Text

2013 Monticello Nuclear Generating Plant Initial License Examination Proposed Scenarios
	ML13057A099
Person / Time
Site:	Monticello
Issue date:	01/29/2013
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	; Xcel Energy
References
	Download: ML13057A099 (86)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 1 Op-Test No.:

Examiners: ____________________________ Operators:

MNGP 2013301 Initial Conditions:

11 Core Spray Pump OOC 100% Power 12 Service Water Pump OOC Turnover:

Perform RB/Torus Vacuum Breaker Test Event No.

Malfunction No.

Event Type*

Event Description 1

C-04-B19 N / TS BOP / SRO BOP performs RB/Torus Vacuum Breaker Test. The second vacuum breaker will fail open.

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

3 SW01A C

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

4 ED05E C

BOP/ OATC

/ SRO Bus 15 will lockout resulting in a loss of the running CRD pump. The OATC will be successful starting the standby pump. The BOP will take actions for loss of Bus 15.

5 CH08B C

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

6 FW16A/B, HP03, RC03 C (Post)

CREW A complete loss of high pressure feed will occur following the scram requiring alternate level control actions.

7 RR01B, RR03B M

Crew A LOCA will begin in the Drywell which will drive RPV level 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:

Total Malfunctions (5-8): 6 Malfunction(s) after EOP (1-2): E6 Abnormal Events (2-4): E2, E3, E4, E5 Major Transient(s) /E-Plan entry (1-2): E7 EOPs (1-2): 1100 & 2002 EOP Contingencies (0-2): 2 (ALC, ED)

Critical Tasks (2-3): 3 ES-301-5 Quantitative attributes:

BOP Normal (1/set): E1 OATC Reactivity (1/set): E2 BOP I/C (4/set): E3, E4 OATC I/C (4/set): E2, E4 SRO-I I/C (4/set incl. 2 as OATC): E2 - E5 SRO Tech Spec (2/set): E1, E2 ALL Major Transients (2/set): E7

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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-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 (Simulator Scenario Development Checklist.)

Date Validated by:

Roman Becker Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2013 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 Evaluations

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 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.

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

6.

Lead Instructor - Crew Turnover Brief paperwork

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References:

1.

Test 0141

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)

Commitments:

1.

None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2013 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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Related PRA Information:

Initiating Event with Core Damage Frequency LOCA with Loss of High Pressure Injection Systems 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:

SS299.354 Apply administrative requirements for Tech Spec Section 3.6 and Bases to Containment Systems 5-7 SS315.167 Direct the response to a Control Rod Drifting 5-7 SS299.349 Apply administrative requirements for Tech Spec Section 3.1 and Bases to Reactivity Control Systems 5-7 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 SS304.226 Implement the response for a small break LOCA or loss of high pressure injection where RPV level can NOT 5-7 be maintained above TAF and RPV blowdown is required 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 CR304.139 Perform actions for a small break LOCA or loss of high pressure injection where RPV level can NOT 1-4 be maintained above TAF and RPV blowdown is required to recover level above TAF with low pressure systems and/or alternate coolant injection systems.

QUANTITATIVE ATTRIBUTES

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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

2.

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

CT-16

3.

Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate or a loss of adequate core cooling.

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

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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.

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.

Event 2: Control Rod 18-15 Drifts OUT

The CRS will declare control rod 18-15 inoperable IAW TS 3.1.3

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 3: Trip of 11 RBCCW Pump

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.

Event 4: Bus 15 LOCKOUT

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.

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

Event 5: Loss of CRD requiring a reactor scram

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

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

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

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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.

Event 7: Alt Level Control with a LOCA requiring Emergency Depressurization

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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: 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 INST

a. Reset the simulator to IC-281 (PW: mallard1) 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 30 to load simulator initial conditions and preloaded malfunctions.

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SCENARIO TIME-LINE:

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

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

g. Verify the status board is updated IAW Section 1

h. Complete the Simulator Setup Checklist

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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

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

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

CRS Crew assumes the duty.

Event 1

5.

BOP RB/Torus Vacuum Breaker Test 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)

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SCENARIO TIME-LINE:

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

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 INST

d.

When AO-2380 is taken to OPEN, verify Event Trigger 28 goes active. This will prevent AO-2380 from closing once opened.

Open/Close and time AO-2380. (11 seconds OPEN) (Step 5)

NOTE: AO-2380 should auto close when the switch is released.

BOP Reports to the CRS that AO-2380 will NOT close.

e.

If notified as Engineering about IST requirements, acknowledge the notification May recognize IST requirements not met

f.

Role Play Ops Mgr as necessary for new LCO.

Will notify the Plant Mgr and NRC Resident.

CRS SS299.354 CR299.356 Evaluates T.S. 3.6.1.6 as NOT met and enters Condition A.

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 INST

a.

When directed by the lead evaluator, 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.

Automatic Actions OATC

None 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

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SCENARIO TIME-LINE:

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

b.

Once the control rod is fully inserted, the OATC will need to hold the rod in at position 00 or the rod will again drift out.

Reselect drifting rod AND insert to position 00 and may release switch to check if the drifting is clear.

c.

If asked about CRD Pump Bypass Flow, Role Play as the RB Operator, wait 2 minutes and report that flow is 30 gpm.

SS315.167 Notifies CRS

d.

If asked to check out HCU, state that SV-122 is hot to the touch.

Verify proper CRD System parameters FLOOR INST NOTE: Depending on how long it takes to perform the immediate actions, reactor power may peak at 108%.

Verify core thermal power and margins to thermal limits have not been exceeded

e.

Acknowledge as Nuclear Engineering about the rod drift and power spike. State that you will assemble a team and investigate immediately.

Notify Supervisor Engineer (Nuclear)

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

CRS SS299.349 CR299.351 Evaluates TS LCO 3.1.3 as NOT met and enters Condition C.

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 BOOTH INST

f.

If asked to electrically and/or hydraulically isolate the HCU, wait 1 minute, and DELETE CH01_023.

Report the HCU is isolated.

May direct the HCU to be electrically and/or hydraulically disarmed

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.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3

7.

11 RBCCW Pump Trip BOOTH INST

a.

When directed by the Lead Examiner, insert 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 BOP

None 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 report as the Outplant operator that the breaker for #11 RBCCW pump has tripped on overcurrent and that there is an acrid odor near the breaker.

Notifies Reactor Building and/or Turbine Building Operator(s) to investigate the cause of the trip.

c.

Depending on how rapidly the BOP starts #12 RBCCW Pump, RWCU may or may not isolate on high temperature.

Notifies Engineering and/or Maintenance of the failure of 11 RBCCW Pump and the failure of 12 RBCCW Pump to auto start.

BOOTH INST

d.

If notified, acknowledge the report.

Verifies RWCU isolates on high temperature NOTE

This SEG is NOT validated for RWCU restoration.

FLOOR INST Once the Loss of RBCCW actions are taken and at the discretion of the lead evaluator, MOVE ON TO THE NEXT EVENT.

CRS SS315.107 Notifies Ops Management and performs crew brief.

Event 4

8.

BUS 15 LOCKOUT

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SCENARIO TIME-LINE:

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

a.

When directed by the Lead Examiner, insert 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 BOP

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

SS315.140 CR200.184 Notifies CRS Determines a LOCKOUT exists on 15 Bus OATC Takes action IAW C.4-B.01.03.A (Loss of CRD Flow)

SS315.102 CR200.147 Notifies CRS and starts #12 CRD Pump C.4-B.09.06-C actions continued BOOTH INST

b.

When called as the Turbine Building Operator to cut in cooling to 11 EDG, wait one minute and insert Manual Trigger 7. Report SW cooling is supplying 11 EDG.

BOP Determines 11 EDG is without cooling water and dispatches Turbine Building Operator to cut in cooling water.

Places the following switches in PULL-TO-LOCK BOOTH INST

c.

When this switch is taken to PTL, verify Event 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

152-511/CS (1AR TRANS TO 15 BUS) 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)

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE: Based on the complete loss of CRD pumps with no possibility of restoration, the CRS may NOT wait until the second accumulator alarm is received.

If no CRD flow is available then insert a reactor scram when the second accumulator low pressure alarm is received.

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

CRS SS315.164 CR200.208 Directs action IAW C.4-K (IMMEDIATE REACTOR SUTDOWN)

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 INST

a.

Verify Event Trigger 26 goes active when the Mode switch is placed in SHUTDOWN. This will initiate the following:

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

1) Trip of RFPs after 5 and 10 second delays.

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

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

Provides scram script to CRS. Reports RPV less than 9 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.

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

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 performed depending on when the LOCA is recognized.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

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.

CRS Loss of High Pressure Feed / Alternate RPV Level Control Directs performance of C.5-1100 (RPV Control)

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

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SCENARIO TIME-LINE:

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

a.

Role Play in-plant operators as necessary. There is no apparent cause for the loss of the Feed Pumps.

OATC Recognizes the loss of both 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 OATC

If these start automatically they will still trip.

Attempts to start HPCI and RCIC NOTE

Both systems are set to trip when flow rises. They will trip on high exhaust pressure complications from the LOCA.

Notifies CRS that HPCI and RCIC both tripped on high exhaust pressure.

CRS Direct Alternate Level control Actions CT-16 Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate or a loss of adequate core cooling.

OATC/

BOP Inhibits ADS OATC/

BOP Starts a SBLC pump for injection IAW C.5-3203 (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 CRS

Containment Spray/Cooling actions may not be taken if the crew prioritizes RPV water level.

Directs performance of C.5-1200 (PC Control)

Start Torus sprays Start all available Torus cooling

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

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SCENARIO TIME-LINE:

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

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

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SCENARIO TIME-LINE:

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

12.

CRS SS304.226 CR304.139 Alternate RPV Level Control / Emergency Blowdown:

Verifies two or more Injection Subsystems lined up with pumps running.

CT-22 When RPV water level can NOT be maintained

>-149, Emergency Depressurize the reactor.

When RPV level is < -126 inches and prior to -149 inches, directs performance of C.5-2002 (Emergency RPV Depressurization)

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 INST

a.

Verify Event Trigger 20 goes active when A SRV Handswitch is taken to Open BOP/

OATC Opens 3 ADS SRVs

1) Verify that Malfunction RR03B (Large Line Break) goes active at 3% severity.

Monitor and report RPV level values and trends BOP Controls RPV injection from RHR.

Opens Knife Switch to Bypass LPCI 5 Minute Timer using C.5-3208 Throttles MO-2013.

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

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SCENARIO TIME-LINE:

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

a.

The scenario may be terminated when Emergency Depressurization has been performed OR RPV water level is recovered above TAF.

b.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew:

Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

Crew:

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

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 2 Op-Test No.:

Examiners: ____________________________ Operators:

MNGP 2013301 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 No.

Malfunction No.

Event Type*

Event 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-04-A35 C

BOP / SRO The RPV Flange will develop a leak. The BOP will take actions to stop the leak.

4 C-05-B20 I - TS OATC / SRO A low condenser vacuum switch will fail with RPS failing to inset a 1/2 scram. The OATC will need to insert a 1/2 scram and the CRS will address Technical Specifications 5

RC02 C - TS BOP / SRO RCIC will inadvertently initiate requiring the BOP to secure the system. The CRS will address Technical Specifications 6

AP01B C - BOP SRV B will fail open. The BOP will take actions but the SRV wont close. The BOP will recognize a scram is required.

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

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

8 CH02_56 C - POST OATC / SRO When the scram is inserted, one control rod will fail to insert.

This will require the OATC to take additional abnormal procedure actions to insert the control rod.

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

Total Malfunctions (5-8): 6 Malfunction(s) after EOP (1-2): E8 Abnormal Events (2-4): E5, E6 Major Transient(s) /E-Plan entry (1-2): E7 EOPs (1-2): 1200 & 2002 EOP Contingencies (0-2): 1 (ED)

Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:

BOP Normal (1/set): E2 OATC Reactivity (1/set): E1 BOP I/C (4/set): E3, E5, E6 OATC I/C (4/set): E4, E8 SRO-I I/C (4/set incl. 2 as OATC): E3 - E6, E8 SRO Tech Spec (2/set): E4, E5 ALL Major Transients (2/set): E7

QF-1075-02 Rev. 3 (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-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 (Simulator Scenario Development Checklist.)

Date Validated by:

Roman Becker Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2013 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 Evaluations

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 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.

Form 2300 and Reactivity Maneuvering steps

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References:

1.

Form 2300 and Nuclear Engineers Reactivity Maneuvering Steps

2.

C.1 (STARTUP)

3.

B.05.07-05.D.4 (Place Remaining B Main FW Reg Valve CV-6-12B in Service)

4.

5-B-20 (Condenser Low Vacuum Scram Trip)

5.

TLCO 3.3.1.1

6.

4-A-14 (RCIC LOW FLOW)

7.

C.4-G (Inadvertent ECCS Initiation)

8.

TS 3.5.3

9.

C.4-B.03.03A (Stuck Open Relief valve)

10.

5-A-46 (SRV Open)

11.

C.4-K (Immediate Reactor Shutdown)

12.

C.4-A (Reactor Scram)

13.

C.5-1100 (RPV Control)

14.

6-B-9/10 (High Water Level In RHR Rooms)

15.

4-B-4 (Torus Hi-Low Level)

16.

4-B-19/24 (Torus Vacuum Breakers Open)

17.

5-A-49 (Radwaste Trouble)

18.

C.5-1200 (Primary Containment Control)

19.

C.5-3401 (Torus Water Level Makeup)

20.

C.5-1300 (Secondary Containment Control)

21.

C.5-2002 (Emergency Depressurization)

Commitments:

1.

None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2013 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 Stuck Open SRV Important Components / Accident Class Class V - Unisolated Torus Leak Important Operator Actions with Task Number XRPVBLDWNY - Failure to Emergency Depressurize FLOODRB16Y - Fail to flood RB within 1-6 hours after torus leak.

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS200.133 Direct Reactor Startup to Full Power IAW C.1 5-7 SS299.362 Apply administrative requirements of Technical Requirements Manual 5-7 SS315.160 Supervise response to inadvertent ECCS initiation 5-7 SS299.355 Apply administrative requirements for Tech Spec Section 3.5 and Bases to ECCS and RCIC 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 SS314.115 Supervise torus water level makeup 5-7 SS304.194 Implement primary containment control 5-7 RO Tasks:

CR200.127 Perform a power ascension after the reactor is on line 1-5 CR259.103 Place Remaining MAIN FW REG VALVE in service (A)(B) 1-4 CR299.364 Apply Requirements of Technical Requirements Manual 5

CR200.204 Perform the procedure for an inadvertent ECCS initiation 1-4 CR299.355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 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 CR314.119 Perform actions associated with Torus Water Level Makeup 1-4 CR304.145 Perform actions for a loss of inventory in the torus requiring RPV blowdown or anticipation of blowdown and depressurizing to the main condenser.

1-4

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QUANTITATIVE ATTRIBUTES Malfunctions Before EOP Entry:

1. RPV Flange Leak

2. Condenser Vacuum Switch failure

3. Inadvertent RCIC start

4. Stuck open SRV After EOP Entry:

1. Stuck Control Rod Abnormal Events

1. Inadvertent RCIC start

2. Stuck open SRV Major Transients

1. Torus Leak requiring RPV Blowdown Critical Tasks

1.

CT-6: When an SRV is stuck open and can NOT

2.

be closed then insert a manual reactor scram.

CT-26: When torus water level can NOT be maintained above -3.3, then scram and execute EMERGENCY DEPRESSURIZATION per C.5-2002.

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SCENARIO OVERVIEW:

SEQUENCE OF EVENTS

IAW C.1, Startup Procedure,Section VIII, Power Ascension and Form 2300 Reactivity Adjustment instructions from the Nuclear Engineer, Recirculation flow is increased to raise power from 37% to 40%.

Event 1: Normal power up with Recirc Event 1: Place the 2nd MFRV in service

IAW C.1, Startup Procedure,Section VIII, Power Ascension Step 17.a, and B.05.07-05, Reactor Level Control, the B MFRV is placed in service.

An annunciator will be received that indicates the RPV flange is leaking. The BOP will follow ARP guidance and take actions to clear the annunciator.

Event 3: RPV Flange Leak

Condenser Low-Vacuum switch fails. The annunciator alarms but the Channel A RPS logic fails to trip, which requires the OATC to insert a 1/2 scram on RPS A. The CRS will evaluate Tech Specs for the inoperable switch.

Event 4: Condenser Vacuum switch Failure

RCIC will inadvertently start requiring the BOP operator to take abnormal procedure actions to secure the system. The CRS will evaluate Tech Specs for inoperable RCIC.

Event 5: RCIC inadvertent initiation

SRV B will fail open. The BOP will take abnormal procedure actions but the valve will not close. This will require the crew to insert a manual scram. Once the scram is inserted the SRV will close and a Torus water leak will begin.

Event 6: SRV B fails open.

An unisolable leak will occur in the bottom of the Torus from the bay where B SRV was stuck open. This will eventually require the crew to perform an Emergency Depressurization.

Event 7: Unisolable Torus leak.

When the reactor scram is inserted from the stuck open SRV one control rod will fail to insert. This will require the OATC to perform additional actions in the scram procedure to insert the control rod.

Event 8: Control Rod 06-27 fails to insert

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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: 37%

c. XCEL System Condition: Green

d. Plant CDF: Yellow for the startup

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: ~195 MWe

h. Staffing: Normal for expected startup activities

i.

Planned Shift Activities: Continue Reactor Startup by raising power and placing the remaining MFRV in service.

j.

The following equipment is OOS:

1) 1AR Transformer for an Oil Leak

2) 12 Service Water Pump for motor repairs

2.

SIMULATOR SET UP BOOTH INST

a. Reset the simulator to IC-282 (PW: mallard2) 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 30 to load simulator initial conditions and preloaded malfunctions.

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SCENARIO TIME-LINE:

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

c. Tag out both of the 1AR Transformer hand switches 152-511/CS & 152-610/CS as follows:

1) Verify both hand switches are in PTL.

2) Hang CAUTION (yellow) cards on both hand switches

3) Verify the GREEN lights are OFF on both hand switches.

d. Tag out 12 Service Water Pump as follows:

1) Place its 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:

f. Turnover checklists (3139 & 3140)

g. Form 2300 and reactivity maneuvering steps

h. C.1 place kept to VIII.A.17.a

i.

ENSURE Cross Flow is DISABLED on PCS as follows:

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

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

j.

Verify the status board is updated IAW Section 1

k. Complete the Simulator Setup Checklist

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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

a.

Role Play as necessary. Turbine Building status:

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

2). A vessel d/p is highest @ 4.4 psid.

3). 12 Service Water Pump is tagged out for motor repairs 4). 1AR Transformer is tagged out for an oil leak

b.

Role Play as necessary. Extra out plant operator.

1) Nothing to add.

c.

Role Play as necessary. Rx Building status:

1) All systems in the Rx Bldg are normal.

CRS Crew assumes the duty.

Event 1

5.

Raise Reactor power to 40% with Recirc Pumps

a. Provide the following:

CRS Performs a Reactivity Manipulation Brief

1) 2300 (Reactivity Adjustment)

SS200.133 CRS directs the OATC to raise Recirc speed to achieve 40% reactor power IAW Reactivity maneuvering Steps and C.1 (Startup)

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SCENARIO TIME-LINE:

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

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

CR200.127 o

Maintains Flow parameters approximately equal o

Monitors the following parameters:

o Pump Speed o

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 o

Core Thermal Limits Event 2

6.

Place the B MFRV in service CRS Directs the BOP to place the B MFRV in service BOP CR259.103 Places B MFRV in service IAW B.05.07-05.D.4 (Place Remaining B MAIN FW REG VALVE CV-6-12B in Service).

Verifies MO-1134 is OPEN Verifies CV-6-12B bias (vertical scale) is zero or slightly negative Slowly opens CV-6-12B and observe output signal increasing (horizontal scale).

BOOTH INST

a.

Depending on how closely matched the scales are, the COND DEMIN SYSTEM TROUBLE alarm Monitor vessel level and FW flow as CV-6-12B When CV-6-12B horizontal scale matches the vertical scale

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES may be received. If so, insert MANUAL TRIGGER 11, wait one minute and respond as the TBO that it was an intermittent low flow alarm.

Place CV-6-12B controller in AUTO Event 3

7.

RPV Flange Seal Leak Alarm BOOTH INST

a.

When directed by the Lead Examiner, insert MANUAL TRIGGER 1

1) Verify Malfunction C-04-A35 goes active Key Parameter Response

Report of the Pressure Indicator reading from the Reactor Bldg.

Key Expected Alarms

4-A-35 (VESSEL FLANGE SEAL LEAK)

Auto Actions BOP

None Respond to annunciator and inform the CRS

b.

Role Play the operator being dispatched as necessary. PI 2-101 is reading 620 psig Dispatch an operator to report reading on PI 2-101 on C55

c.

Verify Event Trigger 28 goes true when Handswitch 16A-S48 is taken to open and Malfunction C-04-A35 is deletes 2 minutes later.

Place Handswitch 16A-S48, CV-2369 Reactor Flange Leakoff in the OPEN position (C-04)

Maintain Handswitch 16A-S48 in the OPEN position for one minute after the annunciator resets, then place 16A-S48 in CLOSE Event 4

8.

Condenser Vacuum Switch Failure BOOTH INST

a.

When directed by the lead evaluator, Insert MANUAL TRIGGER 3.

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SCENARIO TIME-LINE:

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

b.

Verify C-05-B20 MALFUNCTION (Annunciator) goes active:

Key Parameter Response

None Key Expected Alarms

5-B-20 (Condenser Low Vacuum Scram Trip)

Auto Actions OATC

None, RPS A fails to trip.

Responds to annunciator and reports to the CRS

c.

Evaluator prompt when the operator goes around back to C-15; 5A-K2A in C-15 is deenergized 5A-K2B, C, & D are all energized Crew Recognize 1/2 scram should have occurred and did NOT CRS Evaluates TLCO 3.3.1.1 as NOT met & enters Condition A SS299.362 CR299.364 Required Action A.2: Place associated trip system in Trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Provides crew brief Directs 1/2 scram be inserted on A RPS OATC Inserts 1/2 scram by depressing A manual scram pushbutton Event 5

9.

Inadvertent RCIC start.

a.

When directed by the Lead Examiner, insert MANUAL TRIGGER 5

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SCENARIO TIME-LINE:

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

1) Verify Malfunction RC02 goes active to cause an auto initiation of RCIC Key Parameter Response Crew

Pump speed rising.

Recognizes the RCIC start and informs CRS BOOTH INST Key Expected Alarms

4-A-14 (RCIC Low Flow)

Makes a plant announcement about RCIC in operation and about evacuation of the RCIC Room Auto Actions CRS SS315.160

RCIC starts and injects, Feed flow may reduce to compensate Directs BOP to use C.4-G (Inadvertent ECCS Initiation) and secure RCIC BOP C.4-G (Inadvertent ECCS Initiation Signal) actions:

CR200.204 Determines was caused by a spurious signal.

Depresses the RCIC Turbine Trip pushbutton.

b.

Role Play plant support personnel as necessary to acknowledge report.

Crew Notifies Management, RP and Single Point of Contact.

CRS Evaluates LCO 3.5.3 as NOT met and enters Condition A.

SS299.355 CR299.355 Required Action A.1: Verify HPCI is operable immediately.

This action can be performed by the crew checking the HPCI lineup and checking the logs.

Required Action A.2: Restore RCIC in 14 Days Event 6

10.

Stuck OPEN B SRV

a.

Insert Manual Trigger 7 and verify Malfunction AP01B goes active.

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SCENARIO TIME-LINE:

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

C-03 Amber light for B SRV will be ON.

MWe and B steam line flow will lower Key Expected Alarms

5-A-46 (SRV OPEN)

Auto Actions BOP

None Implement C.4-B.03.03.A (Stuck Open Relief Valve)

CR200.154 Place handswitch 2E-S4B for SRV B in OPEN and then return to the normal position.

Place handswitch 2E-S4B for SRV B in CLOSE.

Monitor and control Reactor pressure NOTE CRS SS315.109

Based on the initial low power to begin the scenario, the crew may not choose to lower power.

Direct Rapid Power Reduction when the SRV fails to close When the B SRV remains open, direct a manual scram of the reactor CT-6 When an SRV is stuck open and can NOT be closed then insert a manual reactor scram.

OATC When directed, manually scrams the reactor

11.

Immediate Reactor Shutdown CRS SS315.164 May direct reactor scram or an Immediate Reactor Shutdown IAW C.4.K (Immediate Reactor Shutdown)

OATC May reduce Recirc Flow to minimum CR200.208 Depresses pushbuttons for REACTOR SCRAM A and B

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES CRS SS315.101 Supervises response to a Reactor Scram OATC C.4-A (Reactor Scram) actions:

a.

When the Mode switch is placed in SHUTDOWN verify Event Trigger 24 goes active. This will close the stuck open SRV and initiate the Torus leak.

CR200.146 Place Mode Switch in SHUTDOWN.

The OATC may address the stuck rod before proceeding with the remaining C.4.A actions (See Event 8).

Verifies all Control Rods are inserted to or beyond position 04 and notices 1 Rod remains full out OATC Provides scram script to CRS and reports EOP entry condition RPV level less than 9 Controls Reactor water level between +9-48. When reactor 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.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Place DISCH VOL ISOL TEST switch in ISOL Place SDV HIGH WATER LEVEL BYPASS in BYPASS Reset the Scram using the SCRAM RESET switch Reset the Rod Drift alarms Evacuate personnel from the RB Floor and Equipment Drain Tank Room OATC Verify the SDV Vent and Drain Valves open Verify the accumulators recharge When Annunciator 5-B-30 (Disch Volume Tank Not Drained) IS RESET, Place SDV HIGH WATER LEVEL BYPASS in NORMAL BOP Starts performance of Part B of C.4.A Announce over the plant paging system that a Reactor Scram has occurred.

Open Main Generator output breakers 8N7 & 8N8.

NOTE

The remaining BOP actions may not be taken based on the Torus level priority.

Trip the Main Turbine.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

Verify Turbine Exhaust Hood Sprays in service.

Start the Turbine Bearing Lift Pumps (P-64A-F)

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

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 7

12.

Unisolable Torus leak BOOTH INST

a.

Verify Event Trigger 24 is active and verify Malfunction PC05 at 100%.

Key Parameter Response

Torus Level on LI-2996 (C-04) or PLR 7251A/B (C-03) lowering Key Expected Alarms

6-B-9/10 (High Water Level In RHR Rooms) 4-B-4 (Torus Hi-Low Level), 4-B-19/24 (Torus Vacuum Breakers Open) and 5-A-49 (Radwaste Trouble)

Auto Actions BOP OATC

Torus to Drywell Vacuum breakers begin to cycle Respond to annunciators

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SCENARIO TIME-LINE:

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

It takes 19 minutes to reach -3.3 ft which is the decision point for a Reactor Scram and Emergency depressurization Notify Rad Protection that a harsh environment or increase radiation environment may exist in the RHR rooms and that entry is required

13.

Unisolable Torus Leak/ EOP 1300 Actions NOTE BOP OATC

The RHR Room water Level is never reported as having reached Max Safe Level (15 inches) and the timeline of local reports allows the Torus water level to be the critical parameter.

Dispatches an operator to investigate BOOTH INST

a.

Role Play in-plant operator. When dispatched, WAIT 2 MINUTES then report that the water level is approximately 8 inches in both RHR rooms.

Receive the report from the plant and relay the information to the CRS.

Reports EOP 1300 Entry Condition of RHR Room water levels above 0 inches.

CRS Enters and directs actions from EOP1300 Secondary Containment Control BOOTH INST NOTE BOP OATC

Torus Level can be monitored on Insight File pct112.

Verify the Reactor Bldg Floor drain Sump Pump is running BOOTH INST

b.

Role Play in-plant operator. If asked to report the source of the leak, WAIT UNTIL Torus Water Level is -1 feet, then report that the Leak is from a weld at the ring header in Bay 4 Attempt to identify and isolate the source of the water CRS Monitor Area Water Levels approach to Max Safe

14.

SS304.194 Unisolable Torus Leak/ EOP 1200 Actions BOP Respond to 4-B-4, (Suppression Water Level Hi/Low)

Check LI-2996 on C-04 or PLR-7251A/B on C-03

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Identifies and reports the lowering trend NOTE

It takes approximately 3 minutes to reach -4 inches Torus water level Reports EOP 1200 Entry Condition when Torus water level (Narrow Range) is < -4 inches Monitors and reports Torus water level throughout CRS Enters and directs actions from EOP-1200 (Primary Containment Control)

SS314.115 Directs performance of C.5-3401 (Torus Water Level Makeup)

a.

Role Play the out-plant operator if assigned to perform C.5-3401: Wait 2 minutes and report that he must find boots as PPE for the water on the floor.

BOP CR314.119 May direct an in-plant operator to perform C.5-3401 steps for Core Spray and RHR. (May choose not to perform due to safety concerns)

Verifies the HPCI CST Suction, MO-2063 Open Opens the HPCI Pump Minimum Flow Valve CV-2065 Verifies the RCIC CST Suction, MO-2201 Open Opens the RCIC Pump Minimum Flow Valve CV-2104

15.

CRS Emergency Depressurization CRS May anticipate Blowdown per a C.5-1100 Override Statement and direct RPV pressure be lowered using the Turbine Bypass Valves CT 26 When torus water level can NOT be maintained above -3.3, then scram and execute EMERGENCY DEPRESSURIZATION CRS per C.5-2002.

When it is determined that Torus Water Level can NOT be maintained above -3.3 ft, Blowdown and enter EOP 2002.

CRS Recognizes when Torus Water Level can NOT be maintained above -3.3 ft Enters and directs EOP-2002 (Blowdown)

Verifies Torus level > -5.9 ft.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Directs that 3 ADS SRVs be opened BOP If directed to ANTICIPATE BLOWDOWN and lower RPV pressure using the Turbine Bypass Valves CR304.145 At C-07, places PRESS REG OVERRIDE in OPEN until both Bypass valves are open BOP Perform Emergency Depressurization When directed by CRS, place 3 ADS SRVs to OPEN Verifies that 3 ADS SRV have opened Monitor RPV Pressure and Level Event 8

16.

Control Rod 06-27 fails to insert Key Parameter Response

Control Rod remains at position 48 and RWM indicates one rod still out.

Key Expected Alarms

None Auto Actions OATC

None Identifies that Rod 06-27 did not fully insert

a.

When the OATC places the ROD MOVEMENT CONTROL switch to ROD IN to insert Rod 06-27, verify EVENT TRIGGER 28 goes active and MALFUNCTION CH02_056 DELETES.

Informs the CRS and performs actions to insert Control Rod 06-27 May reset the scram and insert the control rod

b.

Role Play the Reactor Bldg Operator as necessary and, as requested wait 1 minute and insert MANUAL TRIGGER 9 to close CRD-14 Direct an out-plant operator to manually close CRD-14

1) Verify REMOTE FUNCTION CH22 goes active to close CRD-14 Bypass the RWM

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Select and insert the full out rod

17.

SCENARIO TERMINATION

a.

The scenario may be terminated as follows:

1) Actions taken to insert all control Rods

2) Emergency Depressurization has been performed

b.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

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

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 3 Op-Test No.:

Examiners: ____________________________ Operators:

MNGP 2013301 Initial Conditions:

78% Power 1AR Transformer OOC HPCI OOC Turnover:

BOP to perform quarterly Bypass Valve Test Event No.

Malfunction No.

Event Type*

Event Description 1

TC07D N & TS BOP / CRS BOP will perform quarterly Bypass Valve Test. The second bypass valve will fail to open. The CRS will address TSs.

2 CH07B C

OATC The CRD Flow Control Valve will fail closed requiring the OATC to place the standby in service.

3 C-08-B01 C & TS BOP / CRS The 2R XFMR will develop a severe oil leak requiring the BOP to perform an emergency transfer to the 1R XFMR.

The CRS will address TSs.

4 ED05A C & R BOP / OATC

/ CRS A Bus 11 Lockout will occur requiring the BOP to take actions including for a Recirc Pump and Feed Pump Trip.

The OATC will insert control rods to exit Stability Region 2.

5 RX03 C

OATC / CRS While inserting control rods, neutron flux oscillations will occur requiring the OATC to insert a manual scram.

6 CH16 & CH19 MAJOR CREW When the reactor is scrammed, a Hydraulic ATWS will occur requiring the crew to take Failure to Scram actions.

7 SL01A/B C (POST)

OATC While taking Failure to Scram actions the first SBLC Pump will fail to start requiring the OATC to start the other pump.

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

Total Malfunctions (5-8): 5 Malfunction(s) after EOP (1-2): E7 Abnormal Events (2-4): E4, E5 Major Transient(s) /E-Plan entry (1-2): E6 EOPs (1-2): 1100 & 2007 EOP Contingencies (0-2): 1 (ATWS)

Critical Tasks (2-3): 3 ES-301-5 Quantitative attributes:

BOP Normal (1/set): E1 OATC Reactivity (1/set): E4 BOP I/C (4/set): E3, E4 OATC I/C (4/set): E2, E5, E7 SRO-I I/C (4/set incl. 2 as OATC): E2-E5 E7 SRO Tech Spec (2/set): E1, E3 ALL Major Transients (2/set): E6

QF-1075-02 Rev. 3 (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-23E SEG TITLE:

2013 ILT NRC SCENARIO 3 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Roman Becker Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2013 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 Evaluations

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 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.

Marked up copy of OPS-TRB-0570

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References:

1.

OSP-TRB-0570

2.

LCO 3.7.7

3.

5-B-41 (CRD Hi Temperature)

4.

B.01.03-05.E.4 (Placing the Standby CRD Flow Control Valve into Service)

5.

8-B-01 (No. 2R XFMR Trouble)

6.

B.09.06-05.E.1 (Transfer of Plant Buses From 2R to 1R - Emergency Method)

7.

LCO 3.8.1

8.

8-B-14 (NO. 11 4160V Bus Lockout)

9.

C.4-B.09.06.A (Loss Of Bus 11 Or Bus 12)

10.

C.4-B.01.04.A (Trip Of One Recirc Pump)

11.

C.4-B.06.05.A (Feedwater Pump Trip)

12.

C.4-B.05.01.02.A (Control Of Neutron Flux Oscillations)

13.

C.4-F (Rapid Power Reduction)

14.

5-A-38 (OPRM Alarm)

15.

5-A-45 (OPRM Trip)

16.

C.4.K (Immediate Reactor Shutdown)

17.

EOP 1100 (RPV Control)

18.

EOP 2007 (Failure to Scram)

19.

C.5-3301 (Defeat MSIV Low-Low Level Isolation)

20.

C.5-3205 (Prevent Core Spray injection)

21.

C.5-3101 (Alternate Rod Insertion)

22.

B.03.05-05.G.1 (SBLC Manual Initiation)

23.

Torus Cooling Hard Cards Commitments:

1.

None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2013 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 ATWS Important Components / Accident Class CRD Important Operator Actions with Task Number UH - Failure to control RPV water level in an ATWS scenario.

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS299.355 Apply administrative requirements for Tech Spec Section 3.7 and Bases to Plant Systems 5

SS299.358 Apply administrative requirements for Tech Spec Section 3.8 and Bases to Electrical Power Systems 5

SS315.138 Supervise response to loss of Bus 11 or Bus 12 5-7 SS315.103 Supervise response to a trip of one recirculation pump 5-7 SS315.119 Supervise response to control neutron flux oscillations 5-7 SS315.159 Supervise rapid power reduction 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS304.213 Implement the bases for RPV Control 5-7 SS304.201 Implement the response for a failure to scram 5-7 SS304.244 Implement the response during a high power ATWS with heat addition to torus requiring entry into level power control with RPV level controlled below -33 and RPV blowdown not required.

5-7 SS314.111 Supervise defeat of RPV low-low level isolation for MSIV closure 5-7 SS314.108 Supervise terminate and prevent 5-7 SS314.101 Supervise alternate rod insertion 5-7 RO Tasks:

CR299.357 Apply Tech Spec Section 3.7 and Bases to Plant Systems 5

CR201.111 Place the Standby CRD Flow Control Valve into Service 1-4 CR262.133 Transfer of Plant Buses From 2R to 1R using the Emergency Method 1-4 CR299.358 Apply Tech Spec Section 3.8 and Bases to Electrical Power Systems 5

CR200.182 Perform procedure for a loss of BUS 11 or 12 1-4 CR200.148 Perform the procedure for one recirculation pump trip 1-4 CR200.168 Perform the procedure for Control of Neutron Flux Oscillations 1-4 CR200.203 Perform the procedure for rapid power reduction 1-4 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR212.105 Manually Initiate the ATWS System 1-4 CR314.104 Perform actions associated with Failure to Scram 1-4 CR314.129 Perform actions during a high power ATWS with heat addition to torus requiring entry into level power control with RPV level controlled below -33 and RPV blowdown not required.

1-4 CR314.115 Defeat RPV Low-Low Level Isolation for MSIV Closure 1-4 CR314.112 Perform actions to Terminate and Prevent injection 1-4 CR314.105 Perform actions associated with Alternate Rod Insertion 1-4 CR211.106 Manually Initiate Standby Liquid Control System 1-4

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QUANTITATIVE ATTRIBUTES Malfunctions Before EOP Entry:

1. Stuck Closed Bypass Valve

2. CRD Flow Control Valve failure

3. 2R Transformer oil leak

4. Bus 11 Lockout After EOP Entry:

1. ARI Failure

2. SBLC Pump failure Abnormal Events

1. Emergency Transfer of plant power from the 2R to 1R transformer.

2. Loss of Bus 11

3. Trip of One Recirc Pump

4. Neutron Flux Oscillations Major Transients

1. Hydraulic ATWS Critical Tasks

1.

CT-8 LPRM HI or DOWNSCALE alarms in a wide area of the core that repeatedly alarm, then clear.

Scram the reactor in response to core oscillations as indicated by:

LPRM indications on the RBM ODA displays indicate oscillation.

APRM recorders indicate a peak-to-peak oscillation greater than 10% that is not attributable to pressure or Recirc flow control problems.

2. CT-46

3.

During failure to scram conditions with reactor power above 3.5%, terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.

CT-48

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.

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SCENARIO OVERVIEW:

SEQUENCE OF EVENTS

BOP operator will perform OPS-TRB-0570 (Quarterly Bypass Valve Test). The second Bypass valve will fail to open, stopping the test and requiring the CRS to evaluate Tech Specs.

Event 1: Exercise Main Turbine Bypass Valves Event 2: CRD Flow Control Valve fails closed

The CRD Flow Control Valve (CV-19A) will fail closed resulting in CRD high temperature alarms. The OATC will take action to transfer to the standby flow control valve.

A 2R Trouble alarm will be received. The Outplant operator will report a large oil leak on the transformer. This will require the BOP operator to perform an emergency transfer to the 1R transformer. The CRS will evaluate Tech Specs.

Event 3: 2R Trouble - Oil Leak

An 11 Bus lockout will occur requiring the BOP to take actions including actions for a trip of a recirc pump. The OATC will need to insert control rods to exit Stability Region 2 of the power to flow map.

Event 4: Bus 11 Lockout

While the OATC is inserting control rods for RPR neutron flux oscillations will begin.

This will require the OATC to insert a manual reactor scram.

Event 5: Neutron Flux Oscillations requiring a manual reactor scram

When the reactor is scrammed multiple control rods will fail to insert. The crew will take action IAW the Failure to Scram procedure to lower power and insert control rods.

Event 6: Hydraulic ATWS.

While the crew is taking failure to scram action the first SBLC pump that the OATC attempts to start will fail. The OATC will be successful in starting the second pump.

Event 7: SBLC Pump Failure.

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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: 78%

c. XCEL System Condition: Green

d. Plant CDF: Yellow for HPCI & 1AR

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: ~455 MWe

h. Staffing: Weekend Night Shift

i.

Planned Shift Activities: Main Turbine Bypass Valve Exercise Test.

j.

The following equipment is OOS:

1) 1AR Transformer for an Oil Leak

2) HPCI for Aux Oil pump repair.

a) LCO 3.5.1 is NOT met b) Condition J was entered at 0600 today c)

Required Action J.1 is complete d) Required Action J.2 is due in 14 days

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SCENARIO TIME-LINE:

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

2.

SIMULATOR SET UP BOOTH INST

a. Reset the simulator to IC-283 (PW: mallard3) 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 30 to load simulator initial conditions and preloaded malfunctions.

c. Tag out both of the 1AR Transformer hand switches 152-511/CS & 152-610/CS as follows:

1) Verify both hand switches are in PTL.

2) Hang CAUTION (yellow) cards on both hand switches

3) Verify the GREEN lights are OFF on both hand switches

d. Tag out HPCI as follows:

1) Verify the Aux Oil Pump hand switch in PTL, hang a CAUTION (yellow) card on the pump hand switch and verify its GREEN light is OFF.

2) Verify MO-2034 & MO-2035 are closed, hang CAUTION (yellow) cards on the valve hand switches and verify their GREEN lights are OFF on C-03 and the MIMIC.

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SCENARIO TIME-LINE:

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

3) Depressurize the HPCI steam line by opening CV-2043 (Steam Line Drain) until 0 psig is indicated.

4) Place a Protected Equipment Sign on C-04 for RCIC

e. Ensure the following are provided for the crew:

1) Turnover checklists (3139 & 3140)

2) LCO Tracking Module for HPCI

3) Marked up copy of OPS-TRB-0570

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

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

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

g. Verify the status board is updated IAW Section 1

h. Complete the Simulator Setup Checklist

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.

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SCENARIO TIME-LINE:

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

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). B vessel d/p is highest @ 5.7 psid.

3). 1AR Transformer is tagged out for an oil leak

b.

Role Play as necessary. Extra out plant operator.

1) Nothing to add.

c.

Role Play as necessary. Rx Building status:

1) HPCI is tagged out for Aux Oil pump repairs CRS Crew assumes the duty.

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

Event 1

5.

Main Turbine Bypass Valve Test CRS May perform refocus brief BOP Performs OSP-TRB-0570 (Exercise Main Turbine Bypass Valves)

BOOTH INST

a. Acknowledge report of changing radiological conditions.

Notifies RP of changing radiological conditions Notifies CRS of required LCO 3.7.7.A entry Selects BV-1 with BYPASS VALVE TEST switch, NOTE

Depending on how long BV-1 is OPEN; the receipt of 5-B-32 (Main Steam Line Leakage) will be expected based on difference in total steam flow and steam flow to the turbine.

Times BV-1 in the OPEN direction o

Expected cycle time 15-25 seconds Times BV-1 in the CLOSED direction o

Expected cycle time 15-25 seconds

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Selects BV-2 with BYPASS VALVE TEST switch Times BV-2 in the OPEN direction o

Recognizes that BV-2 will NOT open and notifies CRS BOOTH INST

b. Acknowledge BV-2 failure as Operations Management.

CRS Informs BOP to stop the test and evaluates LCO 3.7.7 as NOT met.

SS299.355 Enters Condition A CR299.357 Required Action A.1 - Restore BV-2 to operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Event 2

6.

The In-Service CRD Flow Control Valve fails BOOTH INST

a.

When directed by the lead instructor, insert Manual Trigger 1 and verify CH07B goes active Key Parameter Response

Reduced CRD cooling water flow Key Expected Alarm OATC

5-B-41 (CRD Hi Temperature)

Responds to annunciator and informs CRS NOTE

It will take several minutes for the alarm to come in.

Auto Actions

None

b.

If directed to investigate CRD temperatures, wait 2 minutes and report that many CRD temperatures are rising and that CRD 26-15 is in alarm. The highest reading temperature is 255°F.

Sends Reactor Building Operator to investigate CRD temperature recorder Recognizes CRD FCV failure CRS Directs performance of B.01.03-05.E.4 (Placing the Standby CRD Flow Control Valve into Service)

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SCENARIO TIME-LINE:

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

c.

When directed to report to the CRD FCV station to support shift of FCV, WAIT 1 minute and report you are standing by.

OATC CR201.111 Coordinates with Reactor Building Operator (RBO) and performs the following:

BOOTH INST

d.

When directed to OPEN CRD-18-2 and CRD 2, WAIT 1 minute then use Manual Trigger 3 to modify REMOTE FUNCTION CH17 to OPEN and report this action to the Control room.

Directs RBO to OPEN CRD-18-2 & 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-3-19B to 54-56 gpm Places CRD Flow Control in auto BOOTH INST

e.

When directed to CLOSE CRD-16-1 and CRD-18-1, WAIT 1 minute, then use Manual Trigger 5 to modify REMOTE FUNCTION CH16 to CLOSE and report this action to the Control room Closes CRD-16-1 & CRD-18-1

f.

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

Acknowledge annunciator 5-B-41 clear and informs Shift Supervision.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 3

7.

Oil leak on 2R / Emergency transfer to 1R BOOTH INST

a.

When directed by the Lead Examiner, insert Manual Trigger 7 and verify C-08-B01, 2TR Trouble goes active Key Parameter Response

None Key Expected Alarms

8-B-01 (No. 2R XFMR TROUBLE)

Auto Actions BOP

None Dispatch an operator to investigate from a distance.

NOTE

The following cue must make it clear that it is imperative to do the emergency transfer operation.

Verify that 2R Voltages appear normal BOOTH INST

b.

Role Play the dispatched operator: Wait 2 minutes and then report that a steady stream of oil is gushing out of 2R and a large pool of oil has already formed Relay information about the oil leak to the CRS and makes plant page to clear personnel from the area CRS Directs performance of B.09.06-05.E.1 (Transfer of Plant Buses From 2R to 1R - Emergency Method)

BOP CR262.133 Performs emergency closed bus transfer from 2R to 1R Verify 115KV system voltage is 117.4 KV or confirm that the 10TR/XFMR auto load tap changer is in service.

Bus 13 o

Place 152-302/CS to CLOSE o

Place 152-301/CS to TRIP Bus 14 o

Place 152-402/CS to CLOSE o

Place 152-401/CS to TRIP

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Bus 11 o

Place 152-102/CS to CLOSE o

Place 152-101/CS to TRIP Bus 12 BOOTH INST NOTE

Verify the BOP has opened the knife switch on C-31. If not, then DO NOT open 3N4 with the following actions.

o Place 152-202/CS to CLOSE o

Place 152-201/CS to TRIP BOOTH INST

c.

Role Play the equipment operator dispatched to open 3N4 as necessary. Wait 1 minutes and:

Open knife switch 16 on panel C-31

1) Activate Manual Trigger 9 Open 3N4 34.5KV Circuit Breaker

2) Verify Remote Function ED06, 3N4 Local operation, to OPEN BOOTH INST

d.

If asked, Role Play personnel to confirm that the 10TR XFMR Auto load tap changer is in service.

BOP Dispatch an operator to place the 2R Load Tap Changers in Manual and adjust voltages locally Notify the System Dispatcher (TSO) of the Transfer to the 1R Transformer CRS Evaluates LCO 3.8.1 as NOT met SS299.358 Condition A is applicable BOOTH INST

e.

Role Play as necessary to inform the crew that another operator will be called in to perform OSP-MSC-0542 CR299.358 Required Action A.1: Initiate SR 3.8.1.1 (OSP-MSC-0542),

Weekly Breaker Alignment, Indicated Power Availability, and Voltage to AC & DC Power Distribution Checks) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Required Action A.2: Declare required features INOP within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when redundant feature is INOP - This action is N/A for these conditions.

Required Action A.3: Restore an Offsite Circuit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months BOOTH INST

f.

For notifications, Role Play Single Point of Contact and plant support personnel as necessary Make notifications for the LCO Entry.

CRS May also evaluate TLCO 3.8.1 as NOT met, however, the LCO 3.8.1 actions are more limiting.

Event 4

8.

Bus 11 Lockout BOOTH INST

a.

When directed by the lead evaluator, Insert Manual Trigger 11 verify ED05A goes active.

SS315.138 CR200.182 Key Parameter Response

Loss of voltage on Bus 11, Trip of 11 Recirc Pump, Trip of 11 Feedpump Key Expected Alarms OATC/

BOP

8-B-14 (NO. 11 4160V BUS LOCKOUT)

Responds to annunciators and reports to the CRS Auto Actions BOP

None Enters C.4-B.09.06.A (Loss Of Bus 11 Or Bus 12)

OATC Monitor and control Reactor water level +9 to +48 BOP Places 11 FW Pump in STOP Enters C.4-B.01.04.A (Trip Of One Recirc Pump)

SS315.103 CR200.148 Closes MO-2-53A (11 RECIRC PUMP DISCHARGE) valve After 5 minutes, verify APRM rod block setpoints and reopens the discharge valve.

Enters C.4-B.06.05.A (Feedwater Pump Trip)

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES OATC Enters C.4-B.05.01.02.A (Control Of Neutron Flux Oscillations)

Determines plant is operating in Stability Region 2 of the power to flow map NOTE

This will be a required action once the OATC performs the reactivity manipulation using C.4-F (Rapid Power Reduction).

If plant is operating in the restricted area, Stability Region I, or Stability Region II, AND neutron flux oscillations are observed for any reason, THEN perform a manual reactor scram.

OATC Enters C.4-F (Rapid Power Reduction)

SS315.159 CR200.203 Inserts control rods to restore operating conditions within the analyzed region of the power flow map.

b.

While the 2nd control rod is being inserted for the reactivity manipulation and at the discretion of the lead evaluator, move on to Event 5 Based on plant conditions, power will need to be reduced to approximately 35-40% power to exit Region 2.

Event 5

9.

Neutron Flux Oscillations BOOTH INST

a.

When the second control rod is being inserted and/or directed by the Lead Examiner, insert Manual Trigger 13 and verify RX03 and CH19 go active.

Key Parameter Response SS315.119

Reactor power oscillation 10-20%

Key Expected Alarms

5-A-38 (OPRM ALARM), 5-A-45 (OPRM TRIP)

Auto Actions OATC

None, OPRM Scram failure Enters C.4-B.05.01.02.A (Control Of Neutron Flux Oscillations)

CT-8 Scram the reactor in response to core oscillations as indicated by:

CR200.168 If plant is operating in the restricted area, Stability Region I or Stability Region II AND neutron flux oscillations are

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES LPRM HI or DOWNSCALE alarms in a wide area of the core that repeatedly alarm, then clear.

LPRM indications on the RBM ODA displays indicate oscillation.

APRM recorders indicate a peak-to-peak oscillation greater than 10% that is not attributable to pressure or Recirc flow control problems.

10.

Immediate Reactor Shutdown 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

11.

Hydraulic ATWS OATC Provides a Scram Report Reactor Scram, Mode Switch is in Shutdown, all rods are NOT in, Reactor power is >3%, EOP Entry CRS SS304.213 SS304.201 SS304.244 CR314.129 CR314.104 Enters EOP 1100 RPV Control, transitions to EOP 2007, Failure to Scram, and directs the following:

NOTE BOP

The CRS may wait to direct this action as time permits.

o Inhibit ADS SS314.111 CR314.115 o C.5-3301 (Defeat MSIV Low-Low Level Isolation)

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE SS314.108 CR314.112

The CRS may wait to direct this action during the Level Leg actions.

o C.5-3205 (Prevent Core Spray injection)

SS314.101 o C.5-3101 (Alternate Rod Insertion)

12.

Hydraulic ATWS Power Leg Actions CT-48 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)

Verifies Recirc pumps are at minimum speed and trips the pumps NOTE CR212.105

ARI will NOT work for this scenario.

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

NOTE OATC

C.5-3101 Part C and/or Part D may be performed. If only one part is performed, the actions from the other part are not applicable Performs PART C (INCREASE COOLING WATER DIFFERENTIAL PRESSURE AND USE RMCS)

Bypasses RWM Starts both CRD pumps Fully open the CRD Flow Control Valve o

Place FC 3-301 in MAN o

Adjust output of FC 3-301 to 100%

Opens MO-3-20 (Drive Pressure to CRD)

BOOTH INST

a. When requested to close CRD-168, activate Manual Trigger 15 and verify CH34 goes active. Wait 1 minute and report it as closed.

Directs Reactor Building Operator to CLOSE CRD-168, CRD-79-1 & CRD-79-2 When control rods no longer drift in, Drive rods using RMCS

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Establish Drive Pressure as high as possible below 400 psig by one or more of the following:

o Throttle closed the CRD Flow Control Valve o

Throttle closed Open MO-3-20 Drive Pressure to CRD BOOTH INST

b. If requested to close CRD-14, activate Manual Trigger 17 and verify CH22 is modified to 0.

o Directs the Reactor Bldg Operator to CLOSE CRD-14 to raise drive pressure BOOTH INST

c. Prior to the OATC inserting control rods, DELETE Malfunction CH19 to allow rods to be driven in.

Select and insert rods in non-peripheral core regions with few or no rods inserted Attempt to achieve a Black and White pattern Performs PART D (RESCRAM CONTROL RODS)

Evacuate personnel from the RB 896 Floor and the Equipment Drain tank Room BOOTH INST

d. When requested to deenergize the ARI valves insert Manual Trigger 19, this modifies RR18 is to Open. Wait 1 minute and report the ATWS 125 VDC Breakers Open.

Directs the in-Plant operator to deenergize the ATWS 125 VDC Valves by opening D-21 & D-11.

NOTE

These contacts are modeled in the simulator. The jumpers are included with the C.5-3101 procedure.

Installs jumpers to bypass all automatic scram signals in C-15

& C-17 Resets the scram BOOTH INST

e. If requested to open CRD-14, modify Remote Function CH22 is to Open, wait 1 minute and report CRD-14 Open.

Directs the Reactor Bldg Operator to open CRD-14 Verifies SDV Vent and drain valves Open NOTE

This may take up to 7 minutes.

When Annunciator C05-B-21 clears, closes the SDV vent and drain valves BOOTH INST

f.

If the Manual Reactor Scram is inserted for Part D, Delete Malfunction CH16 to allow the control rods to insert.

Inserts a Manual Reactor Scram

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Verifies all control rods fully inserted and informs the CRS

13.

SBLC Initiation Problems BOOTH INST NOTE

Event Triggers 28 or 29 will auto activate to clear the trip on the second SBLC pump that is started.

a. If #11 SBLC is attempted to be started first, verify Event Trigger 29 goes True and SL01B deletes after 1 second so

12 SBLC pump will start.

CRS Directs SBLC initiation before Torus temp reaches 110ºF using the SBLC Hard Card, B.03.05-05.G.1 (SBLC Manual Initiation)

b. If #12 SBLC is attempted to be started first, verify Event Trigger 28 goes True and SL01A deletes after 1 second so

11 SBLC pump will start.

Key Parameter Response OATC CR211.106

Selected pump Green light stays on and Red light stays off, SBLC discharge pressure remains at 0 psig Places 11A-S1 SBLC System Selector Switch to SYS 1 or SYS 2 and recognizes that the first pump fails to start.

Key Expected Alarms

None Starts the other SBLC pump Auto Actions

RWCU isolates and pumps trip ONLY when the second pump starts.

Verifies the RWCU Pumps trip and the Group 3 isolation valves close.

Verifies SBLC Pump running light is ON and, discharge pressure is slightly higher than RPV pressure with SBLC Tank level decreasing.

14.

Hydraulic ATWS Level Leg Actions CRS Verify needed auto actions

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Identifies that power >3.5% & RPV level above -33 and directs Terminate and Prevent actions CT-46 During failure to scram conditions with reactor power above 3.5%,

terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.

BOP CR314.112 Prevents injection from Condensate & Feedwater by placing the FRV Controllers in Manual and closing the Reg Valves BOP Prevents injection form HPCI by placing the Aux Oil Pump in PTL Prevents Core Spray injection as follows:

Place the A & B CS INJECTION BYPASS Switches to BYPASS Close MO-1751 (1752) Injection Outboard Place A and B CS Pump switches to PTL Close MO-1753 (1754) Injection Inboard Prevents LPCI injection as follows Open Knife switches (C-03)

Verify LPCI OBD Valves are closed, MO-2012/13 CRS Lets level drop until Power is <3.5% or All SRVs stay closed and DW pressure is < 1.84 psig or RPV Level reaches -126 inches For level control, the CRS should direct condensate and feedwater injection re-established and used to maintain level in the desired band.

Records final level and sets level band

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Uses Condensate & Feedwater as necessary to maintain established level band.

15.

Hydraulic ATWS Pressure Leg Actions CRS/ BOP Stabilize RPV pressure below 1056 psig using the one remaining Bypass Valve and/or SRVs (LL-SET)

16.

BOP (PRIMARY CONTAINMENT CONTROL)

Monitor Primary Containment Parameters NOTE

Based on Crew priorities and Torus water temperature EOP-1200 actions may be taken.

If Torus Water Temperature exceeds 90°F, notify the CRS of the EOP C.5-1200 entry condition.

CRS Enters EOP C.5-1200 Primary (Containment Control)

Directs start of all available Torus Cooling BOP Starts all available Torus Cooling IAW the Hard Card.

Verify CV-1728 (1729), RHR HX SW Outlet, controller set at 20%.

START No 11(12) and/or No 13(14) RHRSW pumps as needed.

Adjust flow for ~3500 gpm per pump using CV-1728 (CV-1729).

Verify 11(12) and/or 13 (14) RHR pumps running.

Partially OPEN MO-2008 (2009), Torus Cooling Inj/Test Inboard, by holding handswitch in OPEN position for 8 seconds.

Give MO-2006 (2007) an OPEN signal by momentarily placing RHR Div 1 Disch to Torus Otbd handswitch 10A-S14A (B) to OPEN.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES THROTTLE OPEN MO-2008 (2009) to provide ~4000 gpm per pump.

CLOSE MO-2002 (2003), HX Bypass.

Verify V-AC-5(4), A(B) RHR RM COOLER in operation.

BOOTH INST When Power & Level Control actions have been performed AND when directed by the Lead Examiner, Delete Malfunction CH16 to allow the control rods to insert.

17.

SCENARIO TERMINATION

a.

The scenario may be terminated as follows:

1) Actions are being taken to insert control Rods or ALL rods are inserted.

2) RPV level and pressure are stable in the directed bands.

b.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew Remain in simulator for potential questions from evaluator.

c.

End the scenario by placing the simulator in FREEZE.

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

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 4(SPARE) Op-Test No.:

Examiners: ____________________________ Operators:

MNGP 2013301 Initial Conditions:

100% Power 12 Service Water Pump Turnover:

BOP to shift RBCCW Pumps Event No.

Malfunction No.

Event Type*

Event Description 1

None N

BOP BOP will transfer to the standby RBCCW pump 2

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

3 AP07 C & TS BOP / CRS The ADS timer will inadvertently initiate requiring the BOP to inhibit it. The CRS will address TSs.

4 04-A2S70-04 C & R BOP / OATC

/ CRS The EPR will fail upscale automatically placing the MPR in service. The BOP will be unsuccessful lowering reactor power and pressure with the MPR requiring the OATC to reduce recirc to stay below 100% power.

5 04-A2S59-02 C

OATC / CRS The MPR will fail in the lowering direction requiring the OATC to insert a manual scram.

6 CH22A/B MAJOR CREW When the reactor is scrammed a set of SDV vent and drain valves will fail to close. This will drive radiation levels up in the RB and require the crew to perform an ED when two max safe values are reached.

7 AP08D C (POST)

BOP When performing actions for the ED, one SRV will fail to open. This will require the BOP to open other SRVs until a total of 3 are verified open.

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

Total Malfunctions (5-8): 6 Malfunction(s) after EOP (1-2): E7 Abnormal Events (2-4): E3, E4, E5 Major Transient(s) /E-Plan entry (1-2): E6 EOPs (1-2): 1300 & 2002 EOP Contingencies (0-2): 1 (ED)

Critical Tasks (2-3): 2 ES-301-5 Quantitative attributes:

BOP Normal (1/set): E1 OATC Reactivity (1/set): E4 BOP I/C (4/set): E3, E4, E7 OATC I/C (4/set): E2, E5 SRO-I I/C (4/set incl. 2 as OATC): E2, E3, E4, E5 SRO Tech Spec (2/set): E2, E3 ALL Major Transients (2/set): E6

QF-1075-02 Rev. 3 (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-24E SEG TITLE:

2013 ILT NRC SCENARIO 4 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Roman Becker Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

This Scenario evaluation has been written for the 2013 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 Evaluations

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 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

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References:

1.

B.02.05-05.E.1 (Transfer to Standby Pump)

2.

C05-A-22 (APRM UPSC/INOP Trip)

3.

C05-A-3 (Rod Withdraw Block)

4.

C05-A14 (APRM ALARM)

5.

LCO 3.3.1.1, LCO 3.3.2.1 and TLCO 3.3.2.1

6.

3-A-25 (Auto Blowdown Timer Activated)

7.

C.4-G (Inadvertent ECCS Initiation)

8.

LCO 3.3.5.1 & LCO 3.5.1

9.

C07-B-15 (EPR Trouble)

10.

C.4-B.05.09-B (Main Steam Pressure Regulator Failure Causing Increased Pressure)

11.

B.04.01-05.E.01 (Changing Recirculation Flow) hard card

12.

5-B-16 (Reactor Press Hi/Low)

13.

C.4-B.05.09.A (Main Steam Pressure Regulator Failure Causing Reduction in Main Steamline Pressure)

14.

C.4-A (Reactor Scram)

15.

C.5-1100 (RPV Control)

16.

C.5-1300 (Secondary Containment Control)

17.

C.5-2002 (Emergency Depressurization)

Commitments:

1.

None Evaluation Method:

The following methods are acceptable methods for examinee evaluation:

2013 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

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

SRO Tasks:

SS299.351 Apply administrative requirements for Tech Spec Section 3.3 and Bases to Instrumentation 5-7 SS315.160 Supervise response to inadvertent ECCS initiation 5-7 SS299.353 Apply administrative requirements for Tech Spec Section 3.5 and Bases to ECCS and RCIC 5-7 SS315.123 Supervise response to increasing pressure caused by main steam pressure regulator failure 5-7 SS315.159 Supervise rapid power reduction 5-7 SS315.122 Supervise response to decreasing pressure caused by main steam pressure regulator failure 5-7 SS315.164 Supervise immediate reactor shutdown 5-7 SS315.101 Supervise response to a reactor scram 5-7 SS304.196 Implement secondary containment control 5-7 SS304.239 Implement the response for a primary system leak in secondary containment, exceeding max safe values in 2 or more areas with an RPV blowdown required.

5-7 SS304.198 Implement emergency RPV depressurization 5-7 RO Tasks:

CR208.102 Transfer to the Standby RBCCW Pump 1-4 CR299.353 Apply Tech Spec Section 3.3 and Bases to Instrumentation 5

CR200.204 Perform the procedure for an inadvertent ECCS initiation 1-4 CR299.355 Apply Tech Spec Section 3.5 and Bases to ECCS and RCIC 5

CR200.167 Perform the procedure for a main steam press regulator failure causing increasing pressure 1-4 CR200.108 Changing recirculation flow 1-4 CR200.166 Perform the procedure for a main steam press regulator failure causing a reduction in main steam pressure 1-4 CR200.203 Perform the procedure for rapid power reduction 1-4 CR200.208 Perform the procedure for immediate reactor shutdown 1-4 CR200.146 Perform the procedure for a Reactor Scram 1-4 CR304.105 Perform action associated with Secondary Containment Control 1-4 CR304.153 Perform actions for a primary system leak in secondary containment, exceeding max safe values in 2 or more areas with an RPV blowdown required.

1-4 CR314.101 Perform action associated with Emergency RPV Depressurization 1-4

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QUANTITATIVE ATTRIBUTES Malfunctions Before EOP Entry:

1. APRM upscale failure

2. Inadvertent ADS timer initiation

3. EPR upscale failure with MPR lock

4. MPR fails downscale

5. Scram Discharge Volume failure to isolate After EOP Entry:

1. ADS Valve failure Abnormal Events

1. Inadvertent ECCS initiation

2. Main Steam Pressure Regulator Failure Causing Increased Pressure

3. Main Steam Pressure Regulator Failure Causing Reduction in Main Steam Line Pressure Major Transients

1. Unisolable leak from SDV resulting in a RPV blowdown Critical Tasks

1.

CT-16

2.

Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate or a loss of adequate core cooling.

CT-34 When a primary system is discharging into the secondary containment through an unisolable break, perform an Emergency Depressurization per C.5-2002 when max safe operating values are exceeded in two or more areas.

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SCENARIO OVERVIEW:

Event 1: Shift Running RBCCW Pumps (Optional)

BOP shifts RBCCW pumps IAW the B-manual for obtaining vibration data.

APRM 3 will experience an upscale failure requiring the crew to bypass the APRM.

Event 2: APRM 3 UPSCALE Failure (Optional)

The CRS will evaluate TS 3.3.1.1.F for APRM 3 being inoperable. Implication only.

The ADS timer will inadvertently initiate. This will require the CRS to direct that the ADS system be placed in Inhibit IAW C.4-G prior to the timer counting down.

Event 3: ADS Timer Failure (Optional)

The CRS will evaluate Tech Specs for ADS being in Inhibit and declare the ADS function for all 3 ADS valves inoperable. This requires entry into 3.5.1.L & 3.5.1.N.

The EPR will fail upscale, resulting in the MPR taking over at a higher CTP and the crew will need to lower reactor pressure.

Event 4: EPR Upscale Failure with MPR Locking in Position (Optional)

When the crew attempts to utilize the MPR to lower reactor pressure, the MPR will lock in place, forcing the OATC to reduce reactor power with Recirc Pumps.

The MPR will fail downscale and the crew will need to take action to scram the reactor prior to the automatic setpoint of 840 psig with the mode switch in RUN.

Event 5: MPR Downscale Failure with Reactor Scram

Reactor pressure control will be restored to the MPR following the placement of the mode switch to the SHUTDOWN position.

Concurrently with the Scram, the SDV Vent and Drain Valves will fail to isolate resulting in an unisolable leak into the Reactor Building.

Event 6: SDV Vent and Drain Valve Failure to Isolate

Upon two areas reaching MAX SAFE, the CRS will direct the performance of an Emergency Depressurization IAW C.5-1300.

Event 7: D SRV fails to open for the Blowdown

The BOP will recognize that the D SRV failed to open for the ED and open additional SRVs until a total of 3 are verified open.

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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: 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: Shift to #12 RBCCW pump for vibration analysis

j.

The following equipment is OOS:

1) 12 Service Water Pump for scheduled maintenance

2.

SIMULATOR SET UP BOOTH INST

a. Reset the simulator to IC-284 (PW: mallard4) 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 30 to load simulator initial conditions and preloaded malfunctions.

c. Tag out 12 Service Water Pump as follows:

1) Place its hand switch in NORMAL-AFTER-STOP

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SCENARIO TIME-LINE:

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

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

3) Verify its GREEN light is OFF.

d. Ensure the following are provided for the crew:

e. Turnover checklists (3139 & 3140)

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

g. Verify the status board is updated IAW Section 1

h. Complete the Simulator Setup Checklist

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). 5 Condensate Demins are in service.

2). E vessel d/p is highest @ 5.2 psid.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 3). 12 Service Water Pump is tagged out for scheduled maintenance 4). All other systems in Turbine building are normal.

Role Play as necessary. Extra out plant operator.

1) Nothing to add.

Role Play as necessary. Rx Building status:

1) All systems in the Rx Bldg are normal.

CRS Crew assumes the duty.

Event 1

5.

SHIFT RUNNING RBCCW PUMPS (Optional)

NOTE CRS

This event is OPTIONAL and has no bearing on the subsequent events. It may be omitted at the discretion of the Lead Examiner when the BOP/CRS candidates have had the requisite NORMAL evolution.

Directs BOP to Transfer RBCCW to #12 RBCCW Pump IAW Booth Operator

a.

Respond as RBO that you are standing by at the RBCCW pumps BOP CR208.102 Directs RBO to be stationed by the RBCCW pumps.

Booth Operator

b.

Respond as RBO that the #12 RBCCW pump suction and discharge valves are fully open.

BOP Directs RBO to verify valve positions.

BOP BOP starts standby pump from C-06 Booth Operator

c.

Respond as RBO that the #12 RBCCW pump is operating normally.

BOP Directs RBO to check pump and motor performance Booth Operator

d.

When directed by the BOP to close the #11 RBCCW pump discharge valve, INSERT MANUAL TRIGGER 1. When ramp is complete, immediately notify the BOP that the #11 RBCCW pump discharge valve is CLOSED.

BOP Directs RBO to slowly CLOSE discharge valve on #11 RBCCW pump and then immediately secures the pump.

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SCENARIO TIME-LINE:

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

e.

When directed to OPEN the #11 RBCCW pump discharge valve, INSERT MANUAL TRIGGER 3 and verify the valve opens. Once OPEN, notify the BOP that the discharge valve for #11 RBCCW pump is OPEN.

BOP Directs RBO to fully open the discharge valve for #11 RBCCW pump.

BOP Reports to the CRS that the #12 RBCCW pump is running and that

11 RBCCW pump is secured.

Event 2

6.

APRM 3 UPSCALE Failure (Optional)

NOTE

This event is OPTIONAL and has no bearing on the subsequent events. It may be omitted at the discretion of the Lead Examiner when the OATC/CRS candidate has had the requisite number of Instrument/Component failures and Tech Spec calls.

Booth Operator

a.

When directed by the lead evaluator, insert MANUAL TRIGGER 5, and verify NI13C goes active:

Key Parameter Response

APRM Channel #3 High or INOP Red indicating light lit; APRM Channel #3 recorder upscale high Key Expected Alarms OATC

C05-A-22 (APRM UPSC/INOP Trip), C05-A-3 (Rod Withdraw Block), C05-A14 (APRM Alarm)

Responds to Annunciators C05-A-3, 14 & 22 and notifies CRS.

Automatic Actions

1/2 Vote trip for APRM 3 on all 2 out of 4 Vote Logic Channels Determines the trip signal by pressing the APRM or APRM ODA TRIP STATUS softkey Determines that APRM Channel 3 is upscale and Inoperable FLOOR INST

b.

When operator goes to Panel C-37 to observe status of 2 of 4 Voter Modules #1, 2 & 4, inform him these voters indicate the same as Voter Module #3 for APRM Channel #3. Voter Modules 1, 2 & 4 are not modeled.

Verifies Automatic actions initiated.

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SCENARIO TIME-LINE:

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

Verifies each 2 of 4 Voter Module APRM UPSC/INOP INPUT SATUS LEDs is ON for APRM #3

Rod Block initiated

INPUT STATUS LEDs activated on the 2 of 4 Voter for APRM UPSC/INOP, OPRM DIDA/INOP, and OPRM CDA/INOP Determines the INOP signal by pressing the APRM or APRM ODA INOP STATUS softkey; Critical Self Test Fault Crew Notifies Plant Engineering.

CRS SS299.351 CR299.353 Acknowledges alarm receipt and declares APRM Channel #3 inoperable.

Evaluates LCO 3.3.1.1, LCO 3.3.2.1 and TLCO 3.3.2.1 as still MET These LCOs only require 3 of 4 APRMs to be operable.

c.

Role Play plant support personnel as necessary to acknowledge report.

CRS Directs OATC to bypass APRM Channel #3.

OATC Bypasses APRM Ch #3 as directed by the CRS.

Event 3

7.

ADS TIMER FAILURE (Optional)

NOTE: This event is OPTIONAL and has no bearing on the subsequent events. It may be omitted at the discretion of the Lead Examiner when the BOP/CRS candidates have had the requisite number of Instrument/Component failures, Critical Tasks and Tech Spec calls.

Booth Operator When directed by the Lead Evaluator, insert MANUAL TRIGGER 7 and verify AP07 is active:

BOP Acknowledges the alarm and informs the CRS that the ADS timer is timing down

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SCENARIO TIME-LINE:

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

ADS timer timing down and Audible Alarm Key Expected Alarms Crew

3-A-25 (Auto Blowdown Timer Activated)

Verifies plant parameters do not require ADS initiation (DW pressure and Reactor level are in the normal band).

Automatic Actions CRS SS315.160

After the ADS timer times out, an ADS actuation will occur, resulting in the depressurization of the RPV.

Directs the BOP to perform actions of C.4-G (Inadvertent ECCS Initiation)

Booth Operator

a.

If Inhibit switches are NOT placed in INHIBIT, Then BOP CR200.204 insert Manual Trigger 8 to activate AP02.

This will open the ADS valves. DELETE AP02 if the switches are then placed in INHIBIT.

Per step 4 of C.4-G, places ADS Inhibit switches to INHIBIT and informs the CRS that ADS is inhibited.

CT-16 Inhibit ADS to avoid auto initiation that would result in a violation of cooldown rate or a loss of adequate core cooling.

CRS Evaluates LCO 3.3.5.1 as NOT Booth Operator MET

b.

If contacted as System Engineer, acknowledge report and inform operator you will assemble a troubleshooting team immediately.

Enters Conditions A & G Required Actions - Declare ADS Valves inoperable within one hour CRS Evaluates LCO 3.5.1 as NOT MET once ADS valves are declared inoperable.

Enters Conditions L & N apply.

Most restrictive Required Action - Condition N requires the plant to be placed in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Event 4

8.

EPR Upscale Failure with MPR Locking in Position (Optional)

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SCENARIO TIME-LINE:

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

This event is OPTIONAL and has no bearing on the subsequent events. It may be omitted at the discretion of the Lead Examiner when the BOP/CRS/OATC candidates have the requisite number of Instrument/Component failures or reactivity manipulations.

Booth Operator

a.

When directed by the lead evaluator, INSERT MANUAL TRIGGER 9 and verify Override 04-A2S70-04 goes active.

Key Parameter Response BOP

RPV Pressure rises which also raises Core Thermal Power Responds to C07-B-15, EPR TROUBLE and notifies the CRS Key Expected Alarms

C07-B-15 (EPR Trouble)

Verifies that the MPR assumes stable steam pressure control Auto Actions

The MPR begins to control pressure Depress the ELECTRIC PRESSURE REG STOP Pushbutton Recognizes that the EPR TROUBLE annunciator does not reset CRS SS315.123 BOP CR200.167 Performs C.4-B.05.09-B Main Steam Pressure Regulator Failure Causing Increased Pressure BOP/ATC Monitor Reactor Pressure Identifies that Reactor pressure increased slightly when the EPR failed BOP Attempts to adjust the MPR to lower RPV pressure but will be unsuccessful and informs CRS.

Booth Operator

b.

Role Play plant support personnel as necessary to acknowledge report.

BOP CRS Initiate an investigation to determine the cause of the EPR failure CRS CR200.203 SS315.159 CR202.108 Directs OATC to reduce Rx Power using recirc pumps IAW the B.04.01-05.E.01 (Changing Recirculation Flow) hardcard, or IAW C.4-F (Rapid Power Reduction).

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SCENARIO TIME-LINE:

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

It is not the intent of this portion of the SEG to evaluate Tech Specs.

Lowers power to restore reactor power within thermal limits.

Event 5

9.

MPR Downscale Failure with Reactor Scram Booth Operator

a.

After crew brief or when directed by the Floor Instructor, INSERT MANUAL TRIGGER 11 and verify override 04-A2S59-01 activates.

Crew Identifies Reactor pressure lowering, reports Reactor low pressure alarm and refers to appropriate ARP.

Key Parameters Reactor pressure lowers, Reactor power lowers Expected Alarms BOP 5-B-16 (Reactor Press Hi/Low)

Determines MPR setpoint is lowering. Reports this to CRS.

Automatic Actions CRS SS315.122 SS315.101

Group 1 Isolation at 840 psig with Mode Switch in RUN Enters C.4-B.05.09.A (Main Steam Pressure Regulator Failure Causing Reduction in Main Steamline Pressure) and directs manual Reactor scram.

OATC CR200.166 SS315.164 Inserts a manual Reactor scram.

OATC Takes actions IAW C.4-A (Reactor Scram) PART A:

Booth Operator

b.

When the Mode switch is placed in SHUTDOWN, verify EVENT TRIGGER 27 activates and the following occurs:

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

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

1) 04-A2S59-01 deletes Provides scram script to CRS. Reports RPV less than 9 EOP entry condition.

2) 01-DS124-02 activates Controls Reactor water level between +9 and +48 inches.

When RPV water level starts to increase:

3) AP08D, RM01F&G activate 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

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SCENARIO TIME-LINE:

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

NOTE

The remaining ATC actions in C.4-A may NOT be performed depending on when the SDV leak is recognized.

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 performed depending on when the SDV leak is recognized.

Verify the Generator Field Breaker Open.

Start the Turbine Aux Oil Pump.

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

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SCENARIO TIME-LINE:

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

SDV Vent and Drain Valve Failure to Isolate

a.

The malfunctions for SDV vent and drain valve failures, CH22A and CH22B, are inserted during the initial setup.

Key Parameter Response:

Scram Discharge Volume Vents and Drains remain open Key Expected Alarms:

3-B-56 (High Area Temp Steam Leak), 4-A-11 (Reactor Building Hi Radiation)

Auto Actions:

None The BOP will respond to annunciators and report to the CRS EOP 1300 Entry Conditions NOTE

It takes approximately 4 minutes for area A-11, West CRD HCU, to reach Max Safe Rad levels (1R/hr). It takes an additional 4 minutes for the second area, A-15 Reactor Bldg Drain Tank, to reach Max Safe (1R/hr).

Crew SS304.196 SS304.239 Perform the actions of EOP-1300 (Secondary Containment Control)

CR304.105 CR304.153 Directs evacuation of area or entire reactor building.

Reports Reactor Building radiation levels and temperatures are rising Keeps the CRS informed of Secondary Containment parameter values and trends

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SCENARIO TIME-LINE:

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

The SDV isolation valves will NOT be able to be reset due to a malfunction on the SDV high level bypass circuitry.

Attempts to manually close SDV isolation valves CRS Enters EOP-1300 (Secondary Containment Control)

Direct isolation of the SDV CRS Monitors Secondary Containment parameters CT-34 When a primary system is discharging into the secondary containment through an unisolable break, perform an Emergency Depressurization per C.5-2002 when max safe operating values are exceeded in two or more areas.

Crew SS304.198 CR314.101 Recognizes when 2 area radiation levels have exceeded Max Safe CRS Enters and directs EOP-2002 (Blowdown)

Verifies Torus level > -5.9 ft.

Directs that 3 ADS SRVs be opened BOP Perform Emergency Depressurization CRS Enters EOP-1300 (Secondary Containment Control)

Booth Operator

a.

Verify AP08D and 01-DS124-02 are active.

These will prevent D SRV from opening.

Directs opening of all 3 ADS SRVs.

BOP Recognizes that D SRV failed to open Opens additional SRVs until a total of 3 are open

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SCENARIO TIME-LINE:

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

12.

SCENARIO TERMINATION FLOOR INST The scenario may be terminated when Emergency Depressurization has been performed.

The scenario may be also terminated at the discretion of lead instructor/evaluator Crew:

Remain in simulator for potential questions from evaluator.

End the scenario by placing the simulator in FREEZE.

Crew:

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

ML13057A099

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