Text

Initial Submittal of the Scenarios for the Prairie Island Initial Examination - August 2005
	ML053200465
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: ML053200465 (89)
	v • d • e

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

Facility: Prairie Island Scenario No.: 1 Op-Test No.: 1,2,4 Examiners: __________________ Operators:

__________________ 1. a

__________________ 2. b

3. c Initial Conditions: 100% Power, BOC, Standard IC "A" Turnover: Breaker 16-10 and 11 TD AFW Pump OOS Event Malf. Event Event No. No. Type* Description 1 RD0916 I Failed RPI Rod G7 (AOP) 2 TC03 C Turbine Control Valve Cycling (AOP) (Reactivity for RO) 3 CL01A C 11 Cooling Water Pump Trip 3 CL03 C 121 Cooling Water Pump Fails to Autostart 3 CL02A C 12 Cooling Water Pump Fails to Autostart 3 CL02B C 22 Cooling Water Pump Fails to Autostart 4 DI-46038C C Isolation of CL to Unit 1 Turbine Building Close 5 MS01B M 12 SG Steamline Break in Containment (Inserts on Rx Trip) 5 FW34B C 12 AFWP Auto Start Failure 5 SI05A/B C Both SI Pumps Fail to Autostart 5 RP06 C MSIVs Fail to Auto Close Retention: Life of policy + 10yrs.

Retain in: Training Program File Page1 of 21

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 IN SEG TITLE: 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 Page2 of 21

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 the Goal of ability to monitor and operate the plant within the limits of the Training: 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 Page 3 of 21

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

14. F3-2 None Commitments:

This is an evaluation scenario for the 2005 ILT NRC Exam, this scenario is Evaluation 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 4 of 21

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 5 of 21

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 6 of 21

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 7 of 21

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 8 of 21

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 9 of 21

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 E 4. WHEN the crew has assumed the duty and at the LEAD / C47013:0407 ROD AT BOTTOM vent 1 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, RO THEN reply that you will get started right

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 SS Failure

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.

E 5. After the crew has adequately addressed Technical C23 AOP2 Malfunction of EH Control System vent 2 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 10 of 21

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 E 6. After the Crew has placed the Turbine in Manual LEAD C47020-0204, Loop A Cooling Water LO Press vent 3 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 the check the low pressure auto start C47020-0106 11 Cooling Water Pump Locked Out LEAD setpoints of the 11 and 22 diesel cooling water 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 SS evaluation, THEN the crew should be Tech Specs allowed to initiate a power reduction prior

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

If the crew elects to investigate the low pressure setpoint this action may be delayed until the report is received.

Page 11 of 21

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 E 7. When the crew has adequately addressed C47, LEAD C47007-0303 Hydrogen and Seal Oil Local Alarm vent 4 and at the discretion of the Lead Evaluator, ENTER

Dispatch an Operator to investigate.

the closure of the Turbine Cooling Water Header Motor Valve. This malfunction is on a 3 minute timer. (Relative Order of 4, Trigger 4). LEAD C47007-0101 Bus Duct Cooler Cooling Water LO Flow

a. If asked to locally investigate MV-32031, report

Dispatch an Operator to investigate.

the valve is closed there is no apparent reason

Monitor bus duct temperature on ERCS for the valve closing.

C47020-0304 Turbine Cooling Water Header MV-32031 LEAD CLOSED

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

RO

Trip the Reactor and Initiate 1E-0 LEAD

Stop the Feedwater Pumps

Place Standby Condensate Pump in Manual

Stop the running Condensate pumps LEAD

Place the Standby Heater Drain Pump in Manual

Stop the running Heater Drain Pump

Place EH Oil Pump switches in PULLOUT Page 12 of 21

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

Verify immediate actions.

Order 0, Trigger 13)

Verify component alignment per Attachment L.

9. During 1E-0: - Manually start SI pump(s) (Critical Task)1 Crew - Manually start AFW Pump (Critical Task)2

a. If requested, report that all category 1 vent

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

b. If requested, report all Turbine Building roof

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

c. If requested to isolate Unit 1 MSRs per

Maintain AFW discharge pressure > 900 psig Attachment J, perform the following:

Close both MSIVs due to RCS cooldown RO

1) Bring up the CAEP Window

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

Trip RCPs if trip criteria is met.

5) After 12.5 minutes, Report that Unit 1 CREW

Diagnose a Faulted SG and transition to E-2.3 MSRs are isolated per 1E-0 Attachment J.

d. 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 flow to turned over. the SGs prior to transitioning out of E-0.

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

Page 13 of 21

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 14 of 21

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.

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 Page 15 of 21

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

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 Page 16 of 21

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 Panel Severity Or Event Order Drawing Type Code 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 TRIGGER EVENT ACTION Rdc0001a<20 13 Enter trigger 13 when RPI for E3 <20 steps 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 3 Malfunction CL02A 3 12 CLPump fails to Auto Start 3 Malfunction CL02B 3 22 CL Pump fails to Auto Start Page 17 of 21

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 Panel Severity Or Event Order Drawing Type Code Value Trigger Timing Description 4 Override DI DI-46038C Close ON 4 180 Seconds Close MV-32031 4 Override DI DI-46038O Open OFF 4 180 Seconds Close MV-32031 4 Override DO LO-46038B ON 4 180 Seconds MV-32031 Blue Light ON 4 Annun Malf M47020:0304W Cry Wolf 4 180 Seconds MV-32031 Annunciator Page 18 of 21

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 19 of 21

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 20 of 21

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

BATP is OOS for seal replacement MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE ne OPERATIONAL PLANS FOR COMING SHIFT ute with 10 gal RMU 1 to 2 times per shift for temperature control NEW PROCEDURES / INSTRUCTIONS ne 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)

Facility: Prairie Island Scenario No.: 2 Op-Test No.: 2, 3 Examiners: __________________ Operators:

__________________ 1. a

__________________ 2. b

3. c Initial Conditions: 100% Power, BOC, Standard IC "A" Turnover: Breaker 16-10 and 11 TD AFW Pump OOS Start 13 Charging Pump and stop 12 Charging Pump in preparation for isolation of 12 Charging Event Malf. 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 3 N/A C 10-Bank Oil Leakage reported, requiring transfer of one safeguards 4160V bus to alternate source in anticipation of loss (AOP) 4 47012-0203 C High Vibration on 12 RCP (AOP) (Power reduction required) 5 RC03B M 12 RCP Shaft Shear 6 TC06 C Turbine Auto Trip Failure (Note: Events 5-8 required to reduce SG inventory enough to cause loss of heat sink post trip) 6 RP06 C MSIV Auto Closure Failure 6 TC01A C Turbine Left Stop Valve Closure Failure 6 TC14C C Turbine CV-3 Fails As Is 7 FW27B C FCV 476 (12 Main Feed Reg) Fails Closed on Trip 8 ED02B C Bus 12 Auto Transfer Failure 9 FW32 M MD AFW Pump Trip on Start- Loss of Heat Sink Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22

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 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 22

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 the Goal of ability to monitor and operate the plant within the limits of the Training: 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 channel Objectives:

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 3 of 22

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 scenario is Method: 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 4 of 22

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:

RCP Shaft Shear/Turbine Trip Failure 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 5 of 22

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.

Event 4: Loss of Secondary Heat Sink Page 6 of 22

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

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 7 of 22

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 8 of 22

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 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.

Reduce 11 Chg speed to get ~6.5 gpm seal inj pump.

Verify chg pressure <2400 psig

a. If asked, report the desurger has been

Start 13 Chg Pump verified pressurized per section 5.13.

Adjust seal inj to ~9.5 gpm, <2550 psig charging

Stop 12 Chg Pump

Adjust seal injection back to 8.0 gpm

Transfer 11 Charging Pump to AUTOMATIC 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

Verify letdown is isolated pressurizer level to fail low. (Relative Order 1, Lead/ RO 47012-0507 Trigger 1)

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

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 Lead/

C51.3 Pressurizer Level 1L-428 - low RO

Operate heaters manually if desired.

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.

Page 9 of 22

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

SS Trip bistable 1LC-428A.

Lead Initiate work order on the failed channel.

Make appropriate log entries.

Event 2 8. When excess letdown is in service and charging is SS Direct entry to C20.3 AOP7 based on imminent loss of 10 restored and at the discretion of the Lead Evaluator, Lead Transformer.

Call as the Turbine Building Operator and report the C20.3 AOP7 following:

Verifies auto actions have NOT occurred as "An oil leak is in progress from 10 bank transformer, transformer has not locked out yet.

through a crack at the base on the north side.

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

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

Lead

Contacts Technical Engineering for assistance.

Verify/transfer Unit 2 safeguard buses to 2RY.

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

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

SPILL, as the Shift Manager direct "Unit 2 will o Bkr 15-7 to MANUAL complete D14.3 AOP1." o Sync scope to CT11 o Verify voltages matched and synchronized

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

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

11. WHEN realignment of Unit 2 buses is addressed, Technical Specifications reply "Bus 25 is already on 2RY and Unit 2

3.8.1 Condition A (7 days, plus perform SP 1118 operators will transfer Bus 26 to 2RY per 2C20.5." 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)

Page 10 of 22

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

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

Page 11 of 22

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 RO

Determine nuclear engineering notification is not

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

System Engineer, "12 RCP should be shutdown

Predict reactivity for power change using C1 Figures within the next hour based on current vibration." and Curves for reactivity balance, or Figure C1-32.

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 12 of 22

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 Lead o Rod bottom lights LIT

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 RO Manually close CV's NOTE: If SG WR level is >50% in either SG when 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. SS o Both SG pressures >530 psig 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 Lead 1FR-H.1.

RO IF SI has actuated:

exhausters are stopped.

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

c. If requested to isolate Unit 1 MSRs per 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 SS

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 o IF wide range level is <50% on both SGs, are isolated per 1E-0 Attachment J. transition to FR-H.1.

Page 13 of 22

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 14 of 22

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 SS verify feed flow to at least one SG o Return to procedure/step in effect (ES-0.1 or E-Lead 0, for No SI/SI)

RO

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

Lead o IF SI pumps running, depressurize RCS to

<1950 psig and block automatic SI 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 15 of 22

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 6a 23. Reactor Trip Recovery 1ES-0.1 SS

Verify reactor trip has been announced Lead

Steam dump to STM PRESS mode or (MSIVs closed)

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

RO of Event 6b instead

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 6b 24. Reactor Trip or Safety Injection (Cont) and SI SS

Return to procedure/step in effect (1E-0 Step 7)

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 16 of 22

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 SS o RCS pressure >2000 psig, stable/increasing o Pressurizer level >7%

Lead

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

Reset SI, CI RO

Verify instrument air to containment

Block/reset AMSAC/DSS Lead

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

Stop SI and RHR pumps

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 Page 17 of 22

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 Panel Severity Event Order 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 18 of 22

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 Panel Severity Event Order 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 monitor OVRD Ramp 300 sec (horizontal) 3 ERCS PT CP-1Y0774A 8.1 3 Start Value 5 12 RCP shaft vibration monitor OVRD Ramp 300 sec (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 monitor OVRD (horizontal) 3a ERCS PT CP-1Y0774A DELETE 12 RCP shaft vibration monitor OVRD (vertical)

Page 19 of 22

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 Panel Severity Event Order Drawing Type Code Or Value Trigger Timing Description 4 SIMRC05B MALF RC03B 4 Delay 12 RCP shaft shear (free wheel impeller) 7 Seconds 4 TC-14C 4 CV-3 Fails as is 4 FW27B 4 FCV 476 Fails Closed on Trip 5 RF FW126 Local 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 20 of 22

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 21 of 22

Appendix D Scenario Outline Form ES-D-1 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:

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG- 1021, Revision 9 38 of 39

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

Facility: Prairie Island Scenario No.: 6 Op-Test No.: 1, 2 Examiners: __________________ Operators:

__________________ 1. a

__________________ 2. b

3. c Initial Conditions: 2% Power Prior to Turbine Roll in 1C1.2 Startup Turnover: No Equipment OOS, Raise power to 6% per 1C1.2 Event Malf. Event Event No. No. Type* Description 1 N/A R Raise power to 6% per 1C1.2 2 DI-46296O 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 6 RH01A C 11 RHR Pump Lockout on Start 6 RH02B C 12 RHR Pump Fails to Start in Auto Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 24

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 24

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 the Goal of ability to monitor and operate the plant within the limits of the Training: 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 roll per Learning 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 3 of 24

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 new Method: 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 4 of 24

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:

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 5 of 24

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%

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 6 of 24

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 7 of 24

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 8 of 24

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 9 of 24

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 10 of 24

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 RO Withdraw control rods to raise power to 6% while monitoring SG level complete.

(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 isolated and failure of the Regen HX Outlet Valve CLOSED charging reduced to minimum as part of plant stabilization efforts at (Relative Order 2, Trigger 2) 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 1C12.1 AOP2 Loss of Charging Flow to the Regen HX LEAD/ Verify seal injection flow has not been lost.

RO Verify RMU controller in AUTO IF VCT<17%, verify auto makeup has initiated.

CLOSE letdown orifice isolation valves.

Page 11 of 24

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

Place Excess letdown in service.

Page 12 of 24

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 OR low. (Relative Order 3, Trigger 3)

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 Notify the Red Wing Fire Department could not be extinguished with one portable extinguisher. 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 Lead Start 12 CC pump per F5 App D report. Direct local control of 12 AFWP per F5 App D Reset fire panel Inform the SS that "Unit 2 will perform classification and Verify auto starts of fire pumps notification."

Notify Security of RWFD arrival WHEN directed, place 12 AFWP in LOCAL (Relative Order Notify Fire Protection/Industrial Safety 4a, Trigger 5) SS Consult Technical Specifications for inoperability of 12 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 )

Page 13 of 24

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 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 14 of 24

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 or 12 AFW pump and / or at the discretion of the Lead 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 Verify aux spray valve closed Verify pressurizer pressure control operating in AUTO SS Refer to TS 3.4.1 (DNB) if <2190 psig RCS pressure LEAD/ Initiate RCS leakrate using ERCS 'LEAK' program SS 47022-0108 Train B High Radiation LEAD 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 Isolate charging to the RCP seals:

Verify both RCP TBHX CC valves open Page 15 of 24

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

Stop the running charging pump and recalculate leakrate LEAD

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

When the leak location is unidentified:

o Refer to LCO 3.4.14 Condition A for total SS 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 C 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 Event 6 13. 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 Page 16 of 24

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

14. 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

Verify SI actuated Attachment J, perform the following: Note: RCP trip criteria should be checked and

1) Bring up the CAEP Window Lead RCP's stopped. For a LBLOCA, this is not a

2) Click on OPEN File critical task.

3) Click on Attachment J-E0 .cae RO

Perform E-0 Att. L (see attached procedure

4) Click on Run button section)

15. After 12.5 minutes, Report that Unit 1 MSRs are o Start 12 RHR pump (Critical Task) isolated per 1E-0 Attachment J o Manually actuate Containment Spray if >23 psig NOTE: IF directed to investigate, report 11 RHR pump

Check AFW Status (>200 gpm and >900 psig) has a 51A overcurrent flag and an 86 lockout flag. o Locally start 12 AFWP if necessary NOTE: IF directed to repair, report after 30 minutes the

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

Check Pzr PORVs and spray valves closed Page 17 of 24

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

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

Verify RCP's stopped

17. 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 18 of 24

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

18. 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 Page 19 of 24

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-31328 OPEN 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 5 SIMRC03 MALF RC10 0.011 6 RCS Leak 11 GPM- Surge Line Page 20 of 24

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 6 SIMRC03 MALF RC10 100 Pzr Surge Line Shear 7 SIMFW08 OVRD DI DI-5151802 ON 7 Local start 12 AFWP START Page 21 of 24

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 3.4.1 47012-0508 47022-0108 1C1.2 Startup Operation 1C12.1 AOP2, Loss of Charging Flow to the Regen HX F5 Appendix A Fire Strategies Page 22 of 24

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 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 23 of 24

Appendix D Scenario Outline Form ES-D-1 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.

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:

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG- 1021, Revision 9 38 of 39

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

Facility: Prairie Island Scenario No.: 7 Op-Test No.: 3, 4 Examiners: __________________ Operators:

__________________ 1. a

__________________ 2. b

3. c Initial Conditions: IC-26 Critical following App C1B startup, 10-8A, critical data taken Turnover: No equipment OOS Event Malf. Event Event No. No. Type* Description 1 N/A R Raise reactor power to .5-2% per 1C1.2 Unit Startup.

2 FW32 C 12 AFWP Lockout 3 DI-46068 C 121 CR Chiller Breaker Trip 3 DI-46076 C 122 CR Chiller Auto start failure 3 47022-0302 C 121 CR Chiller Tripped annunciator 4 SG01A C Steam Generator Tube Leak (AOP) 5 ED14 M Loss of Offsite Power (Rx Trip) 5 ED09E C Bus 15 Lockout 6 DI-46523 C 22 Diesel Cooling Water Pump start failure 7 SG02A M 11 SG Steam Generator Tube Rupture (SI) (Causes Loop B CL isolation and loss of pressure)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22

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, SGTR WITH SEG TITLE: 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 the Goal of ability to monitor and operate the plant within the limits of the Training: 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 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 Evaluation This is an evaluation scenario for the 2005 ILT NRC Exam, this is a new Method: 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 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 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. 11 RCP Thermal Barrier Heat Exchanger leak

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. CC Leakage into RCS

2. SG Tube Leak Major Transients:

Loss of Offsite Power Steam Generator Tube Rupture Critical Tasks:

1. Restore Train B cooling water prior to lockout of D2

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

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 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 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 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 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 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 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 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 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 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 pump 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 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 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. SS (Relative order 2, Trigger 2).

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 SS

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

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

Specs.

Action to be in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

c. After the Crew enters LCO 3.0.3 and at the discretion of the Lead Evaluator DELETE 122 CR Chiller auto start malfunction (Relative Crew may or may not:

Order 2a) and report as the WIN team, the 122

Refer to C37.9 AOP 1 CR chiller auto start relay has been repaired and you recommend starting the chiller.

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 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 4 9. WHEN the Crew exits LCO 3.0.3 and / or at the C47022-0108 Hi Radiation Train B discretion of the Lead Evaluator, THEN enter the LEAD

Determine 1R-19 is in alarm Steam Generator Tube Leak (Relative Order 3, Trigger 3).

a. As the Duty Chemist, Report Primary to C47048 1R-19 Secondary Leakage on A Steam Generator is LEAD

Verify Automatic actions occur detected but leak rate cannot be determined yet.

Notify Rad Protection to determine leak rate

b. As the Ops Manager and / or NRC Resident acknowledge entry into the AOP. 1C4 AOP2 Steam Generator Tube Leak

c. When asked, report AR-8-2 is open and AR-8-2 LEAD is closed.

Monitor R-19

Direct Duty Chemist to obtain Samples

Notify Ops Manager and NRC Resident Inspector

Direct Duty Chemist to determine Leak Rate

Verify no Blowdown to the river

Determine Action Level 2 is appropriate based on no R-15 data 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 E 10. After the Crew determines Action Level 2 is RO 1E-0, Reactor Trip or Safety Injection vent 5 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 SS report, 22 Cooling Water Pump has an air leak

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.

RO than 75 psig

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

Check Feedwater Status

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

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 LEAD /

Verify Charging and Letdown in service

5) After 12.5 minutes, Report that Unit 1 RO

Check Pressurizer pressure greater than Event 6 MSRs are isolated per 1E-0 Attachment J 1830psig

12. When the Crew transitions to 1ES-0.1, and at the

Manually actuate SI and transition to 1E-0, discretion of the Lead Evaluator, ENTER the Steam Reactor Trip or Safety Injection.

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

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

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

Verify Reactor Trip LEAD

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

Check if SI is actuated with the EOP RO

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

Check Total AFW flow greater than 200 gpm

Check RCS temperature stable or trending to RO 547F

Check PZR PORVs Closed

Check PZR Spray valves Closed

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 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

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-32036, 121 CLG WTR HDR VLV C

OR

Close MV-32037, 121 CLG WTR HDR VLV D

Open V-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

Rest SI

Check 11 SG pressure greater than 210psig

Initiate RCS Cooldown

Dump steam to the from 12 SG PORV

Stop Cooldown when reach required CETC temp 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

Check 12 SG Level - Control level 5-50%

Check PZR PORVS Closed

Check Block valves - at least one open LEAD /

Reset SI RO

Reset Containment Isolation

Establish Instrument Air to Containment

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 LEAD / o Total feed flow - greater than 200 gpm RO o RCS pressure stable or increasing o PZR level - greater than 7%

Stop Both SI Pumps 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 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 Panel Severity Or Event Order Drawing Type Code 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 C47022:0302 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 3 Malfunction RM15 35 3 120 Sec Ramp R-19 Miscalibration, raise setpoint >500 CPM 4 Malfunction ED14 4 Loss of Offsite Power 4 Malfunction ED09E 4 Bus 15 Lockout 4 Override DI DI-46523P PTL ON 4 22 CL Pump Failure 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 Panel Severity Or Event Order Drawing Type Code Value Trigger Timing Description 5 Malfunction SG02A 10 5 120 Sec Ramp Steam Generator Tube 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

C37.9 AOP 2

LCO 3.7.11 Condition A.

LCO 3.0.3 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

C47022-0108

C47048 1R-19

1C4 AOP2

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

Appendix D Scenario Outline Form ES-D-1 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:

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG- 1021, Revision 9 38 of 39

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