ML15174A373

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2015 Monticello Nuclear Generating Plant Initial License Examination Administered Simulator Scenarios
ML15174A373
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 06/15/2015
From: Mcneil D
NRC/RGN-III/DRS/OLB
To:
Xcel Energy
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Download: ML15174A373 (54)
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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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS 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 a. Respond as RBO that you are standing by at the BOP Directs RBO to be stationed by the RBCCW pumps Operator RBCCW pumps CR208.102 Booth b. Respond as RBO that the #12 RBCCW pump BOP Directs RBO to verify suction and discharge valves for Operator suction and discharge valves are fully open #12 RBCCW pump are fully open (Step 3)

BOP BOP starts #12 RBCCW pump from C-06 Booth c. Respond as RBO that the #12 RBCCW pump is BOP Directs RBO to locally check pump and motor Operator operating normally performance of #12 RBCCW pump Booth d. When directed by the BOP to close the #11 BOP Directs RBO to slowly CLOSE discharge valve on #11 Operator RBCCW pump discharge valve, INSERT RBCCW pump and then immediately secures the pump MANUAL TRIGGER 1. When ramp is complete, immediately notify the BOP that the #11 RBCCW pump discharge valve is CLOSED Booth e. When directed to OPEN the #11 RBCCW pump BOP Directs RBO to fully open the discharge valve for #11 Operator discharge valve, INSERT MANUAL TRIGGER 3 RBCCW pump and verify the valve opens. Once OPEN, notify Reports to the CRS that the #12 RBCCW pump is the BOP that the discharge valve for #11 RBCCW running and that #11 RBCCW pump is secured pump is OPEN 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 2 2. #11 CRD PUMP SHAFT SHEAR Booth a. When directed by the Lead Evaluator, insert Operator MANUAL TRIGGER 5 and verify CH26A activates:

Key Parameter Response: CRDH pressures and flows SS315.102 lower 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 Direct / Perform C.4-B.01.03.A (Loss Of CRD Pump OATC Flow)

Booth b. As the RB Operator, wait one minute and respond OATC Starts 12 CRD Pump Operator as follows:

Booth 1) 11 CRD Pump is running but has an Verifies CRDH parameters are restored Operator extremely high pitch sound.

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 c. Acknowledge any investigation / notification BOP Initiates investigation Operator requests to Engineering, Maintenance and Plant Management.

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 3 3. STUCK OPEN G SRV Booth a. When directed by the Lead Evaluator, Insert Operator Manual Trigger 7 and verify Malfunction AP01G goes active.

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

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

CRS Direct Rapid Power Reduction C.4-F when the SRV fails SS315.109 to close SS315.159 Booth 3 seconds after the OATC takes the #12 Recirc Pump to OATC Reduces recirculation flow as needed Operator lower, VERIFY EVENT TRIGGER 9 goes active and CR200.203 APO1G is deleted. This will cause SRV G to CLOSE.

Booth b. Acknowledge any investigation / notification CRS Evaluates TS 3.3.6.3 (LLS INST) as NOT MET with the Operator requests to Engineering, Maintenance and Plant SS299.354 switch in OFF (Div 1) and Div 2 circuits bypassed.

Management. CR299.356

  • Condition A applies which requires the channels to be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> NOTE: If SRV left open long enough, the crew may place May also evaluate TS 3.6.1.5 (LLS Valves) & TRM 3.4.4 Torus cooling in service. (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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 4 4. Oil leak on 2R / Emergency transfer to 1R Booth a. When directed by the Lead Examiner, insert Operator 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
  • Dispatch an operator to check the 2R transformer imperative to do the emergency transfer operation. or request security to observe 2R transformer with cameras Booth b. Role Play the dispatched operator or as security if
  • Relay information about the oil leak to the CRS Operator 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 CRS Directs performance of B.09.06-05.E.1 (Transfer of Plant Buses From 2R to 1R - Emergency Method)

BOP Performs emergency closed bus transfer from 2R to 1R CR262.133

  • 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:

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

  • 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 NOTE: Verify the BOP has opened the knife switch on
  • Open knife switch 16 on panel C-31 Operator C-31. If not, then DO NOT open 3N4 with the following actions.

Booth c. Role Play the equipment operator dispatched to

  • Open 3N4 34.5KV Circuit Breaker Operator open 3N4 as necessary. Wait 10 minutes and:
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
  • Notify the System Dispatcher (TSO) of the operation, to OPEN Transfer to the 1R Transformer CRS Evaluates LCO 3.8.1 as NOT met SS299.358 CR299.358
  • 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Booth d. Role Play as necessary to inform the crew that

  • Required Action A.1: Initiate SR 3.8.1.1 Operator another operator will be called in to perform (OSP-MSC-0542), Weekly Breaker Alignment, OSP-MSC-0542 Indicated Power Availability, and Voltage to AC &

DC Power Distribution Checks) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

  • Required Action A.2: Declare required features INOP within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Booth e. For notifications, Role Play Single Point of Contact
  • Make notifications for the LCO Entry.

Operator and plant support personnel as necessary 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 5. STUCK OPEN G SRV Booth a. When directed by the Lead Evaluator, Insert Operator 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 CRS Direct Rapid Power Reduction C.4-F when the SRV fails already been completed and will not be re-performed. SS315.109 to close SS315.159 OATC REDUCEs recirculation flow as needed CR200.203 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 OATC

  • When directed, manually scrams the reactor then insert a manual reactor scram prior to reaching 110°F bulk torus water temperature.

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

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

6. IMMEDIATE REACTOR SHUTDOWN CRS May direct reactor scram or an Immediate Reactor SS315.164 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 Supervises response to a Reactor Scram SS315.101 OATC C.4-A (Reactor Scram) actions:

Booth a. When the Mode switch is placed in SHUTDOWN CR200.146

  • Place Mode Switch in SHUTDOWN.

Operator verify Event Trigger 17 goes active. This will close the stuck open SRV and initiate the Torus leak.

The OATC may address the stuck rod before proceeding

  • Verifies all Control Rods are inserted to or with the remaining C.4.A actions (See Event 7). 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:

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

  • 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 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

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

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

  • 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.

  • 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:

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

  • 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 a. Verify Event Trigger 17 is active and verify Operator 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 BOP Respond to annunciators cycle OATC NOTE: It takes ~19 minutes to reach -3.3 ft which is the

  • Notify Rad Protection that a harsh environment or decision point for a Reactor Scram and Emergency increase radiation environment may exist in the depressurization RHR rooms and that entry is required
8. UNISOLABLE TORUS LEAK/ EOP 1300 ACTIONS NOTE: The RHR Room water Level is never reported as BOP
  • Dispatches an operator to investigate having reached Max Safe Level (15 inches) and the OATC timeline of local reports allows the Torus water level to be the critical parameter.

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Booth a. Role Play in-plant operator. When dispatched,

  • Receive the report from the plant and relay the Operator WAIT 2 MINUTES then report that the water level information to the CRS.

is approximately 8 inches in both RHR rooms.

  • 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 BOP

  • Verify the Reactor Bldg Floor drain Sump Pump is pct112. OATC running Booth b. Role Play in-plant operator. If asked to report the
  • Attempt to identify and isolate the source of the Operator source of the leak, WAIT UNTIL Torus Water water Level is -1 feet, then report that the Leak is unisolable from a weld at the ring header in Bay 4.

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
  • Reports EOP 1200 Entry Condition when Torus Torus water level water level (Narrow Range) is < -4 inches

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS SS314.115

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

Booth a. Role Play the out-plant operator if assigned to BOP

  • May direct an in-plant operator to perform Operator perform C.5-3401: Wait 2 minutes and report that CR314.119 C.5-3401 steps for Core Spray and RHR. (May he must find boots as PPE for the water on the choose not to perform due to safety concerns) floor.
  • 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 CRS When it is determined that Torus Water Level can NOT above -3.3, then scram and execute EMERGENCY be maintained above -3.3 ft, Blowdown and enter EOP DEPRESSURIZATION per C.5-2002. 2002.

CRS

  • Recognizes when Torus Water Level can NOT be maintained above -3.3 ft
  • Verifies Torus level > -5.9 ft.

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS 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 a. Role Play the Reactor Bldg Operator as necessary
  • Informs the CRS and performs actions to insert Operator and, as requested wait 1 minute and insert Control Rod 14-27 MANUAL TRIGGER 19 to close CRD-14
  • May reset the scram and insert the control rod Booth 1) Verify REMOTE FUNCTION CH22 goes 1. Direct an out-plant operator to manually close Operator active to close CRD-14 CRD-14 Booth b. If the OATC places the ROD MOVEMENT
  • Bypass the RWM Operator CONTROL switch to ROD IN to insert Rod 14-27,
  • Select and insert the full out rod verify EVENT TRIGGER 21 goes active and MALFUNCTION CH02_058 DELETES.

Booth c. If the OATC uses EMERG ROD IN to insert Rod Operator 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:

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

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 Crew
  • Remain in simulator for potential questions from discretion of lead instructor/evaluator evaluator.
c. End the scenario by placing the simulator in Crew
  • No discussion of scenario or erasing of procedure FREEZE. 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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

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:

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

  • Verifies MO-1134 is OPEN.

CR259.103

  • 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 a. When directed by the lead evaluator, INST 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS 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
  • Condition A is still met because the plant is not CR299.353 below the limit specified in the COLR.

Event 3 3. VESSEL FLANGE SEAL LEAK BOOTH a. When directed by the lead evaluator, INST 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 BOP Responds to annunciator and reports to the CRS LEAK)

Auto Actions: None.

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS BOOTH c. When CV-2369 is placed in OPEN, verify Event BOP Places CV-2369 in OPEN INST Trigger 29 activates. This will delete the Vessel Flange Seal Leak alarm after a 2 minute delay.

BOOTH d. If confirmatory indication requested, state as the Alarm will clear after 2 minutes and 1 minute later CV-INST RBO that PS 2-102 reads 616 psig. 2369 is placed back in the closed position.

BOOTH e. Acknowledge as Plant Technical Staff the receipt Notifies Plant Technical Staff of the receipt of the INST of the annunciator. annunciator Event 4 4. CONTROL ROD 18-19 DRIFTS OUT BOOTH When directed by the Lead Evaluator, insert OATC Acknowledges the alarm and informs the CRS that Control INST MANUAL TRIGGER 5 and verify 03-S72-02 CR200.226 Rod 18-19 is drifting out.

activates for 2 seconds and CH01_034 activates. SS315.167 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 a. Once the OATC holds the Rod Insert switch to IN
  • May hold the Rod Insert Switch to IN or release it.

INST for 5 seconds, verify the control rod drift malfunction CH01_034 deletes.

BOOTH b. As the Reactor Building Operator; when directed CRS/ Directs the Reactor Building Operator to hydraulically INST to isolate and/or disarm Control Rod 26-27, wait 3 BOP isolate and/or electrically disarm HCU 18-19 IAW B.01.03-minutes, insert Manual Trigger 7 and report that 05.G.2 (HYDRAULIC CONTROL UNIT ISOLATION).

the control rod is isolated and/or disarmed.

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS SS299.349

  • Action C.1: Fully insert control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> CR299.351
  • Action C.2: Disarm CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Event 5 5. 12 STATOR WATER COOLING PUMP TRIP WITH REACTOR SCRAM BOOTH a. When directed by the lead evaluator, INST 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 SS315.126 Enters procedure C.4-B.06.02.04.A (STATOR COOLING COOLING WTR FAILURE WATER FAILURE).

Auto Actions: Turbine Generator Runback. An automatic CR200.171 Recommends that a Manual Reactor Scram be inserted.

scram will occur if both Main Turbine Bypass Valves go full open due to the Runback.

OATC Inserts a manual Reactor scram.

CR200.166 SS315.164 OATC Takes actions IAW C.4-A (Reactor Scram) PART A:

SS315.101

  • Place Mode Switch in SHUTDOWN.

CR200.146 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:

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

  • 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

  • Verify SDV Vent and Drain Valves closed.

performed depending on when the SDV leak is recognized.

  • 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.

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

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

  • Verify the Generator Field Breaker Open.

performed depending on when the SDV leak is recognized.

  • 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS 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 Perform the actions of EOP-1300 (Secondary SS304.196 Containment Control)

SS304.239 CR304.105

  • Directs evacuation of area or entire reactor CR304.153 building.
  • Reports Reactor Building radiation levels and temperatures are rising
  • Attempts to manually close SDV isolation valves reset due to a malfunction on the SDV high level bypass circuitry.

CRS Enters EOP-1300 (Secondary Containment Control)

  • Direct isolation of the SDV CRS
  • Recognizes when 2 area radiation levels have secondary containment through an unisolable break, SS304.198 exceeded Max Safe CR314.101 perform an Emergency Depressurization per C.5-2002 when max safe operating values are exceeded in two or more areas.

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

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

  • Verifies Torus level > -5.9 ft.

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. BOP

  • Recognizes that C & D SRVs failed to open
  • Opens additional SRVs until a total of 3 are open
8. SCENARIO TERMINATION FLOOR The scenario may be terminated when Emergency INST Depressurization has been performed.

The scenario may be also terminated at the discretion of Crew:

  • Remain in simulator for potential questions from lead instructor/evaluator 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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 1. RESTORE RCIC SUCTION TO THE CSTS Optional: This normal evolution has been validated as an CRS May perform refocus brief optional event. If the BOP operator does not need a BOP Performs B.02.03-05.G.2 (MANUAL SWITCHOVER OF normal evolution, this event may be omitted from the CR217.111 RCIC SUCTION FROM THE TORUS TO THE scenario.

CONDENSATE STORAGE TANKS).

  • Verifies Torus level <+2 and CST level >28 NOTE: Based on initial conditions, this TS has already
  • Concurrently closes MO-2100 and MO-2101 NOTE: Without an automatic transfer signal, MO-2102
  • Once dual indication is observed on MO-2100 &

must be manually opened. 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 a. When directed by the lead instructor, insert INST 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:

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

b. If directed to investigate CRD temperatures, wait 2 Sends Reactor Building Operator to investigate CRD minutes and report that many CRD temperatures temperature recorder.

are rising and that CRD 26-15 is in alarm. The Recognizes CRD FCV failure highest reading temperature is 255°F.

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 OATC Coordinates with Reactor Building Operator (RBO) and support shift of FCV, WAIT 1 minute and report CR201.111 performs the following:

you are standing by.

BOOTH d. When directed to OPEN CRD-18-2 and CRD

  • Directs RBO to OPEN CRD-18-2 & CRD-16-2 INST 2, WAIT 1 minute then use Manual Trigger 3 to modify REMOTE FUNCTION CH17 to OPEN and report this action to the Control room.
  • 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 e. When directed to CLOSE CRD-16-1 and
  • Closes CRD-16-1 & CRD-18-1 INST CRD-18-1, WAIT 1 minute, then use Manual Trigger 5 to modify REMOTE FUNCTION CH16 to CLOSE and report this action complete.
f. If directed to report CRD temperatures, report all
  • Acknowledge annunciator 5-B-41 clear and alarms are clear and all temperatures are lowering informs Shift Supervision.

to normal.

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 3 3. RCIC STEAM LEAK WITH GROUP 5 FAILURE BOOTH a. When directed by the Lead Examiner, insert INST 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 b. If sent as the RBO to investigate the steam leak,

  • May direct the RBO to investigate the leak.

INST wait one minute and report that it appears there is a steam leak coming from the vicinity of MO-2078.

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

SS315.116 BOP Enters C.4-B.04.01.E (PRIMARY CONTAINMENT CR200.151 ISOLATION - GROUP 5)

CR200.161 BOOTH c. When MO-2075 is closed, verify Event Trigger 29 Closes MO-2075 and MO-2076 INST activates. This will delete the RCIC leak (RC07)

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS BOOTH d. If directed as the RBO to provide status after CRS Evaluates TS LCO 3.5.3 Condition A as NOT MET INST RCIC isolation valves have been shut, state that SS299.353 there is NO steam flow noise and steam is

  • Action A.1 - Verify HPCI operable immediately clearing from the room. 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 a. When directed by the lead evaluator, INST Insert Manual Trigger 9 verify AP07 activates.

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

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> CR299.353
  • Action G.2 - Restore to operable in 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> NOTE: With the Inhibit switches in INHIBIT the ADS Evaluates TS LCO 3.5.1 K & L as NOT MET system is non-functional. CRS should not wait the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as allowed by LCO 3.3.5.1.
  • Action L - Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> / Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

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

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 5 5. MAIN TURBINE VIBRATIONS BOOTH a. When directed by the Lead Examiner, insert INST 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 BOP Follows ARP 7-B-33 (TURBINE VIBRATION HIGH)

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 Directs C.4-F (Rapid Power Reduction)

SS315.159 NOTE: Lowering Reactor power will NOT be successful in OATC

  • Lowers reactor power by lowering recirc flow in an reducing turbine vibration. CR200.203 attempt to mitigate turbine vibrations.
6. CONTINUED VIBRATIONS - REACTOR SCRAM CRS Directs a reactor scram IAW C.4.K (Immediate Reactor SS315.164 Shutdown)

BOOTH NOTE: When the Mode switch is placed in SHUTDOWN, OATC Depresses pushbuttons for REACTOR SCRAM A and B INST verify EVENT TRIGGER 28 activates TC02 tripping the CR200.208 and places the Mode Switch in SHUTDOWN turbine and TU03A/B/C turbine vibrations ramp to 0%.

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

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

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 Enters EOP 1100 RPV Control, transitions to EOP 2007, SS304.213 Failure to Scram, and directs the following:

SS304.201 SS304.244 CR314.129 CR314.104 NOTE: The CRS may wait to direct this action as time BOP o Inhibit ADS permits.

SS314.111 o C.5-3301 (Defeat MSIV Low-Low Level Isolation)

CR314.115 o Places 4 Key switches to BYPASS on C-15 and C-17.

NOTE: The CRS may wait to direct this action during the SS314.108 o C.5-3205 (Prevent Core Spray injection)

CR314.112 Level Leg actions.

- 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:

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

8. Hydraulic ATWS Power Leg Actions CT-48 During failure to scram conditions with a critical OATC
  • Performs C.5-3101 (Alternate Rod Insertion) reactor, insert control rods using one or more CR314.105 methods contained within C.5-3101 to achieve reactor shutdown under all conditions.

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. OATC Performs PART C (INCREASE COOLING WATER If only one part is performed, the actions from the other DIFFERENTIAL PRESSURE AND USE RMCS) part are not applicable

  • 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 a. When requested to close CRD-168, activate

  • Directs Reactor Building Operator to CLOSE INST Manual Trigger 13 and verify CH34 goes active. CRD-168, CRD-79-1 & CRD-79-2 Wait 1 minute and report it as closed.
  • 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS o Throttle closed the CRD Flow Control Valve o Throttle closed Open MO-3-20 Drive Pressure to CRD BOOTH b. If requested to close CRD-14, activate Manual o Directs the Reactor Bldg Operator to INST Trigger 15 and verify CH22 is modified to 0. CLOSE CRD-14 to raise drive pressure BOOTH

  • Select and insert rods in non-peripheral core INST 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.

  • Evacuate personnel from the RB 896 Floor and If only one part is performed, the actions from the other the Equipment Drain tank Room part are not applicable BOOTH c. When requested to deenergize the ARI valves
  • Directs the in-Plant operator to deenergize the INST insert Manual Trigger 17, this modifies RR18 is to ATWS 125 VDC Valves by opening D-21 & D-11.

Open. Wait 1 minute and report the ATWS 125 VDC Breakers Open.

NOTE: These contacts are modeled in the simulator. The

  • Installs jumpers to bypass all automatic scram jumpers are included with the C.5-3101 procedure. signals in C-15 & C-17
  • Resets the scram BOOTH d. If requested to open CRD-14, modify Remote
  • Directs the Reactor Bldg Operator to open CRD-14 INST Function CH22 is to Open, wait 1 minute and report CRD-14 Open.
  • 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS BOOTH e. IF THE SCRAM IS RESET and a Manual Reactor

9. SBLC Initiation Problems BOOTH NOTE: Event Triggers 28 or 29 will auto activate to clear INST the trip on the second SBLC pump that is started.
a. If #11 SBLC is attempted to be started first, verify CRS Directs SBLC initiation before Torus temp reaches 110ºF Event Trigger 27 goes True and SL01B deletes using the SBLC Hard Card, B.03.05-05.G.1 (SBLC after 1 second so #12 SBLC pump will start. 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 OATC Places 11A-S1 SBLC System Selector Switch to SYS 1 or stays on and Red light stays off, SBLC discharge pressure CR211.106 SYS 2 and recognizes that the first pump fails to start.

remains at 0 psig Key Expected Alarms: None

  • Starts the other SBLC pump Auto Actions: RWCU isolates and pumps trip ONLY when
  • Verifies the RWCU Pumps trip and the Group 3 the second pump starts. 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:

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

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 BOP
  • Prevents injection from Condensate & Feedwater above 4%, terminate and prevent injection from all CR314.112 by placing the FRV Controllers in Manual and sources except SBLC, RCIC, and CRD until level closing the Reg Valves lowers to at least -33.

BOP

  • Prevents injection form HPCI by placing the Aux Oil Pump in PTL
  • Prevents LPCI injection as follows
  • 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

  • Records final level and sets level band and feedwater injection re-established and used to maintain level in the desired 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:

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

11. Hydraulic ATWS Pressure Leg Actions CRS/
  • Stabilize RPV pressure below 1056 psig using the BOP 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
  • If Torus Water Temperature exceeds 90°F, notify the temperature EOP-1200 actions may be taken. 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:

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

  • CLOSE MO-2002 (2003), HX Bypass.
  • Verify V-AC-5(4), A(B) RHR RM COOLER in operation.

BOOTH When control rods are being inserted using Part C INST 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 Crew
  • Remain in simulator for potential questions from discretion of lead instructor/evaluator evaluator.
c. End the scenario by placing the simulator in Crew
  • No discussion of scenario or erasing of procedure FREEZE. 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 Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 1 1. EXERCISE MAINTURBINE BYPASS VALVES Optional: This normal evolution has been validated as an BOP Performs Test OSP-TRB-0570 (EXERCISE MAIN optional event. If the BOP/CRS does not need a Normal TURBINE BYPASS VALVES)

Evolution/Tech Spec call, this event may be omitted from the scenario.

BOOTH a. Acknowledge report of changing radiological Notifies RP of changing radiological conditions INST 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 NOTE: Depending on how long BV-1 is OPEN; the receipt
  • Presses BYPASS VALVE TEST pushbutton INST of 5-B-32 (Main Steam Line Leakage) will be expected based on difference in total steam flow and steam flow to BOP
  • Times and records valve travel to the OPEN position the turbine.

(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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS BOOTH b. Acknowledge BV-2 failure as Operations CRS Instructs BOP to stop test and reevaluates TS 3.7.7 INST Management.

  • Enters Condition A
  • Required Action A.1 - Restore BV-2 to operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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 a. When directed by the Lead Examiner, insert INST 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
  • Notifies Reactor Building and/or Turbine Building report as the Outplant operator that the breaker Operator(s) to investigate the cause of the trip.

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

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

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

c. Depending on how rapidly the BOP starts #12
  • Notifies Engineering and/or Maintenance of the RBCCW Pump, RWCU may or may not isolate on failure of 11 RBCCW Pump and the failure of 12 high temperature. RBCCW Pump to auto start.

BOOTH d. If notified, acknowledge the report.

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

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

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

Event 3 3. 11 RECIRC PUMP LOCKOUT BOOTH a. When directed by the Lead Examiner, insert INST 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)

b. When contacted as engineering, maintenance or
  • Closes 11 Recirc Pump Discharge valve plant management, state that the appropriate investigations and/or notifications will be initiated.
  • 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:

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

NOTE: Based on validation, the crew should decide to

  • Inserts control rods to exit Unanalyzed Region lower power to approximately 45-55%.

CRS Evaluates TS LCO 3.4.1 as NOT met.

  • Condition A applies for mismatched Recirc flows
  • 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 OATC from the directional solenoid valves or CRDH.

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

  • Place Rod Out Notch Override Switch in EMERG based on entry into C.4-F (RAPID POWER ROD IN.

REDUCITON). These procedures may NOT be used.

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS 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 a. Verify Event Trigger 29 goes active when the SS315.101

  • Place Mode Switch in SHUTDOWN.

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

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

  • Verify all Control Rods are inserted to or beyond INST Verify FW16A & B activate. position 04.
2) A small break LOCA on a 2 minute ramp after
  • Provides scram script to CRS. Reports RPV less a 2 minute delay. Verify RR01B activates. 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:

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

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

  • Verify the Generator Field Breaker Open.

performed depending on when the LOCA is recognized.

  • Start the Turbine Aux Oil Pump.
  • 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:

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

  • 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 CRS Directs performance of C.5-1100 (RPV Control)

Control

a. Role Play in-plant operators as necessary. There OATC
  • Recognizes the loss of both Feed Pumps is no apparent cause for the loss of the Feed Pumps.
  • Attempts to restart the Feed Pumps
  • Notifies CRS that Feed Pumps will not start.

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

  • Attempts to start HPCI and RCIC INST 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).

NOTE: Both systems are set to trip on high exhaust

  • Notifies CRS that HPCI and RCIC both tripped on pressure complications from the LOCA. 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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS CT-16: Inhibit ADS to avoid auto initiation that would result in OATC/

  • Inhibits ADS a violation of cooldown rate or a loss of adequate core BOP cooling.

BOOTH b. If directed to Close CRD-168, insert Trigger 7 and

  • May close CRD-168 IAW C.5-3204 (RPV Makeup INST verify remote CH34 activates With CRD) - Only one CRD Pump OATC/
  • Starts a SBLC pump for injection IAW C.5-3203 BOP (Use of Alternate Injection Systems for RPV Makeup) o Verifies injection o Adequately monitors and reports RPV level and Pressure, both values and trends.

Event 7 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 CRS Directs performance of C.5-1200 (PC Control) taken if the crew prioritizes RPV water level.

  • Start Torus sprays
  • Start all available Torus cooling
  • Spray the Drywell BOP
  • Performs C.5 1200 actions

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:

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

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:

CREW SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES EXPECTED STUDENT RESPONSES POS Event 7 8. Alternate RPV Level Control / Emergency CRS Verifies two or more Injection Subsystems lined up with CONT Blowdown: SS304.226 pumps running.

CR304.139 CT-22 When RPV water level can NOT be maintained When RPV level is < -126 inches and prior to -149

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

  • Verifies Torus level > -5.9 ft.
  • Directs RPV Level restoration BOP
  • Verifies that both Core Spray Subsystems and LPCI Pumps are available for injection BOOTH a. Verify Event Trigger 28 goes active when A SRV BOP/
  • Opens 3 ADS SRVs INST Handswitch is taken to Open OATC
1) Verify that Malfunction RR03B (B Loop
  • Monitor and report RPV level values and trends Rupture) goes active at 3% severity.

BOP

  • Controls RPV injection from RHR.
  • Opens Knife Switch to Bypass LPCI 5 Minute Timer using C.5-3208
  • Throttles MO-2013.
  • May divert LPCI flow using B.03.04-05.H (TORUS COOLING HARD CARDS)

BOP

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:

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

9. SCENARIO TERMINATION FLOOR a. The scenario may be terminated when Emergency INST Depressurization has been performed OR RPV water level is recovered above TAF.
b. The scenario may be also terminated at the Crew:
  • Remain in simulator for potential questions from discretion of lead instructor/evaluator evaluator.
c. End the scenario by placing the simulator in Crew:
  • No discussion of scenario or erasing of procedure FREEZE. marking is allowed.
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