ML071220399

Proposed Scenarios for the Monticello Initial Examination - February 2007

ML071220399
Person / Time
Site:	Monticello
Issue date:	02/19/2007
From:	Valos N NRC/RGN-III/DRS/OLB
To:
References
50-263/07-301
Download: ML071220399 (71)

Text

QF-1030-19 Rev. 5 (05/12/05)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 23 Appendix D Scenario Outline Form ES-D-1 Facility: ____MNGP__________ Scenario No.: NRC-01 Op-Test No.: MNGP-07 Examiners: ____________________________ Operators: ____________________________

Initial Conditions: 100% reactor power with RCIC inoperable due to planned maintenance on the trip/throttle valve. Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST is scheduled to be performed.

Turnover:

Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST.

Event No.

Malf.

No.

Event Type*

Event Description 1

MS06A N (BOP)

(SRO)

Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST. The A Outboard MSIV will fail to close when required by test resulting in an ITS LCO.

2 CH07B I (RO)

CRD Flow Control Valve Fails Closed. The STBY FCV will be placed in service when High CRD Temperature annunciator alarms.

3 AP07 C (BOP)

(SRO)

Inadvertent ADS timer actuation. ADS taken to inhibit.

ITS LCO 4

TU03G TU03H R (RO)

Main Turbine Vibrations, lower reactor power to lower /

stabilize vibrations.

5 SW01A C (BOP)

RBCCW system degradation. RBCCW Pump Trip.

Standby pump fails to auto start.

6 FW20A C (RO)

Loss of Air to A Feed Reg. Valve. FRV Lockup and recovery.

7 RR01A M (ALL)

M (ALL)

M (ALL)

C (BOP)

Recirc line break inside primary containment.

Scram. Unable to spray D/W.

EOP 1100 entry (RPV Control).

EOP 1200 entry (Primary Containment Control).

EOP 2002 entry (Blowdown)

Failure of 1 ADS SRV to open

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

QF-1030-19 Rev. 5 (05/12/05)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 27 SIMULATOR EXERCISE GUIDE (SEG)

SITE:MNGP SEG #

2007 ILT NRC 1 SEG TITLE:

LOCA, Blowdown REV. #

0 PROGRAM:

ILT MT-ILT COURSE:

NRC EXAM N/A TOTAL TIME:

1.5 HOURS Additional site-specific signatures may be added as desired.

Developed by:

J. Ruth Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 3 of 27 Guide Requirements Goal of Training:

ILT NRC EXAM Learning Objectives:

1.

ILT NRC EXAM Prerequisites:

1.

COMPLETION OF MT-ILT PROGRAM Training Resources:

1.

SIMULATOR

References:

1.

FP-T-SAT-72 Commitments:

1.

N/A Evaluation Method:

ILT NRC EXAM Operating Experience:

N/A Related PRA Information:

Initiating Event with Core Damage Frequency:

LOCA Important Components:

Containment Important Operator Actions with Task Number:

XRPVBLDNY-Blowdown to prevent core damage.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 4 of 27 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. A CRD FCV fails closed

2. Inadvertent ADS Timer initiation

3. Turbine Vibrations

4. RBCCW Pump trip

5. Feedwater Reg. Valve lockup After EOP Entry:

1. Drywell Spray failure

2. 1 ADS SRV fails to open Abnormal Events:

1. Inadvertent ADS Timer initiation

2. RBCCW Pump trip

3. Feedwater Reg. Valve lockup Major Transients:

1. LOCA Critical Tasks:

1. [When D/W temperature cannot be restored and maintained below 281°F, blowdown.]

2. [When a blowdown is initiated and <3 ADS SRVs can be opened, open a non-ADS SRV to ensure 3 SRVs are open.]

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 5 of 27 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

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

IC-231

3. The following equipment is OOS:

RCIC SEQUENCE OF EVENTS:

Event 1: MSIV Closure Test 0008 Reactor power is 100%. RCIC is inoperable due to planned maintenance on the trip/throttle valve. The schedule requires test 0008, MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST be performed.

The test will progress normally for the 4 Inboard MSIVs.

When step 3A for the A Outboard MSIV (Depress and hold MSIV test pushbutton until protective relays energize) the MSIV will not move from its fully open position.

ITS will be reviewed and be determined that LCO 3.6.1.3 is applicable, Condition A, Required Action A.1 requiring the steam line be isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Event 2: CRD Flow Control Valve Failure In-service CRD Flow Control Valve fails and approximately 3 minutes later annunciator 5-B-41 (CRD HI TEMPERATURE) alarms.

The OATC recognizes that the CRD Flow Control Valve failed closed requiring a shift to the standby FCV.

Event 3: ADS Inadvertent Initiation Annunciators 3-A-25, (AUTO BLOWDOWN TIMER ACTIVATED), prompt the crew to determine an ADS timer initiation.

The BOP operator takes action to verify timer actuation and carries out the actions of C.4-G to place the ADS AUTO/INHIBIT switch to INHIBIT.

ITS will be reviewed and be determined that LCO 3.5.1 is applicable, Condition L. The CRS should prepare to be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 6 of 27 Event 4: Main Turbine Vibration Vibration on bearings 7 and 8 are noted by the crew to be rising or acknowledged when

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 7 of 27 annunciator 7-B-33, TURB VIBRATION HIGH alarms at 10 mils. The computer alarm actuates at 7 mils.

The CRS will direct a power reduction to mitigate the condition.

When the reactor power is lowered, turbine vibrations will lower and stabilize.

Event 5: RBCCW Pump Trip The running RBCCW pump trips and the standby pump fails to auto start.

The BOP responds to annunciator 6-B-32 (RBCCW LOW DISCH PRESS)

BOP starts the standby pump per C.4-B.02.05.A, Loss of RBCCW, and reports system pressure returns to normal.

Annunciators 4-B-21 (CLEAN UP FILTER DEMIN FAILURE) 4-B-26 (CLEAN UP DEMIN TEMP HI) and 4-B-31 (CLEAN UP DEMIN TEMP HI HI) will cue the crew that the RWCU system has tripped.

Event 6: Loss of Air to A FRV, FRV Lockup The A FRV experiences a loss of air due to a localized air line fitting leak and the FRV locks up as expected.

The OATC responds to annunciator 5-B-40 (FW CONTROL VALVE LOCKED) and places the un-locked FRV in manual control.

The out plant operator will be dispatched and report that the leak has been repaired allowing the FRV lockup to be reset and restore FWLC to automatic control.

Event 7: Recirc Leak Inside Primary Containment A small Recirc line break inside the primary containment will occur which will result in rising drywell pressure.

The CRS will direct a reactor scram and EOPs-1100 (RPV CONTROL) and 1200 (PRIMARY CONTAINMENT CONTROL) will be entered.

Torus cooling, sprays and drywell sprays will be directed to mitigate conditions in the primary containment. Drywell sprays will not be able to be initiated on either RHR loop.

The CRS will direct a blowdown (or Anticipate Emergency Depressurization) due to no being able to maintain drywell temperature below 281°F.

3 ADS valves will be directed to be opened to depressurize the RPV. One of the ADS valves will not open and a non-ADS SRV must be manually opened.

The scenario will be terminated when the RPV has been depressurized, RPV water level is being maintained above 9 inches, and with concurrence of the lead evaluator.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 8 of 27

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 9 of 27 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

TASK DESCRIPTION OBJECTIVE CR240.101 Perform the MSIV exercise test 1-5 CR200.146 Perform the procedure for a reactor scram 1-5 1-5 CR201.111 Place the Standby CRD FCV into service CR203.111 Transfer the A(B) RHR from LPCI to Torus cooling 1-5 1-5 CR200.203 Perform the procedure for rapid power reduction CR200.162 Perform the procedure for leak inside the primary containment 1-5 1-5 CR304.102 Perform the actions associated with RPV Control CR200.204 Perform the procedure for inadvertent ECCS initiation 1-5 1-5 CR200.152 Perform the procedure for loss of RBCCW flow CR200.164 Perform the procedure for loss of reactor water level control 1-5 CR304.103 Perform the actions associated with Primary Containment Control 1-5 CR314.123 Perform the actions associated with Containment Spray 1-5 6, 7 SS304.193 Implement RPV Control SS299.328 Apply Tech Spec 3.6 and Bases to the Primary System Boundary 6, 7 SS299.327 Apply Tech Spec 3.5 and Bases to the Core and Containment/Cooling System 6, 7 6, 7 SS304.194 Implement Primary Containment Control 6, 7 SS315.101 Supervise response to reactor scram SS315.160 Supervise the response to an inadvertent ECCS initiation 6, 7

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 10 of 27 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

Standard IC-15 (IC-231)

Mode: 1 Exposure: MOC Power: 100%

Pressure: 1000 Generator: 611 Mwe (RO/LO

/SRO) 1.

SIMULATOR SET UP (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 11 of 27 CDF is GREEN, XCEL condition is GREEN. RCIC is in 2.

Simulator Pre-brief:

day 2 of LCO 3.5.3 Action A.2, action A.1 has been completed. RCIC is unavailable. Turbine Building Status:

5 Condensate F/D are in service, C demin has highest d/p indication at 4.8 psid. All other conditions are normal.

Reactor Building Status: RCIC maintenance is in progress, all other conditions are normal.

The following support is available: Normal Day Shift Operations: normal crew compliment plus 1 relief crew NLO Maintenance: support available upon request Engineering: support available upon request Management: support available upon request 3.

COMPLETE TURNOVER:

a.

Review applicable current Unit Status b.

Review relevant At-Power Risk status c.

Review current LCOs not met and Action Requirements d.

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

Performs pre-shift briefing

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 12 of 27 4.

EVENT 1: MSIV Closure Test 0008 a.

No trigger is required for this event b.

For each Inboard MSIV, when the green light is lit, inform the BOP operator that the respective protected relays de-energize (see TEST 0008, Table 1 for relay numbers).

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

d.

After the ITS call has been made, call as the Ops Manager and state that an entry into the steam chase to investigate the problem will be planned and made before the steam line is isolated.

BOP CRS CRS CRS Performs Test 0008:

Uses test push button to partially close each Inboard MSIV Releases test pushbutton when relays de-energize Records response Attempts to close first Outboard MSIV and reports failure to close to Shift Supervision Directs test suspended Refers to ITS and enters Required Action A.1 for LCO 3.6.1.3 (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to isolate the steam line).

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 13 of 27 9.

EVENT 2: CRD Flow Control Valve Failure a.

When directed by the lead evaluator, INSERT TRIGGER 1, CRD FCV FAILURE.

b.

If directed to investigate CRD temperatures, wait 2 minutes and report that many CRD temperatures are rising and that CRD 26-15 is in alarm.

c.

When directed to report to the CRD FCV station to support shift of FCV, WAIT 3 minutes and report you are standing by.

d.

When directed to OPEN CRD-16-2 and CRD-18-2, INSERT TRIGGER 2 and WAIT 2 minutes, then report valves are open.

e.

When directed to CLOSE CRD-16-1 and CRD-18-1, INSERT TRIGGER 3 and WAIT 2 minutes, then report valves are closed.

f.

If directed to report CRD temperatures, report all alarms are clear and all temperatures are lowering to normal.

OATC CRS OATC OATC CRS Responds to annunciator 5-B-41, CRD HI TEMPERATURE Informs Shift Supervision Sends Reactor Building Operator to investigate CRD temperature recorder Refers to procedure B.01.03-05 CRDH Recognizes CRD FCV failure Directs swap to standby CRD FCVCoordinates with Reactor Building Operator and performs the following:

Opens standby FCV manual inlet/outlet valves Places Flow Controller in MANUAL Manually runs controller to 0 Places the CRD Flow Selector to the B position Slowly OPENS the B FCV manually to approximately 54 to 56 gpm Places the FCV in AUTO Closes previously in-service FCV manual inlet/outlet valves Acknowledge annunciator 5-B-41 clear and informs Shift Supervision.Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 14 of 27

21. EVENT 3: ADS Inadvertent Initiation a.

When directed by the lead evaluator, INSERT TRIGGER 4, ADS TIMER.

b.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC BOP BOP CRS CRS Reports the following alarms:

3-A-25, AUTO BLOWDOWN TIMER ACTIVATED Reports the following:

ADS timer actuation Enters C.4-G, INADVERTENT ECCS INITIATIONPlaces ADS AUTO/INHIBIT control switch to INHIBIT Refers to ITS and enters Required Action G for LCO 3.3.5.1 and declares ADS SRVs inoperable per table 3.3.5.1-1 Refers to ITS and enters Required Action L for LCO 3.5.1 (be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 15 of 27

24. EVENT 4: Main Turbine Vibration a.

When directed by the lead evaluator, INSERT TRIGGER 5, TURBINE BEARINGS HIGH VIBRATION (bearings 7 and 8).

b.

When reactor power is reduced, manually lower the malfunction severity of TU03G and TU03H over the span of 5 minutes to approximately 5 mils each.

c.

If directed to investigate the turbine, WAIT until vibrations have been lowered and report no unusual noise or vibrations are detected.

BOP BOP CRS OATC BOP CRS CRS Reports annunciator 7-B-33, TURB VIBRATION HIGH (crew may identify condition via computer alarm at 7 mils)

Reviews ARP actions:

Verifies vibration readings on VR-1716 If >10 mils, enter shutdown procedure If rapid power reduction is necessary, enter C.4-F (RAPID POWER REDUCTION)

If vibrations approach 15 mils, then reduce recirc flow to min, scram, trip the turbine Informs Shift Supervision Directs power reduction to stabilize/reduce turbine vibrationReduces reactor power per C.4-F with reactor recirc Reports turbine vibrations loweringDirects power reduction securedProvides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 16 of 27

30. EVENT 5: RBCCW Pump Trip a.

When directed by the lead evaluator, INSERT TRIGGER, 6 RBCCW pump 11 trip.

b.

If directed to investigate the RBCCW pumps, WAIT 3 minutes and then report that the bearings on the 11 pump motor appear to be hot, the 12 pump appears to be operating normally.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

d.

If directed to help restore RWCU, report that both filter demins are in hold.

Recognize lowering RBCCW system pressure BOP Reports annunciator 6-B-32, RBCCW LOW DISCH PRESS Performs immediate actions of C.4-B.02.05.A, LOSS OF RBCCW Starts 12 RBCCW pump Verifies RBCCW pressures return to normal

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 17 of 27

33. EVENT 6: Loss of Air to A FRV a.

When directed by the lead evaluator, INSERT TRIGGER 7, LOSS OF AIR TO THE A FRV.

b.

If directed to investigate, WAIT 4 minutes and report that the air connection to the FRV has come lose and air is escaping from the loose connection. Also report that the connection can easily be tightened, and if directed to do so, WAIT 2 minutes and report that the connection has been tightened and the air leak has stopped. The system engineer recommend resetting the lock out. DELETE malfunction LOSS OF AIR TO THE A FRV.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC OATC CRS OATC Reports annunciator 5-B-40, (FW CONTROL VALVE LOCK) and performs the following:

Reports the Feedwater Control Valve Lockup/reset amber light for the A FRV is lit.

Monitors RPV water level Enters C.4-B.05.07.A Places the UNLOCKED FRV in controller in manual When the report that that air leak has been repaired is given, the CRS will direct that the lockup be reset.

When directed to attempt to reset the lockup:

Verify the M/A station for the locked valve is in MANUAL Verify the M/A station output meter is at the black memory pointer Verify no major air leakage at the valve Depress the reset pushbutton for the affected FRV

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 18 of 27 OATC OATC Place First FRV in Automatic:

Verify Master Controller is in MANUAL Adjust Master Controller to match demand Adjust the Feedwater Control MAN/AUTO station to match the deviation Place Feedwater controller in AUTO Adjust dial on Master Controller for deviation in the green band and place the Master Controller in AUTO Place Second FRV in Automatic:

Adjust the Feedwater Control MAN/AUTO station to match the deviation Place the Feedwater Control MAN/AUTO in AUTO

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 19 of 27

48. EVENT 7: Recirc Leak Inside Primary Containment a.

When directed by the lead evaluator, INSERT TRIGGER 8, SMALL RECIRC LINE BREAK INSIDE PRIMARY CONTAINMENT and RR03B, Recirc pipe break.

BOP CRS OATC BOP BOP CRS Reports Drywell pressure rising Directs reactor scram Inserts manual scram:

Depresses manual scram pushbuttons Places Mode Switch in SHUTDOWN Verifies all rods in Makes scram report Carries out subsequent actions of C.4-A (REACTOR SCRAM)

Reports drywell pressure and temperature and torus temperature EOP entry conditions Carries out subsequent actions of C.4-A (REACTOR SCRAM)

Enters EOP-1100 and EOP-1200 and directs:

Start all available torus cooling Start all available drywell cooling Start torus sprays Start drywell sprays

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 20 of 27 If requested to investigate the problem with Div 2 cooling / spray function, report you will investigate.

BOP /

OATC Start all available torus cooling: (B.03.04) (Div 2 Torus Cooling will not be able to be initiated)

Close RHR HX Bypass valve Place RHRSW pumps LPCI and ECCS Load Shed Manual Override switch to OVERRIDE Start RHRSW pumps Adjust RHRSW flow to ~3500 gpm Place Containment Spray/Cooling LPCI Initiation Bypass Switch to BYPASS OPEN Torus Cooling Inj/TEST inboard valve for

~8 seconds OPEN Disch to Torus Close LPCI outboard injection valve(s) while establishing ~8000 gpm flow BOP /

OATC Start all available drywell cooling (C.5-3503)

Place all D/W fan control switches to OFF Open Knife switch KS3100 Verify fan inlet dampers are in AUTO Place all D/W fan control switches to ON OPEN associated fan disch dampers

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 21 of 27 BOP /

OATC Start torus sprays (Div 2 Sprays will not be able to be initiated)

Reports inability to spray torus BOP /

OATC Start D/W sprays (Sprays will not be able to be initiated)

Reports inability to spray drywell

[When D/W temperature cannot be restored and maintained below 281°F, blowdown.]

Directs Blowdown when D/W temp cannot be maintained CRS below 281°F

[When a blowdown is initiated and <3 ADS SRVs can be opened, open a non-ADS SRV to ensure 3 SRVs are open.]

BOP /

OATC Opens 2 ADS SRVs, and reports 3 ADS SRV will not rd open. Opens a non-ADS SRV to obtain 3 SRVs open when directed by CRS.

Directs opening of a non-ADS SRV to obtain 3 SRVs CRS open.

73. When the conditions are stabilized or at discretion of lead instructor/evaluator

74. End the scenario by placing the simulator in freeze Crew:

Remain in simulator for potential questions from evaluator.

No discussion of scenario or erasing of procedure marking is allowed.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Page 22 of 27 SIMULATOR INPUT

SUMMARY

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Malfunction CH07B True 1

N/A CV-19A Fails Closed Remote CH17 Open 2

N/A B CRD FCV Isolations Open Remote CH16 Close 3

N/A A CRD FCV Isolations Close Malfunction AP07 True 4

N/A Actuation of ADS Timer Malfunction TU03H 41 5

00:10:00 Turbine Bearing #8 Vibration Malfunction TU03G 43 5

00:10:00 Turbine Bearing #7 Vibration Malfunction SW01A True 6

N/A 11 RBCCW Pump Trip Malfunction FW20A True 7

N/A Loss of Air to A FRV Malfunction RR01A 100 8

00:16:00 Small Break on A Recirc Malfunction RR03B 3

8 00:06:00 (delay)

Break on B Recirc Malfunction MS06A True N/A N/A A Outboard MSIV Failure to Close Override DS178-02 Off N/A N/A RCIC MO-2075 Green Lamp Override DS140-02 Off N/A N/A RCIC MO-2076 Green Lamp Override DS090-02 Off N/A N/A RCIC MO-2078 Green Lamp Override A02DS033-02 Off N/A N/A RCIC MO-2076 Green Lamp on Mimic Override A02DS035-02 Off N/A N/A RCIC MO-2075 Green Lamp on Mimic Override S103-01 Off N/A N/A Div 2 CTMT SPR LPCI BYP

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SIMULATOR INPUT

SUMMARY

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Page 23 of 27 Override S030-01 Close N/A N/A MO-2022 Hand Switch Override S030-02 Open N/A N/A MO-2022 Hand Switch Override A1DS126 On N/A N/A 12 RBCCW Pump White Light Override S054-01 Off N/A N/A D SRV Fails to Open Hang caution tags on RCIC steam isolation and stop valves.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEGs new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power Risk Assessment provided by the PRA group.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

Yes No

8. The scenario includes related industry experience.

Yes No

9. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.

Yes No

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Appendix D, Page 38 of 39 Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved.

Yes No

2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes No

3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes No

5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes No

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Yes No

7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes No Discrepancies noted (Check none or list items found)

G None SAR = Simulator Action Request SAR:

SAR:

SAR:

SAR:

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Appendix D, Page 38 of 39 Comments:

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

QF-1030-19 Rev. 5 (05/12/05)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 20 Appendix D Scenario Outline Form ES-D-1 Facility: ____MNGP__________ Scenario No.: NRC-02 Op-Test No.: MNGP-07 Examiners: ____________________________ Operators: ____________________________

Initial Conditions: 89% reactor power. Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES, is scheduled to be completed.

Turnover:

Complete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES and return to 100% power.

Event No.

Malf.

No.

Event Type*

Event Description 1

TC06B N (BOP)

(SRO)

Complete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES The #2 Turbine Bypass Valve will not open as required by the test resulting in an ITS LCO.

2 CH08A C (RO) 11 CRD Pump trip. Start 12 CRD pump.

3 TC05A I (BOP)

EPR Oscillations and placing the MPR in control.

4 RR02C PP06 I (RO)

(SRO)

RPV press inst fails upscale, half scram fails to be initiated.

ITS LCO.

5 RR07 RR08 R (RO)

C (BOP)

(SRO) 12 Recirc pump motor bearing temp and vibrations high and subsequent shutdown of pump.

ITS LCO.

6 PP05A PP05C CH16 M (ALL)

Group 1 isolation, ATWS EOP-2007 (Failure to Scram) entry.

All rods inserted, EOP-1100 (RPV Control) entry and RPV parameter recovery

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

QF-1030-19 Rev. 5 (05/12/05)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 23 SIMULATOR EXERCISE GUIDE (SEG)

SITE:MNGP SEG #

2007 ILT NRC 2 SEG TITLE:

ATWS REV. #

0 PROGRAM:

ILT MT-ILT COURSE:

NRC EXAM N/A TOTAL TIME:

1.5 HOURS Additional site-specific signatures may be added as desired.

Developed by:

J. Ruth Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 3 of 23 Guide Requirements Goal of Training:

ILT NRC EXAM Learning Objectives:

1.

ILT NRC EXAM Prerequisites:

1.

COMPLETION OF MT-ILT PROGRAM Training Resources:

1.

SIMULATOR

References:

1.

FP-T-SAT-72 Commitments:

1.

N/A Evaluation Method:

ILT NRC EXAM Operating Experience:

N/A Related PRA Information:

Initiating Event with Core Damage Frequency:

Group 1 Isolation Important Components:

Class IV-Accident sequences involving failure to scram leading to a high-pressure challenge to containment resulting from power generation into the containment.

Important Operator Actions with Task Number:

See critical task listing

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 4 of 23 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. 11 CRD Pump Trip

2. EPR Oscillations

3. RPV Pressure Inst Fails Upscale

4. 12 RR Pump Motor Bearing Hi Temp/Vibration

5. Group 1 Isolation After EOP Entry:

1. ARI Failure Abnormal Events:

1. 11 CRD Pump Trip

2. EPR Oscillations

3. 12 RR Pump Motor Bearing Hi Temp/Vibration Major Transients:

1. ATWS Critical Tasks:

1. [With Reactor power >3% or unknown, insert control rods to shutdown the reactor.]

2. [With Reactor power >3% or unknown, RPV water level above -33 inches, prevent RPV injection to lower power.]

3. [With an ATWS condition present, inhibit ADS before ADS valve actuation.]

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 5 of 23 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

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

IC-232

3. The following equipment is OOS:

None SEQUENCE OF EVENTS:

Event 1: OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES Reactor power is ~89%. The schedule requires test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES be performed.

When step 2 is performed for the #2 turbine bypass valve, it will fail to open due to an instrument malfunction.

ITS will be reviewed and be determined that LCO 3.7.7 is applicable, action A.1. The CRS should direct that repairs be initiated to be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

A report from the I&C shop will be made to inform the CRS that the repairs can be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Event 2: 11 CRD Pump Trip The running CRD pump trips.

Annunciators 5-B-17 (CHARGING WATER LO PRESS), 5-B-25 (CRD PUMP 3-16A BREAKER TRIPPED), and 5-B-26 (CRD PUMP 3-16A OL) alarm.

The non-running pump is required to be manually started.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 6 of 23 Event 3: Pressure Regulator Oscillation, EPR The OATC / BOP operator reports oscillations of reactor power, level, and/or pressure, and MWe output.

The BOP operator will initiate action to stabilize pressure control by lowering the MPR set point so it will take control and running down the EPR setpoint to clear the oscillations per B.05.09-05.H.1 and B.05.09-05.H.3.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 7 of 23 ITS will be reviewed and be determined that LCO Condition 3.11.A (B), (C) are not applicable, at this time, but would need to be reviewed again if power is <90%.

Event 4:

RPS RPV high pressure relay 5A-K5C fails initiating annunciators 5-B-11 (REACTOR VESSEL HI PRESS SCRAM TRIP) and 5-B-4 (REACTOR AUTO SCRAM CHANNEL A).

The crew determines that a 1/2 scram condition should exist but does not.

CRS reviews ITS section 3.3.1.1 and directs a 1/2 scram be inserted on the A side of RPS within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Event 5: 12 Reactor Recirc Pump Motor Bearing High Temp / Vibration The 12 Reactor Recirc pump motor will experience bearing high temperatures and subsequent vibration. Annunciator 4-C-24 (RECIRC PUMP MTR B HI VIBRATION) will alarm.

When vibrations exceed 3 mils the 12 Reactor Recirc pump will be shutdown. This will require a power reduction via lowering both recirc pump speed and inserting control rods to meet the requirements of power/flow map.

The CRS will recognize LCO Conditions 3.11.A (B), (C) are applicable at this time, when power is lowered below 90%.

Event 6: Group 1 Isolation / ATWS A spurious Group 1 isolation (MSIV closure) will occur and an ATWS condition will result in the crew performing actions of EOP-2007, Failure to Scram.

After the initial actions of the EOP power leg are performed, the OATC will insert control rods and initiate SBLC.

The BOP will take actions to prevent injection into the RPV.

When all control rods are inserted, SBLC will be secured.

RPV water level will be returned to the normal band.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 8 of 23 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

TASK DESCRIPTION OBJECTIVE CR245.102 Perform the Turbine Generator Weekly operational tests 1-5 CR200.147 Perform the procedure for a loss of CRD pump flow 1-5 CR200.157 Perform the procedure for primary containment Group 1 isolation 1-5 1-5 CR200.203 Perform the procedure for rapid power reduction CR202.112 Shutdown one Recirc pump with the reactor at power 1-5 1-5 CR203.117/118 Placing A / B Loop RHR in torus cooling 1-5 CR211.106 Manually initiate SBLC system 1-5 CR314.104 Perform actions associated with Failure to scram CR314.112 Perform actions to Terminate and Prevent injection 1-5 SS299.323 Apply T.S. 3.1 and Bases to the Reactor Protection System 6,7 SS299.329 Apply T.S. 3.1 and Bases to the Containment System 6,7 SS299.328 Apply T.S. 3.1 and Bases to the Primary System Boundary 6,7 6,7 SS304.201 Implement the response for a failure to scram 6,7 SS314.101 Supervise alternate rod insertion 6,7 SS314.108 Supervise terminate and prevent 6,7 SS315.159 Supervise rapid power reduction

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 9 of 23 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

Standard IC-15 (IC-232)

Mode: 1 Exposure: MOC Power: ~89%

Pressure: 1000 Generator: ~543 Mwe (RO/LO

/SRO) 1.

SIMULATOR SET UP (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

2.

Simulator Pre-brief:

CDF is GREEN, XCEL condition is GREEN. Turbine Building Status: 5 Condensate F/D are in service, C demin has highest d/p indication at 4.8 psid. All other conditions are normal. Reactor Building Status: All conditions are normal.

The following support is available: Normal Day Shift Operations: normal crew compliment plus 1 relief crew NLO Maintenance: support available upon request Engineering: support available upon request Management: support available upon request

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 10 of 23 3.

COMPLETE TURNOVER:

a.

Review applicable current Unit Status b.

Review relevant At-Power Risk status c.

Review current LCOs not met and Action Requirements d.

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

4.

EVENT 1: OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES a.

No trigger is required for this event b.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

c.

After the ITS call has been made, call as the I&C Supervisor and state that repairs are estimated to be complete within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

BOP CRS Performs Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES:

Record generator gross load Select respective valve with BYPASS VALVE TEST switch Press the BYPASS VALVE TEST pushbutton Time the bypass valve travel to the OPEN position Release the BYPASS VALVE TEST pushbutton Time the bypass valve travel to the CLOSE position When second TBPV test is attempted reports failure to open to Shift Supervision Directs test suspended Refers to ITS and enters Required Action A.1 for LCO 3.7.7 (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to return to service or Action B reduce thermal power to <25%).

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 11 of 23

12. EVENT 2: 11 CRD Pump Trip a.

When directed by the lead evaluator, INSERT TRIGGER 1, 11 CRD pump trip.

b.

If called to investigate the CRD pump trip, wait 3 minutes and report that the pump motor is very hot and the breaker indicates tripped.

(over current flag is tripped) c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC CRS Responds to annunciators B-5-17 (CHARGING WATER LO PRESS), 5-B-25 (CRD PUMP 3-16A BREAKER TRIPPED), and 5-B-26 (CRD PUMP 3-16A OL):

Notifies CRS Takes action per C.4-B.01.03.A, Loss of CRD Flow Starts 12 CRD pump Verifies system pressures/flows return to normal Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 12 of 23

17. EVENT 3: Pressure Regulator Oscillation, EPR a.

When directed by the lead evaluator, INSERT TRIGGER 2, Pressure Regulator Oscillation, EPR.

b.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

BOP CRS Reports oscillations of reactor power, level, and/or pressure, and MWe output.

Performs actions of B.05.09-05.H.1:

Switch control from the EPR to the MPR by:

o Lower the MPR setpoint using the MECH PRESS REGULATOR control switch until the red CONTROLLING YES light comes ON o

Raise the EPR setpoint until the green CONTROLLING NO light comes ON Reports reactor power, level, and/or pressure, and MWe output have stabilized.

Refers to ITS and reviews LCO Conditions 3.11.A (B), (C)

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 13 of 23

19. EVENT 4: RPV High Press RPS Relay Failure a.

When directed by the lead evaluator, INSERT TRIGGER 3, RPV High Press.

b.

If called, respond as I&C that RPS relay 5A-K5C has de-energized. Will need to check the calibration of the RPV pressure instrument to troubleshoot event.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC ALL CRS OATC Responds to annunciators 5-B-11 (REACTOR VESSEL HI PRESS SCRAM TRIP) and 5-B-4 (REACTOR AUTO SCRAM CHANNEL A). Recognize 1/2 scram should have occurred and did not Refers to ITS and enters Required Action C.1 for LCO 3.3.1.1 (Restore RPS trip capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

Provides crew brief Directs 1/2 scram be inserted on A RPS Inserts 1/2 scram by depressing A manual scram pushbutton

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 14 of 23

20. EVENT 5: 12 Reactor Recirc Pump Motor Bearing High Temp / Vibration a.

When directed by the lead evaluator, INSERT TRIGGER 4, 12 Recirc pump high bearing temperature and motor vibration.

b.

When requested to check Recirc pump motor vibrations, WAIT 3 minutes and report 12 Recirc pump motor vibrations are 4 mils and slowly rising.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

d.

When the 12 Recirc pump is shutdown, Wait 30 seconds and DELETE the motor vibration malfunction.

BOP

/OATC CRS Responds to annunciator 4-C-24 (RECIRC PUMP MTR B HI VIBRATION) alarms.

Performs actions of ARPs:

Check TR 2-2-31 to verify alarm conditions Reduce Recirc pump heat load by lowering pump speed Dispatch operator to determine vibrations IF Recirc pump motor vibration remains above 3 mils, THEN shutdown the Recirc MG per B.01.04-05 Performs actions of B.01.04-05, Recirc:

Reduce power with Recirc pumps to ~50%

Insert control rods to achieve 5% margin to the unanalyzed region Reduce speed of 12 Recirc pump to 30%

Place 12 Recirc MG control switch to STOP Performs action of C.4-B.05.01.02.A Neutron Flux:

Checks power/flow map Inserts control rods to exit buffer region Refers to ITS and enters LCO Conditions for single loop operations (2.1.1, 3.4.1, and 3.3.1.1)

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 15 of 23

31. EVENT 6: Group 1 Isolation / ATWS a.

When directed by the lead evaluator, INSERT TRIGGER 5, Group 1 Isolation. (Malfunction should be inserted prior to the second round of rod insertion to ensure sufficient power to drive torus temperature during ATWS) b.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

[With an ATWS condition present, inhibit ADS before ADS valve actuation.][With Reactor power >3% or unknown, insert control rods to shutdown the reactor.]

OATC CRS OATC Responds to reactor scram and performs the following:

Scram report:

o Reactor Scram o

Mode Switch in Shutdown o

All rods NOT in Reports reactor power Enters EOP 2007, Failure to Scram and directs:

ATWS hard card actions performed Inhibit ADS Terminate and Prevent injection Performs actions of ATWS hard card:

Runback recirc to minimum Trip recirc pump Actuate ATWS Insert control rods per C.5.1-3101 o

Bypass RWM o

Fully OPEN CRD FCV o

Establish high as possible but <400 psid o

Insert non-peripheral control rods o

Insert remaining control rods

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 16 of 23

41. EVENT 6: Group 1 Isolation / ATWS (cont)

[With Reactor power >3% or unknown, RPV water level above -33 inches, prevent RPV injection to lower power.]

BOP CRS CRS Inhibits ADSPerforms Terminate and Prevent per C.5-3205:

Places CS pumps in PTL, Close injection valves, Place injection bypass keylock in BYPASS Place HPCI Aux Oil Pump in PTL Close both FRVs and Low flow FRV Open LPCI knife switches 10A-S31A/B and close LPCI outboard injection valves Reports rising Torus temperatureDirects SBLC injection Enters EOP 1200 Directs torus cooling placed in service Starts either 11 or 12 SBLC pump and verifies disch press

> RPV pressure Reports all rods at 00 Directs SBLC secured Exits EOP 2007, Enters EOP 1100 Directs RPV water level restored to 9-48 inches

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 17 of 23 Raises RPV water level with FW BOP Start all available torus cooling: (B.03.04) (Div 2 Torus Cooling will not be able to be initiated)

Close RHR HX Bypass valve Place RHRSW pumps LPCI and ECCS Load Shed Manual Override switch to OVERRIDE Start RHRSW pumps Adjust RHRSW flow to ~3500 gpm Place Containment Spray/Cooling LPCI Initiation Bypass Switch to BYPASS OPEN Torus Cooling Inj/TEST inboard valve for ~8 seconds OPEN Disch to Torus Close LPCI outboard injection valve(s) while establishing ~8000 gpm flow

55. When the conditions are stabilized or at discretion of lead instructor/evaluator

56. End the scenario by placing the simulator in freeze

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 18 of 23 SIMULATOR INPUT

SUMMARY

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Malfunction TC06B True N/A N/A

1. 2 TBPV Stuck Malfunction CH08A True 1

N/A 11 CRD Pump Trip Malfunction TC05A 25 2

00:05:00 Pressure Regulator Oscillation, EPR Remote RR02C 950 3

N/A RPV High Press Remote PP06 Instld 3

N/A Scram (Auto) Bypass Malfunction B04 On 3

N/A Annunciator 5-B-4 Cry Wolf Malfunction RR07 100 4

N/A 12 Recirc Pmp Mtr Bearing Hi Temp Malfunction RR08 100 4

00:05:00 12 Recirc Pmp Mtr Vibration Malfunction CH16 True 5

N/A Failure to Scram Malfunction PP05A True 5

N/A Spurious Grp 1 Malfunction PP05C True 5

N/A Spurious Grp 1 Override S07-02 Off N/A N/A ATWS A Man Trip Override S08-02 Off N/A N/A ATWS C Man Trip Override S23-02 Off N/A N/A ATWS B Man Trip Override S24-02 Off N/A N/A ATWS D Man Trip Override S36-06 Off N/A N/A B Man Scram PB Override S34-04 On N/A N/A Mode Switch-Run Override S34-03 Off N/A N/A Mode Switch-Refuel

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SIMULATOR INPUT

SUMMARY

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Page 19 of 23 Override S34-01 Off N/A N/A Mode Switch-Shutdown Override S34-02 Off N/A N/A Mode Switch-Startup

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEGs new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power Risk Assessment provided by the PRA group.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

Yes No

8. The scenario includes related industry experience.

Yes No

9. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.

Yes No

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Appendix D, Page 38 of 39 Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved.

Yes No

2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes No

3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes No

5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes No

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Yes No

7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes No Discrepancies noted (Check none or list items found)

G None SAR = Simulator Action Request SAR:

SAR:

SAR:

SAR:

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Appendix D, Page 38 of 39 Comments:

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

Appendix D Scenario Outline Form ES-D-1 Facility: ____MNGP__________ Scenario No.: NRC-03 Op-Test No.: MNGP-07 Examiners:____________________________ Operators:

Initial Conditions: Reactor power is ~95% with APRM 2 inoperable.

Turnover:

W ithdraw control rod 26-27 to position 08 and then perform Test 0255-03-IA-1-1, CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TESTS.

Even t

No.

Malf.

No.

Event Type*

Event Description 1

CH02 C (RO)

W ithdraw control rod with raised drive pressure.

2 N/A N (BOP)

Perform Test 0255-03-IA-1-1, CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TESTS.

3 SL02A (SRO)

SBLC Squib Valve Loss of Continuity ITS LCO 4

NI13D I (RO)

APRM 4 Fails Upscale. Bypass APRM and reset half scram.

5 FW15B C (BOP)

R (RO) 12 RFP bearing high temperature, shutdown 12 RFP.

Lower reactor power to support removal of 12 RFP.

6 HP01 I (BOP)

(SRO)

HPCI inadvertent initiation and shutdown. HPCI will be inoperable.

ITS LCO.

7 RU07 M (ALL)

RW CU Leak, un-isolable, EOP-1300 Entry, Scram Blowdown, EOP 2002 Entry.

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

QF-1030-19 Rev. 5 (05/12/05)

Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 21 SIMULATOR EXERCISE GUIDE (SEG)

SITE:MNGP SEG #

2007 ILT NRC 3 SEG TITLE:

RWCU LEAK, BLOWDOWN REV. #

0 PROGRAM:

ILT MT-ILT COURSE:

NRC EXAM N/A TOTAL TIME:

1.5 HOURS Additional site-specific signatures may be added as desired.

Developed by:

J. Ruth Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 3 of 21 Guide Requirements Goal of Training:

ILT NRC EXAM Learning Objectives:

1.

ILT NRC EXAM Prerequisites:

1.

COMPLETION OF MT-ILT PROGRAM Training Resources:

1.

SIMULATOR

References:

1.

FP-T-SAT-72 Commitments:

1.

N/A Evaluation Method:

ILT NRC EXAM Operating Experience:

N/A Related PRA Information:

Initiating Event with Core Damage Frequency:

RWCU Leak Important Components:

Secondary Containment Important Operator Actions with Task Number:

XRPVBLDWNY-Failure to depressurize in time to prevent core damage.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 4 of 21 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Withdraw control rod with elevated drive pressure

2. SBLC Squib Loss of Continuity

3. #4 APRM Fails Upscale

4. #12 RFP Motor Bearing Hi Temp

5. HPCI Inadvertent Initiation

6. RWCU Leak After EOP Entry:

1. Failure of Group 3 Isolation Abnormal Events:

1. #12 RFP Motor Bearing Hi Temp

2. HPCI Inadvertent Initiation Major Transients:

1. RWCU Leaking into Secondary Containment Critical Tasks:

1. [Before any area temperature, radiation, or water level reaches max safe value (Tables W, X, Z), scram.]

2. [Wait until 2 or more areas above max safe values of same parameter (Tables W, X, Z),

blowdown.]

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 5 of 21 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

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

IC-233

3. The following equipment is OOS:

1. 2 APRM SEQUENCE OF EVENTS:

Event 1: Withdraw Control Rod with Elevated Drive Pressure Reactor Engineering requests control rod 26-27 be withdrawn from 00 to 08.

Initial attempt to withdraw the rod will be unsuccessful requiring drive water pressure to be raised to withdraw the rod per B.01.03-05.H.4. When drive pressure is raised the rod will withdraw.

Event 2: Perform Test 0255-03-IA-1-1 (CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TEST).

Performance of test will consist of valve stroke and timing and pump start with head/flow measurement.

ITS will be evaluated for LCO 3.5.1 Conditions for applicability per the test instruction.

Event 3: SBLC Squib Valve Loss of Continuity The RO will respond to and report annunciator 5-B-31 (LOSS OF CONTINUITY TO SQUIB VALVE) alarm.

ITS will be reviewed and be determined that LCO 3.1.7 is applicable, Required Action B.1 provides a 7 day period before further actions are required.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 6 of 21 Event 4: #4 APRM Fails Upscale The RO will respond to and report annunciators 5-A-3 (ROD WITHDRAW BLOCK), 5-A-14 (APRM HI), 5-A-30 (APRM HI HI INOP CH 4, 5, 6), 5-B-3 (REACTOR NEUTRON MONITOR SCRAM TRIP), 5-B-5 (REACTOR AUTO SCRAM CHANNEL B) alarms.

ITS will be reviewed and be determined that LCO 3.3.1 is not applicable, as the requirement is 2 operable APRMs per trip system.

The APRM will be bypassed and the 1/2 scram reset.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 7 of 21 Event 5: #12 RFP Bearing High Temp / Shutdown The BOP will respond to and report annunciator 6-A-26 (RCT FEED PUMP BRG HIGH TEMP), alarm.

Recognize bearing high temperature on trend recorder approaching 225°F.

Lower reactor power and remove RFP from service.

Event 6: HPCI Inadvertent Initiation BOP responds to start of the HPCI turbine.

Determines that initiation is inadvertent by verifying RPV level and D/W pressure are normal.

Shuts down HPCI by tripping and taking the Aux Oil Pump to PTL.

ITS will be reviewed and be determined that LCO 3.5.1 is applicable, Required Action H.1 provides a 14 day period before further actions are required.

Event 7: RWCU Leak / Scram The BOP will respond to and report annunciators 3-B-56 (HIGH AREA TEMP STEAM LEAK), 4-A-11 (REACTOR BUILDING HI RADIATION) alarms.

Recognizes event is in RWCU room by observing ARMs and area temperatures.

EOP-1300, SECONDARY CONTAINMENT CONTROL, is entered and attempts to isolate RWCU are unsuccessful and a scram is initiated.

When 2 areas above max safe radiation, Blowdown.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 8 of 21 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

TASK DESCRIPTION OBJECTIVE CR200.133 Perform a power reduction from >90% to 75%

1-5 CR200.146 Perform the procedure for a reactor scram 1-5 1-5 CR200.203 Perform the procedure for rapid power reduction CR200.204 Perform the procedure for inadvertent ECCS initiation 1-5 1-5 CR209.106 Startup a Core Spray Loop 11(12)

CR259.126 Take the actions for Reactor Feed pump and Reactor Feed pump Motor Bearing High Temperature 1-5 CR299.353 Apply T.S. section 3.3 and bases to instrumentation 1-5 CR299.355 Apply T.S. section 3.5 and bases to ECCS and RCIC 1-5 CR299.351 Apply T.S. section 3.1 and bases to Reactivity control systems 1-5 CR304.105 Perform actions associated with Secondary Containment control 1-5 CR314.101 Perform the actions associated with Emergency RPV depressurization 1-5 6,7 SS304.196 Implement secondary containment control 6,7 SS304.193 Implement RPV control 6,7 SS304.198 Implement emergency RPV depressurization 6,7 SS315.160 Supervise response to inadvertent ECCS initiation 6,7 SS315.159 Supervise rapid power reduction 6,7 SS315.101 Supervise response to reactor scram SS299.349 Apply administrative requirements for T.S. 3.1 and bases to reactivity control systems 6,7 SS299.351 Apply administrative requirements for T.S. 3.3 and bases to instrumentation 6,7 SS299.353 Apply administrative requirements for T.S. 3.5 and bases to ECCS and RCIC 6,7

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 9 of 21 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

Standard IC-15 (IC-233)

Mode: 1 Exposure: MOC Power: 100%

Pressure: 1000 Generator: 611 Mwe (RO/LO

/SRO) 1.

SIMULATOR SET UP (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

2.

Simulator Pre-brief:

CDF is GREEN, XCEL condition is GREEN. #2 APRM is downscale. Turbine Building Status: 5 Condensate F/D are in service, C demin has highest d/p indication at 4.8 psid. All other conditions are normal. Reactor Building Status: Conditions are normal.

The following support is available: Normal Day Shift Operations: normal crew compliment plus 1 relief crew NLO Maintenance: support available upon request Engineering: support available upon request Management: support available upon request

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 10 of 21 3.

COMPLETE TURNOVER:

a.

Review applicable current Unit Status b.

Review relevant At-Power Risk status c.

Review current LCOs not met and Action Requirements d.

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

4.

EVENT 1: Withdraw Control Rod 26-27 to position 08.

a.

No event trigger is required for this event.

b.

The malfunction will automatically delete after 1 or 2 drive water 30 psig increments.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

Attempts to withdraw control rod 26-27.

OATC When unable to withdraw with normal drive flow, refers to B.01.03-05.H.4 (WITHDRAW OF A CRD UNDER HIGH DRIVE PRESSURE)

Raise drive water pressure in increments up to 30 psid, to a maximum of 400 psid and give the drive a withdraw signal after each increment Before moving a different CRD, return drive water pressure to approximately 265 psid

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 11 of 21 7.

EVENT 2: Core Spray Test a.

No event trigger is required for this event.

b.

When directed to report Core Spray suction pressure, WAIT 1 minute and report suction pressure is 5 psig.

c.

When directed to report Core Spray amperage, wait 1 minute and report 98 amps.

d.

Acknowledge directions to complete remaining portions of test for out plant actions and report completion during event 3.

Performs Test 0255-03-IA-1-1:

BOP Performs valve timing Starts Core Spray pump Establishes head/flow requirements Shuts down Core Spray pump

12. EVENT 3: SBLC Squib Valve Loss of Continuity a.

When directed by the lead evaluator, INSERT TRIGGER 2, Loss of Squib A Continuity.

b.

When the operator goes to investigate the milliamp meter behind panel C-05, inform him that the meter indicates 0 milliamps.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC CRS CRS Responds to annunciator 5-B-31 (LOSS OF CONTINUITY TO SQUIB VALVE):

Informs CRS Observes white squib ready light NOT lit for the A squib valve on C-05 Observes meter indication for A squib valve behind C-05 indicates 0 milliamps Refers to ITS and enters Required Action B.1 for LCO 3.1.7 (7 day).

Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 12 of 21

16. EVENT 4: #4 APRM Fails Upscale a.

When directed by the lead evaluator, INSERT TRIGGER 3, APRM #4 Fullscale.

b.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

OATC BOP CRS OATC CRS The RO will respond to and report annunciators 5-A-3 (ROD WITHDRAW BLOCK), 5-A-14 (APRM HI),

5-A-30 (APRM HI HI INOP CH 4, 5, 6), 5-B-3 (REACTOR NEUTRON MONITOR SCRAM TRIP), 5-B-5 (REACTOR AUTO SCRAM CHANNEL B):

Informs CRS Observes #4 APRM HI HI/INOP light and #4 APRM recorder full scale Observes RPS channel B trip (1/2 scram)

Observes and reports HI HI light lit and meter full scale and INOP light not litMay refer to ITS and review Required Action A.1 for LCO 3.1.1 to determine the LCO for APRMs is met.

Directs #4 APRM bypassed and 1/2 scram reset Bypasses #4 APRM and resets the 1/2 scram Provides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 13 of 21

20. EVENT 5: #12 RFP Bearing High Temp / Shutdown a.

When directed by the lead evaluator, INSERT TRIGGER 4, RFP #12 Bearing Hi Temp.

b.

If called respond as the out plant operator and WAIT 3 minutes to report confirmation of high bearing temperature and vibrations on the 12 RFP. There appears to be no or little cooling water flow.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

d.

If directed to close the 12 RFP discharge valve (FW-68-2) go to the FW system page and after 5 minutes, close valve by selecting override FW-47 to CLOSE.

BOP CRS OATC BOP CRS The BOP will respond to and report annunciator 6-A-26 (RCT FEED PUMP BRG HIGH TEMP):

Monitor bearing temperatures Dispatch operator to the turbine building Take actions of B.06.05-05 o

Immediately remove the RFP from service Directs Rapid Power reduction per C.4-FLowers power with recirc and control rods to be within the limits of 1 RFP (<50% power)Reviews power/flow map to ensure not in buffer regionSecures the 12 RFPProvides crew brief

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 14 of 21

24. EVENT 6: HPCI Inadvertent Initiation a.

When directed by the lead evaluator, INSERT TRIGGER 5, HPCI Initiation.

b.

If called, respond as RP technician and/or out plant operator to investigate the HPCI turbine.

c.

If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning notification of the event.

BOP CRS CRS BOP responds to start of the HPCI turbine per C.4-G, Inadvertent ECCS Initiation:

Recognize inadvertent initiation by checking RPV water level and D/W pressure normal Place Aux Oil Pump in RUN Depress HPCI TURBINE TRIP pushbutton Verify HPCI turbine has stopped After 5 seconds, place the Aux Oil Pump in PTL Refers to ITS and enters Required Action B.1 for LCO 3.5.1 action H.1 (14 day).Provides crew brief.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 15 of 21

30. EVENT 7: RWCU Leak (un-isolable) a.

When directed by the lead evaluator, INSERT TRIGGER 6, RWCU Suction Line Break.

[Before any area temperature, radiation, or water level reaches max safe value (Tables W, X, Z), scram.]

BOP CRS OATC The BOP will respond to and report annunciators 3-B-56 (HIGH AREA TEMP STEAM LEAK), 4-A-11 (REACTOR BUILDING HI RADIATION):

Reports RWCU room radiation levels and room temperatures are rising Attempts to insert a manual group 3 isolation Attempts to manually close RWCU isolation valves Reports RWCU valves will not isolate Enters EOP-1300 (Secondary Containment Control) and EOP-1100 (RPV control)Directs Reactor ScramInserts a manual scram, provides scram report:

Reactor scram Mode switch in shutdown All rods inserted

[Wait until 2 or more areas above max safe values of same parameter (Tables W, X, Z), blowdown.]

CRS BOP Determines 2 area radiation levels are above max safe Enters EOP-2002 (Blowdown)

Directs BlowdownOpens 3 ADS valves

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Page 16 of 21

38. When the conditions are stabilized or at discretion of lead evaluator.

39. End the scenario by placing the simulator in freeze

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Page 17 of 21 SIMULATOR INPUT

SUMMARY

Relative Order System Or Panel Drawing Type Code Severity Or Value Event Trigger Timing Description Malfunction NI12B True N/A N/A APRM #2 Downscale Malfunction CH02 True 1

N/A Control rod 26-27 stuck Malfunction SL02A True 2

N/A Loss of Squib A Continuity Malfunction NI13D True 3

N/A APRM #4 Fullscale Malfunction FW15B 100 4

N/A RFP #12 Bearing Hi Temp Malfunction HP01 True 5

N/A HPCI Auto Initiation Malfunction RU08 True 6

N/A Grp 3 Isolation Failure Malfunction RU07 25 6

00:30:00 RWCU Suction Line Break Override S75-02 On N/A N/A MO-2397 HS Open Override S75-01 Off N/A N/A MO-2397 HS Close Override S50-02 On N/A N/A MO-2398 HS Open Override S50-01 Off N/A N/A MO-2398 HS Close Override S25-02 On 6

N/A MO-2399 HS Open Override S25-01 Off 6

N/A MO-2399 HS Close Place caution tag on APRM bypass joystick for #2 APRM

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations. (This action applies to all SEGs new or revised for those on the ANS/ANSI-3.5-1998 standard. This action is NOT applicable for those on the ANS/ANSI-3.5-1985 standard.)

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power Risk Assessment provided by the PRA group.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

Yes No

8. The scenario includes related industry experience.

Yes No

9. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.

Yes No

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Appendix D, Page 38 of 39 Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Appendix D, Page 38 of 39 Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved.

Yes No

2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes No

3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes No

5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes No

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could not be satisfied, identify the objectives in the Simulator Action Request Yes No

7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes No Discrepancies noted (Check none or list items found)

G None SAR = Simulator Action Request SAR:

SAR:

SAR:

SAR:

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK, BLOW DOW N, Rev. 0 Appendix D, Page 38 of 39 Comments:

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