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)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page1 of 21 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 No.

Malf.

No.

Event Type*

Event 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 Close C

Isolation of CL to Unit 1 Turbine Building 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

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page2 of 21 SIMULATOR EXERCISE GUIDE (SEG)

SITE:

PRAIRIE ISLAND SEG #

2005 NRC SCENARIO 1 SEG TITLE:

RPI FAILURE/TURB LOAD CYCLING/ LOSS OF COOLING WATER PUMP, LOSS OF TURBINE BUILDING COOLING WATER HEADER/STEAM LINE BREAK IN CONTAINMENT SCEN 1 REV. #

0 PROGRAM:

INITIAL LICENSED OPERATOR P8100 COURSE:

INITIAL LICENSED OPERATOR P8100 TOTAL TIME:

2 HOURS Developed by:

Travis Ouret 3/16/05 Instructor Date Reviewed by:

Instructor Date Validated by:

Validation Lead Instructor Date Approved by:

Training Supervision Date

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 Goal of Training:

During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

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

Learning Objectives:

1.

Diagnose and take corrective actions for a failed RPI per C47, SP1319, and C5 AOP5

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.

Prerequisites:

None Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Lead Evaluator

4.

Human Performance Evaluator

5.

Comment Recorder

6.

Booth Operator (Primary Communicator)

7.

Backup Communicator

References:

1.

C47013:0407

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 Commitments:

None Evaluation Method:

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

Operating Experience:

None - Evaluation Scenario Related PRA Information:

Initiating Event with Core Damage Frequency:

Normal transient (4%)

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 POS EXPECTED STUDENT RESPONSES 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 POS EXPECTED STUDENT RESPONSES

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 POS EXPECTED STUDENT RESPONSES E

vent 1

4. WHEN the crew has assumed the duty and at the discretion of the Lead Evaluator, enter the failed RPI for rod G-7 (Relative Order of 1, Trigger 1).

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

b. Allow the crew to hold a brief.

LEAD /

RO LEAD /

RO RO SS SS C47013:0407 ROD AT BOTTOM

Refer to C5 AOP4 (May go directly to C5 AOP5)

C47013:0507 ROD DEVIATION/SEQUENCING

Verify cause using ERCS RODS

Initiate SP-1319 1C5AOP4 Dropped Rod

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

Notify Ops Manager and NRC Resident Inspector

Diagnose the symptoms are indicative of a failed RPI.

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 vent 2

5. After the crew has adequately addressed Technical Specifications for the failed RPI and initiated action to verify rod position, and at the discretion of the Lead Evaluator, enter the Turbine Load cycling malfunction. (Relative Order of 2, Trigger 2).

LEAD SS RO C23 AOP2 Malfunction of EH Control System

Place turbine in MANUAL

Notify System Engineer and/or WIN Team

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 POS EXPECTED STUDENT RESPONSES E

vent 3

6. After the Crew has placed the Turbine in Manual and at the discretion of the Lead Evaluator, ENTER the malfunction to trip 11 Cooling Water Pump.

(Relative Order 3, Trigger 3)

a. If asked to investigate Loss of 11 Cooling Water pump, report breaker 13-8 has a 50-G flag.

b. If asked the check the low pressure auto start setpoints of the 11 and 22 diesel cooling water pumps, report both low pressure auto start setpoints were found set at 52 psig.

c. NOTE: The low pressure auto start of the pumps is 70 psig.

d. IF the turbine CV cycling has not resulted in a sufficient reactivity change for RO evaluation, THEN the crew should be allowed to initiate a power reduction prior to continuing to the next event. The SM can direct the SS to initiate the power reduction per 3.0.3 if required.

LEAD LEAD SS C47020-0204, Loop A Cooling Water LO Press C47020-0205, Loop B Cooling Water LO Press

Verify Pressure low

Start available pumps as necessary o Crew may start any pump C47020-0106 11 Cooling Water Pump Locked Out

Verify Cooling Water Header Pressure restored to Normal

Start 12 Diesel Driven CL Pump

OR

Start 121 CL Pump Tech Specs

Enter LCO 3.7.8 Condition A due to failure of the low pressure auto start of 11 and 22 diesel cooling water pumps at 70 psig.

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 POS EXPECTED STUDENT RESPONSES E

vent 4

7. When the crew has adequately addressed C47, and at the discretion of the Lead Evaluator, ENTER the closure of the Turbine Cooling Water Header Motor Valve. This malfunction is on a 3 minute timer. (Relative Order of 4, Trigger 4).

a. If asked to locally investigate MV-32031, report the valve is closed there is no apparent reason for the valve closing.

LEAD LEAD LEAD LEAD /

RO LEAD LEAD C47007-0303 Hydrogen and Seal Oil Local Alarm

Dispatch an Operator to investigate.

C47007-0101 Bus Duct Cooler Cooling Water LO Flow

Dispatch an Operator to investigate.

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

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

Trip the Reactor and Initiate 1E-0

Stop the Feedwater Pumps

Place Standby Condensate Pump in Manual

Stop the running Condensate pumps

Place the Standby Heater Drain Pump in Manual

Stop the running Heater Drain Pump

Place EH Oil Pump switches in PULLOUT Page 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 POS EXPECTED STUDENT RESPONSES Event 5

8. WHEN the reactor is tripped, THEN verify that the Steam line break has automatically entered.

a. If not, ENTER the Steam line break (Relative Order 0, Trigger 13)

9. During 1E-0:

a. If requested, report that all category 1 vent doors are closed.

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

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

1) Bring up the CAEP Window

2) Click on OPEN File

3) Click on Attachment J-E0.cae

4) Click on Run button

5) After 12.5 minutes, Report that Unit 1 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 attachment is complete. IF an extra operator is performing attachment L, THEN it may NOT be turned over.

RO/LRO Crew LRO Crew RO CREW 1E-0, Reactor Trip or Safety Injection

Perform Immediate actions from memory.

Verify immediate actions.

Verify component alignment per Attachment L.

- Manually start SI pump(s) (Critical Task)1

- Manually start AFW Pump (Critical Task)2

Check AFW status and RCS temperature (steps 6 & 7)

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

Maintain AFW discharge pressure > 900 psig

Close both MSIVs due to RCS cooldown

May also be done by lead during performance of Attachment L.

Trip RCPs if trip criteria is met.

Diagnose a Faulted SG and transition to E-2.3

1. Manually start at least one 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.

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 POS EXPECTED STUDENT RESPONSES

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

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 necessary.

Crew 1E-2: Faulted Steam Generator Isolation1 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 POS EXPECTED STUDENT RESPONSES

12. Allow crew to complete actions of 1E-1 as necessary.

1E-1: Loss of Reactor or Secondary Coolant 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 necessary.

1ES-0.2: SI Termination 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 POS EXPECTED STUDENT RESPONSES

14. WHEN the crew verifies SI is not required and / or at the discretion of the Lead Evaluator, place the simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented Crew Assemble near fire detection panel while evaluators consult 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 Order System Or Panel Drawing Type Code Severity Or Value Event 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 Order System Or Panel Drawing Type Code Severity Or Value Event 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 TENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG TE:

DAY/NIGHT SHIFT: Day T 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 eaker 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)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22 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 No.

Malf.

No.

Event Type*

Event 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

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22 SIMULATOR EXERCISE GUIDE (SEG)

SITE:

PRAIRIE ISLAND SEG #

2005 NRC SCENARIO 2 SEG TITLE:

PZR LVL LOW/IMMINENT LOSS OF 10 BANK XFMR/RCP VIB HI/RCP 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

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 Goal of Training:

During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

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

Learning Objectives:

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

2. Diagnose and perform corrective actions for a pressurizer level channel failure high per 1C51.

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

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

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

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

Prerequisites:

None Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Lead Evaluator

4.

Human Performance Evaluator

5.

Comment Recorder

6.

Booth Operator (Primary Communicator)

7.

Backup Communicator

References:

1. 1C51

2. C47

3. C12.1 AOP3

4. C1.4/C1.4 AOP1

5. 1E-0

6. 1C12.1 Commitments:

None 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 Method:

This is an evaluation scenario for the 2005 ILT NRC Exam, this scenario is based on P9160S-002 Evaluation #27.

Operating Experience:

None - Evaluation Scenario Related PRA Information:

Initiating Event with Core Damage Frequency:

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

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 POS EXPECTED STUDENT RESPONSES 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:

a. UNIT 1 LPEO / PEO TURNOVER LOG

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

CREW Review the Unit 1 LPEO / PEO Turnover log Walk down the control boards and ask questions as 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 POS EXPECTED STUDENT RESPONSES Event 0

5. When the crew has assumed the duty and at the discretion of the Lead Evaluator report as the Aux Building Operator, 12 Charging pump belt is frayed and recommend swapping from 12 to 13 charging pump.

a. If asked, report the desurger has been verified pressurized per section 5.13.

RO 1C12.1, Section 5.4 Verify desurger pressurized.

Transfer 11 Charging Pump to MANUAL.

Verify 13 Charging Pump in MANUAL/minimum.

Reduce 11 Chg speed to get ~6.5 gpm seal inj Verify chg pressure <2400 psig Start 13 Chg Pump 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 discretion of the Lead Evaluator, enter the malfunction to cause the controlling channel of pressurizer level to fail low. (Relative Order 1, Trigger 1)

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

(Relative Order 2, Trigger 2)

RO Lead/ RO Lead/

RO 47012-0607, Pressurizer Lo-Lo level Verify all pressurizer heaters deenergized Verify letdown is isolated 47012-0507 Verify level low on 1L-428 only Verify heaters ON Take manual control of the charging pump speed to maintain level at program.

Refer to C51 C51.3 Pressurizer Level 1L-428 - low 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 POS EXPECTED STUDENT RESPONSES SS Lead Refer to T.S.3.3.1 Condition A and Table 3.3.1-1 Function 9 (6 hr LCO for B/S tripping).

Trip bistable 1LC-428A.

Initiate work order on the failed channel.

Make appropriate log entries.

Event 2

8. When excess letdown is in service and charging is restored and at the discretion of the Lead Evaluator, Call as the Turbine Building Operator and report the following:

"An oil leak is in progress from 10 bank transformer, through a crack at the base on the north side.

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

9. IF the Shift Supervisor enters D14.3 AOP1 OIL SPILL, as the Shift Manager direct "Unit 2 will complete D14.3 AOP1."

10. IF TSO or Engineering is contacted, recommend isolation of the transformer from the System Control Center once plant loads are shifted to alternate sources using plant procedures.

NOTE: IF C20.3 AOP7 is not entered based on the imminent loss, transfer of Bus 15 to CT11 per normal procedures is adequate.

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

SS Lead SS Lead Lead SS Direct entry to C20.3 AOP7 based on imminent loss of 10 Transformer.

C20.3 AOP7 Verifies auto actions have NOT occurred as transformer has not locked out yet.

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

Contacts Technical Engineering for assistance.

Verify/transfer Unit 2 safeguard buses to 2RY.

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

o Bkr 15-7 to MANUAL o Sync scope to CT11 o Verify voltages matched and synchronized o Announce transfer/stand clear Bus 15 o Close breaker 15-7 CT11 source and trip breaker 15-3 1RY source within 5 seconds o Verify bus voltage on meter and mimic light o Sync scope to OFF o Bkr 15-7 to AUTO Place 1RY source breakers to buses 15/16 in MANUAL and PULLOUT Technical Specifications 3.8.1 Condition A (7 days, plus perform SP 1118 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter)

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 POS EXPECTED STUDENT RESPONSES

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 POS EXPECTED STUDENT RESPONSES Event 3

13. WHEN 1RY source breakers to Bus 15 are in PULLOUT and at the discretion of the Lead Evaluator Enter the 12 RCP Vibration Alarm and ERCS overrides (Relative Order 3, Trigger #3)

14. WHEN directed, report "12 RCP shaft vibration is 10.5 mils and stable."

15. IF asked for direction on rate of load decrease or chosen rate is 1%/min or less, reply as the RCP System Engineer, "12 RCP should be shutdown within the next hour based on current vibration."

RO SS Lead/

RO 47012-0203 Determine RCP vibration using ERCS GRPDIS "RCPVIBES" Determine shaft vibration requires a controlled shutdown.

Unit Power Reduction (option selected by SS) 1C1.4 Power Operation option Determine nuclear engineering notification is not required as BOC, >400 ppm boron and no load follow history.

Predict reactivity for power change using C1 Figures 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 POS EXPECTED STUDENT RESPONSES Event 4

16. WHEN 5% power reduction has been achieved and at the discretion of the Lead Evaluator, Enter the 12 RCP Shaft Shear (Relative Order 4, Trigger #4).

Then DELETE Relative Order 3 RCP vibration alarms. (Relative Order #3a)

NOTE: It is expected that the turbine trip will occur before SI actuates on excessive cooldown. IF SI actuates, additional steps are included in the expected student responses for E-0 actions until transition to FR-H.1 is directed.

NOTE: If SG WR level is >50% in either SG when AFW status is checked, E-0 actions will continue until decay heat causes sufficient inventory loss to reach RED path criteria for heat sink.

17. During 1E-0:

a. If requested, report that all category 1 vent doors are closed.

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

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

1) Bring up the CAEP Window

2) Click on OPEN File

3) Click on Attachment J-E0.cae

4) Click on Run button

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

SS RO Lead Lead RO SS Lead RO SS Direct entry to 1E-0 Verify reactor trip o Trip/bypass breakers OPEN o Flux decreasing o RPIs at 0 o Rod bottom lights LIT Verify Turbine Trip (critical task) o Note: turbine will not automatically trip and when manually tripped the left stop valves will not close. The MSIV's will not auto close.

o Manually trip turbine using CB pushbutton Manually close CV's IF NOT, manually close MSIV's Verify both safeguards buses energized Verify SI not actuated or required o Both SG pressures >530 psig o Pzr Press >1830 psig o Containment pressure <3.5 psig Transition to 1ES-0.1 Reactor Trip Recovery IF Red Path exists on CSF for Heat Sink, Transition to 1FR-H.1.

IF SI has actuated:

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

2. Check AFW Status o Total AFW flow <200 gpm o Attempt/verify 12 AFW start (allowable per ARP if SG pressure is <700 psig, but will lock out on restart. If SG pressure high will not be allowed to start.)

o IF wide range level is <50% on both SGs, 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 POS EXPECTED STUDENT RESPONSES Event 5

18. During Loss of Heat Sink (1FR-H.1)

19. IF asked to check breaker 16-3, report a 51A overcurrent flag is present.

20. IF asked to cross connect 21 AFW pump to Unit 1, wait 5 minutes and report 21 AFW pump failed to start.

RO Lead Verify RCS pressure >SG pressure Verify hot leg temperature >350°F Verify secondary heat sink exists o Either WR SG level >9%

o Pzr Pressure <2335 psig Attempt to restore AFW flow o Close SG Blowdown Isolation valves o Determine 12 AFWP locked out 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 POS EXPECTED STUDENT RESPONSES (cont)

21. Loss of Heat Sink (cont)

NOTE: Critical task is met if MFW or Condensate flow is restored prior to Bleed and Feed cooling required per FR-H.1 Step 2.

22. IF directed, locally open MFWP discharge isolation:

a. For 11 FWP enter (Relative Order 5, Trigger 5)

b. For 12 FWP enter (Relative Order 6, Trigger 6)

Lead SS Lead RO Lead Attempt to restore MFW flow (critical task) o Reset SI o Verify/Start one condensate pump o Verify FW Containment Isolation valves open IF NOT, reset CI, verify FRV/BFRV in MANUAL/CLOSED and open valves o Establish MFW flow Reset FW bypass isolation Start either MFWP Manually open at least one bypass FRV to establish flow >200 gpm on ERCS/clear heat sink RED path Check SG levels o Check SG NR levels >5% in either SG OR verify feed flow to at least one SG o Return to procedure/step in effect (ES-0.1 or E-0, for No SI/SI)

IF MFW not established, establish Condensate Flow (critical task) 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 POS EXPECTED STUDENT RESPONSES Event 6a

23. Reactor Trip Recovery 1ES-0.1 NOTE: IF Safety Injection has actuated, perform tasks of Event 6b instead NOTE: WHEN cold leg temperatures are under control and evaluator concurs, terminate the scenario.

SS Lead RO Verify reactor trip has been announced Steam dump to STM PRESS mode or (MSIVs closed)

SG PORVs to 71.8%

Check RCS cold leg temperatures stable/trending to 547°F o IF NOT, stop dumping steam, verify SGB 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 Termination NOTE: Only performed if SI is actuated during previous events.

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

Check RCS cold leg temperatures stable/trending to 547°F o IF NOT, stop dumping steam, verify SGB 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 POS EXPECTED STUDENT RESPONSES SS Lead RO Lead o Subcooling >20°F o Total FW flow >200 gpm OR >5% NR SG level o RCS pressure >2000 psig, stable/increasing o Pressurizer level >7%

Transition to 1ES-0.2 SI Termination 1ES-0.2 SI TERMINATION Reset SI, CI Verify instrument air to containment Block/reset AMSAC/DSS 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 discretion of the Lead Evaluator, place the simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented Crew Assemble near fire detection panel while evaluators consult 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 Order System Or Panel Drawing Type Code Severity Or Value Event 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 WOLF 3

Delay 200 sec 11 or 12 RCP high vibration 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 Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description 3

ERCS PT OVRD CP-1Y0771A 9.0 3

Start Value 5 Ramp 300 sec 12 RCP frame vibration monitor (horizontal) 3 ERCS PT OVRD CP-1Y0772A 7.5 3

Start Value 5 Ramp 300 sec 12 RCP frame vibration monitor (vertical) 3 ERCS PT OVRD CP-1Y0773A 10.5 3

Start Value 8 Ramp 300 sec 12 RCP shaft vibration monitor (horizontal) 3 ERCS PT OVRD CP-1Y0774A 8.1 3

Start Value 5 Ramp 300 sec 12 RCP shaft vibration monitor (vertical) 3a C1-C2 ANN MALF M47012:0203W DELETE 11 or 12 RCP high vibration alarm 3a ERCS PT OVRD CP-1Y0771A DELETE 12 RCP frame vibration monitor (horizontal) 3a ERCS PT OVRD CP-1Y0772A DELETE 12 RCP frame vibration monitor (vertical) 3a ERCS PT OVRD CP-1Y0773A DELETE 12 RCP shaft vibration monitor (horizontal) 3a ERCS PT OVRD CP-1Y0774A DELETE 12 RCP shaft vibration monitor (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 Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description 4

SIMRC05B MALF RC03B 4

Delay 7 Seconds 12 RCP shaft shear (free wheel impeller) 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 5

RF FW129 Open 5

11 FWP Discharge Valve Open Pushbutton 6

RF FW127 Local 6

12 FWP Discharge Valve Control Switch 6

RF FW131 Open 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 ary Heat Sink ondition A, and Table 3.3.1-1 Function 9 1 Condition A OP7 P1 1ES-0.1 Tr 1C51.3, Pressurizer Level IL-428 - Low 1E-0, Reactor Trip or Safety Injection 1FR-H.1, Response to Loss of Second F3-2, Classifications of Emergencies T.S. LCO 3.3.1 C T.S. LCO 3.4.14 T.S. LCO 3.8.

C20.3 A 1C1.4 1C1.4 AO C51.3 C47010-0107 After aining for the Day Information Tags removed and put away Signs/placards removed and put away unless normal simulator configuration 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 Instructor station returned to normal with all books, paper, and etc. put away Headsets turned off and put away Page 21 of 22

Appendix D Scenario Outline Form ES-D-1

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

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 24 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 No.

Malf.

No.

Event Type*

Event Description 1

N/A R

Raise power to 6% per 1C1.2 2

DI-46296O Off C

Regen HX Charging Line Outlet FCV fails CLOSED (AOP) 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

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 24 SIMULATOR EXERCISE GUIDE (SEG)

SITE:

PRAIRIE ISLAND SEG #

2005 NRC SCENARIO 6 SEG TITLE:

LOSS OF REGEN HX/ STEAM HEADER PRESSURE FAILURE/PLANT FIRE/RCS 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

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 Goal of Training:

During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

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

Learning Objectives:

1.

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

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 Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Lead Evaluator

4.

Human Performance Evaluator

5.

Comment Recorder

6.

Booth Operator (Primary Communicator)

7.

Backup Communicator

References:

1.

1C1.2 Startup Operation

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 Commitments:

None Evaluation Method:

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

Operating Experience:

None - Evaluation Scenario Related PRA Information:

Initiating Event with Core Damage Frequency:

Large Break LOCA 1.2%

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 POS EXPECTED STUDENT RESPONSES INITIAL CONDITIONS (IC):

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

/SRO)

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 POS EXPECTED STUDENT RESPONSES

6. COMPLETE TURNOVER:

a. UNIT 1 LPEO / PEO TURNOVER LOG (should be provided with the scenario IC)

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

CREW Review the following with the offgoing operator:

Unit 1 LPEO / PEO Turnover log Walk down the control boards and ask questions as 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 POS EXPECTED STUDENT RESPONSES Event 1

7.

Increase reactor power to 6% for turbine roll.

8.

If asked, to complete 1C1.2 Step 5.12.4, A,B,C, wait 2 minutes and report 1C1.2 Step 5.12.4, A,B,C are complete.

Lead RO Per 1C1.2 section 5.12:

Log entry to MODE 1 when above 5% power.

Withdraw control rods to raise power to 6% while monitoring SG level (in auto) and steam dump (in auto)

Event 2

9. WHEN the crew has increased power to 6% and/

or at the discretion of the Lead Evaluator, enter the failure of the Regen HX Outlet Valve CLOSED (Relative Order 2, Trigger 2)

CREW RO LEAD/

RO Diagnose failure of outlet valve.

NOTE: One charging pump may be stopped, letdown isolated and charging reduced to minimum as part of plant stabilization efforts at any time.

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

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

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 POS EXPECTED STUDENT RESPONSES 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 POS EXPECTED STUDENT RESPONSES Event 3

10. WHEN the crew has placed Excess Letdown in service and / or at the discretion of the Lead Evaluator, enter the Steam Header Pressure PT-484 Instrument failure low. (Relative Order 3, Trigger 3)

a.

If asked as I&C to trouble shoot the failed Instrument, report an I&C Technician will be in the Control Room in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NOTE: There are no alarms associated with this malfunction. The operators will see the Steam Dumps close, RCS Temp increasing and Reactor power decreasing.

Crew LEAD LEAD RO RO Plant Stabilization Actions Control the Steam Dump in Manual OR Adjust the PORV setpoint to 1005 psig Control Reactor Power Control Tave Event 4

11. WHEN the crew has stabilized Reactor Power and Tave and / or at the discretion of the Lead Evaluator, enter the Zone 8 Fire Alarm (Relative Order 4, Trigger 4)

WHEN called as Aux Building Operator, wait 2 minutes then call back and report a fire in progress on the north end of 11 RHR pit, involving consumables and staged equipment, and could not be extinguished with one portable extinguisher.

Two minutes after the Fire page, come up on the radio as the Fire Brigade Chief and receive a turnover on the fire report.

Inform the SS that "Unit 2 will perform classification and notification."

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

LEAD SS Lead SS 47022-0601 FIRE ALARM Determine fire alarm is in ZONE 8 Aux Bldg 695' Page Aux Building Operator Actuate the fire alarm Announce the fire and simulate fire brigade auto paging Notify the Red Wing Fire Department Establish radio communication with the Fire Brigade Chief Consult Att A of ARP Start 12 CC pump per F5 App D Direct local control of 12 AFWP per F5 App D Reset fire panel Verify auto starts of fire pumps Notify Security of RWFD arrival Notify Fire Protection/Industrial Safety 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 POS EXPECTED STUDENT RESPONSES 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 POS EXPECTED STUDENT RESPONSES Event 5

12. WHEN the crew has assumed the Tech Spec for 12 AFW pump and / or at the discretion of the Lead Evaluator, enter the 11 gpm RCS Leak (Relative Order 5, Trigger 6)

Note: The high radiation alarm takes 5 minutes to come in.

RO SS LEAD/

SS LEAD RO LEAD Note lowering pressurizer level and adjust charging or excess letdown flow to stabilize.

47012-0508 Pressurizer Hi/Lo Pressure Check pressure low.

Verify all pressurizer heaters ON Verify both pressurizer PORVs closed Verify aux spray valve closed Verify pressurizer pressure control operating in AUTO Refer to TS 3.4.1 (DNB) if <2190 psig RCS pressure Initiate RCS leakrate using ERCS 'LEAK' program 47022-0108 Train B High Radiation Determine alarm is 1R-11/1R-12 1C4 AOP1 RCS LEAK

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

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 POS EXPECTED STUDENT RESPONSES LEAD SS

Stop the running charging pump and recalculate leakrate

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 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 RCS leak and / or at the discretion of the Lead Evaluator, enter the Large Break LOCA (increase SS RO 1E-0 Reactor Trip or Safety Injection

Direct entry to 1E-0

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 POS EXPECTED STUDENT RESPONSES RC10 severity to 100%) (Relative Order 6).

14. 1E-0 Implementation

a. If requested, report that all category 1 vent doors are closed.

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

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

1) Bring up the CAEP Window

2) Click on OPEN File

3) Click on Attachment J-E0.cae

4) Click on Run button

15. After 12.5 minutes, Report that Unit 1 MSRs are isolated per 1E-0 Attachment J NOTE: IF directed to investigate, report 11 RHR pump has a 51A overcurrent flag and an 86 lockout flag.

NOTE: IF directed to repair, report after 30 minutes the motor failed its megger and must be replaced, ETR 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NOTE: IF directed to locally start 12 AFWP, wait 2 minutes and enter DI-5151802 START (Relative Order 7, Trigger 7)

Lead Lead RO Lead RO o Trip/bypass breakers OPEN o Flux decreasing o RPIs at 0 o Rod bottom lights LIT

Verify Turbine Trip

Verify both safeguards buses energized

Verify SI actuated Note: RCP trip criteria should be checked and RCP's stopped. For a LBLOCA, this is not a critical task.

Perform E-0 Att. L (see attached procedure section) o Start 12 RHR pump (Critical Task) o Manually actuate Containment Spray if >23 psig

Check AFW Status (>200 gpm and >900 psig) o Locally start 12 AFWP if necessary

Check RCS Cold Leg Temp o Verify no steam dump in progress o Throttle AFW flow to just above 200 gpm unless either SG is >50% WR, then it may be throttled further or stopped 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 POS EXPECTED STUDENT RESPONSES (E-0 continued)

RO SS

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

Transition to 1E-1

16. E-1 Loss of Reactor or Secondary Coolant

17. If asked as Unit 2, report Unit 2 will unload diesel generators as required.

RO Lead RO Lead RO SS

Verify RCP's stopped

Verify SGs not faulted

Control AFW flow to maintain 50-59% WR SG

Check secondary radiation NORMAL

Check Pzr PORV's/blocks closed

Reset SI

Reset CI

Open Instrument Air to Ctmt valves

Verify offsite power to safeguards buses

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)

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 POS EXPECTED STUDENT RESPONSES

18. WHEN the crew verifies SI can not be stopped and

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

a. Do not reset the simulator until the Lead Evaluator has consented Crew Assemble near fire detection panel while evaluators consult 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 Order System Or Panel Drawing Type Code Severity Or Value Event 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 OPEN OFF 2

Regen HX outlet valve CV-31328 fails CLOSED 3

D1-D5 REMOTE RX225 1

3 Steam Header Pressure Fails LOW (PT-484) 4 FDP-4 REMOTE CH121 8

4 Zone 8 Fire Alarm 4a SIMFW08 OVRD DI DI-51517 LOCAL ON 5

12 AFWP local control 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 Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description 6

SIMRC03 MALF RC10 100 Pzr Surge Line Shear 7

SIMFW08 OVRD DI DI-5151802 START ON 7

Local start 12 AFWP 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

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

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22 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 No.

Malf.

No.

Event Type*

Event 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)

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

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 22 SIMULATOR EXERCISE GUIDE (SEG)

SITE:

PRAIRIE ISLAND SEG #

2005 NRC SCENARIO 7 SEG TITLE:

RAISE REACTOR POWER, 12 AFW PUMP LOCKOUT, LOSS OF CONTROL ROOM CHILLERS, SG TUBE LEAK, SGTR WITH LOSS OF COOLING WATER SCEN 7 REV. #

0 PROGRAM:

INITIAL LICENSED OPERATOR P8100 COURSE:

INITIAL LICENSED OPERATOR P8100 TOTAL TIME:

1.5 HOURS Developed by:

J. Kempkes 3/14/05 Instructor Date Reviewed by:

Instructor (See page 10, Simulator Development Checklist.)

Date Validated by:

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

Date Approved by:

Training Supervision Date

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 Goal of Training:

During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

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

Learning Objectives:

1.

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

2.

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

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 Training Resources:

1.

Full Scope Simulator

2.

Operations Management Representative

3.

Lead Evaluator

4.

Human Performance Evaluator

5.

Comment Recorder

6.

Booth Operator (Primary Communicator)

7.

Backup Communicator

References:

1.

C47

2.

1C14 AOP2

3.

1C4 AOP2

4.

1E-0

5.

1ES-0.1

6.

1E-3

7.

C35 AOP1 Commitments:

None 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 Method:

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

Operating Experience:

None - Evaluation Scenario Related PRA Information:

Initiating Event with Core Damage Frequency:

Steam Generator Tube Rupture (18%)

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 POS EXPECTED STUDENT RESPONSES 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:

a. UNIT 1 LPEO / PEO TURNOVER LOG

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

CREW Review the following with the offgoing operator:

Unit 1 LPEO / PEO Turnover log Walk down the control boards and ask questions as 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 POS EXPECTED STUDENT RESPONSES 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 and / or at the discretion of the Lead Evaluator, THEN enter the Lockout of 12 AFW Pump.

(Relative Order 1, Trigger 1)

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

b. If asked, the status of the AFW Prestartup Checklist, report the AFW Prestart Checklist is complete.

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

d. If asked to verify local operation, report 11 TD AFW Pump local start checks are complete.

(Step 5.1.10)

Lead SS LEAD C47010-0107, 12 AFW Pump Locked Out

Dispatch operator to inspect breaker 16-3

Notify Electrical Department Tech Specs LCO 3.7.5 Condition B

72 Hour action to return 12 AFW to service LCO 3.0.4

A mode change to Mode 1 can not be made 1C28.1 Auxiliary Feedwater

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 POS EXPECTED STUDENT RESPONSES Event 3

8. WHEN the crew manually started 11 TD AFW pump and / or at the discretion of the Lead Evaluator, THEN, enter the loss of Control Room Chillers.

(Relative order 2, Trigger 2).

a. If ask to investigate 121 CR Chiller, wait 2 minutes and report as the Aux building operator, 121 CR Chiller has tripped on high motor temperature.

b. Report as Unit 2, Unit 2 will take C37.9 AOP 1 and C37.9 AOP 2 and address Unit 2 Tech Specs.

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 Order 2a) and report as the WIN team, the 122 CR chiller auto start relay has been repaired and you recommend starting the chiller.

LEAD/

SS SS C47022-0302, 121 CR Water Chiller Tripped

Enter LCO 3.7.11

Refer to C37.11 AOP 1

Determine cause of trip locally C37.11 AOP 1, Loss of Safeguards Chilled Water

Enter to LCO 3.7.11 Condition E

Requires entry into LCO 3.0.3 due to both trains of safeguards cooling lost.

Action to be in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Crew may or may not:

Refer to C37.9 AOP 1

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

Enter LCO 3.7.11 Condition A.

Action to restore 121 CR chiller in 30 days.

Page 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 POS EXPECTED STUDENT RESPONSES Event 4

9. WHEN the Crew exits LCO 3.0.3 and / or at the discretion of the Lead Evaluator, THEN enter the Steam Generator Tube Leak (Relative Order 3, Trigger 3).

a. As the Duty Chemist, Report Primary to Secondary Leakage on A Steam Generator is detected but leak rate cannot be determined yet.

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

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

LEAD LEAD LEAD C47022-0108 Hi Radiation Train B

Determine 1R-19 is in alarm C47048 1R-19

Verify Automatic actions occur

Notify Rad Protection to determine leak rate 1C4 AOP2 Steam Generator Tube Leak

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 POS EXPECTED STUDENT RESPONSES E

vent 5 Event 6

10. After the Crew determines Action Level 2 is appropriate and / or at the discretion of the Lead Evaluator, THEN enter the Loss of Offsite Power with Bus 15 Lockout and Loss of Cooling Water (Relative Order 4, Trigger 4).

a. If asked to investigate Bus 15 Lockout, Report Bus 15 has a 50G Flag

b. If asked to investigate 22 Cooling Water pump, report, 22 Cooling Water Pump has an air leak and will not be able to be started.

11. 1E-0 Implementation

a. If requested, report that all category 1 vent doors are closed.

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

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

1) Bring up the CAEP Window

2) Click on OPEN File

3) Click on Attachment J-E0.cae

4) Click on Run button

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

12. When the Crew transitions to 1ES-0.1, and at the discretion of the Lead Evaluator, ENTER the Steam Generator Tube Rupture. (Relative Order 5, Trigger 5).

RO LEAD SS RO LEAD RO RO LEAD /

RO RO LEAD 1E-0, Reactor Trip or Safety Injection

Verify Reactor Trip

Verify Turbine Trip

Verify Both Safeguards Busses energized

Check if SI is actuated

Transition to 1ES-0.1, Reactor Trip Recovery 1ES-0.1, Reactor Trip Recovery

Announce Unit 1 Reactor Trip

Transfer Steam Dump to Pressure Mode

Check RCS Temperature stable at 547F

Check Cooling Water Header Pressures greater than 75 psig

Check Feedwater Status o RCS Temp o MFRV Closes o Total AFW Flow greater than 200gpm

Verify all rods inserted

Check Pressurizer level greater that 15%

Verify Charging and Letdown in service

Check Pressurizer pressure greater than 1830psig

Manually actuate SI and transition to 1E-0, Reactor Trip or Safety Injection.

NOTE: The transition to 1E-0 can be made at step 9 on PZR Pressure or from the Info Page based on PZR level less than 5%.

Page 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 POS EXPECTED STUDENT RESPONSES

13. 1E-0 implementation, continued.

NOTE: The Lead will be investigating the loss of Cooling Water Header pressure while the RO Continues with the EOP RO LEAD RO RO 1E-0, Reactor Trip or Safety Injection

Verify Reactor Trip

Verify Turbine Trip

Verify Both Safeguards Busses energized

Check if SI is actuated

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 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 POS EXPECTED STUDENT RESPONSES

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 /

RO 1E-3, Steam Generator Tube Rupture

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 POS EXPECTED STUDENT RESPONSES LEAD /

RO LEAD /

RO

Check 12 SG Level - Control level 5-50%

Check PZR PORVS Closed

Check Block valves - at least one open

Reset SI

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 o Total feed flow - greater than 200 gpm 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 at the discretion of the Lead Evaluator, place the simulator in freeze.

a. Do not reset the simulator until the Lead Evaluator has consented Assemble near fire detection panel while evaluators consult 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 Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description 0

Override DI DI-46076 ST START OFF 122 CR Chiller Auto 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 START DELETE 122 CR Chiller Auto 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 Order System Or Panel Drawing Type Code Severity Or Value Event 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

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

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