Text

2013 Monticello Nuclear Generating Plant Initial License Examination Administered Scenarios
	ML13057A150
Person / Time
Site:	Monticello
Issue date:	01/29/2013
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	; Xcel Energy
References
	Download: ML13057A150 (88)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 1 Op-Test No.: MNGP 2013301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Power 11 Core Spray Pump OOC 12 Service Water Pump OOC Turnover: Perform RB/Torus Vacuum Breaker Test Event Malfunction No. Event Type* Event No. Description 1 C-04-B19 N / TS BOP performs RB/Torus Vacuum Breaker Test. The BOP / SRO second vacuum breaker will fail open.

2 CH01_023 I / R / TS Control Rod 18-15 Drifts OUT. The OATC will be successful OATC / SRO inserting the control rod and reducing Rx power < 100%.

3 SW01A C The running RBCCW pump will trip and the standby pump BOP / SRO will fail to auto start. The BOP will be successful in manually starting the standby pump.

4 ED05E C Bus 15 will lockout resulting in a loss of the running CRD BOP/ OATC pump. The OATC will be successful starting the standby

/ SRO pump. The BOP will take actions for loss of Bus 15.

5 CH08B C While the BOP is taking actions for the loss of Bus 15, the OATC / SRO remaining CRD pump will trip resulting in a complete loss of CRD and requiring a reactor scram.

6 FW16A/B, HP03, C (Post) A complete loss of high pressure feed will occur following RC03 CREW the scram requiring alternate level control actions.

7 RR01B, RR03B M A LOCA will begin in the Drywell which will drive RPV level Crew to lower. Alternate level control actions will be unsuccessful which will require the crew to perform an Emergency Depressurization.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal (1/set): E1 Malfunction(s) after EOP (1-2): E6 OATC Reactivity (1/set): E2 Abnormal Events (2-4): E2, E3, E4, E5 BOP I/C (4/set): E3, E4 Major Transient(s) /E-Plan entry (1-2): E7 OATC I/C (4/set): E2, E4 EOPs (1-2): 1100 & 2002 SRO-I I/C (4/set incl. 2 as OATC): E2 - E5 EOP Contingencies (0-2): 2 (ALC, ED) SRO Tech Spec (2/set): E1, E2 Critical Tasks (2-3): 2 ALL Major Transients (2/set): E7

QF-1075-02 Rev. 3 (FP-T-SAT-75)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-21E SEG TITLE: 2013 ILT NRC SCENARIO 1 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME: 60-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by: Roman Becker Instructor Date Reviewed by:

Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Roman Becker Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 3 of 22 Guide Requirements This Scenario evaluation has been written for the 2013 ILT NRC Exam.

Goal of Once this exam is complete and exam security is relaxed, this SEG should Training: be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

LOR Crew development

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

1. Completion of the MT-ILT Training Program, or Prerequisites: 2. Completion of the SRO Certification Program, or

3. Currently enrolled in the LOR Training Program

1. Full Scope Simulator Training 2. MTF-7100-051 (Attendance Record) or LMS Equivalent Resources: 3. 3139 (Control Room Shift Turnover Checklist)

4. 3140 (Shift Supervisors Office Shift Turnover Checklist)

5. Marked up copy of Test 0141 with LCO tracking module & PJB

6. Lead Instructor - Crew Turnover Brief paperwork Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 4 of 22

1. Test 0141

References:

2. T.S. 3.6.1.6

3. ARP 5-A-27 (Rod Drift)

4. ARP 5-A-3 (Rod Withdraw Block)

5. ARP 5-A-14 (APRM Alarm)

6. ARP 5-A-51 (RBM HI/INOP)

7. C.4-B.01.03.C (Control Rod Drifting)

8. B.01.03-05.G.2 (HCU Isolation)

9. B.01.03-05.H.10 (Rod Drift Out procedure)

10. TS LCO 3.1.3

11. ARP 6-B-32 (RBCCW Low Disch Pres)

12. C.4-B.02.05A (Loss of RBCCW)

13. ARP 8-B-18 (NO. 15 4160V Bus Lockout)

14. ARP 5-B-17 (Charging Water Lo Press)

15. C.4-B.09.06-C (Loss of 15 Bus)

16. C.4-B.01.03.A (Loss of CRD Flow)

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.5-2002 (Emergency Depressurization)

22. C.5-3203 (Use of Alternate Injection Systems for RPV Makeup)

23. C.5-3204 (RPV makeup with CRD)

24. C.5-3502 (Containment Sprays)

25. C.5-3503 (Defeat Drywell Cooler Trips)

26. C.5-3208 (Bypass LPCI 5 Minute Timer)

27. B.03.04-05.H1-8 (Torus Cooling Hard Cards)

1. None Commitments:

The following methods are acceptable methods for examinee evaluation:

Evaluation

2013 ILT NRC Exam Process (NUREG 1021 & FP-T-SAT-72)

Method:

MT-ILT (MNGP ILT Program Description)

M-9700 (SRO Certification Program Description)

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

Not Applicable to Evaluation Scenarios Operating Experience:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 5 of 22 Initiating Event with Core Damage Frequency:

Related PRA LOCA with Loss of High Pressure Injection Systems Information:

Important Components / Accident Class:

Class 1A - Accident sequence involving loss of inventory makeup in which reactor pressure remains high.

Important Operator Actions with Task Number:

XRPVBLDWNY - Failure to Emergency Depressurize TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

Apply administrative requirements for Tech Spec Section 3.6 and Bases to SS299.354 5-7 Containment Systems SS315.167 Direct the response to a Control Rod Drifting 5-7 Apply administrative requirements for Tech Spec Section 3.1 and Bases to Reactivity SS299.349 5-7 Control Systems SS315.107 Supervise response to a loss of RBCCW flow 5-7 SS315.140 Supervise response to loss of Bus 15 or Bus 16 5-7 SS315.102 Supervise response to a loss of CRD pump flow 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 Implement the response for a small break LOCA or loss of high pressure injection where RPV level can NOT be maintained above TAF and RPV blowdown is required SS304.226 5-7 to recover level above TAF with low pressure systems and/or alternate coolant injection systems.

RO Tasks:

CR299.356 Apply Tech Spec Section 3.6 and Bases to Containment Systems 1-5 CR200.226 Respond to a drifting control rod 1-4 CR299.351 Apply Tech Spec Section 3.1 and Bases to Reactivity Control Systems 5 CR200.152 Perform the procedure for a Loss of RBCCW Flow 1-4 CR200.184 Perform the procedure for a loss of BUS 15 or 16 1-4 CR200.147 Perform the procedure for a loss of CRD pump flow 1-4 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a Reactor Scram 1-4 Perform actions for a small break LOCA or loss of high pressure injection where 1-4 RPV level can NOT be maintained above TAF and RPV blowdown is required to CR304.139 recover level above TAF with low pressure systems and/or alternate coolant injection systems.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 6 of 22 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. RB to Torus Vacuum Breaker fails OPEN

2. Control Rod drifts out (SV-122 failure)

3. RBCCW Pump trip

4. Bus 15 Lockout

5. CRD Pump trip After EOP Entry:

1. Loss of High Pressure Feed (Reactor Feed Pumps, HPCI and RCIC)

Abnormal Events:

1. Control Rod Drifting

2. Loss of RBCCW Flow

3. Loss of Bus 15

4. Loss of CRD Flow Major Transients:

1. LOCA requiring Emergency Depressurization Critical Tasks:

1. CT 1: Scram the reactor when no CRD pump is running and the second accumulator low pressure alarm is received.

2. CT 22: When RPV water level can NOT be maintained >-149, Emergency Depressurize the reactor.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 7 of 22 SCENARIO OVERVIEW:

SEQUENCE OF EVENTS:

Event 1: RB/Torus Vacuum Breaker Test (0141)

BOP performs Reactor Building to Torus Vacuum Breaker Test.

The second valve tested fails open which requires the CRS to declare the valve inoperable IAW TS 3.6.1.6.

Event 2: Control Rod 18-15 Drifts OUT

The selected control rod (18-15) will begin drifting out. This will require the OATC to take action to insert the control rod. Once inserted the control rod need to be electrically disarmed to remain at position 00.

The CRS will declare control rod 18-15 inoperable IAW TS 3.1.3 Event 3: Trip of 11 RBCCW Pump

11 RBCCW Pump will trip on overload and 12 RBCCW pump will fail to automatically start. This will require the BOP operator to manually start #12 RBCCW pump.

Event 4: Bus 15 LOCKOUT

Bus 15 will Lockout resulting in a loss of the running CRD Pump. The OATC will be required to take action to start 12 CRD pump and restore CRD parameters.

While the BOP operator is taking actions for the loss of 15 Bus, the remaining CRD pump will trip resulting in a complete loss of CRD flow.

Event 5: Loss of CRD requiring a reactor scram

The complete loss of CRD flow will require the crew to insert a reactor scram.

Following the scram a complete loss of high pressure feed will occur.

Event 6: Loss of High Pressure Feed requiring Alternate RPV Level Control

A loss of high pressure feed will occur and the crew will be unable to restart Reactor Feed pumps, HPCI or RCIC.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 8 of 22 Event 7: Alt Level Control with a LOCA requiring Emergency Depressurization

While in alternate level control a LOCA will continue to lower RPV water level.

Eventually RPV water level will lower below TAF and require the crew to perform an Emergency Depressurization. Low pressure injections systems will be used to restore level.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 9 of 22 NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

1. INITIAL CONDITIONS (IC):

a. Mode: 1

b. Present Power Level: 100%

c. XCEL System Condition: Green

d. Plant CDF: Green

e. Electrical lineup - 2R.

f. Fuel Pool Status: Green, 79.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to boil

g. Generator Output: ~605 MWe

h. Staffing: Normal Weekday Dayshift

i. Planned Shift Activities: Test 0141

j. The following equipment is OOS:

1) 11 Core Spray Pump for motor replacement.

a) LCO 3.5.1 is NOT met b) Condition B was entered at 0600 yesterday c) Required Action B.1 is due in 7 Days

2) 12 Service Water Pump for scheduled maintenance

2. SIMULATOR SET UP BOOTH a. Reset the simulator to IC-281 (PW: mallard1) and INST place in RUN. Verify the correct malfunctions, remotes, overrides and event triggers are loaded as listed in the Simulator Input Summary page(s).

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 10 of 22 SCENARIO TIME-LINE:

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

b. Insert Manual Trigger 30 to load simulator initial conditions and preloaded malfunctions.

c. Tag out 11 Core Spray Pump as follows:

1) Place its hand switch in PTL.

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

3) Verify its GREEN light is OFF.

4) Hang a PROTECTED EQUIPMENT sign on the B Core Spray system.

d. Tag out 12 Service Water Pump as follows:

1) Place hand switch in NORMAL-AFTER-STOP

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

3) Verify its GREEN light is OFF.

e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) Marked up copy of Test 0141

3) LCO Tracking Module

4) Two stopwatches

f. ENSURE Cross Flow is ENABLED on PCS as follows:

1) Verify computer points CFW966-CFW969 are set to ENABLED

2) ENSURE Remote PO03 (CROSSFLOW DISABLED/ENABLED) is set to ENABLED Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 11 of 22 SCENARIO TIME-LINE:

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

g. Verify the status board is updated IAW Section 1

h. Complete the Simulator Setup Checklist

3. SIMULATOR PRE-BRIEF:

FLOOR a. REVIEW the scenario initial conditions as listed in INST 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 Crew Performs walk down of control boards and reviews control boards prior to starting the shift brief. turnover checklists.

4. SHIFT BRIEF

a. 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). 12 Service Water Pump is tagged out for scheduled maintenance 4). All other systems in Turbine building are normal.

b. Role Play as necessary. Extra out plant operator.

1) Nothing to add.

c. Role Play as necessary. Rx Building status:

1) 11 Core Spray Pump is tagged out CRS Crew assumes the duty.

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 12 of 22 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 5. RB/Torus Vacuum Breaker Test BOP Performs Test 0141 (Reactor Building to Torus Vacuum Breaker Operability Check)

a. DPIS readings for Step 1 are provided. Verifies DPIS 2572 and 2573 are reading less than 0. (Step 1)

b. Respond as RBO that DWV-8-2 is closed Verifies locally DWV-8-2 is CLOSED (Step 2)

Open/Close and time AO-2379. (14 seconds) (Step 3)

c. Respond as RBO that DWV-8-1 is closed Verifies locally DWV-8-1 is CLOSED (Step 4)

BOOTH d. When AO-2380 is taken to OPEN, verify Event Open/Close and time AO-2380. (11 seconds OPEN) (Step 5)

INST Trigger 28 goes active. This will prevent AO-2380 from closing once opened.

NOTE: AO-2380 should auto close when the switch is BOP Reports to the CRS that AO-2380 will NOT close.

released.

e. If notified as Engineering about IST requirements,

May recognize IST requirements not met acknowledge the notification

f. Role Play Ops Mgr as necessary for new LCO. CRS

Evaluates T.S. 3.6.1.6 as NOT met and enters Condition A.

SS299.354 Will notify the Plant Mgr and NRC Resident. CR299.356 o A.1 is a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to close the Vacuum Breaker.

Event 2 6. Rod Drift OUT BOOTH a. When directed by the lead evaluator, INST insert MANUAL TRIGGER 1,and verify the following malfunction goes active:

1) CH01_023 Control Rod 18-15 Drift OUT Key Parameter Response: Control Rod 18-15 drifting out and reactor power rising above 100%

Key Expected Alarms: 5-A-27 (Rod Drift), 5-A-3 (Rod Withdraw Block), 5-A-14 (APRM Alarm), 5-A-51 (RBM HI/INOP.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 13 of 22 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Automatic Actions: None OATC Takes actions IAW C.4-B.01.03.C (Control Rod Drifting)

CR200.226

Take ROD SELECT POWER SWITCH to OFF and back to ON BOOTH b. Once the control rod is fully inserted, the OATC

Reselect drifting rod AND insert to position 00 and INST will need to hold the rod in at position 00 or the may release switch to check if the drifting is clear.

rod will again drift out.

c. If asked about CRD Pump Bypass Flow, Role SS315.167

Notifies CRS Play as the RB Operator, wait 2 minutes and report that flow is 30 gpm.

d. If asked to check out HCU, state that SV-122 is

Verify proper CRD System parameters hot to the touch.

FLOOR NOTE: Depending on how long it takes to perform the

Verify core thermal power and margins to thermal INST immediate actions, reactor power may peak at 108%. limits have not been exceeded

e. Acknowledge as Nuclear Engineering about the

Notify Supervisor Engineer (Nuclear) rod drift and power spike. State that you will assemble a team and investigate immediately.

Refer to B.01.03-05.H.10 (Rod Drift Out procedure) and B.01.03-05.G.2 (HCU Isolation).

CRS Evaluates TS LCO 3.1.3 as NOT met and enters Condition C.

SS299.349 CR299.351

Required action C.1 (Insert rod) is met

Required action C.2 (Disarm rod) is due in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 14 of 22 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS BOOTH f. If asked to electrically and/or hydraulically isolate

May direct the HCU to be electrically and/or hydraulically INST the HCU, wait 1 minute, and DELETE CH01_023. disarmed Report the HCU is electrically and/or electrically isolated.

g. Once the rod is inserted, TS are addressed and at the discretion of the Lead Evaluator then move on to the next event.

NOTE: The B Manual actions are not required for evaluation.

Event 3 7. #11 RBCCW Pump Trip BOOTH a. When directed by the Lead Examiner, insert INST MANUAL TRIGGER 3

1) Verify the following Malfunction goes active:

SW01A, #11 RBCCW Pump Trip Key Parameter Response: #11 RBCCW Pump trips and the Standby

12 RBCCW Pump fails to auto start.

Key Expected Alarms: 6-B-32 (RBCCW LOW DISCH PRES)

Automatic Actions: None BOP Takes action IAW C.4-B.02.05A (Loss of RBCCW)

CR200.152

Verify a RBCCW pump is running o Notices that #12 RBCCW Pump failed to auto start and manually starts the pump

b. When notified to investigate, wait 2 minutes and

Notifies Reactor Building and/or Turbine Building report as the Outplant operator that the breaker Operator(s) to investigate the cause of the trip.

for #11 RBCCW pump has tripped on overcurrent and that there is an acrid odor near the breaker.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 15 of 22 SCENARIO TIME-LINE:

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

c. Depending on how rapidly the BOP starts #12

Notifies Engineering and/or Maintenance of the failure of 11 RBCCW Pump, RWCU may or may not isolate on RBCCW Pump and the failure of 12 RBCCW Pump to auto high temperature. start.

BOOTH d. If notified, acknowledge the report.

Verifies RWCU isolates on high temperature INST NOTE: This SEG is NOT validated for RWCU restoration.

FLOOR Once the Loss of RBCCW actions are taken and at the CRS Notifies Ops Management and performs crew brief.

INST discretion of the lead evaluator, MOVE ON TO THE NEXT SS315.107 EVENT.

Event 4 8. BUS 15 LOCKOUT BOOTH a. When directed by the Lead Examiner, insert INST MANUAL TRIGGER 5

1) Verify the following Malfunction goes active:

ED05E, #15 BUS LOCKOUT.

Key Parameter Response: No voltage on 15 Bus, loss of 1/2 control room lighting, and loss of a CRD Pump.

Key Expected Alarms: 8-B-18 (NO. 15 4160V BUS LOCKOUT), 5-B-17 (CHARGING WATER LO PRESS)

Automatic Actions: None BOP Takes actions IAW C.4-B.09.06-C (Loss of 15 Bus)

SS315.140

Notifies CRS CR200.184

Determines a LOCKOUT exists on 15 Bus OATC Takes action IAW C.4-B.01.03.A (Loss of CRD Flow)

SS315.102

Notifies CRS and starts #12 CRD Pump CR200.147 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 16 of 22 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS C.4-B.09.06-C actions continued BOOTH b. When called as the Turbine Building Operator to BOP

Determines 11 EDG is without cooling water and INST cut in cooling to 11 EDG, wait one minute and dispatches Turbine Building Operator to cut in cooling insert Manual Trigger 7. Report SW cooling is water.

supplying 11 EDG.

Places the following switches in PULL-TO-LOCK BOOTH c. When this switch is taken to PTL, verify Event o 152-511/CS (1AR TRANS TO 15 BUS)

INST Trigger 22 goes active. This will initiate a trip of

12 CRD pump and require a reactor scram for a complete loss of CRD o 152-502/CS (11 STBY DG TO 15 BUS)

Event 5 9. Loss of CRD & Reactor Scram: CRS Directs actions IAW C.4-B.01.03.A (Loss of CRD Flow)

NOTE: Based on the complete loss of CRD pumps with no

If no CRD flow is available then insert a reactor scram possibility of restoration, the CRS may NOT wait until the when the second accumulator low pressure alarm is second accumulator alarm is received. received.

CT 1 Scram the reactor when no CRD pump is running and CRS Directs action IAW C.4-K (IMMEDIATE REACTOR SS315.164 SHUTDOWN) the second accumulator low pressure alarm is CR200.208 received.

OATC

Reduce recirculation flow to minimum and insert a reactor scram using the scram pushbuttons OATC Takes actions IAW C.4-A (Reactor Scram) PART A:

BOOTH a. Verify Event Trigger 26 goes active when the SS315.101

Place Mode Switch in SHUTDOWN.

INST Mode switch is placed in SHUTDOWN. This will CR200.146 initiate the following:

1) Trip of RFPs after 5 and 10 second delays. o Verify all Control Rods are inserted to or beyond position 04.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 17 of 22 SCENARIO TIME-LINE:

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

2) A small break LOCA on a 2 minute ramp after

Provides scram script to CRS. Reports RPV less than 9 a 2 minute delay. EOP entry condition.

Controls Reactor water level between +9 and +48 inches.

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 o Close both Main FW Reg Valves o Close MO-1133 and MO-1134 (HP Feedwater Line Block 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 BOP Takes actions IAW C.4-A (Reactor Scram) PART B:

Plant page that a Reactor Scram has occurred.

Open Main Generator output breakers 8N7 & 8N8.

Trip the Main Turbine.

NOTE: The remaining BOP actions in C.4-A may NOT be

Verify the Generator Field Breaker Open.

performed depending on when the LOCA is recognized.

Start the Turbine Aux Oil Pump.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 18 of 22 SCENARIO TIME-LINE:

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

Verify Turbine Exhaust Hood Sprays in service.

Start the Turbine Bearing Lift Pumps

Verify Main Steam Pressure Control or Low-Low Set is controlling Reactor Pressure.

At C-25, Place the POST SCRAM switch in ON and verify all available Drywell Recirculation Fans are operating

Verify 3300 gpm through each operating Feed Pump

Verify Auxiliary Oil Pump running on any non-operating Feed Pump

Verify 3000 gpm through each operating Condensate Pump Event 6 10. Loss of High Pressure Feed / Alternate RPV Level CRS Directs performance of C.5-1100 (RPV Control)

Control

a. Role Play in-plant operators as necessary. There OATC

Recognizes the loss of both Feed Pumps is no apparent cause for the loss of the Feed Pumps.

Attempts to restart the Feed Pumps

Notifies CRS that Feed Pumps will not start.

CRS Directs RPV level control using HPCI and/or RCIC NOTE: If these start automatically they will still trip. OATC

Attempts to start HPCI and RCIC NOTE: Both systems are set to trip when flow rises. They

Notifies CRS that HPCI and RCIC both tripped on will trip on high exhaust pressure complications from the high exhaust pressure.

LOCA.

CRS Direct Alternate Level control Actions OATC/

Inhibits ADS BOP Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 19 of 22 SCENARIO TIME-LINE:

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

Starts a SBLC pump for injection IAW C.5-3203 BOP (Use of Alternate Injection Systems for RPV Makeup) o Verifies injection o Adequately monitors and reports RPV level and Pressure, both values and trends.

Event 7 11. LOCA in Primary Containment (Drywell): BOP Reports Drywell pressure rising

Reports EOP entry conditions.

o DW pressure, DW Temp and Torus temp NOTE: Containment Spray/Cooling actions may not be CRS Directs performance of C.5-1200 (PC Control) taken if the crew prioritizes RPV water level.

Start Torus sprays

Start all available Torus cooling

Spray the Drywell BOP

Performs C.5 1200 actions

Places Torus Sprays in service IAW C.5-3502 (Containment Sprays):

o Verifies RHR Pumps running o Takes Cont Spray/Cooling LPCI Initiation Bypass (B) to BYPASS o Opens MO-2007, 2011, & 2009 (B Loop) o Verifies LPCI Inject Outboard Valves are closed; MO-2012 and MO-2013.

BOP

Initiates Containment Cooling Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 20 of 22 SCENARIO TIME-LINE:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS o RHRSW Outlet valve controller set 20%

o Place HX Bypass in CLOSE o ECCS Load Shed to MANUAL OVERRIDE o Start RHRSW Pump(s) o Adjust flow to 3500 gpm per pump

Start all available drywell cooling IAW C.5-3503 (Defeat Drywell Cooler Trips) o Place all D/W fan control switches to OFF o Open Knife switch KS3100 o Verify fan inlet dampers are in AUTO o Place all D/W fan control switches to ON o OPEN associated fan disch dampers BOP

Initiates Drywell Spray IAW C.5-3502 (Containment Sprays):

o Open Drywell Spray Outboard MO-2021 o Open Drywell Spray Inboard MO-2023 o Close Torus Cooling MO-2009 Event 7 12. Alternate RPV Level Control / Emergency CRS Verifies two or more Injection Subsystems lined up with CONT Blowdown: SS304.226 CR304.139 pumps running.

CT-22 When RPV water level can NOT be maintained When RPV level is < -126 inches and prior to -149 inches, directs

>-149, Emergency Depressurize the reactor. performance of C.5-2002 (Emergency RPV Depressurization)

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 21 of 22 SCENARIO TIME-LINE:

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

Verifies Torus level > -5.9 ft.

Directs opening of all 3 ADS SRVs.

Directs RPV Level restoration BOP

Verifies that both Core Spray Subsystems and LPCI Pumps are available for injection BOOTH a. Verify Event Trigger 20 goes active when A SRV BOP/

Opens 3 ADS SRVs INST Handswitch is taken to Open OATC

1) Verify that Malfunction RR03B (Large Line

Monitor and report RPV level values and trends Break) goes active at 3% severity.

BOP

Controls RPV injection from RHR.

Opens Knife Switch to Bypass LPCI 5 Minute Timer using C.5-3208

Throttles MO-2013.

May divert LPCI flow using B.03.04-05.H (Torus Cooling Hard Cards)

BOP

Controls RPV injection from Core Spray.

o Throttles MO-1754 OATC

Controls RPV injection from the Condensate system.

13. SCENARIO TERMINATION FLOOR a. The scenario may be terminated when Emergency INST Depressurization has been performed OR RPV water level is recovered above TAF.

b. The scenario may be also terminated at the Crew:

Remain in simulator for potential questions from evaluator.

discretion of lead instructor/evaluator Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

MT-ILT-21E (2013 ILT NRC Scenario 1) Rev. 0 Page 22 of 22 SCENARIO TIME-LINE:

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

c. End the scenario by placing the simulator in Crew:

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

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

Monticello NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 2 Op-Test No.: MNGP 2013 Examiners: ____________________________ Operators: _____________________________

Initial Conditions:

37% Power with plant startup in progress 1AR Transformer OOC 12 Service Water Pump OOC Turnover:

OATC to raise reactor power with recirc pumps to 40%

BOP to place B MFRV in service Event Malfunction No. Event Type* Event No. Description 1 None R - OATC OATC raises reactor power to 40% with recirc pumps 2

None N - BOP At 40%, the BOP will place the remaining MFRV in service.

3 C The RPV Flange will develop a leak. The BOP will take C-04-A35 BOP / SRO actions to stop the leak.

C & TS APRM 3 will fail upscale requiring the OATC to bypass the 4 NI14C OATC / CRS APRM. CRS will address TSs.

5 C - TS RCIC will inadvertently initiate requiring the BOP to secure RC02 BOP / SRO the system. The CRS will address Technical Specifications 6 SRV B will fail open. The BOP will take actions but the SRV AP01B C - BOP wont close. The BOP will recognize a scram is required.

The Crew will insert a scram and then the SRV will close.

MAJOR After the scram, a torus rupture will occur. The crew will 7 PC05 take actions to fill the torus but eventually will need to CREW perform an Emergency Depressurization.

8 When the scram is inserted, one control rod will fail to insert.

C - POST CH02_56 This will require the OATC to take additional abnormal OATC / SRO procedure actions to insert the control rod.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 6 BOP Normal (1/set): E2 Malfunction(s) after EOP (1-2): E8 OATC Reactivity (1/set): E1 Abnormal Events (2-4): E5, E6 BOP I/C (4/set): E3, E5, E6 Major Transient(s) /E-Plan entry (1-2): E7 OATC I/C (4/set): E4, E8 EOPs (1-2): 1200 & 2002 SRO-I I/C (4/set incl. 2 as OATC): E3 - E6, E8 EOP Contingencies (0-2): 1 (ED) SRO Tech Spec (2/set): E4, E5 Critical Tasks (2-3): 2 ALL Major Transients (2/set): E7

Monticello NRC EXAM Scenario 2 SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-22E SEG TITLE: 2013 ILT NRC SCENARIO 2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC SIMULATOR EVALUATION #: N/A TOTAL TIME: 60-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by: Roman Becker Instructor Date Reviewed by:

Instructor Date (Simulator Scenario Development Checklist.)

Validated by: Roman Becker Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

Training Supervision Date

Monticello NRC EXAM Scenario 2 Guide Requirements This Scenario evaluation has been written for the 2013 ILT NRC Exam.

Goal of Once this exam is complete and exam security is relaxed, this SEG should Training: be appropriate to use for the following activities:

Future ILT NRC / Audit Exam Evaluations

SRO Certification Evaluations

LOR Crew development