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2016 Monticello Nuclear Generating Plant Initial License Examination Proposed Simulator Scenarios
	ML17142A425
Person / Time
Site:	Monticello
Issue date:	05/18/2017
From:	Reeser D W; NRC/RGN-III/DRS/OLB
To:	; NRC/RGN-III/DRS/OLB
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Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

1 Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions: 100% Power; There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, and 50-31); HPCI is in PTL due to inadvertent initiation the previous shift.

Turnover: 12 EDG Monthly Surveillance test in progress, ready to unload. Event No. Malfunction No. Event Type* Event Description 1 N (BOP) EDG 12 Monthly Surveillance Test The BOP will u nload and shutdown 12 EDG 2 C (BOP) The Main Seal Oil Pump (MSOP) will trip and the Emergency Seal Oil Pump (ESOP) will fail to auto start. The BOP will take action to start the ESOP.

3 C/TS (SRO) #10 Transformer Lockout CRS will address TS for a loss of an offsite power source (1AR) 4 C (OATC) CRD Flow Control Valve Fails Open resulting in CR 26-27 drifting in 1 notch. OATC will discover the flow control valve failure and swap CRD flow control valves 5 R (OATC) Crew will be directed by Nuclear Engineering to perform a power reduction to 9 7-98% with Recirc flow and then fully withdraw the drifted control rod.

6 C (OATC) TS (SRO) When withdrawing the drifted control rod it will become uncoupled. The OATC will take actions for an uncoupled control rod and the CRS will evaluate TSs.

7 M C (BOP) Station Power Transfer

- Scram w/electrical ATWS A 2R Lockout will occur requiring the crew to scram on degrading condenser vacuum An ATWS will occur, the OATC will be successful with ARI (CT) 8 C-(POST) A steam leak will occur in the HPCI room. HPCI will fail to auto-isolate requiring the crew to manually isolate HPCI when a max

-safe temperature is received (CT). 9 C-(POST) A 1R Lockout will occur causing a LOOP, 11 EDG

-ESW pump and 12 EDG will fail to auto start. The BOP will be required to: manually start or cross

-connect 11 EDG

-ESW with Service Water; OR manually start and ensure loading of 12 EDG. (CT) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

QF107502 Rev. 4 (FP

-T-SAT-75) Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP

-G-RM-01. SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-40 E SEG TITLE:

201 6 ILT NRC SCENARIO 1 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME:

45-90 MINUTES Additional site

-specific signatures may be added as desired.

Developed by:

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 QF107502 Rev. 4 (FP

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-G-RM-01. Guide Requirements Goal of Training: This Scenario evaluation has been written for the 201 6 ILT NRC Exam. Once this exam is complete and exam security is relaxed, this SEG should be appropriate to use for the following activities: Future ILT NRC / Audit Exam Evaluation s SRO Certification Evaluations LOR Crew development Learning Objectives:

1. Demonstrate the ability to predict and/or monitor changes in parameters associated with operating system controls for the

appropriate tasks. 2. Demonstrate the ability to correctly use procedures to correct, control, or mitigate the consequences of normal and abnormal operations for the appropriate tasks.

3. Demonstrate the ability to monitor automatic operations of the

systems to ensure proper operation for the appropriate tasks.

4. Demonstrate the ability to manually operate and/or monitor systems in the control room in accordance with approved

procedures for the appropriate tasks.

5. Demonstrate the ability to complete administrative requirements

, as necessary, in order to operate the plant for the appropriate tasks. 6. Demonstrate knowledge of and ability to implement shift supervision duties as they relate to crew operations for the

appropriate tasks.

7. Given a degrading or improving plant condition or event, demonstrate the ability to: (CRS)

a. Evaluate trends that may result in equipment damage or reduction in plant safety.

b. Ensure proper diagnosis of plant problems by monitoring and interpreting data (information from panel indications).

c. Evaluate and diagnose challenges to Critical Plant Parameters.

d. Evaluate events and accidents.

Prerequisites:

1. Completion of the MT-ILT Training Program

, or 2. Completion of the SRO Certification Program

, or 3. Currently enrolled in the LOR Training Program

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-G-RM-01. Training Resources:

1. Full Scope Simulator

2. MTF-7100-051 (Attendance Record) or LMS Equivalent

3. 3139 (Control Room Shift Turnover Checklist)

4. 3140 (Shift Supervisors Office Shift Turnover Checklist)

5. Lead Instructor

- Crew Turnover Brief paperwork

References:

1. 0187-02B (12 EDG/12 ESW MONTHLY PUMP AND VALVE TEST)

2. 8-A-22 (NO. 1 GEN H2 SYSTEM TROUBLE)

3. 83-B-6 (EMERG SEAL OIL PUMP RUNNING)

4. 8-A-3 (345 KV & 115 KV YARD TROUBLE)

5. LCO 3.8.1 (OFFSITE SOURCES)

6. 5-A-27 (ROD DRIFT)

7. C.4-B.01.03.C (CONTROL ROD DRIFTING)

8. B.01.03-05.E.4 (PLACING THE STANDBY CRD FLOW CONTROL VALVE INTO SERVICE)

9. C.4-F (RAPID POWER REDUCTION)

10. 5-A-11 (ROD OVERTRAVEL)

11. LCO 3.1.3 (CONTROL RODS)

12. 8-B-02 (NO. 2R XFMR LOCKOUT)

13. 5-B-20 (CONDENSER LO VACUUM SCRAM TRIP)

14. C.4.K (IMMEDIATE REACTOR SHUTDOWN)

15. C.4-A (REACTOR SCRAM)

16. C.5-1100 (RPV CONTROL)

17. C.5-2007 (FAILURE TO SCRAM

) 18. C.5-3301 (DEFEAT MSIV LOW

-LOW LEVEL ISOLATION)

19. C.5-3101 (ALTERNATE ROD INSERTION)

20. 8-C-04 (NO. 1R RES TRANS LOCKOUT)

21. C.4-B.09.02.B (LOSS OF NORMAL OFFSITE POWER)

22. B.08.01.02

-05.H.3 (TRANSFER EDG COOLING FROM EDG

-ESW TO SERVICE WATER)

23. 3-B-56 (HIGH AREA TEMP STEAM LEAK)

24. C.4-B.04.01.D (GROUP 4 ISOLATION)

25. C.5-1300 (SECONDARY CONTAINMENT CONTROL)

Commitments:

1. None Evaluation Method: The following methods are acceptable methods for examinee evaluation:

201 6 ILT NRC Exam Process (NUREG 1021

& FP-T-SAT-72) MT-ILT (MNGP ILT Program Description)

M-9700 (SRO Certification Program Description)

FP-T-SAT-73 (Licensed Operator Requalification Program)

Operating Experience:

Not Applicable to Evaluation Scenarios

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-G-RM-01. Related PRA Information:

Initiating Event with Core Damage Frequency

Important Components

/ Accident Class

Important Operator Actions with Task Number

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-G-RM-01. TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks: SS299.356 Apply Admin requirements for TS 3.8 and Bases.

5-7 SS315.167 Direct the response to a control rod drifting 5-7 SS315.159 Supervise rapid power reduction 5-7 SS299.349 Apply admin requirements to TS 3.1 and Bases 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.193 Implement RPV Control 5-7 SS304.201 Implement the response for a failure to scram 5-7 SS314.111 Supervise defeat of RPV Low

-Low Level Isolation for MSIV closure 5-7 SS314.101 Supervise alternate rod insertion 5-7 SS315.137 Supervise response to a loss of normal off

-site power 5-7 SS315.115 Supervise response to a Group 4 isolation 5-7 RO Tasks: CR299.358 Apply TS 3.8 and Bases 5 CR200.226 Respond to a control rod drifting 1-4 CR201.111 Place the standby CRD Flow Control Valve in service 1-4 CR200.203 Perform the procedure for rapid power reduction 1-4 CR299.351 Apply TS 3.1 and Bases 5 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a reactor scram 1-4 CR304.102 Perform actions associated with RPV Control 1-4 CR314.104 Perform actions associated with failure to scram 1-4 CR314.115 Defeat RPV Low

-Low Level Isolation for MSIV closure 1-4 CR314.105 Perform actions associated with alternate rod insertion 1-4 CR200.181 Perform the procedure for loss of normal off

-site power 1-4 CR200.160 Perform the procedure for a Group 4 isolation 1-4 QF107502 Rev. 4 (FP

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-G-RM-01. QUANTITATIVE ATTRIBUTES Malfunctions

Before EOP Entry:

1. Main Seal Oil Pump trip

2. #10 Transformer Lockout

3. CRD Flow Control Valve fails OPEN causing rod to drift

4. Uncoupled Control Rod

5. Station Power Transfer with electrical ATWS

After EOP Entry:

1. Loss of All Offsite Power

2. 11 EDG-ESW pump fails to start

3. 12 EDG fails to start

4. HPCI Steam Line rupture Abnormal Events

1. Control Rod Drift

2. Loss of All Offsite Power

3. Group 4 Isolation Major Transients

1. Loss of All Offsite Power with EDG failures

Critical Tasks

1. CT-47: During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained within C.5

-3101 to achieve reactor shutdown under all conditions.

2. CT-34: When a system fails to isolate, manually isolate the system prior to exceeding max safe operating values in two areas.

3. CT-EDG: Under a loss of all off

-site power condition, maintain and/or restore electrical power to an essential bus prior to reaching TAF.

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-G-RM-01. SCENARIO OVERVIEW:

Event 1: 12 EDG Monthly Surveillance Test (0187

-02B) BOP will continue Test 0187

-02B with steps to unload and shutdown 12 EDG.

Event 2: Trip of Main Seal Oil Pump (MSOP)

After shutting down the 12 EDG, the MSOP will trip and the Emergency Seal Oil Pump (ESOP) will fail to auto start. The BOP will manually start the ESOP

. Event 3: #10 Transformer Lockout The # 10 Bank Transformer will receive a lockout and the CRS will evaluate TSs for offsite power sources

. Event 4: CRD Flow Control Valve Fails OPEN 11 CRD Flow Control Valve will fail OPEN causing a control rod to drift in one notch. While verifying CRDH parameters the failed flow control valve will be discovered and the OATC will swap to the standby flow control valve.

Event 5/6: Rapid Power Reduction with Uncoupled Control Rod The OATC will reduce power to 9 7-98% with recirc flow IAW Nuclear Engineering recommendation and then fully withdraw the drifted control rod

. The drifted control rod will be uncoupled requiring the OATC to fully insert the control rod. CRS will evaluate TSs for an inoperable control rod.

Event 7: Station Power Transfer

- Electrical ATWS A 2R Lockout will occur requiring the crew to scram on degrading condenser vacuum. An ATWS will occur; the OATC will be successful with ARI (CT).

Event 8: HPCI Steam Line Rupture A steam leak will occur in the HPCI room. HPCI will fail to auto

-isolate requiring the crew to manually isolate HPCI when a max

-safe temperature is received (CT).

Event 9: Loss of Off

-Site Power A 1R Lockout will occur causing a LOOP, 11 EDG

-ESW pump and 12 EDG will fail to auto start.

The BOP will be required to manually start or cross

-connect 11 EDG

-ESW with Service Water and/or start 12 EDG (CT).

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-G-RM-01. NOTE: Table may be modified as needed to include all scenario time

-line items SCENARIO TIME

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

1. INITIAL CONDITIONS (IC):

a. Mode: 1 b. Present Power Level:

100% c. XCEL System Condition: Green

d. Plant CDF & LERF: Yellow e. Plant Fire LERF: Yellow

f. Electrical lineup

- 2R. g. Fuel Pool Status: Green, 1 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months to boil

h. Generator Output: ~6 9 5 M W e i. Staffing: Normal Weekday Dayshift

j. Planned Shift Activities: Continue 0187

-02B k. The following equipment is OOS

1) HPCI for Inadvertent initiation

. a) LCO 3.5.1 is NOT met b) Condition I was entered at 0400 to day c) Required Action I.1 is complete and I.2 is due in 14 days d) RCIC and 13 Battery are protected

2) 12 EDG for 0187

-02B since 1800 yesterday

. a) LCO 3.8.1 is NOT met B.1 complete due at 1400 today B.2 complete B.3 complete B.4 due in 7 days

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES b) 12 EDG ready to unload and secure c) 11 EDG & EDG

-ESW protected

3) The following control rods have slow scram times: a) 38-47, 42-43, 46-39, 50-31 2. SIMULATOR SET UP BOOTH INST a. Reset the simulator to IC-2 9 1 (PW: rpb 1) and place in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

b. Insert Manual Trigger 5 0 to load simulator initial conditions and preloaded malfunctions.

BOOTH INST c. Verify HPCI OOS but available as follows:

1) Place Aux Oil Pump in PTL with Caution tag

2) Hang PROTECTED EQUIPMENT sign on RCIC

3) Mark up C.4

-G appropriately for HPCI

d. Line up 12 EDG as follows:

1) Hang a CAUTION (yellow) card on the pump

2) Verify its GREEN light is OFF.

3) Place a PROTECTED EQUIPMENT sign near 11 EDG and switch box on 11 EDG

-ESW pump e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

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-G-RM-01. SCENARIO TIME

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

f. ENSURE Cross Flow is ENABLED on PCS as follows: 1) Verify computer points CFW966

-CFW969 are set to "ENABLED"

g. ENSURE Remote PO03 (CROSSFLOW DISABLED/ENABLED) is set to ENABLED

1) Verify status board is updated IAW Section 1 2) Complete the Simulator Setup Checklist

3. SIMULATOR PRE

-BRIEF: a. REVIEW the scenario initial conditions as listed in Section 1: For examination purposes a "Lead Instructor

- Crew Turnover Brief" has been created. This should be reviewed with the crew prior to allowing the crew in the simulator.

b. VERIFY the crew performs a walk

-down of the control boards prior to starting the shift brief.

Crew Performs walk down of control boards and reviews turnover checklists.

FLOOR INST 4. SHIFT BRIEF

c. Role Play as necessary. Turbine Building status:

Crew Conduct and participate in the Shift Brief 1). 5 Condensate Demins are in service.

2). C vessel d/p is highest @ 5.4 psid.

3). 0187-02B in progress for 12 EDG. 11 EDG &

EDG-ESW and 13 Battery are protected. All other systems in T B are normal.

d. Role Play as necessary. Extra out plant operator

- Nothing to add.

e. Role Play as necessary. Rx Building status:

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-G-RM-01. SCENARIO TIME

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

1) HPCI is OOS, troubleshooting in progress , RCIC is protected.

2) All other systems in the Rx Bldg are normal.

CRS Crew assumes the duty.

Event 1 5. CONTINUE 0187

-02B 12 EDG MONTHLY BOOTH INST a. When contacted as the Turbine Building Operator (TBO), respond appropriately that you are standing by for EDG shutdown. CRS Directs BOP to continue 0187

-02B (12 EDG/12 ESW MONTHLY PUMP AND VALVE TEST) at Step 73a.3)

Makes 4KV Breaker cycling announcement Lowers 12 EDG speed and loading to <2250 kW Lowers 12 EDG speed and loading to 200

-300 kW Opens 12 EDG output breaker BOOTH INST b. When directed to set speed droop to zero, Insert Trigger 8 Directs TBO to adjust speed droop to zero Adjusts 12 EDG frequency to 60.4

-60.6 Hz BOOTH INST c. When directed to set speed droop to the scribe mark, Set remote DG11 back to IN. Directs TBO to adjust speed droop to scribe mark

d. The OATC and BOP should swap and perform IV Adjusts 12 EDG voltage to ~4350 V and perform IV BOOTH INST e. KS 36 must be placed in CLOSE before moving to Event 2.

Places 12 EDG Control Switch to STOP FLOOR INST f. Perform CV as the Floor Instructor Places Knife Switch 36 back to CLOSE with Concurrent Verification

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2 6. MAIN SEAL OIL PUMP (MSOP) TRIP BOOTH INST a. When directed by the lead evaluator Insert TRIGGER 2. Parameter response

MSOP trips Expected alarms

8-A-22 (NO. 1 GEN H2 SYSTEM TROUBLE) BOP BOP responds to alarm and sends TBO to investigate.

Automatic actions: Emergency Seal Oil Pump (ESOP) fails to AUTO start when the MSOP trips.

BOP may recognize that MSOP pump is off and ESOP failed to auto start BOOTH INST b. When directed to investigate the trouble alarm, wait 1 minute and state that "Alarm 83-B-6 (EMERG SEAL OIL PUMP RUNNING) is in alarm but the ESOP is NOT running. Nothing appears to be wrong with the ESOP

". c. If asked as the TBO, report that Seal oil pressure locally is 52 psig. CRS Directs the BOP to start the ESOP from C

-08. BOOTH INST d. When asked to investigate cause of MSOP trip, wait 1 minute and state that breaker B3101 has tripped on overload.

e. Once the ESOP is started, if asked, report that seal oil pressure is 82 psig.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3 7. #10 TRANSFORMER LOCKOUT BOOTH INST a. When directed by the lead instructor, Insert Trigger 3 and verify ED08, ED127 and ED128 activate. Parameter response

1AR XFMR voltage 0 VAC Expected alarms

8-A-3 (345 KV & 115 KV YARD TROUBLE) BOP Acknowledges alarm and dispatches operator to 345 KV House to investigate.

Automatic actions: None Identifies 1AR voltage has been lost BOOTH INST b. When sent to investigate, wait 2 minutes and report that Panel 5P4 Annunciator Point 79 (10 TR LOCKOUT) is in alarm.

CRS SS299.356 CR299.358 Evaluates LCO 3.8.1 & TLCO 3.8.1 (OFFSITE SOURCES) as still met since 2R and 1R XFMRs are still available.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4 8. CRD FLOW CONTROL VALVE FAILS OPEN BOOTH INST a. When directed by the lead instructor, Insert Trigger 4 and verify CH07A and CH06_061 activ at e (CH06_061 will delete in 3 seconds). Parameter response: CRDH Drive pressure rises and cooling water header flow rises. CR 26-27 drifts in one notch. SS315.167 CR200.226 BOOTH INST Expected alarms

5-A-27 (ROD DRIFT)

OATC Enters C.4

-B.01.03.C (CONTROL ROD DRIFTING)

Automatic actions: None Rod Select Power Switch to OFF and back to ON BOOTH INST b. As the RBO, if asked to investigate CRD H or after the C.4 page announcement, wait 1 minute and report unusual high flow noise from the 'A' CRD Flow Control valve.

Recognizes the rod is no longer drifting Verifies CRD system operating parameters and determines the Flow Control valve has failed open Resets the Rod Drift alarm CRS Directs swapping CRD Flow Control Valves BOOTH INST c. When directed to report to the CRD FCV station to support shift of FCV, report you are standing by.

OATC CR201.111 Performs B.01.03-05.E.4 (PLACING THE STANDBY CRD FLOW CONTROL VALVE INTO SERVICE)

BOOTH INST d. When directed to OPEN CRD

-1 8-2 and CRD-1 6-2, WAIT 1 minute then Insert Trigger 9 and report this action to the Control room.

Directs RBO to OPEN CRD 2 & CRD-16-2 Places CRD Flow Controller in MANUAL Closes CV-3-19A with the flow controller Places the CRD Flow Selector to the B position Slowly opens CV 19B to 60-62 gpm Places CRD Flow Control in auto Closes CRD 1 & CRD-18-1 BOOTH INST e. Verify CH07A deletes when the flow controller is placed in Manual (Event Trigger 7)

BOOTH INST f. When directed to CLOSE CRD 1 and CRD-18-1 WAIT 1 minute & Insert Trigger 1 0.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5 9. POWER REDUCTION BOOTH INST a. When directed by the Lead Evaluator, call the CRS as the Operations Manager. State that time compression is in effect and the Nuclear Engineer recommends a power reduction to 9 7-98% with Recirc pumps and then fully withdrawing CR 26-27 and performing a coupling check.

OATC SS315.159 CR200.203 Lowers Recirc flow until reactor power is approximately 9 7-98%. May refer to Hard Card.

Selects CR 26-27 and single notch withdraws it to 48 Floor INST b. Provide Reactivity Maneuvering sheet to crew Event 6 10. UNCOUPLED CONTROL ROD

a. The uncoupled control rod malfunction is inserted as part of initial Setup trigger 50.

Parameter response: Rod Position goes blank Notifies CRS and recouples CR as follows: Expected alarms

5-A-11 (ROD OVERTRAVEL)

Insert CR until position 46 is observed Automatic actions: None Verifies 5

-A-11 resets Resets CR Drift Alarm Continuously withdraws CR to position 48 for coupling check

b. As the Nuclear Engineer, concur with the request to bypass the RWM Repeats previous steps as CR is NOT recoupled Inserts CR to 00 as its still uncoupled

c. When directed to electrically disarm control rod

26-27, wait 1 minute and Insert Trigger 14. Directs RBO to electrically disarm the CR CRS Evaluates LCO 3.1.6 (ROD PATTER N CONTROL) and LCO 3.1.3 (CONTROL RODS) as NOT met for CR 26

-27 SS299.349 CR299.351 QF107502 Rev. 4 (FP

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7 11. STATION POWER TRANSFER

- SCRAM W/ ELECTRICAL ATWS BOOTH INST a. When directed by the lead instructor, Insert Trigger 5. Key Parameter response: Loss of power to 12 Bus, Dual Recirc Pump trip, Dual Circ Water Pump trip, rapidly degrading condenser vacuum.

BOP Announces 2R Lockout and/or Station Power Transfer Recognizes rapidly degrading condenser vacuum Key Expected alarms

8-B-02 (NO. 2R XFMR LOCKOUT), 5

-B-20 (CONDENSER LO VACUUM SCRAM TRIP) Automatic actions: Failure of Manual and Automatic scram CRS SS315.164 Directs a reactor scram IAW C.4.K (IMMEDIATE REACTOR SHUTDOWN

) OATC CR200.208 Depresses pushbuttons for REACTOR SCRAM A and B and places the Mode Switch in SHUTDOWN OATC Provides a Scram Report SS304.201 CR314.104 Reactor Scram, Mode Switch is in Shutdown, no rod motion, Reactor power is >4%, EOP Entry CRS Enters EOP 1100 RPV Control, transitions to EOP 2007

(FAILURE TO SCRAM

) and directs the following

NOTE: The CRS may wait to direct this action as time permits. BOP o Inhibit ADS NOTE: This action may not be taken based on the loss of Circ Water pumps BOP SS314.111 CR314.115 C.5-3301 (DEFEAT MSIV LOW

-LOW LEVEL ISOLATION)

Places 4 Key switches to BYPASS on C

-15/17.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES CT-4 7 During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained within C.5

-3101 to achieve reactor shutdown under all conditions.

OATC CR314.105 Performs C.5

-3101 (ALTERNATE ROD INSERTION)

SS314.101 Verifies Recirc pumps are at minimum speed and trips the pumps NOTE: ARI will work for this scenario.

CR212.105 Arms and Actuates A/B ATWS and determines ARI is having success.

Notifies CRS that all control rods are inserted OATC Continues actions IAW C.4-A (REACTOR SCRAM

) PART A: Controls Reactor water level between +

11 and +4 6 inches. When RPV water level starts to increase:

Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches Close both Main FW Reg Valves o Verify CV-6-13 controls RPV level when it reaches +15 to +20 inches o Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

OATC Range down on IRMs as necessary.

o Verify SDV Vent and Drain Valves closed.

BOP Takes actions IAW C.4-A (REACTOR SCRAM)

PART B:

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Plant pag e that a Reactor Scram has occurred.

Open Main Generator output breakers 8N 7 & 8N 8. Trip the Main Turbine.

Verify the Generator Field Breaker Open.

NOTE: The remaining BOP actions in C.4

-A may NOT be performed depending on when the LOOP occurs.

Start the Turbine Aux Oil Pump.

Verify Turbine Exhaust Hood Sprays in service.

Verify Turbine Stop Valves are closed Start Turbine Bearing Lift Pumps NOTE: Circ water pumps will need to be restarted for condenser vacuum or LL

-SET will be used for pressure control. Verify Main Steam Pressure Control & Bypass valves are controlling Reactor Pressure.

At C-25, Place the POST SCRAM switch in ON and verify all available Drywell Recirculation Fans are operating Verify 4500 gpm through each operating Pump Verify AC Auxiliary Oil Pump running on any non

-operating Feed Pump Verify 4100 gpm through each operating Condensate Pump

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 8 12. HPCI STEAM LEAK BOOTH INST a. Verify HP07 activates 5 minutes after the scram.

Key Parameter response: Rising temperatures and Rad levels in the HPCI room.

SS315.115 CR200.160 Key Expected alarms

3-B-56 (HIGH AREA TEMP STEAM LEAK)

BOP Goes to back panel C

-11 & C-21to check temperatures Automatic actions: HPCI will fail to automatically isolate on high temperature.

Recognizes rising temperatures and radiation levels in the HPCI room and evacuates the Reactor Building BOOTH INST b. Two minutes after HPCI leak is initiated, report as maintenance that there is a steam leak in the HPCI room and all personnel have left the room.

CRS Enters C.5

-1300 (SECONDARY CONTAINMENT CONTROL) Isolate all discharges into the area CT-34 When a system fails to isolate, manually isolate the system prior to exceeding max safe operating values in two areas.

BOP Manually closes MO

-2034 & MO-2035 (HPCI STEAM LINE ISOLATION VALVES)

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-G-RM-01. SCENARIO TIME

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

13. LOSS OF ALL OFF

-SITE POWER

a. One minute after HPCI is isolated, verify ED04C activates. This will cause a 1R lockout.

Key Parameter response: Loss of off

-site power to Busses 11-16 and a temporary loss of control room lighting. Key Expected alarms

8-C-4 (NO. 1R TRANS LOCKOUT)

Automatic actions: 11 EDG will automatically load onto 15 Bus but 11 EDG

-ESW Pump will fail to automatically start. 12 EDG will fail to automatically start and 16 Bus will remain deenergized.

Performs switch lineup for loss of Busses 11

-14 NOTE: With a Loss of Offsite Power and 16 Bus deenergized, ONLY 11 Service Water Pump is available and must be manually restarted.

Performs switch lineup for no 1AR voltage to 15 & 16 Bus Recognizes that 11 EDG

-ESW pump failed to auto start

b. If 11 Service Water pump is NOT restarted and you are directed to cross

-tie service water to 11 EDG-ESW, wait 30 seconds and report that NONE of the Service Water pumps are running.

Performs one of the following:

o Manually starts 11 EDG

-ESW pump or o Restarts 11 Service Water pump and dispatches the TBO to cross

-tie Service Water to 11 EDG

-ESW IAW B.08.01.02

-05.H.3 (TRANSFER EDG COOLING FROM EDG-ESW TO SERVICE WATER) o Starts 12 EDG from C

-08 or directs a local start. c. Once 11 Service Water pump is running and you are directed to cross

-tie service water to 11 EDG

-ESW, wait 30 seconds and Insert Trigger 16

. CT-EDG Under a loss of all off

-site power condition, maintain and/or restore electrical power to an essential bus prior to reaching TAF.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Performs switch lineup for loss of bus 16 Booth INST NOTE: 12 EDG can be manually started by the crew. Malfunction DG02B will auto delete on Event Trigger 26 if started from C

-08. If directed by the crew to start the 12 EDG locally, manually delete malfunction DG02B. Both options will allow 12 EDG to auto load onto 16 bus from the EBT. Places 12 EDG O/P breaker in PTL Verifies 11 Service Water Pump is running BOP Starts 11 RBCCW Pump Starts 11 CRD Pump Performs switch line up for loss of Condensate, Feed and Circ Water pumps Restores Drywell cooling as required Verifies 11 EDG meets load limitations.

d. Based on initial scenario conditions, HPCI could also be used to restore RPV level. However, HPCI will be lost once the steam leak occurs.

CRS Enters C.5

-1100 (RPV CONTROL) Level Leg and directs OATC to place RCIC in service IAW the Hard Card to restore and maintain RPV level +9 to +48" OATC Verifies flow control in Auto at 400 gpm Opens MO-2096 Starts Barometric Cdsr Vacuum Pump Opens MO-2107 Opens MO-2106 Opens MO-2078 NOTE: If main condenser available, and

-47" RPV Level was not reached and the Main Turbine Aux Oil pump Lockout is reset, pressure control can be restored with the Bypass Valves 800

-1000 psig.

Verifies RCIC turbine comes up to speed and injects CRS Enters C.5-1100 (RPV CONTROL) Pressure Leg and directs a pressure band of 900

-1056 psig using LL

-SET.

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-G-RM-01. SCENARIO TIME

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

14. SCENARIO TERMINATION

a. The scenario may be terminated when

11 EDG has cooling supplying 15 Bus or 12 EDG is restarted supplying 16 Bus and HPCI is isolated RPV water level is being controlled

b. The scenario may be also terminated at the discretion of lead instructor/evaluator FLOOR INST c. 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 allowe d

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-G-RM-01. SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s) Ramp Final Initial / Value MALFUNCTIONS (Allow Tracking Off)

C-08-A22 NO 1 GEN H2 SYSTEM TROUBLE 2 Active InActive C-08-A03 345 KV _ 115 KV YARD TROUBLE 3 Active InActive CH07A CRD Flow Control Valve CV

-19A fails OPEN 4 Active InActive CH07A CRD Flow Control Valve CV

-19A fails OPEN (Deletes in 1 second) 17 Active InActive CH06_061 Control Rod 26

-27 Drift IN (Deletes in 3 seconds) 4 00:00:05 100 0 CH03_061 Control Rod 26

-27 Uncoupled 4 00:00:02 Active InActive ED04D Loss of 2R XFMR 5 Active InActive PP02 ELECTRICAL ATWS 5 Active InActive DG02B #12 EDG Start Failure 5 Active InActive DG02B #12 EDG Start Failure (Deletes in 1 second) 26 Active InActive ED04C Loss of 1R XFMR 15 00:01:00 Active InActive HP01 HPCI AUTO-INITIATION 50 Active Active HP01 HPCI AUTO-INITIATION (Deletes in 1 second) 15 Active Active HP08 Failure of HPCI to Auto Isolate 50 Active Active HP07 HPCI Steam Leak 6 00:05:00 Active InActive REMOTES ED08 1AR XFMR PRI SUPPLY BKR 1N2 3 OPEN CLOSE ED127 345 KV 10 TR DISC 3 OPEN CLOSE ED128 115 KV 10 TR DISC 3 OPEN CLOSE CH17 CRD-18-2 & 16-2 9 OPEN CLOSE QF107502 Rev. 4 (FP

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-G-RM-01. SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s) Ramp Final Initial / Value CH16 CRD-18-1 & 16-1 10 CLOSE 00:00:00 CH15_061 Control Rod 26

-27 Electrically Disarmed 14 DISARM 00:00:00 DG11 12 EDG Speed Droop 8 OUT IN SW09 SW-228 & SW 229 to OPEN 16 OPEN CLOSE CH18 ATWS - ARI Fails to Energize 20 Active InActive CH18 ATWS - ARI Fails to Energize 21 Active InActive CH18 ATWS - ARI Fails to Energize 22 Active InActive Code Description Event Trigger Delay(s) Ramp Final Initial / Value OVERRIDES 05-S050-01 MSOP Handswitch RUN position 2 FALSE TRUE 05-S071-02 ESOP in AUTO 50 FALSE FALSE 05-S071-03 ESOP in STOP 50 TRUE TRUE 05-S071-02 ESOP in AUTO 12 TRUE FALSE 05-S071-03 ESOP in STOP 12 FALSE TRUE 05-S106-02 11 ESW Pump

- AUTO 50 FALSE FALSE 05-S106-03 11 ESW Pump

- STOP 50 TRUE TRUE 05-S106-02 11 ESW Pump

- AUTO 7 TRUE FALSE 05-S106-03 11 ESW Pump

- STOP 7 FALSE TRUE 03-S36-06 B Manual Scram Pushbutton 5 FALSE FALSE 05-DS032-02 MSOP GREEN Light 2 OFF OFF QF107502 Rev. 4 (FP

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-G-RM-01. Event Trigger Definitions

Code Description Event Trigger ZD_SESOP ESOP Handswitch to START 12 ZD_EMSTA(1) 11 EDG-ESW Pump to START 7 ZD_S1SHD Mode Switch to SHUTDOWN 6 ZD_HS3CL HPCI MO-2035 to CLOSE 15 ZD_CNMAN CRDH Flow Controller to MANUAL 17 rrpdome > 1075 RPV Steam Dome pressure >1075 psig 20 ZD_S5amn A ARI Pushbutton depressed 21 ZD_S5bmn B ARI Pushbutton depressed 22 ZD_SDG2 12 EDG Control Switch to START 26 QF107502 Rev. 4 (FP

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-G-RM-01. Attach the following site

-specific information as necessary:

Simulator Set

-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log His torical Record:

1. New Create for the 201 6 ILT NRC Exam

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-G-RM-01. 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.

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 or Shutdown Safety Risk Assessment.

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 anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No 8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No 9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No 10. 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 11. For evaluations, it has been verified that without operator action the critical tasks will be failed.

Yes No Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

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-G-RM-01. 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 conditions agreed with the reference plant with respect to reactor status, plant configuration, and system operation.

Yes No 2. The simulator operated in real time during conduct of validation.

Yes No 3. The simulator demonstrated expected plant response to operator input and to normal, transient, and accident conditions.

Yes No 4. The simulator permitted use of the reference plant's procedures. The scenario was completed without procedural exceptions, simulator performance exceptions, or deviation from the scenario sequence.

Yes No 5. The simulator did not "fail to cause" or "unexpectedly cause" any first principle alarm or primary automatic action.

Yes No 6. Observable changes in parameters relevant to the scenario corresponded in trend and direction to reference plant's expected response. Yes No 7. All malfunctions and other instructor interface items were functional and demonstrated the expected reference plant's response to the initiating cause. Yes No 8. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No 9. The scenario satisfies the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence.

Yes No 10. Simulator fidelity has been demonstrated to be adequate for this scenario.

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

None SMAR = Simulator Action Request SMAR: SMAR: SMAR: S MAR:

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-G-RM-01. Comments: Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Validation Personnel Name Job Title / Qualification Validation Position Jason Pearce SM / SRO CRS Greg Pagel NPE&RO / RO OATC Troy Teige N LPE&RO / RO BOP

Appendix D Scenario Outline Form ES-D-1 Facility:

MONTICELLO Scenario No.:

2 Op-Test No.:

2016-301 Examiners:

Operators:

Initial Conditions:

Plant Start-up in progress (38% power) following a n outage; There are 4 control rods with "slow" scram times (38-47, 42-43, 46-39, 50-31).

Turnover: Continue the start

-up, raise power to 40% using single notch control rod withdrawal starting at Step 30 of ASR5.

At 40%, place 12 Condensate pump in service. Once 12 Condensate pump is in service, raise power to 45% using Recirc flow.

Event No. Malfunction No. Event Type Event Description

1. R (OATC) I (OATC) Operator will raise power from 38% to 40% using control rods. While withdrawing a control rod from 12 to 48, the control rod will be stuck at 12. The OATC will raise drive pressure to free the control rod. Crew will continue with startup activities.

2. N (BOP) When power is

~40%, BOP will place 12 Condensate Pump in service 3. R (OATC) C (OATC) TS (SRO) OATC will raise power to 45% with Recirc flow. When raising power to 45%, a 12 Recirc Pump Speed Controller failure will occur. The OATC will lock "B" Scoop Tube. The CRS will evaluate LCO 3.4.1 flow mismatch

> 10% between loops.

4. C (BOP) TS (CRS) Loss of LC

-103 feeder breaker to MCC

-131. BOP will manually start 12 Steam Packing Exhauster and verify auto actions. The CRS will evaluate TSs for loss of power to #11 EDG control panel (LCO 3.8.1). 5. C (BOP) SRV D will begin leaking. Tailpipe temperature will rise requiring the BOP to place B RHR in the Torus Cooling Mode.

6. M (CREW) SRV D will fail full open and will not close when immediate actions are taken. The OATC will insert a manual scram (CT). The SRV will close following the scram. Following the insertion of the scram, a large steam leak will occur in the Drywell. Pressure and Temperature in the Drywell will rise requiring t he crew to initiate Drywell Sprays.

7. C - (POST) When DW pressure CANNOT be maintained below 12 psig, the CRS will direct Drywell Sprays (CT). The LPCI Initiation Bypass will fail for the first Division of RHR that is used for Containment Sprays. The crew will be forced to use the opposite Division of RHR. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor QF107502 Rev. 4 (FP

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-G-RM-01. SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-41 E SEG TITLE:

201 6 ILT NRC SCENARIO 2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME:

45-90 MINUTES Additional site

-specific signatures may be added as desired.

Developed by:

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 QF107502 Rev. 4 (FP

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-G-RM-01. Guide Requirements Goal of Training: This Scenario evaluation has been written for the 201 6 ILT NRC Exam. Once this exam is complete and exam security is relaxed, this SEG should be appropriate to use for the following activities

Future ILT NRC / Audit Exam Evaluation s SRO Certification Evaluations LOR Crew development Learning Objectives:

1. Demonstrate the ability to predict and/or monitor changes in parameters associated with operating system controls for the

appropriate tasks.

2. Demonstrate the ability to correctly use procedures to correct, control, or mitigate the consequences of normal and abnormal operations for the appropriate tasks.

3. Demonstrate the ability to monitor automatic operations of the

systems to ensure proper operation for the appropriate tasks.

4. Demonstrate the ability to manually operate and/or monitor systems in the control room in accordance with approved

procedures for the appropriate tasks.

5. Demonstrate the ability to complete administrative requirements, as necessary, in order to operate the plant for the appropria te tasks. 6. Demonstrate knowledge of and ability to implement shift supervision duties as they relate to crew operations for the

appropriate tasks.

7. Given a degrading or improving plant condition or event, demonstrate the ability to: (CRS)

a. Evaluate trends that may result in equipment damage or reduction in plant safety.

b. Ensure proper diagnosis of plant problems by monitoring and interpreting data (information from panel indications).

c. Evaluate and diagnose challenges to Critical Plant Parameters.

d. Evaluate events and accidents.

Prerequisites:

1. Completion of the MT-ILT Training Program

, or 2. Completion of the SRO Certification Program

, or 3. Currently enrolled in the LOR Training Program Training Resources:

1. Full Scope Simulator

2. MTF-7100-051 (Attendance Record) or LMS Equivalent

3. 3139 (Control Room Shift Turnover Checklist)

4. 3140 (Shift Supervisors Office Shift Turnover Checklist)

5. Lead Instructor

- Crew Turnover Brief paperwork 6. 2167 (Plant Startup) & 2300 (Reactivity Adjustment)

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-G-RM-01.

References:

1. FORM 2167 (PLANT STARTUP) 2. 2300 REACTIVITY MANEUVERING STEPS

3. B.01.03-05.H.3 (ELEVATING DRIVE PRESSURE TO WITHDRAW A CONTROL ROD)

4. B.06.05-05.D.3 (STARTUP 12 CONDENSATE PUMP WITH 11 CONDENSATE PUMP RUNNING)

5. B.01.04-05 (UNSTABLE SPEED CONTROL ON ONE PUMP)

6. LCO 3.4.1 (RECIRCULATION LOOPS OPERATING)

7. 8-B-32 (NO. 103 480V LDCTR MCC FEEDER TRIP)

8. C.4-B.09.07.C (LOSS OF POWER TO LC

-103 OR ITS MCCs)

9. LCO 3.8.1(OFFSITE SOURCES)

10. 3-A-9 (AUTO BLOWDOWN RELIEF VLV LEAKING)

11. C.4-B.03.03.B (RELIEF VALVE LEAKING)

12. B.03.04-05.H.5/H.6 (PLACING A/B LOOP RHR TORUS COOLING IN SERVICE DURING ABNORMAL AND EMERGENCY CONDITIONS WITH NORMAL OFF

-SITE POWER AVAILABLE)

13. B.03.01-05.G.4/G.5 (CORE SPRAY A/B LOOP TORUS MIXING MODE) 14. 5-A-46 (SRV OPEN)

15. C.4-B.03.03.A (STUCK OPEN RELIEF VALVE)

16. C.4-F (RAPID POWER REDUCTION)

17. C.4-K (IMMEDIATE REACTOR SHUTDOWN)

18. C.4-A (REACTOR SCRAM)

19. C.5-1100 (RPV CONTROL)

20. C.5-1200 (PRIMARY CONTAINMENT CONTROL)

21. C.5-3503 (DEFEAT DW COOLER TRIPS)

22. C.5-3502 (CONTAINMENT SPRAY)

Commitments:

1. None Evaluation Method: The following methods are acceptable methods for examinee evaluation:

201 6 ILT NRC Exam Process (NUREG 1021

& FP-T-SAT-72) MT-ILT (MNGP ILT Program Description)

M-9700 (SRO Certification Program Description)

FP-T-SAT-73 (Licensed Operator Requalification Program)

Operating Experience:

Not Applicable to Evaluation Scenarios Related PRA Information:

Initiating Event with Core Damage Frequency

None Important Components

/ Accident Class

None Important Operator Actions with Task Number

None QF107502 Rev. 4 (FP

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-G-RM-01. TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks: SS200.133 Direct a reactor startup to full power 5-7 SS299.352 Apply administrative requirements for TS 3.4 and Bases 5-7 SS315.143 Supervise response to a loss of LC

-103 or its MCCs 5-7 SS299.356 Apply administrative requirements for TS 3.8 and Bases 5-7 SS315.110 Supervise response to a relief valve leaking 5-7 SS315.109 Supervise response to a stuck open relief valve 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.193 Implement RPV control 5-7 SS304.194 Implement primary containment control 5-7 SS314.120 Supervise defeat drywell cooler trips 5-7 SS314.119 Supervise containment spray 5-7 RO Tasks: CR200.103 Perform a Startup Checklist 1-4 CR200.1 2 7 Perform a power ascension after the reactor is on line 1-4 CR201.122 Elevating drive pressure to withdraw a control rod 1-4 CR256.113 Start 12 Condensate pump with 11 Pump running 1-4 CR202.114 Respond to unstable speed control on one pump 1-4 CR299.354 Apply TS 3.4 and Bases 5 CR200.187 Perform procedure for a loss of power to LC

-103 or its MCCs 1-4 CR299.358 Apply TS 3.8 and Bases 5 CR200.155 Perform the procedure for a relief valve leaking 1-4 CR203.117 Place RHR in Torus Cooling during abnormal or emergency conditions with normal off

-site power available 1-4 CR209.115 Place Core spray in Torus mixing mode 1-4 CR200.154 Perform the procedure for a stuck open relief valve 1-4 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a Reactor Scram 1-4 CR304.102 Perform actions associated with RPV Control 1-4 CR304.103 Perform actions associated with Primary Containment Control 1-4 CR314.124 Defeat drywell cooler trips 1-4 CR314.123 Perform actions associated with containment spray 1-4 QF107502 Rev. 4 (FP

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-G-RM-01. QUANTITATIVE ATTRIBUTES Malfunctions

Before EOP Entry:

1. Stuck control rod

2. Recirc speed control failure

3. Loss of LC

-103 4. SRV leaking

5. SRV stuck open

After EOP Entry:

1. Drywell spray failure Abnormal Events

1. Loss of LC

-103 2. Leaking SRV

3. Stuck Open SRV

Major Transients

1. Unisolable Steam leak in the Drywell requiring Containment Sprays

Critical Tasks

1. CT-6 When an SRV is stuck open and can NOT be closed then insert a manual reactor scram prior to Torus water temperature reaching 110°F

. 2. CT-30 When Drywell pressure reaches 12 psig, then initiate Drywell sprays to prevent Emergency Depressurization

.

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-G-RM-01. SCENARIO OVERVIEW:

Event 1: Raise reactor power with Control Rods to ~4 0% OATC will continue the A2R5 startup sequence to raise power to 40%

. The control rod that is withdrawn will be stuck at position 12. The OATC will take action to free the stuck rod.

Event 2: Place the second Main Condensate Pump in service BOP will place the second Main Condensate Pump in service.

Event 3: 12 Recirc Runaway The OATC will continue raising power with Recirc pumps to ~45%

. The 12 Recirc pump will runaway requiring the OATC to lock the scoop tube. The CRS will evaluate TS 3.

4.1. Event 4: Loss of MCC

-131 Loss of LC

-103 feeder breaker to MCC

-131. BOP will manually start 12 Steam Packing Exhauster and verify auto actions. The CRS will evaluate TSs for loss of power to #11 EDG control panel (LCO 3.8.1).

Event 5: Leaking SRV D SRV D will begin leaking. Tailpipe temperature will rise requiring the BOP to place B RHR in the Torus Cooling Mode

. Event 6: Stuck Open SRV D SRV D will fail full open and will not close when actions are taken. The OATC will insert a manual scram (CT). The SRV will close following the scram. Following the insertion of the scram, a large steam leak will occur in the Drywell. Temperatures in the Drywell will rise requiring the crew to initiate Drywell Sprays

. Event 7: Drywell Spray failure The BOP will be required to initiate Drywell Sprays when Drywell pressure exceeds 12 psig (CT). The LPCI Initiation Bypass will fail for the first division of RHR, requiring the BOP to use the opposite division.

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-G-RM-01. NOTE: Table may be modified as needed to include all scenario time

-line items SCENARIO TIME

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

1. INITIAL CONDITIONS (IC)

a. Mode: RUN b. Present Power Level:

38% c. XCEL System Condition: Green

d. Plant CDF: Green LERF: Green e. Plant Fire LERF: Green

f. Electrical lineup

- 2R supplying g. Fuel Pool Status: Green, 1 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months to boil

h. Generator Output: ~2 31 M W e i. Staffing: Normal Weekday Dayshift

j. Planned Shift Activities:

1) Raise reactor power to 4 0% 2) Place 2 nd Main Condensate Pump in service

3) Raise reactor power to 45%

k. The following equipment is OOS

1) The following control rods have been declared slow a) 38-47, 42-43, 46-39, 50-31 QF107502 Rev. 4 (FP

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-G-RM-01. SCENARIO TIME

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

2. SIMULATOR SET UP BOOTH INST b. Reset the simulator to IC-2 9 2 (PW: rpb 2) and place in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

c. Insert Manual Trigger 5 0 to load simulator initial conditions and preloaded malfunctions.

d. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Form 2300 & 2167 marked up for raising power and starting the 2 nd Main Condensate Pump

. a) Step 17 3 of Form 2167 (PLANT STARTUP) Revision 9 3. 3) A2R5 Roller Tape and Binder appropriately marked up to Step 30

4) B.06.05-05.D.3, Steps 1

-6 complete. e. ENSURE Cross Flow is DISABLED on as follows:

1) Verify computer points CFW966

-CFW969 are set to "DISABLED" 2) ENSURE Remote PO03 (CROSSFLOW DISABLED/ENABLED) is set to DISABLED f. Verify the status board is updated IAW Section 1

g. Complete the Simulator Setup Checklist

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-G-RM-01. SCENARIO TIME

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

3. SIMULATOR PRE

-BRIEF: FLOOR INST a. REVIEW the scenario initial conditions as listed in Section 1: For examination purposes a "Lead Instructor

- Crew Turnover Brief" has been created. This should be reviewed with the crew prior to allowing the crew in the simulator.

b. VERIFY the crew performs a walk

-down of the control boards prior to starting the shift brief.

Crew Performs walk down of control boards and reviews turnover checklists.

4. SHIFT BRIEF Role Play as necessary. Turbine Building status:

Crew Conduct and participate in the Shift Brief 1). 4 Condensate Demin s are in service.

2). A vessel d/p is highest @ 5.2 psid. 3). Ready to start 12 Condensate pump 4). 11 RFP is in service, 12 RFP is in warmup 5). All other systems in T B are normal.

Role Play as necessary. Extra out plant operator.

1) Nothing to add.

Role Play as necessary. Rx Building status:

1) All system in the Reactor Building are normal for plant startup.

CRS Crew assumes the duty.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1 5. RAISE REACTOR POWER TO 4 0% WITH RODS a. Provide the following:

CRS Performs a Reactivity Manipulation Brief Booth Operator 1) 2300 (Reactivity Adjustment)

SS200.133 CR200.103 CRS directs the OATC to raise reactor power to 40% with A2R5 Step 30 control rods IAW 2300 Reactivity Maneuvering Steps and Form 2167 (Plant Startup) Step 17 3. 2) Nuclear Engineer Reactivity Maneuvering Steps BOP Provide a Peer Check

3) A2R5 Roller Tape and Binder appropriately marked up to Step 30 OATC Withdraws control rods continuing with Step 30 of the A2R5 Startup sequence.

Booth Operator b. If APRM gain adjustments are requested prior to, during, or after the power adjustment, open remote NI18 and SET until gains are

+2% CR200.127 Selects Control Rod 14

-23 Uses single notch withdrawal from position 12 to 48 Monitors control rod position, CRDH and APRMs Key Parameter Response

CR 14-23 will not move Recognizes control rod is stuck at position 12 Key Expected Alarms

None CR201.122 Enters B.01.03

-05.H.3 (ELEVATING DRIVE PRESSURE TO WITHDRAW A CONTROL ROD)

Auto Actions

None Raises Drive pressure in 30 psid increments by closing MO 20 c. Acknowledge any requests to Engineering, Maintenance and Plant Management.

When Drive pressure is >280 psig the control rod will withdraw

d. If required, role play as the Operations Manager and state to continue startup activities.

Continue s with startup and withdraws the control rod until reactor power is

~40%.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2 6. START 12 CONDENSATE PUMP Booth Operator NOTE: Steps 1-6 have been completed. This has been communicated to crew as part of the Pre

-Scenario Brief.

CRS Directs the BOP to continue B.06.05

-05.D.3 (STARTUP 12 CONDENSATE PUMP WITH 11 CONDENSATE PUMP RUNNING) at Step 7. Booth Operator a. Respond as TBO standing by for pump start BOP CR256.113 Dispatch operator to observe pump start Starts 12 Condensate Pump Booth Operator b. When requested to open the discharge valve, Insert Trigger 2, wait 1 minute and report the valve is open.

Slowly OPEN FW 2 (12 COND PMP DISCH) locally (TBO)

Booth Operator Raise Condensate Recirc Flow Controller setpoint to achieve a flow of 8500 gpm. Observes rising flow. c. As the TBO, wait 2 minutes and report D.3 is complete. Informs TBO to complete procedure D.3

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3 7. RAISE POWER TO 45% WITH RECIRCS

a. Provide the following:

CRS Performs a Reactivity Manipulation Brief Booth Operator 1) 2300 (Reactivity Adjustment)

SS200.133 CR200.103 CRS directs the OATC to raise Recirc speed to achieve 45% reactor power IAW 2300 Reactivity maneuvering Steps and Form 2167 (Plant Startup) Step 173.

2) Nuclear Engineer Reactivity Maneuvering Steps BOP Provide a Peer Check OATC Raises Recirc speed to raise power.

CR200.127 Maintains Flow parameters approximately equal

b. If APRM gain adjustments are requested prior to, during, or after the power adjustment, open remote NI18 and SET until gains are +2%

c. When reactor power is ~4 2% Verify Event Trigger 10 activates and RR09D inserts. Monitors the following parameters:

o Pump Speeds & Scoop Tube positions o Reactor Differential pressure o Total Jet Pump Flow o Reactor Water Level and Feedwater Flow o Reactor Pressure and Steam Flow o APRMs & Core Thermal limits Key Parameter Response

Recirc Pump speed, scoop tube position and reactor power rising.

OATC CR202.114 Recognizes 12 Recirc pump speed rising and locks the scoop tube IAW B.01.04

-05 (UNSTABLE SPEED CONTROL ON ONE PUMP)

Key Expected Alarms

5-A-51 (RBM HI/INOP)

CRS Evaluates difference in Jet pump flows and evaluates LCO 3.4.1 (RECIRCULATION LOOPS OPERATING)

Auto Actions

Rod Withdraw Block SS299.352 CR299.354 <70% rated core flow, mismatch needs to be

<10% (~5.7 Mlbm/hr)

Enters LCO 3.4.1 Condition A (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) if flow mismatch is >10%.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4 8. LOSS OF MCC

-131 BOOTH INST a. When directed by the lead evaluator, Insert MANUAL TRIGGER 4 and verify ED70 activates.

Key Parameter Response

Loss of voltage to MCC

-131 Key Expected Alarms

8-B-32 (NO. 103 480V LDCTR MCC FEEDER TRIP)

Auto Actions

Main Xfmr Cooling switch to alternate source (MCC

-121), BOP Enters C.4

-B.09.07.C (LOSS OF POWER TO LC

-103 OR ITS MCCs) and evaluates Table MCC

-131 b. As the TBO, wait 2 minutes and report the following:

1) All MCC-131 equipment transferred power properly 2) No Steam Packing Exhauster is running

3) 11 EDG Control Panel C

-93 is deenergized

4) The MCC-131 supply breaker tripped on overload. SS315.143 CR200.187 Dispatches operator to verify proper operation of standby equipment

. Starts 12 Steam Packing Exhauster o B.06.01-05.E.15/E.17 Verifies 12 SWC Pump auto started Verifies ESOP auto started CRS Evaluates LCO 3.8.1(AC POWER SOURCES) for loss of power to 11 EDG Control Panel C

-93 SS299.356 CR299.358 Enters LCO 3.8.1 Condition B for one EDG INOP.

o B.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months o B.2 will be N/A o B.3 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months o B.4 within 7 days

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5 9. SRV D LEAKING BOOTH INST a. When directed by the lead evaluator, Insert TRIGGER 5 and verify AP03D activates. Key Parameter Response

Rising tailpipe temperatures BOP Enters C.4

-B.03.03.B (RELIEF VALVE LEAKING)

Key Expected Alarms

3-A-9 (AUTO BLOWDOWN RELIEF VLV LEAKING)

SS315.110 CR200.155 If SRV D tailpipe temperature exceeds 210°F then mix water in the torus with RHR or Core Spray Auto Actions

None. CR203.117 B.03.04-05.H.5/H.6 (PLACING A/B LOOP RHR TORUS COOLING IN SERVICE DURING ABNORMAL AND EMERGENCY CONDITIONS WITH NORMAL OFF

-SITE POWER AVAILABLE)

b. If Torus Cooling is placed in service the CRS should evaluate TS 3.5.1 for inoperable LPCI injection paths.

Sets RHRSW Outlet controller at 20%

Starts RHRSW Pump(s), adjust s flow 3500 gpm/pump Starts RHR Pump(s) and opens Torus Cooling Inb & Otbd valves to achieve 4000 gpm/pump NOTE: With 11 EDG INOP the crew should use Division 1 RHR or Division 1 Core Spray to prevent the inoperability of redundant features which would require performance of LCO 3.8.1 Condition B.2.

Closes HX bypass valve Places Room Air Cooling Unit in service BOP CR209.115 B.03.01-05.G.4/G.5 (CORE SPRAY A/B LOOP TORUS MIXING MODE)

Verifies injection inboard valve is closed

c. When directed to check local pump suction pressure, state that suction pressure is 20 psig.

Verifies system pressures Starts a Core Spray pump Opens Torus Test Return valve until flow is ~3000 gpm

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 6 10. SRV D STUCK OPEN BOOTH INST a. When directed by the Lead Evaluator, insert TRIGGER 6 and verify AP01D activates. SS315.109 CR200.154 Key Parameter Response

MWe lowering, D Main Steam line flow lowers.

Key Expected Alarms

5-A-46 (SRV OPEN)

BOP Enters C.4

-B.03.03.A (STUCK OPEN RELIEF VALVE)

Automatic Actions

None Places SRV D handswitch to open then back to normal NOTE: At the lower reactor power and 12 Recirc Pump scoop tube locked, the crew may not reduce reactor power Enters C.4

-F (RAPID POWER REDUCTION)

CT-6 When an SRV is stuck open and can NOT be closed then insert a manual reactor scram.

If SRV remains open then manually scram the reactor OATC CR200.208 SS315.164 Inserts a manual Reactor scram IAW C.4-K (IMMEDIATE REACTOR SHUTDOWN

) OATC Takes actions IAW C.4-A (REACTOR SCRAM

) PART A: BOOTH INST b. When the Mode Switch is placed in SHUTDOWN, verify Event Trigger 7 activates.

SS315.101 CR200.146 Place Mode Switch in SHUTDOWN.

o Verify all Control Rods are inserted to or beyond position 04.

Provides scram script to CRS. Reports RPV less than 9" EOP entry condition.

Controls Reactor water level +

9-4 8". When RPV water level starts to increase:

o Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES o Close both Main FW Reg Valves o Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

Verify SDV Vent and Drain Valves closed.

Verify Recirc Pumps have run back to minimum CRS Enters C.5

-1100 (RPV CONTROL) SS304.193 CR304.102 Directs OATC to restore and maintain RPV level

+9 to +48" using Condensate and Feedwater NOTE: This pressure band may be lower when the crew realizes that the SRV has closed.

Directs BOP to restore and maintain RPV pressure 800-1000 psig using the Bypass valves CRS Enters C.5

-1200 (PRIMARY CONTAINMENT CONTROL)

NOTE: This action may be performed as part of placing Torus Spray in service.

Directs BOP to place Torus Cooling in service BOP Takes actions IAW C.4-A (Reactor Scram)

PART B: Plant pag e that a Reactor Scram has occurred.

Open Main Generator output breakers 8N 7 & 8N 8. Trip the Main Turbine.

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE: The remaining BOP actions in C.4

-A may NOT be performed depending on when the steam leak is recognized.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

Verify Turbine Exhaust Hood Sprays in service.

Verify Turbine Stop Valves are closed Start the Turbine Bearing Lift Pumps Verify Main Steam Pressure Control and Bypass Valves are controlling Reactor Pressure.

Event 7 10. STEAM LINE RUPTURE IN THE DRYWELL

a. The malfunctions for the stream line rupture will insert when the Mode Switch is taken to SHUTDOWN SS304.194 CR304.103 Key Parameter Response: Rising DW pressure and temperature.

Key Expected Alarms:

3-B-54 (CONTAINMENT SPRAY PERMISSIVE), 4

-B-35 (DRYWELL

-TORUS HI PRESS)

BOP When DW pressure reaches 1.84 psig, announces EOP entry conditions Auto Actions:

ECCS Initiation CRS Enters C.5

-1200 (PRIMARY CONTAINMENT CONTROL)

NOTE: The LPCI Initiation Bypass will not work for the first Division of RHR that is used for Containment Sprays Manually delete the override for the 2nd Division of RHR that is placed in service

. BOP SS314.120 CR314.124 Starts all available Drywell Cooling IAW C.5

-3503 (DEFEAT DW COOLER TRIPS)

BOOTH INST Places RHR in Torus Sprays IAW C.5

-3502 (CONTAINMENT SPRAY)

SS314.119 CR314.123 Bypass' 2/3 Core Height interlock Bypass' LPCI initiation

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-G-RM-01. SCENARIO TIME

-LINE: SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Announces failure of LPCI Initiation Bypass Opens Torus Cooling/Spray valves on the opposite division of RHR Recognizes that DW pressure is still rising once Torus sprays are in service.

Verifies Recirc Pumps are tripped Places all Drywell Fan controls switches in OFF BOP Places RHR in DW Sprays IAW C.5

-3502 (CONTAINMENT SPRAY)

Opens DW Spray INBOARD CT-30 When Drywell pressure reaches 12 psig, then initiate Drywell sprays to prevent Emergency Depressurization.

Opens DW Spray OUTBOARD Before Drywell and Torus Pressure reach 0 psig, terminate drywell sprays.

14. SCENARIO TERMINATION FLOOR INST The scenario may be terminated when Drywell sprays have been initiated and Drywell pressure is <12 psig.

Crew: Remain in simulator for potential questions from evaluator.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew: No discussion of scenario or erasing of procedure marking is allowed.

End the scenario by placing the simulator in FREEZE.

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-G-RM-01. SIMULATOR INPUT

SUMMARY

Code Description Event Trigger Delay(s) Ramp Final Value MALFUNCTIONS (Allow Tracking Off)

RR09D 12 Recirc Pump Runaway 10 60 0 AP03D D SRV Leaking 5 00:05:00 70 0 AP01D D SRV Stuck OPEN 6 Active InActive AP01D D SRV Stuck OPEN (Deletes in 1 Second) 7 Active InActive MS04A Main Steam Line Rupture in the Drywell 7 00:02:00 00:03:00 100 0 CH02_045 Control Rod 14

-23 Stuck 50 Active InActive CH02_045 Control Rod 14

-23 Stuck (Deletes in 1 Second) 1 Active InActive REMOTES FW02 FW-7-2 Condensate Pump Discharge Valve 50 10 1 0 FW02 FW-7-2 Condensate Pump Discharge Valve 2 100 10 ED70 MCC-131 Supply Breaker 4 OPEN 00:00:00 QF107502 Rev. 4 (FP

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-G-RM-01. Code Description Event Trigger Delay(s) Ramp Final Value OVERRIDES 01-D103-01 Div 2 Containment Spray LPCI Bypass 50 False False 01-S089-01 Div 1 Containment Spray LPCI Bypass 50 False False Event Trigger Definitions:

Code Description Event Trigger ZACHDRWP>.7 Drive Water Header Pressure

> 280 psid 1 ZD_S1SHD Mode Switch to SHUTDOWN 7 nijaprm(1)>42 ZD_MAAUT(2)

Power >42% and 12 Recirc in Raise 10 QF107502 Rev. 4 (FP

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-G-RM-01. Attach the following site

-specific information as necessary:

Simulator Set

-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log Historical Record:

1. New Create for the 201 6 ILT NRC Exam

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