____ Simulator placed in DORT if simulator will not be used again that day

_____ Recorder power "OFF" Page 22 of 23

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 64 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS None PROTECTED EQUIPMENT None RAD MONITORS OOS ANNUNCIATORS OOS None None OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS None None OTHER EQUIPMENT OOS / STATUS 12 BATP OOS, seal replacement MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE None OPERATIONAL PLANS FOR COMING SHIFT Start up in progress, continue with 1C1.2 at step 5.12. Increase power to 6% for Turbine roll.

Xenon is starting to build in, diluting 25 gallons every 20 minutes to maintain power.

NEW PROCEDURES / INSTRUCTIONS None WATCHSTANDERS LPEO: OURET, TRAVIS PEO: KEMPKES, JOHN LPEO Relieved By: Time: Date:

PEO Relieved By: Time: Date:

CB WALKDOWN LPEO: Time:

PEO: Time:

Page 23 of 23

QF-1030-19 Rev. 4 (FP-T-SAT-30)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: PRAIRIE ISLAND SEG # 2005 NRC SCENARIO 7 RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SEG TITLE: SGTR WITH LOSS OF COOLING WATER #: SCEN 7 REV. # 0 PROGRAM: INITIAL LICENSED OPERATOR #: P8100 COURSE: INITIAL LICENSED OPERATOR #: P8100 TOTAL TIME: 1.5 HOURS Developed by: J. Kempkes 3/14/05 Instructor Date Reviewed by:

Instructor Date (See page 10, Simulator Development Checklist.)

Validated by:

Validation Lead Instructor Date (See page 11, Simulator Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 Guide Requirements During all plant operating conditions, the crew will demonstrate Goal of the ability to monitor and operate the plant within the limits of Training: the Operations Manuals and Technical Specifications.

When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. Raise reactor power to the POAH per 1C1.2.

Learning 2. Respond to loss of 12 AFW pump at lower power per C47.

Objectives: 3. Respond to loss of CR Chillers per C37 and Tech Specs.

4. Diagnose and respond to tube leakage into 11 SG per 1C4 AOP2 and C47.

5. Respond to a Steam Generator Tube Rupture with Loss of Offsite Power/Bus 15 lockout per 1E-0 and 1E-3.

6. Respond to a loss of Train B Cooling Water Header per C47 and C35 AOP1.

Prerequisites: None

1. Full Scope Simulator Training 2. Operations Management Representative Resources: 3. Lead Evaluator

4. Human Performance Evaluator

5. Comment Recorder

6. Booth Operator (Primary Communicator)

7. Backup Communicator

1. C47

References:

2. 1C14 AOP2

3. 1C4 AOP2

4. 1E-0

5. 1ES-0.1

6. 1E-3

7. C35 AOP1 None Commitments:

Page 2 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 Evaluation This is an evaluation scenario for the 2005 ILT NRC Exam, this is a Method: new scenario.

Operating None - Evaluation Scenario Experience:

Initiating Event with Core Damage Frequency:

Related PRA Steam Generator Tube Rupture (18%)

Information: Loss of Cooling Water (2%)

Important Components:

121 Cooling Water Pump Page 3 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. 12 AFW Pump Lockout

2. 11 SG Tube Leak After EOP Entry:

1. Loss of Offsite Power

2. Lockout of Safeguards 4160V Bus 15

3. Failure of 22 Cooling Water Pump Abnormal Events:

1. Loss of Control Room Chillers

2. SG Tube Leak Major Transients:

1. Loss of Offsite Power

2. Steam Generator Tube Rupture Critical Tasks:

1. Recognize Tech Spec 3.0.3 entry for both Units due to inoperable Control Room Chillers.

2. Cooldown and depressurize the RCS and terminate SI prior to 11 SG going water solid.

Page 4 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. Initialize the simulator to IC-26:

Startup in progress per 1C1.2 at step 5.9.17, reactor power 10-8A, Appendix C1B was just completed

Next step is to increase power to the POAH

2. No equipment is OOS:

SEQUENCE OF EVENTS:

Event 1: Raise Reactor Power to the POAH

Per 1C1.2 Event 2: Lockout of 12 AFW pump

12 AFW pump locks out requiring action to start 11 TD AFW pump Event3: Loss of Control Room Chillers

Loss of 121 CR Chiller with 122 CR Chiller failure to auto start

Action to shutdown IAW LCO 3.0.3.

Chiller restored prior to commencing unit shutdown Event 4: Steam Generator Tube Leak

A 50 gpd tube leak develops on 11 SG.

R-19 is used due to MSIVs being Closed.

Leakage is estimated per Duty Chemist.

Action Level 2 is entered (>30, <75 gpd leakage)

Event 5: Loss of Offsite Power with Bus 15 Lockout and Loss of Cooling Water

Offsite power is lost and Bus 15 locks out.

22 DDCLP fails to start.

Page 5 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 Event 6: Steam Generator Tube Rupture

After transfer to 1ES-0.1 Reactor Trip Recovery, a SGTR occurs on 11 SG.

1E-0 is reentered following manual or automatic SI actuation.

Loop A CL Pressure is lost on SI.

121 Cooling Water Pump must be aligned to Loop A.

1E-3 is used to isolate 11 SG and terminate SI.

Page 6 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

This is an evaluation scenario and as such, tasks are not credited for training and therefore are not listed here.

Page 7 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC-26):

IC-26

Mode: 2

Exposure: ZBC

Power: 10-8A

Boron: (CB): 1850 ppm

Temperature: 549 F

Pressure: 2235

Xenon: 0

Rods: Manual

Generator: Offline

1. SIMULATOR SET UP

a. Reset the simulator to IC-26.

b. Place the simulator in RUN.

2. Enter the malfunctions, remotes, and overrides, as specified by the Simulator Input Summary, to cause the following pre-existing conditions (Relative Order 0):

a. 122 CR Chiller auto start failure.

3. Pull out 1C1.2 and sign off step up to and including 5.9.16.

4. Complete the Simulator Setup Checklist.

5. COMPLETE TURNOVER: CREW Review the following with the offgoing operator:

a. UNIT 1 LPEO / PEO TURNOVER LOG

Unit 1 LPEO / PEO Turnover log

b. Verify crew performs walk down of control Walk down the control boards and ask questions as boards and the reviews turnover checklists. appropriate.

Page 8 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1 6. Increase Reactor Power to the POAH Crew 1C1.2 Unit 1 Startup Procedure

Increase Power to approximately 2%.

Event 2 7. WHEN the Crew has initiated the power increase C47010-0107, 12 AFW Pump Locked Out and / or at the discretion of the Lead Evaluator, Lead

Dispatch operator to inspect breaker 16-3 THEN enter the Lockout of 12 AFW Pump.

(Relative Order 1, Trigger 1)

Notify Electrical Department

a. IF asked to investigate the 12 AFW pump, report the motor is hot to the touch and breaker Tech Specs 16-3 has a 50G Flag. SS

b. If asked, the status of the AFW Prestartup LCO 3.7.5 Condition B Checklist, report the AFW Prestart Checklist is

72 Hour action to return 12 AFW to service complete.

c. If asked, as the Duty Chemist, Report Chemical Feed is aligned for starting 11 AFW Pump. LCO 3.0.4

d. If asked to verify local operation, report 11 TD

A mode change to Mode 1 can not be made AFW Pump local start checks are complete.

(Step 5.1.10) 1C28.1 Auxiliary Feedwater LEAD

Close MV-32238, 11 TD AFWP Discharge Valve

Close MV-32239, 11 TD AFWP Discharge Valve

Place CS-46438, 11 TDAFW Pump selector switch in Manual.

Start 11 TD AFWP using CS-46424 Page 9 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3 8. WHEN the crew manually started 11 TD AFW pump C47022-0302, 121 CR Water Chiller Tripped and / or at the discretion of the Lead Evaluator, LEAD/

Enter LCO 3.7.11 THEN, enter the loss of Control Room Chillers.

(Relative order 2, Trigger 2). SS

Refer to C37.11 AOP 1

a. If ask to investigate 121 CR Chiller, wait 2

Determine cause of trip locally minutes and report as the Aux building C37.11 AOP 1, Loss of Safeguards Chilled Water operator, 121 CR Chiller has tripped on high motor temperature.

Enter to LCO 3.7.11 Condition E

b. Report as Unit 2, Unit 2 will take C37.9 AOP 1 SS

Requires entry into LCO 3.0.3 due to both and C37.9 AOP 2 and address Unit 2 Tech trains of safeguards cooling lost.

Specs.

CRITICAL TASK

c. After the Crew enters LCO 3.0.3 and at the discretion of the Lead Evaluator DELETE 122

Action to be in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months CR Chiller auto start malfunction (Relative Order 2a) and report as the WIN team, the 122 Crew may or may not:

CR chiller auto start relay has been repaired and you recommend starting the chiller.

Refer to C37.9 AOP 1

Refer to C37.9 AOP 2 After 122 CR Chiller is restarted,

Enter LCO 3.7.11 Condition A.

Action to restore 121 CR chiller in 30 days.

Page 10 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4 9. WHEN the Crew exits LCO 3.0.3 and / or at the 1C4 AOP2 Steam Generator Tube Leak discretion of the Lead Evaluator, THEN enter the LEAD

Monitor R-19 (maybe isolated if Blowdown is not Steam Generator Tube Leak (Relative Order 3, reset)

Trigger 3).

a. Call as the Duty Chemist and report daily SG

Direct Duty Chemist to obtain Samples sample has been taken and 11 Steam LEAD

Notify Ops Manager and NRC Resident Inspector Generator Cation Column was frisked. The 11

Direct Duty Chemist to determine Leak Rate SG Cation Column has higher than normal activity.

Verify no Blowdown to the river

b. If asked for additional sample, report the

Determine Action Level 2 is appropriate based on backup sample shows Primary to Secondary no R-15 data Leakage on 11 Steam Generator is 80 gpd LEAD

c. When C4 AOP2 is entered, as the Duty Chemist, Report Primary to Secondary Leakage on 11 Steam Generator is 80 gpd.

d. As the Ops Manager and / or NRC Resident acknowledge entry into the AOP.

e. When asked, report AR-8-2 is open and AR-8-1 is closed.

Page 11 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5 10. After the Crew determines Action Level 2 is RO 1E-0, Reactor Trip or Safety Injection appropriate and / or at the discretion of the Lead LEAD

Verify Reactor Trip Evaluator, THEN enter the Loss of Offsite Power

Verify Turbine Trip with Bus 15 Lockout and Loss of Cooling Water

Verify Both Safeguards Busses energized (Relative Order 4, Trigger 4).

Check if SI is actuated

a. If asked to investigate Bus 15 Lockout, Report

Transition to 1ES-0.1, Reactor Trip Recovery Bus 15 has a 50G Flag

b. If asked to investigate 22 Cooling Water pump, 1ES-0.1, Reactor Trip Recovery report, 22 Cooling Water Pump has an air leak SS

Announce Unit 1 Reactor Trip and will not be able to be started. RO

Transfer Steam Dump to Pressure Mode

11. 1E-0 Implementation LEAD

Check RCS Temperature stable at 547F

a. If requested, report that all category 1 vent

Check Cooling Water Header Pressures greater doors are closed.

than 75 psig

b. If requested, report all Turbine Building roof exhausters are stopped.

RO

Check Feedwater Status

c. If requested to isolate Unit 1 MSRs per o RCS Temp Attachment J, perform the following: o MFRV Closes RO

1) Bring up the CAEP Window o Total AFW Flow greater than 200gpm

2) Click on OPEN File

Verify all rods inserted

3) Click on Attachment J-E0 .cae

Check Pressurizer level greater that 15%

4) Click on Run button

Verify Charging and Letdown in service

5) After 12.5 minutes, Report that Unit 1

Check Pressurizer pressure greater than LEAD / 1830psig MSRs are isolated per 1E-0 Attachment J RO

Manually actuate SI and transition to 1E-0, Event 6 12. When the Crew transitions to 1ES-0.1, and at the discretion of the Lead Evaluator, ENTER the Steam Reactor Trip or Safety Injection.

Generator Tube Rupture. (Relative Order 5, Trigger 5). NOTE: The transition to 1E-0 can be made at step 9 on PZR Pressure or from the Info Page based on PZR level less than 5%.

Page 12 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

13. 1E-0 implementation, continued. RO 1E-0, Reactor Trip or Safety Injection LEAD

Verify Reactor Trip

Verify Turbine Trip NOTE: The Lead will be investigating the loss of

Verify Both Safeguards Busses energized Cooling Water Header pressure while the RO Continues RO

Check if SI is actuated with the EOP LEAD

Perform Attachment L o Cooling Water Pressure will be low o Enter C35 AOP1, Loss of Pumping RO Capacity or Supply Header with SI.

Check Total AFW flow greater than 200 gpm

Check RCS temperature stable or trending to 547F

Check PZR PORVs Closed

Check PZR Spray valves Closed RO

Check if RCPS should be stopped.

Check if SG are not Faulted

Check if SG Tubes are not ruptured o Transition to 1E-3, Steam Generator Tube Rupture Page 13 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

14. C35 AOP 1 implementation LEAD C35 AOP1, Loss of Pumping Capacity or Supply Header with SI

Place 121 Cooling Water Pump in PULLOUT

Reset SI

Close MV-32034, 121 CLG WTR HDR VLV A

OR

Close MV-32035, 121 CLG WTR HDR VLV B Verify the following due to no power:

Open MV-32036, 121 CLG WTR HDR VLV C

Open MV-32037, 121 CLG WTR HDR VLV D

Start 121 Cooling Water Pump CRITICAL TASK

15. 1E-3 implementation LEAD / 1E-3, Steam Generator Tube Rupture RO

Check if RCPs should be stopped

Identify Ruptured SG o Determine 11 SG is Ruptured

Isolate Flow from 11 SG o Verify PORV setpoint is 75%

o Check PORV Closed o Closed Steam Supply from 11 SG to TD AFW pump o Verify 11 SG blowdown valves are closed

Close 11 SG MSIV and Bypass

Stop Feed flow to 11 SG

Reset SI

Check 11 SG pressure greater than 210psig

Initiate RCS Cooldown

Dump steam from 12 SG PORV Page 14 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

Stop Cooldown when reach required CETC temp

Check 12 SG Level - Control level 5-50%

Check PZR PORVS Closed

Check Block valves - at least one open

Reset SI

Reset Containment Isolation LEAD /

Establish Instrument Air to Containment RO

Stop both RHR Pumps

Check Charging Pumps - at least one running

Align Charging to RWST

Establish Max Charging flow

Check 11 SG pressure stable or increasing

Check RCS Subcooling - greater than 40F

Depressurize RCS using PORV

Check if SI flow should be terminated o RCS Subcooling - greater than 20 o Total feed flow - greater than 200 gpm o RCS pressure stable or increasing o PZR level - greater than 7%

LEAD /

Stop Both SI Pumps RO CRITICAL TASK

16. WHEN the crew stops the SI Pump in 1E-3 and / or Assemble near fire detection panel while evaluators at the discretion of the Lead Evaluator, place the consult simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented Page 15 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

17. The Classification will be performed by the SS after the conclusion of the Scenario.

a. The EAL for this Scenario is SAE on 4E Page 16 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 0 Override DI DI-46076 ST OFF 122 CR Chiller Auto Start START Failure 1 Malfunction FW32 1 12 AFW Pump Lockout 2 M47022:0302 Cry Wolf 2 121 CR Chiller Trip 2 Override DI DI-46068 PTL ON 2 121 CR Chiller Breaker Trip 2a Override DI DI-46076 ST DELETE 122 CR Chiller Auto Start START Failure 3 Malfunction SG01A .001 3 11 SG Tube Leak 50 gpd 4 Malfunction ED14 4 Loss of Offsite Power 4 Malfunction ED09E 4 Bus 15 Lockout 4 Override DI DI-46523P ON 4 22 CL Pump Failure PTL Page 17 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 5 Malfunction SG02A 10 5 120 Sec Steam Generator Tube Ramp Rupture- 11 SG, 300 gpm 6 Remote MS-138 CLOSE 6 MV-32016 close without power Page 18 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 SIMULATOR SETUP CHECKLIST Before Training

_____ Simulator in "Training Load"

_____ Step counters "ON"

_____ Alarm sound "ON"

_____ Recorder power "ON"

_____ Simulator Reset to correct IC (malfunctions, remotes, and overrides for Relative Order 0 conditions and conditions actuated by event triggers entered per "Simulator Input Summary")

_____ High Flux at Shutdown alarm placards updated to: 5000 cps

_____ Control Valve position placard on Turbine Panel updated to: CV-1 @ 0, CV-2 @ 0, CV-3

@ 0, and CV-4 @ 0

_____ Feedwater Reg Valve placard updated to: A @ 0/0, B @ 0/0

_____ ZBC I sheet displayed on C panel

_____ Boric Acid/RMU integrators set to: BA: 3, RMU: 10, and reset

_____ Placard on CVCS Letdown panel updated: boron: 1850

_____ Turbine reference/setter positions: 0/0

_____ Reactivity Guidance placard updated to: BA: 3 gal, RMU: 67 gal

_____ Chart recorders operating and forwarded (Paperless 'messages' not flashing red)

_____ ERCS driven recorders are on-scale

_____ All ERCS terminals operating

_____ ERCS alarm screen up and reset

_____ ERCS Group Displays update rate entered (5 seconds)

_____ ERCS TPM screen displayed, NIS selected

_____ I displayed on ERCS single point display #1 (1U1613A)

_____ Pens/Paper/Markers available on the simulator

_____ Turnover sheet/LCO log/PRA sheet/Protected Equipment sheet available

_____ Procedures to be used during scenario are cleaned of any place keeping marks

1C1.2

C47010-0107

LCO 3.7.5 Condition B

LCO 3.0.4

1C28.1

C37.11 AOP 1

C37.9 AOP 1 Page 19 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0

C37.9 AOP 2

LCO 3.7.11 Condition A.

LCO 3.0.3

C47022-0108

C47048 1R-19

1C4 AOP2

1C28 AOP4

1E-0

1ES-0.1

C35 AOP1

1E-3

_____ Log in on floor PCs using user ID: <pitrgsim> (password is the same as user ID)

_____ Magnetic placards in place:

11 BA TANK "Lined Up For Service"

11 BA PUMP "Lined Up To 11 BA Tank"

CC TO SFP MV-32115 "In Service"

Blowdown 46470 "SGB To CDSR"

Protected equipment signs on:

Page 20 of 22

QF-1030-19 Rev. 4 (FP-T-SAT-30) 2005 NRC SCENARIO 7, RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER, Rev 0 After Training for the Day

_____ Information Tags removed and put away

_____ Signs/placards removed and put away unless normal simulator configuration

_____ Floor PCs logged off

_____ All books, note pads, and calculators put away

_____ Instructor station returned to normal with all books, paper, and etc. put away

_____ Headsets turned off and put away

_____ Simulator reset to IC-10 unless another IC will be used for further training

_____ ERCS computer restored to normal

_____ Simulator placed in DORT if simulator will not be used again that day

_____ Recorder power "OFF" Page 21 of 22

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 64 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS None PROTECTED EQUIPMENT None RAD MONITORS OOS ANNUNCIATORS OOS None None OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS None None OTHER EQUIPMENT OOS / STATUS None MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE None OPERATIONAL PLANS FOR COMING SHIFT Continue with Unit Startup. Raise Power to the POAH per 1C1.2.

NEW PROCEDURES / INSTRUCTIONS None WATCHSTANDERS LPEO: OURET, TRAVIS PEO: KEMPKES, JOHN LPEO Relieved By: Time: Date:

PEO Relieved By: Time: Date:

CB WALKDOWN LPEO: Time:

PEO: Time:

Page 22 of 22

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Prairie Island U1/U2 Sce nario No.: 1 Op -Test N o.: 2005301 Exam iners: D. McN eil Operators:

D. Ree ser C. Zoia Initial Conditions: Initial Con ditions: 100% Pow er, BO C, S tand ard IC "A" Tu rnov er: Turnov er: Break er 16 -10 a nd 1 1 T D A FW Pum p O OS .

Event Malf. No. Event Event No. Type* Description 1 RD0916 I Failed RPI Rod G7 (AOP) 2 TC03 C/R Turbine Control Valve Cycling (AOP) (Reactivity for RO) 3 CL01A C 11 Cooling W ater Pump T rip 3a CL03 C 121 C ooling W ater Pum p Fails to Autostart 3c CL02A C 12 & 22 C ooling W ater Pum ps Fail to Autostart DI-46038C 4 C Isolation of CL to Unit 1 Turbine Building Close 5 RP07 C Rx Trip Breakers Mechanically Stuck 6 MS01B M 12 SG Steamline Break in Containment (Inserts on Rx Trip) 7a FW 34B C 12 AF W P Auto Start Failure 7b SI05 A/B C Both SI Pum ps Fail to Autostart 7c RP06 C MSIVs Fail to Auto Close

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Prairie Island U1/U2 Sce nario No.: 2 Op -Test N o.: 2005301 Exam iners: D. McN eil Operators:

D. Ree ser C. Zoia Initial Conditions: 100 % Pow er, BO C, S tand ard IC "A" Tu rnov er: Breaker 16-10 and 11 TD AFW Pump O OS. Start 13 Charging Pump and stop 12 Charging Pump in preparation for isolation of 12 Charging Event M alf. Event Event No. No. Type* Description 1 N/A N Swap from 11-12 Chg to 11-13 Chg in service 2 RX206 I PRZR Level controlling channel fails Low 10-Bank Oil Leakage reported, requiring transfer of one 3 N/A C safeguards 4160V bus to alternate source in anticipation of loss (AOP) 47012-4 C High Vibration on 12 RCP (AOP) (Power reduction required) 0203 5 RC03B M 12 RC P Sha ft Shear Turbine Auto Trip Failure (Note: Events 5-8 required to reduce SG 6 TC06 C inventory enough to cause loss of heat sink post trip) 6 RP06 C MS IV Auto Closure Failure 6 TC01A C Turbine Le ft Stop Valve Closure F ailure 6 TC14C C Tu rbine CV -3 Fails As Is 7 FW 27B C FC V 476 (12 Main Fe ed Re g) Fa ils C losed on Trip 8 ED02B C Bus 12 Auto Tran sfer Failure 9 FW 32 M MD AF W Pump T rip on Start- Loss of Heat Sink

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Prairie Island U1/U2 Sce nario No.: 6 Op -Test N o.: 2005301 Exam iners: D. McN eil Operators:

D. Ree ser C. Zoia Initial Conditions: 2% Power Prior to Turbine Roll in 1C1.2 Startup Tu rnov er: No Equipment OOS, Raise power to 6% per 1C1.2 Event Malf. No. Event Event No. Type* Description 1 N/A R Ra ise po wer to 6% per 1 C1 .2 DI-46296O 2 C Regen HX Charging Line Outlet FCV fails CLOSED (AOP)

Off 3 RX 225 I Steam Header Pressure fails LOW 4 CH121 8 N Fire in the Aux Building (requires hot short actions for CC, AFW )

5 RC10 C Pressurizer Surge Line Leakage 11 gpm (AOP) 6 RC10 M Large Break LOCA- Surge Line Shear 6a RH01A C 11 RH R Pu m p Lock out on Start 6b RH02B C 12 R HR Pum p Fa ils to Start in Auto

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Prairie Island U1/U2 Sce nario No.: 7 Op -Test N o.: 2005301 Exam iners: D. McN eil Operators:

D. Ree ser C. Zoia Initial Conditions: Critical following App C1B startup, 10-8A, critical data taken Tu rnov er: No equipment OOS Event Malf. No. Event Event No. Type* Description 1 N/A R Raise reactor power to .5-2% per 1C1.2 Unit Startup.

2 FW 32 C 12 AFW P Lockout 3 DI-46068 C 121 C R Ch iller B reak er Trip 3 DI-46076 C 122 C R C hiller Auto start failure 47022-3 C 121 CR Chiller Tripped annunciator 0302 4 SG01A C Steam G enerator Tube Leak (AOP) 5 ED14 M Loss of Offsite Power (Rx Trip) 5 ED09E C Bus 15 Lockout 6 DI-46523 C 22 Diesel Co oling W ater Pum p start failure 11 SG Steam Generator Tube Rupture (SI) (Causes Loop B CL 7 SG02A M isolation and loss of pressure)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Prairie Island U1/U2 Sce nario No.: 4(spare) Op -Test N o.: 2005301 Exam iners: D. McN eil Operators:

D. Ree ser C. Zoia Initial Conditions: Initial Conditions: 100% Power, MOC , Standard IC, RCS Boron Concentration 721 ppm . Add ing 10 Ga llons R MU 3-4 tim es p er sh ift for T em pera ture C ontro l.

Tu rnov er: D1 OO S for fuel injector replacem ent, estim ated return to service is 8 ho urs. .

Event Malf. No. Event Event No. Type* Description 1 FW 30 I Heater D rain Tank Level Trans m itter Failure 2 RC22A C Pressurizer PORV Leakage 3 VC08 C Letdown HX Leak 4 ED14 M Loss of All AC Power

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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