Text

Final As-Administered Scenarios for the Monticello Initial Examination - February 2007
	ML071090587
Person / Time
Site:	Monticello
Issue date:	04/19/2007
From:	Valos N; NRC/RGN-III/DRS/OLB
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QF-1030-19 Rev. 5 (05/12/05)

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 Malf. Event Event No. No. Type* Description 1 MS06A N (BOP) Perform Test 0008 MAIN STEAM LINE ISOLATION (SRO) 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) Inadvertent ADS timer actuation. ADS taken to inhibit.

(SRO) ITS LCO 4 TU03G R (RO) Main Turbine Vibrations, lower reactor power to lower /

TU03H 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 MS04A M (ALL) Steam line break inside primary containment.

MS04B Scram. Unable to spray D/W.

M (ALL) EOP 1100 entry (RPV Control).

M (ALL) EOP 1200 entry (Primary Containment Control).

EOP 2002 entry (Blowdown) 8 S054- C (BOP) Failure of D ADS SRV to open 01

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Retention: Life of policy + 10yrs.

Retain in: Training Program File Page 1 of 24

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

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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

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

Retain in: Training Program File Page 1 of 24

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

1. ILT NRC EXAM Learning Objectives:

1. COMPLETION OF MT-ILT PROGRAM Prerequisites:

1. SIMULATOR Training Resources:

1. FP-T-SAT-72

References:

1. N/A Commitments:

ILT NRC EXAM Evaluation Method:

N/A Operating Experience:

Initiating Event with Core Damage Frequency:

Related PRA LOCA Information:

Important Components:

Containment Important Operator Actions with Task Number:

XRPVBLDNY- Blowdown to prevent core damage.

Page 3 of 24

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

Page 4 of 24

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

INITIAL CONDITIONS:

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

IC-231

2. 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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

Annunciator 3-A-25, (AUTO BLOWDOWN TIMER ACTIVATED), prompts 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Page 5 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 Event 4: Main Turbine Vibration

Vibration on bearings 7 and 8 are noted by the crew to be rising or acknowledged when 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: Steam Leak Inside Primary Containment

A small steam 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.

Event 8: D ADS SRV Fails to Open

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.

Page 6 of 24

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

TASK DESCRIPTION OBJECTIVE CR240.101 Perform the MSIV exercise test 1-5 CR200.146 1-5 Perform the procedure for a reactor scram CR201.111 Place the Standby CRD FCV into service 1-5 CR203.111 Transfer the A(B) RHR from LPCI to Torus 1-5 cooling CR200.203 Perform the procedure for rapid power reduction 1-5 CR200.162 Perform the procedure for leak inside the primary 1-5 containment CR304.102 Perform the actions associated with RPV Control 1-5 CR200.204 Perform the procedure for inadvertent ECCS 1-5 initiation CR200.152 Perform the procedure for loss of RBCCW flow 1-5 CR200.164 Perform the procedure for loss of reactor water 1-5 level control CR304.103 Perform the actions associated with Primary 1-5 Containment Control CR314.123 Perform the actions associated with Containment 1-5 Spray SS304.193 Implement RPV Control 6, 7 SS299.328 Apply Tech Spec 3.6 and Bases to the Primary 6, 7 System Boundary SS299.327 Apply Tech Spec 3.5 and Bases to the Core and 6, 7 Containment/Cooling System SS304.194 Implement Primary Containment Control 6, 7 SS315.101 Supervise response to reactor scram 6, 7 SS315.160 Supervise the response to an inadvertent ECCS 6, 7 initiation Page 7 of 24

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

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

Standard IC-15 (IC-231) /SRO)

Mode: 1

Exposure: MOC

Power: 100%

Pressure: 1000

Generator: 611 Mwe Page 8 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

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. RCIC is in 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 Page 9 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

3. COMPLETE TURNOVER: Performs pre-shift briefing

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: MSIV Closure Test 0008 BOP Performs Test 0008:

a. No trigger is required for this event

Uses test push button to partially close each Inboard MSIV

b. For each Inboard MSIV, when the green light is

Releases test pushbutton when relays de-energize lit, inform the BOP operator that the respective protected relays de-energize (see TEST 0008,

Records response Table 1 for relay numbers).

Attempts to close first Outboard MSIV and reports failure to close to Shift Supervision

c. If called, respond as the Ops Manager, Plant Directs test suspended Manager, and/or System Engineer concerning Refers to ITS and enters Required Action A.1 for LCO notification of the event. CRS 3.6.1.3 (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to isolate the steam line).

CRS Provides crew brief

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

Page 10 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

5. EVENT 2: CRD Flow Control Valve Failure OATC Responds to annunciator 5-B-41, CRD HI

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

Informs Shift Supervision

Sends Reactor Building Operator to investigate

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

Refers to procedure B.01.03-05 CRDH in alarm.

Recognizes CRD FCV failure Directs swap to standby CRD FCV

c. When directed to report to the CRD FCV CRS Coordinates with Reactor Building Operator and performs station to support shift of FCV, WAIT 3 minutes OATC the following:

and report you are standing by.

Opens standby FCV manual inlet/outlet valves

d. When directed to OPEN CRD-16-2 and

Places Flow Controller in MANUAL CRD-18-2, INSERT TRIGGER 2 and WAIT 2

Manually runs controller to 0 minutes, then report valves are open.

Places the CRD Flow Selector to the B position

Slowly OPENS the B FCV manually to

e. When directed to CLOSE CRD-16-1 and approximately 54 to 56 gpm CRD-18-1, INSERT TRIGGER 3 and WAIT 2

Places the FCV in AUTO minutes, then report valves are closed.

Closes previously in-service FCV manual

f. If directed to report CRD temperatures, report inlet/outlet valves all alarms are clear and all temperatures are Acknowledge annunciator 5-B-41 clear and informs lowering to normal. Shift Supervision.

OATC Provides crew brief CRS Page 11 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

6. EVENT 3: ADS Inadvertent Initiation OATC Reports the following alarms:

a. When directed by the lead evaluator, INSERT

3-A-25, AUTO BLOWDOWN TIMER TRIGGER 4, ADS TIMER. ACTIVATED Reports the following:

b. If called, respond as the Ops Manager, Plant BOP Manager, and/or System Engineer concerning

ADS timer actuation notification of the event. BOP Enters C.4-G, INADVERTENT ECCS INITIATION Places ADS AUTO/INHIBIT control switch to INHIBIT Refers to ITS and enters Required Action G for LCO CRS 3.3.5.1 and declares ADS SRVs inoperable per table 3.3.5.1-1 (function 4.b within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

Refers to ITS and enters Required Action L for LCO 3.5.1 (be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ).

Provides crew brief CRS Page 12 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

7. EVENT 4: Main Turbine Vibration BOP Reports annunciator 7-B-33, TURB VIBRATION HIGH

a. When directed by the lead evaluator, INSERT BOP (crew may identify condition via computer alarm at 7 mils)

TRIGGER 5, TURBINE BEARINGS HIGH Reviews ARP actions:

VIBRATION (bearings 7 and 8).

Verifies vibration readings on VR-1716

b. When reactor power is reduced, manually

If >10 mils, enter shutdown procedure lower the malfunction severity of TU03G and

If rapid power reduction is necessary, enter C.4-F TU03H over the span of 5 minutes to (RAPID POWER REDUCTION) approximately 5 mils each.

If vibrations approach 15 mils, then reduce recirc flow to min, scram, trip the turbine

c. If directed to investigate the turbine, WAIT until

Informs Shift Supervision vibrations have been lowered and report no Directs power reduction to stabilize/reduce turbine unusual noise or vibrations are detected.

vibration Reduces reactor power per C.4-F with reactor recirc CRS Reports turbine vibrations lowering OATC Directs power reduction secured BOP Provides crew brief CRS CRS Page 13 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

8. EVENT 5: RBCCW Pump Trip BOP Recognize lowering RBCCW system pressure Reports annunciator 6-B-32, RBCCW LOW DISCH

a. When directed by the lead evaluator, INSERT PRESS TRIGGER, 6 RBCCW pump 11 trip. Performs immediate actions of C.4-B.02.05.A , LOSS OF RBCCW

b. If directed to investigate the RBCCW pumps, WAIT 3 minutes and then report that the

Starts 12 RBCCW pump bearings on the 11 pump motor appear to be

Verifies RBCCW pressures return to normal 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.

Page 14 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

9. EVENT 6: Loss of Air to A FRV OATC Reports annunciator 5-B-40, (FW CONTROL VALVE

a. When directed by the lead evaluator, INSERT LOCK) and performs the following:

TRIGGER 7, LOSS OF AIR TO THE A FRV.

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

b. If directed to investigate, WAIT 4 minutes and

Monitors RPV water level report that the air connection to the FRV has come loose and air is escaping from the loose OATC Enters C.4-B.05.07.A connection. Also report that the connection

Places the UNLOCKED FRV in controller in can easily be tightened, and if directed to do manual so, WAIT 2 minutes and report that the When the report that that air leak has been repaired is connection has been tightened and the air leak CRS given, the CRS will direct that the lockup be reset.

has stopped. The system engineer When directed to attempt to reset the lockup:

OATC recommends resetting the lock out. DELETE

Verify the M/A station for the locked valve is in malfunction LOSS OF AIR TO THE A FRV. MANUAL

c. If called, respond as the Ops Manager, Plant

Verify the M/A station output meter is at the black Manager, and/or System Engineer concerning memory pointer notification of the event.

Verify no major air leakage at the valve

Depress the reset pushbutton for the affected FRV Page 15 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS OATC Place First FRV in Automatic (per B.05.07):

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 OATC Place Second FRV in Automatic (per B.05.07):

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

Place the Feedwater Control MAN/AUTO in AUTO Page 16 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

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

10. EVENT 7: Steam Leak Inside Primary BOP Reports Drywell pressure rising Containment CRS Directs reactor scram

a. When directed by the lead evaluator, INSERT Inserts manual scram:

TRIGGER 8, SMALL STEAM LINE BREAK OATC INSIDE PRIMARY CONTAINMENT and

Depresses manual scram pushbuttons MS04B, Steam pipe break (after 10 minute

Places Mode Switch in SHUTDOWN delay)

Verifies all rods in

Makes scram report

Carries out subsequent actions of C.4-A (REACTOR SCRAM)

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

BOP Enters EOP-1100 and EOP-1200 and directs:

CRS

Start all available torus cooling

Start all available drywell cooling

Start torus sprays

Start drywell sprays Page 17 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS If requested to investigate the problem with Div 2 BOP / Start all available torus cooling: (B.03.04) (Div 2 Torus cooling / spray function, report you will investigate. OATC Cooling will not be able to be initiated due to logic malfunction)

Start all available torus cooling: (B.03.04-05)

Verify RHR SW Outlet controll set at 20%

Close RHR HX Bypass valve

Place ECCS Load Shed Keylock to OVERRIDE

Start RHRSW pump(s)

Adjust RHRSW flow for ~3500 gpm per pump

Place 2/3 Core Height bypass to OVERRIDE

Place LPCI Iniitiation switch to BYPASS

Partially open Torus Cooling Inj/Test inboard valve for 8 seconds

Open Disch to Torus Outboard valve

Trottle Torus Cooling Inj/Test inboard valve to obtain ~4000 gpm per pump

Verify RHR RM Air Cooling Unit in operation BOP / Start Torus Sprays: (C.5-3502):

OATC

Place LPCI Initiation to BYPASS

OPEN Disch to Torus Outboard Valve

OPEN Torus Spray Inboard Valve

Trottle Torus Cooling Test Inboard Valve Page 18 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP / Start all available drywell cooling (C.5-3502)

OATC

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 BOP / Start torus sprays (Div 2 Sprays will not be able to be OATC initiated due to logic malfunction)

Reports inability to spray torus BOP / Start D/W sprays (Sprays will not be able to be OATC initiated due to logic malfunction on Div 2 and Stuck Valve on Div 1)

Reports inability to spray drywell

[When D/W temperature cannot be restored and CRS Directs Blowdown when D/W temp cannot be maintained maintained below 281°F, blowdown.] below 281°F

11. EVENT 8: D ADS SRV Fails to Open

[When a blowdown is initiated and <3 ADS SRVs can BOP / Opens 2 ADS SRVs, and reports 3rd ADS SRV (D) will be opened, open a non-ADS SRV to ensure 3 SRVs OATC not open. Opens a non-ADS SRV to obtain 3 SRVs open are open.] when directed by CRS.

Page 19 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CRS Directs opening of a non-ADS SRV to obtain 3 SRVs open.

12. When the conditions are stabilized or at discretion Crew:

of lead instructor/evaluator

Remain in simulator for potential questions from evaluator.

13. End the scenario by placing the simulator in freeze

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

Page 20 of 24

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

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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 MS04A 0-20 8 00:10:00 Small Break on A Steam line Malfunction MS04B 2.5 8 00:10:00 (delay) Break on A Steam line 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 Page 21 of 24

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

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description 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 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.

Page 22 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 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 Yes No performance tools.

2. The scenario identifies key parameter response, expected alarms, and Yes No 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.)

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

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

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

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

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

8. The scenario includes related industry experience. Yes No

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

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

Appendix D, Page 38 of 39

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 1,LOCA/ Blowdown, Rev. 0 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 Yes No and responded to support the simulator scenario.

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

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

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

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

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

Discrepancies noted (Check none or list items found) None SAR = Simulator Action Request SAR: SAR: SAR: SAR:

Comments:

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

Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: MNGP-Facility: ____ MNGP __________ Scenario No.: NRC-02 07

____________________________ Operators: ____________________________

Examiners:

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.

Even M alf. Event Event t No. Type* Description No.

1 TC06B N (BOP) Complete Test OSP-TRB-0570, EXERCISE MAIN (SRO) 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 I (RO) RPV press inst fails upscale, half scram fails to be initiated.

PP06 (SRO) ITS LCO.

5 MS09 C (BOP) 11 Steam Packing Exhauster trip, start standby blower.

6 RR07 R (RO) 12 Recirc pump motor bearing temp and vibrations RR08 C (BOP) high and subsequent shutdown of pump.

(SRO) ITS LCO.

7 PP05A M (ALL) Group 1 isolation, ATW S EOP-2007 (Failure to PP05C Scram) entry.

CH16 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)

S IMULATOR E XERCISE G UIDE (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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

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

Retain in: Training Program File Page 1 of 24

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

1. ILT NRC EXAM Learning Objectives:

1. COMPLETION OF MT-ILT PROGRAM Prerequisites:

1. SIMULATOR Training Resources:

1. FP-T-SAT-72

References:

1. N/A Commitments:

ILT NRC EXAM Evaluation Method:

N/A Operating Experience:

Initiating Event with Core Damage Frequency:

Related PRA Group 1 Isolation Information:

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 Page 3 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 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. Steam Packing Exhauster Blower Trip

5. 12 RR Pump Motor Bearing Hi Temp/Vibration

6. 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.]

Page 4 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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.

Page 5 of 24

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

Page 6 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 ITS will be reviewed and be determined that LCO Condition 3.2.1, 3.2.2, and 3.2.3 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Event 5: Steam Packing Exhauster Fan Trip The running Steam Packing Exhauster will trip resulting in alarm 7-A-28 (STM PKG EXH K3A & K3B BLWR MTR HI TEMP)

The operator will start the standby blower, open its outlet valve, and close the outlet valve on the tripped unit.

Event 6: 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 2.1.1, 3.4.1, and 3.3.1.1 are applicable at this time, when power is lowered below 90%.

Event 7: 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.

Page 7 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 Page 8 of 24

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

TASK DESCRIPTION OBJECTIVE Perform the Turbine Generator Weekly CR245.102 1-5 operational tests CR200.147 1-5 Perform the procedure for a loss of CRD pump flow CR200.157 Perform the procedure for primary containment 1-5 Group 1 isolation CR200.203 Perform the procedure for rapid power reduction 1-5 CR202.112 Shutdown one Recirc pump with the reactor at 1-5 power 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 1-5 CR314.112 Perform actions to Terminate and Prevent 1-5 injection SS299.323 Apply T.S. 3.1 and Bases to the Reactor 6,7 Protection System SS299.329 Apply T.S. 3.1 and Bases to the Containment 6,7 System SS299.328 Apply T.S. 3.1 and Bases to the Primary System 6,7 Boundary 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 6,7 Page 9 of 24

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

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

Standard IC-15 (IC-232) /SRO)

Mode: 1

Exposure: MOC

Power: ~89%

Pressure: 1000

Generator: ~543 Mwe

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 Page 10 of 24

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

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

a. No trigger is required for this event

Record generator gross load

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

Select respective valve with BYPASS VALVE notification of the event. TEST switch

c. After the ITS call has been made, call as the

Press the BYPASS VALVE TEST pushbutton I&C Supervisor and state that repairs are Time the bypass valve travel to the OPEN position estimated to be complete within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 CRS 3.7.7 (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to return to service or Action B reduce thermal power to <25%).

Provides crew brief Page 11 of 24

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

12. EVENT 2: 11 CRD Pump Trip OATC Responds to annunciators B-5-17 (CHARGING WATER

a. When directed by the lead evaluator, INSERT LO PRESS), 5-B-25 (CRD PUMP 3-16A BREAKER TRIGGER 1, 11 CRD pump trip. TRIPPED), and 5-B-26 (CRD PUMP 3-16A OL):

b. If called to investigate the CRD pump trip, wait

Notifies CRS 3 minutes and report that the pump motor is very hot and the breaker indicates tripped.

Takes action per C.4-B.01.03.A, Loss of CRD (over current flag is tripped) Flow

c. If called, respond as the Ops Manager, Plant

Starts 12 CRD pump Manager, and/or System Engineer concerning Verifies system pressures/flows return to normal notification of the event.

Provides crew brief CRS Page 12 of 24

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

17. EVENT 3: Pressure Regulator Oscillation, EPR BOP Reports oscillations of reactor power, level, and/or

a. When directed by the lead evaluator, INSERT pressure, and MWe output.

TRIGGER 2, Pressure Regulator Oscillation, EPR. Performs actions of B.05.09-05.H.1:

b. If called, respond as the Ops Manager, Plant

Switch control from the EPR to the MPR by:

Manager, and/or System Engineer concerning o Lower the MPR setpoint using the MECH notification of the event.

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 Performs actions of C.4- B.05.09A (instead of or in addition to the above actions):

CRS

Place the EPR pushbutton to STOP Reports reactor power, level, and/or pressure, and MWe output have stabilized.

If reactor power is between 25% and 90%, enter T.S. 3.2.1, 3.2.2, and 3.2.3:

1) Within 15 minutes, either initiate action to establish reactor power <25% or >90%

2) In cannot do the above, restore the press regulator with 2 hrs or be <25% within next 4 hrs.

Provides crew brief Page 13 of 24

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

3. EVENT 4: RPV High Press RPS Relay Failure OATC Responds to annunciators 5-B-11 (REACTOR

a. When directed by the lead evaluator, INSERT VESSEL HI PRESS SCRAM TRIP) and 5-B-4 TRIGGER 3, RPV High Press. (REACTOR AUTO SCRAM CHANNEL A). Recognize

b. If called, respond as I&C that RPS relay 1/2 scram should have occurred and did not 5A-K5C has de-energized. Will need to check the calibration of the RPV pressure instrument ALL to troubleshoot event. Refers to ITS and enters Required Action C.1 for LCO

c. If called, respond as the Ops Manager, Plant 3.3.1.1 (Restore RPS trip capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

Manager, and/or System Engineer concerning Provides crew brief notification of the event. CRS Directs 1/2 scram be inserted on A RPS Inserts 1/2 scram by depressing A manual scram pushbutton OATC

4. Event 5: Steam Packing Exhauster Fan Trip BOP Respond to alarm 7-A-28 (STM PKG EXH K3A & K3B

a. When directed by the lead evaluator, INSERT BLWR MTR HI TEMP):

TRIGGER 9, Exhauster Blower #11 Motor Trip.

Report alarm to CRS

b. If asked to investigate, wait 5 minutes and report that the motor bearings feel very hot.

Start K-3B Steam Packing Exhauster

Open K-3B Steam Packing Exhauster outlet

Place K-3A Steam Packing Exhauster control switch to OFF

Close K-3A Steam Packing Exhauster outlet Page 14 of 24

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

8. EVENT 6: 12 Reactor Recirc Pump Motor BOP Responds to annunciator 4-C-24 (RECIRC PUMP MTR B Bearing High Temp / Vibration /OATC HI VIBRATION) alarms.

a. When directed by the lead evaluator, INSERT Performs actions of ARPs:

TRIGGER 4, 12 Recirc pump high bearing temperature and motor vibration.

Check TR 2-2-31 to verify alarm conditions

b. When requested to check Recirc pump motor

Reduce Recirc pump heat load by lowering pump vibrations, WAIT 3 minutes and report 12 speed Recirc pump motor vibrations are 4 mils and

Dispatch operator to determine vibrations slowly rising.

c. If called, respond as the Ops Manager, Plant

IF Recirc pump motor vibration remains above 3 Manager, and/or System Engineer concerning mils, THEN shutdown the Recirc MG per B.01.04-notification of the event. 05

d. When the 12 Recirc pump is shutdown, Wait Performs actions of B.01.04-05, Recirc:

30 seconds and DELETE the motor vibration

Reduce power with Recirc pumps to ~50%

malfunction.

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 CRS Refers to ITS and enters LCO Conditions for single loop operations (2.1.1, 3.4.1 required action B.1, and 3.3.1.1 function 2a)

Provides crew brief Page 15 of 24

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

19. EVENT 7: Group 1 Isolation / ATWS OATC Responds to reactor scram and performs the following:

a. When directed by the lead evaluator, INSERT

Scram report:

TRIGGER 5, Group 1 Isolation. (Malfunction should be inserted prior to the second round of o Reactor Scram rod insertion to ensure sufficient power to drive o Mode Switch in Shutdown torus temperature during ATWS) o All rods NOT in

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

Reports reactor power notification of the event. Enters EOP 2007, Failure to Scram and directs:

CRS

[With an ATWS condition present, inhibit ADS before

ATWS hard card actions performed ADS valve actuation.][With Reactor power >3% or

Inhibit ADS unknown, insert control rods to shutdown the reactor.]

Terminate and Prevent injection Performs actions of ATWS hard card:

OATC

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 Page 16 of 24

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

29. EVENT 6: Group 1 Isolation / ATWS (cont) BOP Inhibits ADSPerforms Terminate and Prevent per C.5-3205:

Places CS pumps in PTL , Close injection

[With Reactor power >3% or unknown, RPV water level valves, Place injection bypass keylock in above -33 inches, prevent RPV injection to lower BYPASS power.]

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 CRS Enters EOP 1200 Directs torus cooling placed in service Starts either 11 or 12 SBLC pump and verifies disch press

> RPV pressure When SBLC tank level lowers to 1040 gal. (HSBW), then directs RPV water level restored to 9-48 inches CRS Reports all rods at 00 Directs SBLC secured Exits EOP 2007, Enters EOP 1100 Page 17 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP Raises RPV water level with FW Start all available torus cooling: (B.03.04-05)

Verify RHR SW Outlet controller set at 20%

Start RHRSW pump(s)

Adjust RHRSW flow for ~3500gpm per pump

Start RHR pump(s)

Partially open Torus Cooling Inj/Test inboard valve for 8 seconds

Open Disch to Torus Outboard valve

Trottle Torus Cooling Inj/Test inboard valve to obtain ~4000gpm per pump

Close RHR HX Bypass valve

Verify RHR RM Air Cooling Unit in operation

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

44. End the scenario by placing the simulator in freeze Page 18 of 24

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

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Malfunction TC06B True N/A N/A #2 TBPV Stuck Malfunction CH08A True 1 N/A 11 CRD Pump Trip Malfunction TC05A 40 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 Malfunction MS09 True 9 N/A Exhauster Blower #11 Motor Trip 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 Page 19 of 24

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

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value Trigger Timing Description Override S34-04 On N/A N/A Mode Switch-Run Override S34-03 Off N/A N/A Mode Switch-Refuel Override S34-01 Off N/A N/A Mode Switch-Shutdown Override S34-02 Off N/A N/A Mode Switch-Startup Page 20 of 24

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 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 Yes No performance tools.

2. The scenario identifies key parameter response, expected alarms, and Yes No 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.)

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

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

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

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

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

8. The scenario includes related industry experience. Yes No

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

Appendix D, Page 38 of 39

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

Appendix D, Page 38 of 39

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 2, ATW S, Rev. 0 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 Yes No and responded to support the simulator scenario.

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

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

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

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

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

Discrepancies noted (Check none or list items found) G None SAR = Simulator Action Request SAR: SAR: SAR: SAR:

Appendix D, Page 38 of 39

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

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

Appendix D, Page 38 of 39

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

____________________________ Operators: ____________________________

Examiners:

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 M alf. Event Event t No. Type* Description No.

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.

[ Event Deleted ]

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 FW 15B C (BOP) 12 RFP bearing high tem perature, shutdown 12 RFP.

R (RO) Lower reactor power to support rem oval of 12 RFP.

6 HP01 I (BOP) HPCI inadvertent initiation and shutdown. HPCI will be inoperable.

(SRO) ITS LCO.

7 RU07 M (ALL) RW CU Leak, un-isolable, EOP-1300 Entry, Scram Blowdown, EOP 2002 Entry.

(N)orm al, (R)eactivity, (I)nstrum ent, (C)om ponent, (M)ajor

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

S IMULATOR E XERCISE G UIDE (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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

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

Retain in: Training Program File Page 1 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 Guide Requirements ILT NRC EXAM Goal of Training:

1. ILT NRC EXAM Learning Objectives:

1. COMPLETION OF MT-ILT PROGRAM Prerequisites:

1. SIMULATOR Training Resources:

1. FP-T-SAT-72

References:

1. N/A Commitments:

ILT NRC EXAM Evaluation Method:

N/A Operating Experience:

Initiating Event with Core Damage Frequency:

Related PRA RWCU Leak Information:

Important Components:

Secondary Containment Important Operator Actions with Task Number:

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

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QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 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.]

Page 4 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 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:

#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). [ Event Deleted }

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.

Page 5 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 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.

Page 6 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 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.

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QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

TASK DESCRIPTION OBJECTIVE Perform a power reduction from >90% to CR200.133 1-5 75%

CR200.146 1-5 Perform the procedure for a reactor scram CR200.203 Perform the procedure for rapid power reduction 1-5 CR200.204 Perform the procedure for inadvertent ECCS 1-5 initiation CR209.106 Startup a Core Spray Loop 11(12) 1-5 CR259.126 Take the actions for Reactor Feed pump and 1-5 Reactor Feed pump Motor Bearing High Temperature CR299.353 Apply T.S. section 3.3 and bases to 1-5 instrumentation CR299.355 Apply T.S. section 3.5 and bases to ECCS and 1-5 RCIC CR299.351 Apply T.S. section 3.1 and bases to Reactivity 1-5 control systems CR304.105 Perform actions associated with Secondary 1-5 Containment control CR314.101 Perform the actions associated with Emergency 1-5 RPV depressurization 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 6,7 SS299.349 Apply administrative requirements for T.S. 3.1 6,7 and bases to reactivity control systems SS299.351 Apply administrative requirements for T.S. 3.3 6,7 and bases to instrumentation SS299.353 Apply administrative requirements for T.S. 3.5 6,7 and bases to ECCS and RCIC Page 8 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 NOTE: Modify this table as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

Standard IC-15 (IC-233) /SRO)

Mode: 1

Exposure: MOC

Power: 100%

Pressure: 1000

Generator: 611 Mwe

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 Page 9 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

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 OATC Attempts to withdraw control rod 26-27.

08. When unable to withdraw with normal drive flow, refers to

a. No event trigger is required for this event. B.01.03-05.H.4 (WITHDRAW OF A CRD UNDER HIGH

b. The malfunction will automatically delete after 1 DRIVE PRESSURE) or 2 drive water 30 psig increments.

c. If called, respond as the Ops Manager, Plant

Raise drive water pressure in increments up to 30 Manager, and/or System Engineer concerning psid, to a maximum of 400 psid and give the drive notification of the event. a withdraw signal after each increment

Before moving a different CRD, return drive water pressure to approximately 265 psid Page 10 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

7. EVENT 2: Core Spray Test [ Event Deleted ] BOP Performs Test 0255-03-IA-1-1:

a. No event trigger is required for this event.

Performs valve timing

b. When directed to report Core Spray suction pressure, WAIT 1 minute and report suction

Starts Core Spray pump pressure is 5 psig.

Establishes head/flow requirements

c. When directed to report Core Spray amperage, Shuts down Core Spray pump 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.

12. EVENT 3: SBLC Squib Valve Loss of Continuity OATC Responds to annunciator 5-B-31 (LOSS OF

a. When directed by the lead evaluator, INSERT CONTINUITY TO SQUIB VALVE):

TRIGGER 2, Loss of Squib A Continuity.

Informs CRS

b. When the operator goes to investigate the milliamp meter behind panel C-05, inform him

Observes white squib ready light NOT lit for the that the meter indicates 0 milliamps. A squib valve on C-05

c. If called, respond as the Ops Manager, Plant

Observes meter indication for A squib valve Manager, and/or System Engineer concerning behind C-05 indicates 0 milliamps notification of the event.

CRS Refers to ITS and enters Required Action B.1 for LCO 3.1.7 (7 day).

CRS Provides crew brief Page 11 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

16. EVENT 4: #4 APRM Fails Upscale OATC The RO will respond to and report annunciators 5-A-3

a. When directed by the lead evaluator, INSERT (ROD WITHDRAW BLOCK), 5-A-14 (APRM HI),

TRIGGER 3, APRM #4 Fullscale. 5-A-30 (APRM HI HI INOP CH 4, 5, 6), 5-B-3

b. If called, respond as the Ops Manager, Plant (REACTOR NEUTRON MONITOR SCRAM TRIP), 5-B-Manager, and/or System Engineer concerning 5 (REACTOR AUTO SCRAM CHANNEL B):

notification of the event.

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 BOP scale and INOP light not litMay refer to ITS and review CRS Required Action A.1 for LCO 3.3.1.1 to determine the LCO for APRMs is met.

Directs #4 APRM bypassed and 1/2 scram reset OATC Bypasses #4 APRM and resets the 1/2 scram Provides crew brief CRS Page 12 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

20. EVENT 5: #12 RFP Bearing High Temp / BOP The BOP will respond to and report annunciator 6-A-26 Shutdown (RCT FEED PUMP BRG HIGH TEMP):

a. When directed by the lead evaluator, INSERT

Monitor bearing temperatures TRIGGER 4, RFP #12 Bearing Hi Temp.

b. If called respond as the out plant operator and

Dispatch operator to the turbine building WAIT 3 minutes to report confirmation of high

Take actions of B.06.05-05 bearing temperature and vibrations on the 12 o Immediately remove the RFP from service RFP. There appears to be no or little cooling CRS water flow. Directs Rapid Power reduction per C.4-FLowers OATC power with recirc and control rods to be within the

c. If called, respond as the Ops Manager, Plant Manager, and/or System Engineer concerning limits of 1 RFP (<50% power)Reviews power/flow notification of the event. map to ensure not in buffer regionSecures the 12

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

CRS Page 13 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

24. EVENT 6: HPCI Inadvertent Initiation BOP BOP responds to start of the HPCI turbine per C.4-G,

a. When directed by the lead evaluator, INSERT Inadvertent ECCS Initiation:

TRIGGER 5, HPCI Initiation.

Recognize inadvertent initiation by checking

b. If called, respond as RP technician and/or out plant operator to investigate the HPCI turbine. RPV water level and D/W pressure normal

c. If called, respond as the Ops Manager, Plant

Place Aux Oil Pump in RUN Manager, and/or System Engineer concerning

Depress and hold HPCI TURBINE TRIP notification of the event. pushbutton

Verify HPCI turbine has stopped

After 5 seconds, place the Aux Oil Pump in CRS PTL

Release HPCI TURBINE TRIP pushbutton CRS Refers to ITS and enters Required Action B.1 for LCO 3.5.1 action H.1 and H.2 (14 days).Provides crew brief.

Page 14 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

31. EVENT 7: RWCU Leak (un-isolable) BOP The BOP will respond to and report annunciators

a. When directed by the lead evaluator, INSERT 3-B-56 (HIGH AREA TEMP STEAM LEAK), 4-A-11 TRIGGER 6, RWCU Suction Line Break. (REACTOR BUILDING HI RADIATION):

[Before any area temperature, radiation, or water level

Reports RWCU room radiation levels and reaches max safe value (Tables W, X, Z), scram.] 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)

CRS and EOP-1100 (RPV control)Directs Reactor ScramInserts a manual scram, provides scram report:

OATC

Reactor scram

Mode switch in shutdown

All rods inserted

[Wait until 2 or more areas above max safe values of same CRS Determines 2 area radiation levels are above max safe parameter (Tables W, X, Z), blowdown.] Enters EOP-2002 (Blowdown)

Directs BlowdownOpens 3 ADS valves BOP Page 15 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

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

40. End the scenario by placing the simulator in freeze Page 16 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 SIMULATOR INPUT

SUMMARY

Relative System Or Severity Event Order Panel Drawing Type Code Or Value 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 Page 17 of 21

QF-1030-19 Rev. 5 (05/12/05) 2007 ILT NRC 3, RW CU LEAK , B LO W D O W N , Rev. 0 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.