Text

2015 Monticello Nuclear Generating Plant Initial License Examination Administered Simulator Scenarios
	ML15174A373
Person / Time
Site:	Monticello
Issue date:	06/15/2015
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	; Xcel Energy
References
	Download: ML15174A373 (54)
	v • d • e

DYNAMIC SIMULATOR SCENARIO 1 Page 1 of 17 MT-ILT-27E (2015 ILT NRC Scenario 1) Rev. 0 SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-27E SEG TITLE:

2015 ILT NRC SCENARIO 1 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING MT-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

DYNAMIC SIMULATOR SCENARIO 1 Page 2 of 17 MT-ILT-27E (2015 ILT NRC Scenario 1) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. CRD Pump trip

2. SRV G fails open (mechanically)

3. 2R Transformer oil leak

4. SRV G fails open (mechanically)

After EOP Entry:

1. One Control Rod stuck out Abnormal Events:

1. Loss of CRD Flow

2. Stuck Open Relief Valve

3. Emergency transfer from 2R to 1R XFMR Major Transients:

1. Torus rupture requiring Emergency Depressurization Critical Tasks:

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

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

DYNAMIC SIMULATOR SCENARIO 1 Page 3 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

1.

SHIFT RUNNING RBCCW PUMPS CRS Directs BOP to Transfer RBCCW to #12 RBCCW Pump IAW B.02.05-05.E.1 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 suction and discharge valves for

12 RBCCW pump are fully open (Step 3)

BOP BOP starts #12 RBCCW pump from C-06 Booth Operator

c. Respond as RBO that the #12 RBCCW pump is operating normally BOP Directs RBO to locally check pump and motor performance of #12 RBCCW pump 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 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 Reports to the CRS that the #12 RBCCW pump is running and that #11 RBCCW pump is secured BOP Places #11 RBCCW pump in auto-standby

DYNAMIC SIMULATOR SCENARIO 1 Page 4 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 2

2.

11 CRD PUMP SHAFT SHEAR Booth Operator

a.

When directed by the Lead Evaluator, insert MANUAL TRIGGER 5 and verify CH26A activates:

Key Parameter Response: CRDH pressures and flows lower SS315.102 CR200.147 Key Expected Alarms: 5-B-17 (Charging Water Lo Press)

OATC Responds to annunciators and notifies CRS of the degraded CRDH parameters.

Automatic Actions: None CRS OATC Direct / Perform C.4-B.01.03.A (Loss Of CRD Pump Flow)

Booth Operator

b.

As the RB Operator, wait one minute and respond as follows:

OATC Starts 12 CRD Pump Booth Operator

1) 11 CRD Pump is running but has an extremely high pitch sound.

Verifies CRDH parameters are restored

2) #12 Pump is running normally Secures 11 CRDH pump OATC Monitors and controls system pressures and flows and adjust as necessary per B.01.03 Booth Operator

c.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management.

BOP Initiates investigation

DYNAMIC SIMULATOR SCENARIO 1 Page 5 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

3.

STUCK OPEN G SRV Booth Operator

a.

When directed by the Lead Evaluator, Insert Manual Trigger 7 and verify Malfunction AP01G goes active.

Key Parameter Response: C-03 Amber light for G SRV will be ON. MWe and B steam line flow will lower BOP Implement C.4-B.03.03.A (Stuck Open Relief Valve)

Key Expected Alarms: 5-A-46 (SRV OPEN)

BOP Place handswitch 2E-S4G for SRV G in OPEN and then return to the normal position.

Auto Actions: None CR200.154 BOP Place handswitch 2E-S4G for SRV G in CLOSE.

BOP On C-253D, Place HS-S3B in BYPASS BOP On C-253D, VERIFY HS-S43 in Off.

CRS SS315.109 SS315.159 Direct Rapid Power Reduction C.4-F when the SRV fails to close Booth Operator 3 seconds after the OATC takes the #12 Recirc Pump to lower, VERIFY EVENT TRIGGER 9 goes active and APO1G is deleted. This will cause SRV G to CLOSE.

OATC CR200.203 Reduces recirculation flow as needed Booth Operator

b.

Acknowledge any investigation / notification requests to Engineering, Maintenance and Plant Management.

CRS SS299.354 CR299.356 Evaluates TS 3.3.6.3 (LLS INST) as NOT MET with the switch in OFF (Div 1) and Div 2 circuits bypassed.

Condition A applies which requires the channels to be restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months NOTE: If SRV left open long enough, the crew may place Torus cooling in service.

May also evaluate TS 3.6.1.5 (LLS Valves) & TRM 3.4.4 (SRVs) as NOT MET Determines that Conditions A applies which requires the valve be restored in 14 days

DYNAMIC SIMULATOR SCENARIO 1 Page 6 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4

4.

Oil leak on 2R / Emergency transfer to 1R Booth Operator

a.

When directed by the Lead Examiner, insert Manual Trigger 11 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: None BOP Clears all personnel from area near 2R Verify that 2R Voltages appear normal NOTE: The following cue must make it clear that it is imperative to do the emergency transfer operation.

Dispatch an operator to check the 2R transformer or request security to observe 2R transformer with cameras Booth Operator

b.

Role Play the dispatched operator or as security if called: 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 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 Makes plant page to clear all personnel from vicinity of 2R Bus 13 o Place 152-302/CS to CLOSE o Place 152-301/CS to TRIP

DYNAMIC SIMULATOR SCENARIO 1 Page 7 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Bus 14 o Place 152-402/CS to CLOSE o Place 152-401/CS to TRIP Bus 11 o Place 152-107/CS to CLOSE o Place 152-101/CS to TRIP Bus 12 o Place 152-207/CS to CLOSE o Place 152-201/CS to TRIP Booth Operator NOTE: Verify the BOP has opened the knife switch on C-31. If not, then DO NOT open 3N4 with the following actions.

Open knife switch 16 on panel C-31 Booth Operator

c.

Role Play the equipment operator dispatched to open 3N4 as necessary. Wait 10 minutes and:

Open 3N4 34.5KV Circuit Breaker

1) Activate Manual Trigger 13 As time allows dispatch an operator to 4 kV rooms to reset relay flags

2) Verify Remote Function ED06, 3N4 Local operation, to OPEN Notify the System Dispatcher (TSO) of the Transfer to the 1R Transformer CRS SS299.358 CR299.358 Evaluates LCO 3.8.1 as NOT met Condition A is applicable

DYNAMIC SIMULATOR SCENARIO 1 Page 8 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

d.

Role Play as necessary to inform the crew that another operator will be called in to perform OSP-MSC-0542 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 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 Operator

e.

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.

DYNAMIC SIMULATOR SCENARIO 1 Page 9 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

5.

STUCK OPEN G SRV Booth Operator

a.

When directed by the Lead Evaluator, Insert Manual Trigger 15 and verify Malfunction AP01G goes active.

Key Parameter Response: C-03 Amber light for G SRV will be ON. MWe and B steam line flow will lower Key Expected Alarms: 5-A-46 (SRV OPEN)

Auto Actions: None Instructor/Evaluator Note: AOP Immediate actions have already been completed and will not be re-performed.

CRS SS315.109 SS315.159 Direct Rapid Power Reduction C.4-F when the SRV fails to close OATC CR200.203 REDUCEs recirculation flow as needed When the G 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 prior to reaching 110°F bulk torus water temperature.

OATC When directed, manually scrams the reactor

DYNAMIC SIMULATOR SCENARIO 1 Page 10 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

6.

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 CRS SS315.101 Supervises response to a Reactor Scram OATC C.4-A (Reactor Scram) actions:

Booth Operator

a.

When the Mode switch is placed in SHUTDOWN verify Event Trigger 17 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 7).

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 +11-46.

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 Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches

DYNAMIC SIMULATOR SCENARIO 1 Page 11 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Monitor Reactor Power OATC o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

Verify SDV Vent and Drain Valves closed.

Verify Recirc pumps have runback to minimum speed Verify RPS power supplies are available Place DISCH VOL ISOL TEST switch in ISOL Verify the REACTOR MODE switch in SHUTDOWN 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 When all scram valves are CLOSED place the DISCH VOL ISOL TEST switch in NORM Verify the SDV Vent and Drain Valves open Verify the accumulators recharge

DYNAMIC SIMULATOR SCENARIO 1 Page 12 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES When Annunciator 5-B-30 (Disch Volume Tank Not Drained) and 5-B-21 (Disch Volume Water Level Scram Tip) 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.

Check the Turbine Stop Valves CLOSED Start the Turbine Bearing Lift Pumps (P-64A-F)

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 4500 gpm through each operating Feed Pump Verify Vapor Extractor and Auxiliary Oil Pump running on any non-operating Feed Pump

DYNAMIC SIMULATOR SCENARIO 1 Page 13 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Verify 4100 gpm through each operating Condensate Pump Notify Duty Chemist, Turbine Building Operator and Reactor Building Operator to perform scram actions Event 6

7.

UNISOLABLE TORUS LEAK Booth Operator

a.

Verify Event Trigger 17 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: Torus to Drywell Vacuum breakers begin to cycle BOP OATC Respond to annunciators 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

8.

UNISOLABLE TORUS LEAK/ EOP 1300 ACTIONS NOTE: 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.

BOP OATC Dispatches an operator to investigate

DYNAMIC SIMULATOR SCENARIO 1 Page 14 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

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 NOTE: Torus Level can be monitored on Insight File pct112.

BOP OATC Verify the Reactor Bldg Floor drain Sump Pump is running Booth Operator

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 unisolable 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

9.

UNISOLABLE TORUS LEAK/ EOP 1200 ACTIONS SS304.194 BOP Respond to 4-B-4, (Suppression Water Level Hi/Low)

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

DYNAMIC SIMULATOR SCENARIO 1 Page 15 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SS314.115 Directs performance of C.5-3401 (Torus Water Level Makeup)

Booth Operator

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-2102 Open Opens the RCIC Pump Minimum Flow Valve CV-2104

10. EMERGENCY DEPRESSURIZATION CRS 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 per C.5-2002.

CRS 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.

Directs that 3 ADS SRVs be opened

DYNAMIC SIMULATOR SCENARIO 1 Page 16 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 and verifies they have opened Monitor RPV Pressure and Level Event 7

11. CONTROL ROD 14-27 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: None OATC Identifies that Rod 14-27 did not fully insert Booth Operator

a.

Role Play the Reactor Bldg Operator as necessary and, as requested wait 1 minute and insert MANUAL TRIGGER 19 to close CRD-14 Informs the CRS and performs actions to insert Control Rod 14-27 May reset the scram and insert the control rod Booth Operator

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

1. Direct an out-plant operator to manually close CRD-14 Booth Operator

b.

If the OATC places the ROD MOVEMENT CONTROL switch to ROD IN to insert Rod 14-27, verify EVENT TRIGGER 21 goes active and MALFUNCTION CH02_058 DELETES.

Bypass the RWM Select and insert the full out rod Booth Operator

c.

If the OATC uses EMERG ROD IN to insert Rod 14-27, verify EVENT TRIGGER 23 goes active and MALFUNCTION CH02_058 DELETES.

DYNAMIC SIMULATOR SCENARIO 1 Page 17 of 17 ILT-SS-27E (2015 ILT NRC Scenario 1) Rev. 0 SCENARIO TIME-LINE:

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

12. SCENARIO TERMINATION

a.

The scenario may be terminated when actions are taken to insert the control rods and an 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.

SIMULATOR SCENARIO 2 Page 1 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-28E SEG TITLE:

2015 ILT NRC SCENARIO 2 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING MT-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

SIMULATOR SCENARIO 2 Page 2 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. RBM B Upscale failure

2. RPV Flange Leak

3. Control Rod Drift out

4. 12 Stator Water Cooling Pump trip

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

1. ADS Valves fail to open on ED Abnormal Events:

1. Control Rod Drifting

2. Loss of Stator Water Cooling Major Transients:

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

1. CT-ADS When two or more ADS valves fail to open when Emergency Depressurization is required, open additional SRVs until a total of three SRVs are open.

2. 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.

SIMULATOR SCENARIO 2 Page 3 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

1.

PLACE THE 2ND MFRV IN SERVICE AND REACTOR WATER LEVEL CONTROL IN 3 ELEMENT CONTROL CRS Directs BOP to place the 2nd MFRV in service IAW Form 2167 (PLANT STARTUP) and B.05.07-05.D.4 (PLACE REMAINING B MAIN FW REG VALVE CV-6-12B IN SERVICE)

BOP CR259.103 Verifies MO-1134 is OPEN.

Verifies MTS-6-84B bias (vertical scale) is set at ZERO Using MTS-6-84B, OPENS CV-6-12B Monitors Vessel level and FW flow as CV-6-12B OPENS When MTS-6-84B output (horizontal scale) matches demand signal (vertical scale), then places MTS 84B in AUTO.

Event 2

2.

RBM B FAILS UPSCALE BOOTH INST

a.

When directed by the lead evaluator, Insert MANUAL TRIGGER 1 and verify NI17B activates.

Key Parameter Response: RBM B indicates upscale

SIMULATOR SCENARIO 2 Page 4 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Key Expected Alarms: 5-A-3 (ROD WITHDRAW BLOCK),

5-A-43 (RBM DOWNSCALE/TROUBLE), 5-A-51 (RBM HI/INOP)

Auto Actions: Rod Withdraw Block OATC Reports alarm and rod block to the CRS Takes action IAW 5-A-51 (RBM HI/INOP)

Presses the Trip Status softkey and Contributions softkey to determine source of INOP trip.

Determines equipment failure is a Critical Self-Test Fault Bypasses RBM B using Joystick 7B-S2 CRS Evaluates LCO 3.3.2.1-A as still MET SS299.351 CR299.353 Condition A is still met because the plant is not below the limit specified in the COLR.

Event 3

3.

VESSEL FLANGE SEAL LEAK BOOTH INST

a.

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

b.

Verify C-04-A35 MALFUNCTION (Annunciator) goes active:

Key Parameter Response: None Key Expected Alarms: 4-A-35 (VESSEL FLANGE SEAL LEAK)

BOP Responds to annunciator and reports to the CRS Auto Actions: None.

SIMULATOR SCENARIO 2 Page 5 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

c.

When CV-2369 is placed in OPEN, verify Event Trigger 29 activates. This will delete the Vessel Flange Seal Leak alarm after a 2 minute delay.

BOP Places CV-2369 in OPEN BOOTH INST

d.

If confirmatory indication requested, state as the RBO that PS 2-102 reads 616 psig.

Alarm will clear after 2 minutes and 1 minute later CV-2369 is placed back in the closed position.

BOOTH INST

e.

Acknowledge as Plant Technical Staff the receipt of the annunciator.

Notifies Plant Technical Staff of the receipt of the annunciator Event 4

4.

CONTROL ROD 18-19 DRIFTS OUT BOOTH INST When directed by the Lead Evaluator, insert MANUAL TRIGGER 5 and verify 03-S72-02 activates for 2 seconds and CH01_034 activates.

OATC CR200.226 SS315.167 Acknowledges the alarm and informs the CRS that Control Rod 18-19 is drifting out.

Key Parameter Response: Control Rod 18-19 drifting out Enters C.4-B.01.03.C (CONTROL ROD DRIFTING)

Key Expected Alarms: 5-A-27 (ROD DRIFT)

Places Rod Select Power Switch to OFF and back to ON Automatic Actions: None Reselects Control Rod 18-19 and inserts to position 00 BOOTH INST

a.

Once the OATC holds the Rod Insert switch to IN for 5 seconds, verify the control rod drift malfunction CH01_034 deletes.

May hold the Rod Insert Switch to IN or release it.

BOOTH INST

b.

As the Reactor Building Operator; when directed to isolate and/or disarm Control Rod 26-27, wait 3 minutes, insert Manual Trigger 7 and report that the control rod is isolated and/or disarmed.

CRS/

BOP Directs the Reactor Building Operator to hydraulically isolate and/or electrically disarm HCU 18-19 IAW B.01.03-05.G.2 (HYDRAULIC CONTROL UNIT ISOLATION).

CRS Evaluates LCO 3.1.3-C as NOT MET

SIMULATOR SCENARIO 2 Page 6 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES SS299.349 CR299.351 Action C.1: Fully insert control rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Action C.2: Disarm CRD within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Event 5

5.

12 STATOR WATER COOLING PUMP TRIP WITH REACTOR SCRAM BOOTH INST

a.

When directed by the lead evaluator, INSERT MANUAL TRIGGER 9 and verify EG02B activates.

Key Parameter Response: Loss of Stator Water Cooling BOP Announces that a complete loss of Stator Water Cooling has occurred.

Key Expected Alarms: 8-A-17 (NO. 1 GENERATOR COOLING WTR FAILURE SS315.126 Enters procedure C.4-B.06.02.04.A (STATOR COOLING WATER FAILURE).

Auto Actions: Turbine Generator Runback. An automatic scram will occur if both Main Turbine Bypass Valves go full open due to the Runback.

CR200.171 Recommends that a Manual Reactor Scram be inserted.

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

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

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

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

SIMULATOR SCENARIO 2 Page 7 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

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.

SIMULATOR SCENARIO 2 Page 8 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES NOTE: The remaining BOP actions in C.4-A may NOT be performed depending on when the 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 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)

SIMULATOR SCENARIO 2 Page 9 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 NOTE: The SDV isolation valves will NOT be able to be reset due to a malfunction on the SDV high level bypass circuitry.

OATC 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

SIMULATOR SCENARIO 2 Page 10 of 10 ILT-SS-28E (2015 ILT NRC Scenario 2) Rev. 0 SCENARIO TIME-LINE:

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

CT-ADS When two or more ADS valves fail to open when Emergency Depressurization is required, open additional SRVs until a total of three SRVs are open.

Directs opening of all 3 ADS SRVs.

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

8.

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.

SIMULATOR SCENARIO 3 Page 1 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-29E SEG TITLE:

2015 ILT NRC SCENARIO 3 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING MT-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

SIMULATOR SCENARIO 3 Page 2 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. RCIC Steam Leak with Group 5 Isolation failure

2. ADS Timer Malfunction

3. CRD Flow Control Valve failure

4. Main Turbine Vibrations After EOP Entry:

1. ARI Failure

2. SBLC Pump failure Abnormal Events:

1. Group 5 Isolation.

2. Inadvertent ECCS Initiation

3. Rapid Power Reduction Major Transients:

1. Hydraulic ATWS Critical Tasks:

1. CT-46: During failure to scram conditions with reactor power above 4.0%, terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.

2. 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.

SIMULATOR SCENARIO 3 Page 3 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 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 Event 1

1.

RESTORE RCIC SUCTION TO THE CSTS Optional: This normal evolution has been validated as an optional event. If the BOP operator does not need a normal evolution, this event may be omitted from the scenario.

CRS May perform refocus brief BOP CR217.111 Performs B.02.03-05.G.2 (MANUAL SWITCHOVER OF RCIC SUCTION FROM THE TORUS TO THE CONDENSATE STORAGE TANKS).

Verifies Torus level <+2 and CST level >28 NOTE: Based on initial conditions, this TS has already been entered for restoring the suction to the CSTs Notifies CRS to evaluate TS 3.5.3 for RCIC Concurrently closes MO-2100 and MO-2101 NOTE: Without an automatic transfer signal, MO-2102 must be manually opened.

Once dual indication is observed on MO-2100 &

MO-2101, opens MO-2102 manually.

Verifies closed MO-2100 and MO-2101 Notifies CRS to exit TS 3.5.3 CRS Exits TS 3.5.3 for RCIC Event 2

2.

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: 5-B-41 (CRD HI TEMPERATURE)

OATC Responds to annunciator and informs CRS NOTE: It will take three minutes for the alarm to come in.

Auto Actions: None

SIMULATOR SCENARIO 3 Page 4 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

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)

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 55-58 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 complete.

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.

SIMULATOR SCENARIO 3 Page 5 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

3.

RCIC STEAM LEAK WITH GROUP 5 FAILURE BOOTH INST

a.

When directed by the Lead Examiner, insert Manual Trigger 7 and verify RC07 activates Key Parameter Response: Rising temperatures and radiation levels in the RCIC room Key Expected Alarms: 4-A-11 (REACTOR BUILDING HI RADIATION), 3-B-56 (HIGH AREA TEMP STEAM LEAK)

@ 130°F Auto Actions: Group 5 Isolation (Disabled)

BOP Monitors and reports rising RCIC area temperatures and radiation level.

BOOTH INST

b.

If sent as the RBO to investigate the steam leak, wait one minute and report that it appears there is a steam leak coming from the vicinity of MO-2078.

May direct the RBO to investigate the leak.

Enters C.4-B.02.04.A (STEAM LEAKS OUTSIDE PRIMARY CONTAINMENT)

Evacuates RCIC room or entire Reactor Building CRS SS315.106 SS315.116 Enters C.5-1300 (SECONDARY CONTAINMENT CONTROL) and directs isolation of RCIC (Group 5)

BOP CR200.151 CR200.161 Enters C.4-B.04.01.E (PRIMARY CONTAINMENT ISOLATION - GROUP 5)

BOOTH INST

c.

When MO-2075 is closed, verify Event Trigger 29 activates. This will delete the RCIC leak (RC07)

Closes MO-2075 and MO-2076

SIMULATOR SCENARIO 3 Page 6 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

d.

If directed as the RBO to provide status after RCIC isolation valves have been shut, state that there is NO steam flow noise and steam is clearing from the room.

CRS Evaluates TS LCO 3.5.3 Condition A as NOT MET SS299.353 Action A.1 - Verify HPCI operable immediately CR299.355 Action A.2 - Restore RCIC within 14 days Event 4

4.

INADVERTENT ADS TIMER INITIATION Optional: This event has been validated as an optional event. If the BOP/CRS does not need an Instrument Malfunction/Tech Spec call, this event may be omitted from the scenario.

BOOTH INST

a.

When directed by the lead evaluator, Insert Manual Trigger 9 verify AP07 activates.

Key Parameter Response: 107 second timer initiates Key Expected Alarms: 3-A-25 (AUTO BLOWDOWN TIMER ACTIVATED)

BOP Announces alarm Auto Actions: None SS315.160 Enters C.4-G (INADVERTENT ECCS INITIAION)

CR200.204 Verifies alarm and timer initiation is inadvertent Places ADS Inhibit Switched to INHIBIT CRS Evaluates TS LCO 3.3.5.1 Condition A & G as NOT MET SS299.351 Action G.1 - Declare ADS valves inoperable in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CR299.353 Action G.2 - Restore to operable in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months NOTE: With the Inhibit switches in INHIBIT the ADS system is non-functional. CRS should not wait the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months as allowed by LCO 3.3.5.1.

Evaluates TS LCO 3.5.1 K & L as NOT MET Action L - Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months / Mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

SIMULATOR SCENARIO 3 Page 7 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

5.

MAIN TURBINE VIBRATIONS BOOTH INST

a.

When directed by the Lead Examiner, insert Manual Trigger 11 and verify TU03A/B/C activates.

Key Parameter Response: Rising vibrations on Main Turbine shaft bearings 1, 2 and 3.

Key Expected Alarms: 7-B-33 (TURBINE VIBRATION HIGH)

BOP Follows ARP 7-B-33 (TURBINE VIBRATION HIGH)

Auto Actions: None If power reduction is necessary then perform C.4-F (Rapid Power Reduction)

If sustained Turbine-Generator vibration levels approach 15 Mils, then reduce recirculation flow to minimum, initiate a manual reactor scram and manually trip the Turbine CRS SS315.159 Directs C.4-F (Rapid Power Reduction)

NOTE: Lowering Reactor power will NOT be successful in reducing turbine vibration.

OATC CR200.203 Lowers reactor power by lowering recirc flow in an attempt to mitigate turbine vibrations.

6.

CONTINUED VIBRATIONS - REACTOR SCRAM CRS SS315.164 Directs a reactor scram IAW C.4.K (Immediate Reactor Shutdown)

BOOTH INST NOTE: When the Mode switch is placed in SHUTDOWN, verify EVENT TRIGGER 28 activates TC02 tripping the turbine and TU03A/B/C turbine vibrations ramp to 0%.

OATC CR200.208 Depresses pushbuttons for REACTOR SCRAM A and B and places the Mode Switch in SHUTDOWN

SIMULATOR SCENARIO 3 Page 8 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

7.

Hydraulic ATWS OATC Provides a Scram Report Reactor Scram, Mode Switch is in Shutdown, all rods are NOT in, Reactor power is >4%, 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: The CRS may wait to direct this action as time permits.

BOP o Inhibit ADS SS314.111 CR314.115 o C.5-3301 (Defeat MSIV Low-Low Level Isolation) o Places 4 Key switches to BYPASS on C-15 and C-17.

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

SS314.108 CR314.112 o C.5-3205 (Prevent Core Spray injection)

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

SIMULATOR SCENARIO 3 Page 9 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

8.

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)

SS314.101 Verifies Recirc pumps are at minimum speed and trips the pumps NOTE: ARI will NOT work for this scenario.

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

NOTE: 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 OATC Performs PART C (INCREASE COOLING WATER DIFFERENTIAL PRESSURE AND USE RMCS)

Bypasses RWM Verifies 12 CRD pump is running 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 13 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 Establish Drive Pressure as high as possible below 400 psig by one or more of the following:

SIMULATOR SCENARIO 3 Page 10 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES 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 15 and verify CH22 is modified to 0.

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

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

c. When requested to deenergize the ARI valves insert Manual Trigger 17, 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

d. 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 C-05-B-21 clears, closes the SDV vent and drain valves

SIMULATOR SCENARIO 3 Page 11 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

e. IF THE SCRAM IS RESET and a Manual Reactor Scram is inserted for Part D, INSERT MANUAL TRIGGER 19 to deleted CH16 allowing the control rods to insert.

Inserts a Manual Reactor Scram Verifies all control rods fully inserted and informs the CRS

9.

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 27 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 26 goes True and SL01A deletes after 1 second so #11 SBLC pump will start.

Key Parameter Response: Selected pump Green light stays on and Red light stays off, SBLC discharge pressure remains at 0 psig OATC CR211.106 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.

SIMULATOR SCENARIO 3 Page 12 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

10. Hydraulic ATWS Level Leg Actions CRS Verify needed auto actions Identifies that power >4% & RPV level above -33 and directs Terminate and Prevent actions CT-46 During failure to scram conditions with reactor power above 4%, 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 LPCI injection as follows Open Knife switches (C-03): 10A-S31A/B Verify LPCI OBD Valves are closed, MO-2012/13 CRS Lets level drop until Power is <4% 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 Uses Condensate & Feedwater as necessary to maintain established level band.

SIMULATOR SCENARIO 3 Page 13 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

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

11. Hydraulic ATWS Pressure Leg Actions CRS/

BOP Stabilize RPV pressure below 1056 psig using the one remaining Bypass Valve and/or SRVs (LL-SET)

12. (PRIMARY CONTAINMENT CONTROL)

BOP 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.

THROTTLE OPEN MO-2008 (2009) to provide ~4000 gpm per pump.

SIMULATOR SCENARIO 3 Page 14 of 14 ILT-SS-29E (2015 ILT NRC Scenario 3) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES CLOSE MO-2002 (2003), HX Bypass.

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

BOOTH INST When control rods are being inserted using Part C AND when directed by the Lead Examiner, INSERT MANUAL TRIGGER 19 to deleted CH16 allowing the control rods to insert.

13. 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 being restored following the all rods in condition.

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.

SIMULATOR SCENARIO 4 Page 1 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-30E SEG TITLE:

2015 ILT NRC SCENARIO 4 REV. #

0 PROGRAM:

INITIAL LICENSE TRAINING MT-ILT COURSE:

NRC SIMULATOR EVALUATION N/A TOTAL TIME: 45-90 MINUTES Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

SIMULATOR SCENARIO 4 Page 2 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Main Turbine Bypass Valve fails CLOSED

2. RBCCW Pump trip

3. 11 Recirc Pump trip

4. RMCS Normal Rod insertion failure

5. Dual Recirc Pump Trip After EOP Entry:

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

Abnormal Events:

1. Loss of RBCCW Flow

2. Trip of One Recirc Pump

3. Trip of Two Recirc Pumps Major Transients:

1. LOCA requiring Emergency Depressurization Critical Tasks:

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

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

SIMULATOR SCENARIO 4 Page 3 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

1.

EXERCISE MAINTURBINE BYPASS VALVES Optional: This normal evolution has been validated as an optional event. If the BOP/CRS does not need a Normal Evolution/Tech Spec call, this event may be omitted from the scenario.

BOP Performs Test 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 to enter TS 3.7.7.A Cycles BV-1 by performing the following:

Selects BV-1 with BYPASS VALVE TEST switch FLOOR INST 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.

Presses BYPASS VALVE TEST pushbutton BOP Times and records valve travel to the OPEN position (15-25 seconds) and generator gross load (MWe)

Releases BYPASS VALVE TEST pushbutton Times and records valve travel to the CLOSED position (15-25 seconds)

Returns BYPASS VALVE TEST switch to OFF Cycles BV-2 by performing the following:

Selects BV-2 with BYPASS VALVE TEST switch Presses BYPASS VALVE TEST pushbutton Times and records valve travel to the OPEN position (15-25 seconds) and generator gross load (MWe)

Notifies CRS that BV-2 will NOT open

SIMULATOR SCENARIO 4 Page 4 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

b.

Acknowledge BV-2 failure as Operations Management.

CRS Instructs BOP to stop test and reevaluates TS 3.7.7 Enters Condition A 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

2.

11 RBCCW PUMP TRIP Optional: This event has been validated as an optional event. If the BOP does not need a component malfunction, this event may be omitted from the scenario.

BOOTH INST

a.

When directed by the Lead Examiner, insert MANUAL TRIGGER 1

1) Verify the following Malfunction goes active:

SW01A, #11 RBCCW Pump Trip Key Parameter Response: #11 RBCCW Pump trips and the Standby #12 RBCCW Pump fails to auto start.

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

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

CR200.152 Verify a RBCCW pump is running o Notices that #12 RBCCW Pump failed to auto start and manually starts the pump

b.

When notified to investigate, wait 2 minutes and 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.

SIMULATOR SCENARIO 4 Page 5 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

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 3

3.

11 RECIRC PUMP LOCKOUT BOOTH INST

a.

When directed by the Lead Examiner, insert MANUAL TRIGGER 3, and verify RR05A activates.

Key Parameter Response: Loss of flow in the A Recirc Loop and Reactor power lowering.

Key Expected Alarms: 4-C-1 (RECIRC A LOCKOUT)

Automatic Actions: None BOP Takes actions IAW C.4-B.01.04.A (TRIP OF ONE RECIRC PUMP)

Notifies CRS

b.

When contacted as engineering, maintenance or plant management, state that the appropriate investigations and/or notifications will be initiated.

Closes 11 Recirc Pump Discharge valve After 5 minutes, re-opens 11 Recirc Pump Discharge Valve OATC Takes actions IAW C.4-B.05.01.02.A (CONTROL OF NEUTRON FLUX OSCILLATIONS)

Determines plant is operating in the Unanalyzed Region of the P-F map

SIMULATOR SCENARIO 4 Page 6 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Takes action IAW C.4-F (RAPID POWER REDUCTION)

NOTE: Based on validation, the crew should decide to lower power to approximately 45-55%.

Inserts control rods to exit Unanalyzed Region CRS Evaluates TS LCO 3.4.1 as NOT met.

Condition A applies for mismatched Recirc flows 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to match flows or establish single loop operations.

Event 4

4.

RMCS NORMAL ROD INSERTION FAILURE

a.

When the OATC attempts to insert the second control rod, the Rod Insert Switch will fail to respond. Verify Event Trigger 25 (03-S72-01) activates when the second control rod (34-31) is selected.

Key Parameter Response: No indicating light response from the directional solenoid valves or CRDH.

OATC Key Expected Alarms: None Auto Actions: None B.01.03-05.H.1 (INOPERABLE CONTROL RODS)

If the Control Rod is NOT at position 00, then attempt to insert the control rod using the following:

NOTE: The crew is also allowed to use EMERG ROD IN based on entry into C.4-F (RAPID POWER REDUCITON). These procedures may NOT be used.

Place Rod Out Notch Override Switch in EMERG ROD IN.

B.05.05-05.H.1 (RMCS FAILURE)

If RMCS failure detected and normal rod insertion capability is lost then place Rod Out Notch Override Switch in EMERG ROD IN.

SIMULATOR SCENARIO 4 Page 7 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

5.

12 RECIRC PUMP LOCKOUT When directed by the Lead Examiner, insert MANUAL TRIGGER 5, and verify RR05B activates.

Key Parameter Response: Loss of flow in the B Recirc Loop and Reactor power lowering.

Key Expected Alarms: 4-C-2 (RECIRC B LOCKOUT)

Automatic Actions: None OATC Takes action IAW C.4-B.01.04.B (TRIP OF TWO RECIRC PUMPS)

If in Mode 1 or 2, then manually scram the reactor IAW C.4-K (IMMEDIATE REACTOR SHUTDOWN)

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

BOOTH INST

a.

Verify Event Trigger 29 goes active when the Mode switch is placed in SHUTDOWN. This will initiate the following:

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

BOOTH INST

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

Verify FW16A & B activate.

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. Verify RR01B activates.

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

SIMULATOR SCENARIO 4 Page 8 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 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.

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.

SIMULATOR SCENARIO 4 Page 9 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 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 6

6.

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

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 BOOTH INST NOTE: If these start automatically they will still trip. Verify the following:

When RCIC flow reaches ~ 100 gpm, verify EVENT TRIGGER 26 activates. This will trip RCIC (RC03) after a 30 second time delay.

When HPCI MO-2036 begins to open (Red Light ON), verify EVENT TRIGGER 27 activates. This will immediately trip HPCI (HP03).

OATC Attempts to start HPCI and RCIC NOTE: Both systems are set to 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

SIMULATOR SCENARIO 4 Page 10 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

b.

If directed to Close CRD-168, insert Trigger 7 and verify remote CH34 activates May close CRD-168 IAW C.5-3204 (RPV Makeup With CRD) - Only one CRD Pump 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

7.

LOCA in Primary Containment (Drywell):

BOP Reports Drywell pressure rising Reports EOP entry conditions.

o DW pressure, DW Temp and Torus temp NOTE: Containment Spray/Cooling actions may not be taken if the crew prioritizes RPV water level.

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

Start Torus sprays Start all available Torus cooling Spray the Drywell BOP Performs C.5 1200 actions Places Torus Sprays in service IAW C.5-3502 (Containment Sprays):

o Verifies RHR Pumps running o Takes Cont Spray/Cooling LPCI Initiation Bypass (B) to BYPASS

SIMULATOR SCENARIO 4 Page 11 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

SIMULATOR SCENARIO 4 Page 12 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

8.

Alternate RPV Level Control / Emergency Blowdown:

CRS SS304.226 CR304.139 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 28 goes active when A SRV Handswitch is taken to Open BOP/

OATC Opens 3 ADS SRVs

1) Verify that Malfunction RR03B (B Loop Rupture) 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.

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.

SIMULATOR SCENARIO 4 Page 13 of 13 ILT-SS-30E (2015 ILT NRC Scenario 4) Rev. 0 SCENARIO TIME-LINE:

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

9.

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.

ML15174A373

Text

Navigation menu

Search