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{{#Wiki_filter:SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 43 NRC Initial License Exam - Scenario #1 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team | |||
==References:== | |||
AOP 255.1, Rev. 44 AOP 255.2, Rev. 42 ARP 1C05A, Rev. 78 ARP 1C94, Rev. 48 IPOI 3, Rev. 143 OI 152, QRC 2, Rev. 1 OI 255, Rev. 87 OI 255 QRC 1, Rev. 3 OI 324, Rev. 113 OI 454, Rev. 65 OI 856.1, Rev. 45 Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 43 NRC Initial License Exam - Scenario #1 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: The plant is operating at 80% power due to a downpour for maintenance. Thunderstorms are forecast for the area. "B" SBDG was recently returned from maintenance. | |||
Turnover: Complete 'B' SBDG Testing per OI 324, SBDG, Section 6.4, synchronize and load. Raise Reactor power using control rods to a load line of 94-95%. Event # Malf # Eventy Type* Event Description 1 None N BOP Synchronize and load the 'B' SBDG IAW OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. 2 None C BOP TS SRO Report from field that 'B' SBDG has a jacket cooling water leak 'B' SBDG declared inoperable per TS 3.8.1 3 None R ATC Raise reactor power with control rods 4 rd02 3023 C ATC Stuck Control Rod 5 rd11b C RO CRD Pump trip 6 hp01 C BOP TS SRO HPCI spurious start requiring manual shutdown/isolation HPCI declared inoperable per TS 3.6. 7 ed01(a-e) rr15b stdg01 M ALL Loss of Offsite Power with Small break LOCA. Failure of 'A' SBDG to start in AUTO, will start in Manual. 8 hp02 C BOP HPCI starts in Manual but trips shortly after. Emergency Depressurization required. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions a. Reset to IC 23 or the Snap (1) Raise power to ~80% with Recirc and Rods. (2) Load Events (3) Load Malfunctions (4) Load Remote Functions b. Verify Events validate FALSE c. Ensure the following procedure is marked up prior to turnover and being provided to the candidates: (1) OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM a) Place a checkmark in the placekeeping area for the NOTE at the beginning of the section b) Place a checkmark in the first two steps of the section regarding bromination not occurring and the SBDG readiness checklist being completed. d. Build a schedule file to remove RD022223 on ET 20. (1) Verify the schedule file is RUNNING. e. Verify MOL Pull Sheets are out. EVENT TRIGGERS Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, 10, 11, 12, 13, 14, 15, 17, 30 Manual Trigger Manual Trigger 20 ZAORDPDI1825 >= .60 Drive Water DP > 295 psig 23 ZLOHPHS2312(2) == 1 & ZDIRPC71AS1(1) == 1 HPCI Inject Valve Opening after mode switch in SHUTDOWN Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 me Malf. No. Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN1C08B(26) 1C08B (C-02) B DIESEL GEN PANEL 1C 94 TROUBLE 1 Crywolf ON Setup rd022223 CONTROL ROD BLADE STUCK- ROD 22-23 3 Inactive Active Setup stdg01 TRIP OVERRIDE - 'A' SBDG 1G31 FAILS TO AUTO START Inactive Active Setup stdg02 TRIP OVERRIDE - 'B' SBDG 1G21 FAILS TO AUTO START Inactive Active Setup rd070615 CONTROL ROD ACCUMULATOR TROUBLE- ROD 06-15 45 sec 5 Inactive Active Setup Rd073435 CONTROL ROD ACCUMULATOR TROUBLE- ROD 34-35 1 min 5 Inactive Active Setup rd11b CRD HYDRAULIC PUMP TRIP- PUMP B 5 Inactive Active Setup hp01 HPCI INADVERTANT INITIATION 7 Inactive Active Setup rc01 RCIC PUMP TRIP 9 Inactive Active Setup ed01a LOSS OF OFF-SITE POWER SOURCES- BKR M 60 Sec 21 Inactive Active Setup ed01b LOSS OF OFF-SITE POWER SOURCES- BKR J 60 Sec 21 Inactive Active Setup ed01c LOSS OF OFF-SITE POWER SOURCES- BKR K 60 Sec 21 Inactive Active Setup ed01d LOSS OF OFF-SITE POWER SOURCES- BKR X5960 60 Sec 21 Inactive Active Setup ed01e LOSS OF OFF-SITE POWER SOURCES- BKR X5940 60 Sec 21 Inactive Active Setup rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP B 8 min 21 0 0.7 rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP B 3 min 23 As Is 1 Setup hp02 HPCI TURBINE TRIP 15 sec 23 Inactive Active Setup rd11a CRD HYDRAULIC PUMP TRIP- PUMP A 24 Inactive Active Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Schedule File for SEG. At Time On Event Action Description None 20 Delete malfunction rd022223 CONTROL ROD BLADE STUCK- ROD 22-23 None 22 Insert malfunction dg03b after 45 1G21 'B' DIESEL GENERATOR TRIP- DG B None 10 Insert remote dg19 to IDLE HS-3281B B DG 1G21 IDLE-RATED SWITCH (RATED,IDLE) None 11 Insert remote dg11 to PARALLEL 'B' DIESEL GEN 1G21 DROOP SWITCH (UNIT,PARALLEL) None 13 Insert remote dg19 to RATED HS-3281B B DG 1G21 IDLE-RATED SWITCH (RATED,IDLE) None 12 Insert remote dg11 to UNIT 'B' DIESEL GEN 1G21 DROOP SWITCH (UNIT,PARALLEL) None 28 Insert remote rd03 to 5.00000 CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 ISOLATION None 27 Insert remote rd03 to 100.00000 in 60 CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 ISOLATION None 14 Delete malfunction rd070615 CONTROL ROD ACCUMULATOR TROUBLE- ROD 06-15 None 15 Delete malfunction rd073435 CONTROL ROD ACCUMULATOR TROUBLE- ROD 34-35 None 17 Insert remote an05 to ACK REMOTE FUNC FEEDBACK AN05- ACK SWITCH 1C94 (NORM,ACK) None 17 Insert remote an05 to NORM after 5 REMOTE FUNC FEEDBACK AN05- ACK SWITCH 1C94 (NORM,ACK) | |||
Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist. | |||
If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Mild summer morning (Plant power levels) o Reactor Power Level % o Core Flow 40 Mlbm/hr Protected train o Protected Train is "A" Technical Specification Action statements in effect o None Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Start and load 'B' SBDG from the Control Room in accordance with OI 324, Section 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM for industry OE investigation. 2 hour load run is required to be performed for maintenance. Offsite Sources STP was completed just prior to turnover (< 1 hour ago). o Power assention in progress following a sequence exchange. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o Raise Power with rod withdrawal to 85% Power per RE Direction Comments, problems, operator workarounds, etc. o None Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Start 'B' ESW IAW OI 454 to support starting "B" SBDG: When directed to perform "B" ESW pump prestart checks: One (1) minute after the "B" ESW Pump is started: Simulator Operator: Inform the control room that time compression is being used and the "B" ESW Pump is ready for start. Simulator Operator Inform the control room that the "B"ESW Pump is running satisfactory. The strainer is rotating, auto vents are closed and that there is air flow in the room. The fan switch has been returned to auto. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. BOP Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. Start Emergency Service Water Pump 1P-99B per OI 454. Manually start either or both ESW pumps by performing either of the following: o Start B ESW PUMP 1P-99B by placing HS-4928B on 1C06 in the START position Verify B ESW PUMP 1P-99B running by observing the following on 1C06: o B ESW PUMP 1P-99B red indicating light is ON. o B ESW PUMP 1P-99B indicates normal running current of approximately 95-115 amps Verify adequate cooling for ESW Pump 1P-99B by observing that FI-4938B B ESW FLOW indicates greater than 300 gpm. As soon as possible after ESW pump start, perform the following: o Inspect the auto vent/vac breaker for evidence of excessive leakage. o Verify air flow from 1V-SF-56B, RHRSW/ESW Supply Fan. o After air flow is verified, operate 1V-SF-56B as directed by CRS. Control ESW/RHRSW pit level in accordance with OI 410. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the "B" SBDG Prelube pump is operating: Simulator Operator Inform the control room that the "B" SBDG Prelube Pump is running satisfactory. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. | |||
CRS Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. BOP Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. If starting the Standby Diesel Generator from the Control Room on 1C08 perform the following: Set Prelube Timer KS-3238B to 2.0 minutes. Start the B DIESEL GENERATOR 1G-21 PRELUBE pump by depressing the prelube pushbutton. After the Prelube Pump has been running for 1 minute, place B DIESEL GENERATOR 1G-21 CONTROL handswitch HS-3231B momentarily in the START position, and then return it to the AUTO position. Verify 1V-SF-21 Diesel Generator Supply Fan is running (verify red running light ON at 1C23). Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Paralleling the "B" SBDG to 1A4: When directed to place HS-3281, IDLE-RATED Switch in IDLE: One (1) minute after the request to place HS-3281B in IDLE: When requested to place HS-3234B, GOVERNOR MODE SWITCH in PARALLEL: One (1) minute after the request to place HS-3234B in PARALLEL: | |||
Simulator Operator Acknowledge the request. | |||
Simulator Operator Activate [ET 10]. Inform the control room that HS-3281B, IDLE-RATED SWITCH is in IDLE. Simulator Operator Acknowledge the request. Simulator Operator Activate [ET 11]. Inform the control room that HS3234B, GOVERNOR MODE SELECT SWITCH is in PARALLEL CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Verify SBDG 1G-21 started. At 1C94, verify HS-3281B, IDLE-RATED SWITCH, in IDLE. Perform the following on 1C08: o Adjusts "B" DIESEL GENERATOR 1G-21 VOLTAGE ADJUST control to maintain "B" DIESEL GENERATOR 1G-21 VOLTS meter at approximately 4160 volts. o Adjusts "B" DIESEL GENERATOR 1G-21 SPEED ADJUST control to maintain "B" DIESEL GENERATOR 1G-21 FREQUENCY meter at approximately 60 hertz. Place the GOVERNOR MODE SWITCH (DROOP) HS-3234B on 1C94 in the PARALLEL position. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Starting the "B" SBDG IAW OI 324 (cont): At the direction of the Lead Examiner: Communications for the leak are on page 14 Simulator Operator Activate [ET 17]. This will acknowledge the 1C94 Annunciator Alarms and clear the Control Room Annunciator on 1C08. This must occur prior to the next event. Simulator Operator: Activate [ET 1]. This will cause 1C08B (C-02), B Diesel Gen Panel 1C-94 Trouble to annunciate. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Enters AC Sources and SBDG LCOs. TS LCO 3.8.1 Condition A- One Offsite Circuit INOPERABLE. TS LCO 3.8.1. Condition B- One DG INOPERABLE BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Verifies AC Sources and SBDG LCOs have been entered. At 1C08, place BUS 1A4 Transfer handswitch to MANUAL. Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 "B" DIESEL GENERATOR 1G-21, to ON. Using the B DIESEL GENERATOR 1G-21 VOLTAGE ADJUST, raise INCOMING VOLTS SYNCHRONIZE to slightly more than RUNNING VOLTS SYNCHRONIZE. Using the B DIESEL GENERATOR 1G-21 SPEED ADJUST, adjust diesel generator speed to a slow, clockwise synchroscope rotation. When the synchroscope is at the 12 o'clock position, momentarily place the control switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 in the CLOSE position. Confirms the red (breaker closed) and white (closing spring charged) indicating lights are ON. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Starting the "B" SBDG IAW OI 324 (cont): When Contacted to verify 1A4 Switchgear Room Clear of Personnel, wait 1 minute and When directed to perform SBDG Operating Checklist OI 324A9 (Attachment 9): Simulator Operator inform the control room that 1A4 Switchgear Room is clear of personnel. Simulator Operator Acknowledge the request. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Exits LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken to AUTO. BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Loads the Diesel Generator to 250-300 KW using 1G21 speed adjust Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 to OFF. Place BUS 1A4 TRANSFER handswitch in AUTO. Use B DIESEL GENERATOR 1G-21 SPEED ADJUST to load B DIESEL GENERATOR 1G-21 to 1,500 KW, observing B DIESEL GENERATOR 1G-21 KILOWATTS meter at 1C08 Adjust 'B' SBDG speed and voltage, as necessary to attain desired loading and power factor (0.9 power factor per Appendix 1). Complete the SBDG Operating Checklist OI 324A9 (Attachment 9). EXAMINER NOTE: After initially loading the 'B' SBDG, wait ~5 minutes then insert the next event. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: When directed to investigate the 1C94 Trouble Alarm: Three (3) minutes after being directed to investigate 1C94 Trouble Alarm: Simulator Operator Acknowledge the request. Simulator Operator: Inform the control room of the following: Coolant is on the floor around the SBDG, the expansion tank is empty. Annunciators in ALARM: 1C94 (A-3), Jacket Coolant Level Low 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Jacket coolant temp is 195°F, rising slowly. Crew Responds to 1C08B (C-2), B Diesel Gen Panel 1C-94 Trouble Alarm Responds to 1C94 (A-3), Jacket Coolant Level Low Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo BOP Send an Operator to 1C94 to determine the cause of the TROUBLE Alarm and take corrective action per ARP 1C-94. At 1C92 monitor TI-3258B to determine if Jacket Coolant temperature is high or low IF SBDG 1G-21 is running and NO LOOP or LOOP/LOCA emergency exists AND IF Jacket coolant temperature is above 195F on TI-3258B THEN Unload and trip SBDG and notify CRS. Unloads the 'B' SBDG (CRITICAL) Trips the 'B' SBDG (CRITICAL) Actions per the OI are on the next page. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Jacket Coolant Leak on the 'B' SBDG. (cont'd) | |||
When contacted as the DSM When contacted as Chemistry to investigate the leak, Floor Instructor The crew may elect to unload and remove the SBDG from service using OI 324. The steps documented to the right are the expected student response using OI 324. Simulator Operator: Acknowledge the request for support. Simulator Operator: Acknowledge the request for support. Crew Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo CRS Directs the operator to unload the B SBDG in accordance with OI 324, Sect 8.3, UNLOAD THE "B" SBDG. Enters LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken to MANUAL and exits 3.8.1.A when taken back to AUTO. BOP Implements OI 324, Sect 8.3, UNLOAD THE "B" SBDG If the SBDG is in PARALLEL OPERATION, then reduce the load on the Diesel Generator to 1500-1600 KW by using the DIESEL GENERATOR 1G-21 SPEED ADJUST CONTROL. Adjust A[B] DIESEL GENERATOR 1G-1G-21 VOLTAGE ADJUST to maintain 0.9 power factor per Appendix 1. Operate at 1500-1600 KW for 10 minutes to allow for cooldown. (Based on the current conditions, the 10 minute cooldown may be waived). Verify AC Sources LCO has been entered if applicable. Place the BUS 1A4 TRANSFER breaker mode selector switch is in MANUAL. (Critical for this evolution) Reduce the load on the Diesel Generator to 50 KW by using the DIESEL GENERATOR 1G-21 SPEED ADJUST CONTROL. Place the control switch for 4KV BREAKER 411 B DIESEL GENERATOR 1G-21 in the TRIP position. (Critical for this evolution) o Observe that the green (breaker tripped) and the white (closing spring charged) indicating lights are ON. Place the BUS 1A4 TRANSFER breaker mode selector switch in the AUTO position. (Critical for this evolution) At 1C08, confirm annunciator 4KV BUS AUTO TRANSFER INOP (1C08A, D-7) is reset. Actions continued on next page. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 43 NRC Initial License Exam, Scenario #1 SEG IF directed to place HS3234B in UNIT: If directed to place HS3281B in RATED: Simulator Operator Acknowledge the request. Activate [ET 12] This will insert RF dg11 to UNIT Inform the control room that HS3234B, B Governor Mode Switch is in UNIT. Simulator Operator Acknowledge the request. Activate [ET13] This will insert RF dg19 to RATED. Inform the control room that HS3281B, IDLE-RATED SWITCH is in RATED. Crew Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo CRS Directs the operator to unload the B SBDG in accordance with OI 324, Sect 8.3, UNLOAD THE "B" SBDG. Place the B GOVERNOR MODE SWITCH (DROOP) HS-3234B at 1C94 in UNIT. Directs placing the B DIESEL GENERATOR 1G-21 CONTROL handswitch HS-3231B on 1C08 in the PULL TO LOCK position. Declares the "B" SBDG INOPERABLE (already INOP potentially due to not exiting when 1A4 transfer switch was in MANUAL) TS LCO 3.8.1 Condition B- One DG INOPERABLE o Perform SR 3.8.1.1 for operable offsite circuits within 1 hour and every 12 hours thereafter. o Determine that the fault is not a common cause failure within 24 hours. o Perform SR 3.8.1.2 for the operable EDG once per 72 hours o Restore the inoperable EDG to operable within 7 days BOP Implements OI 324, Sect 8.3, UNLOAD THE "B" SBDG At 1C94, place HS-3281B, IDLE-RATED SWITCH, in RATED. EXAMINER NOTE: After the applicants shutdown the 'B' SBDG and after declaring the 'B' SBDG inoperable, the crew should proceed to withdrawing control rods. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 43 NRC Initial License Exam, Scenario #1 SEG Event 3 Increase Reactor Power with control rods If the crew does not transition to raising reactor power after the SBDG event: If called as organizational personnel to support the power rise: Simulator Operator: Contact the control room as the Reactor Engineer and inform them that raising reactor power is a priority. Simulator Operator Acknowledge the requests and provide needed support. CRS Directs Operators to increase power IAW IPOI and RE guidance RO Continues control rod withdrawal IAW OI 856.1 following the sequence. Monitor neutron monitoring instrumentation during control rod movements. Verifies the following indications: o White backlight on the Rod Select pushbutton turns ON o On the Full Core Display, the white "XX-XX" select light corresponding to the rod selected turns ON o On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod. Momentarily places the ROD MOVEMENT CONTROL in the OUT-NOTCH position and verifies: o The green ROD IN light turns ON momentarily and then turns OFF o The red ROD OUT light turns ON after the green ROD IN light turns OFF. o The red ROD OUT light turns OFF o The amber ROD SETTLE light turns ON and then turns OFF o The rod has been with drawn as indicated on the Four Rod Group Display BOP Provides Peer checks to RO during rod withdrawals. Monitors balance of plant equipment /plant status. Examiner Note: The 3rd control rod will stick. Go to Event 4. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 43 NRC Initial License Exam, Scenario #1 SEG Event 4: Stuck Control Rod At the direction of the Lead Examiner, When CRD drive water pressure is greater than 295 psig: If contacted as organizational personnel: Simulator Operator Activate [ET 3] This will stick Rod 22-23 at its current position. Simulator Operator Verify [ET 20] actuates. This will remove MF RD023023. This will allow rod 22-23 to move. Simulator Operator Acknowledge the information. Evaluator Note: It is satisfactory to adjust pressure greater than normal but less than 350# to limit stress on the CRD Evaluator Note: There is the potential to double notch a control rod with elevated drive water pressure. There is a large note in the AOP to direct the crew to recover from the double notch IAW OI 255 CREW Diagnoses control rod 22-23 is stuck CRS Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, when informed of stuck control rod. Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, requirements are met. Contacts RE and/or Duty Manager. RO While pulling control rods, recognizes 22-23 stuck and informs the SRO. Implements AOP 255.1, takes actions to address the stuck rod as follows: Verify power is available to RMCS. Verify the rod is actually selected. Demand a Rod Position Log and verify control rod positions. Verify the following parameters indicate approximately their normal values at 1C05 o CRD Pump flow at FC-1814 CRD System Flow Control (40 gpm) o CRD Charging Water header pressure at PI-1816A (CRD Pressure) Charging Water Press (1450 psi) o CRD Drive Water pressure at PDI-1825A (CRD Pressure) Drive Water P (260 psid) Raises drive water pressure to 310-350 psid by adjusting MO1830 until drive water pressure PI-1825A is 310-350 psid. Attempts to move the rod Recognizes rod movement and reports success to SRO Returns drive water pressure to its normal band Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 43 NRC Initial License Exam, Scenario #1 SEG Event 4: When directed to the HCU to perform local actions: Two (2) minutes after initial direction to verify condition at the HCU: If contacted to monitor HCU during control rod movement after RD022223 is removed: Simulator Operator Acknowledge the request. | |||
Simulator Operator Inform the control room that the HCU lineup is normal and HCU pressure is normal. Simulator Operator Inform the control room that the HCU looked and sounded normal during the move. BOP Monitors balance of plant equipment/plant status. Contacts SANSOE to inspect control rod 22-23 HCU for abnormalities. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 43 NRC Initial License Exam, Scenario #1 SEG If the crew double notches the control rod, actions to recover are included. If contacted as the Reactor Engineer, Simulator Instructor Acknowledge the Double Notch and inform the crew that inserting the rod and continuing with the power change is permissible. Crew Recognize the Double Notch of the Control Rod. CRS Direct actions IAW OI 255, Section 10.1, Restoration from a Withdraw Double Notch. Notify Reactor Engineering. RO Verify thermal limits on an official or a predicted 3D case. Use the CONTROL ROD MOVEMENT SWITCH C11A-S2 at 1C05 to INSERT the rod one notch to its intended position. NA if the double notch is anticipated as part of a planned reactivity manipulation and thermal limits are not adversely affected. The crew should recommence the withdrawal of control rods IAW IPOI 3 once the double notched rod is restored. EXAMINER NOTE: Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 43 NRC Initial License Exam, Scenario #1 SEG Event 5: After the crew has performed AOP 255.1, raised power and at the direction of the examiner: When directed to investigate the cause of the "B" CRD pump trip. Two (2) minutes after being directed to investigate "B" CRD Pump breaker: Three (3) minutes after being directed to investigate "B" CRD pump locally: Simulator Operator ACTIVATE [ET 5]. This will cause a trip of the "B" CRD pump and accumulator alarms for 06-15 and 34-35. | |||
Simulator Operator Acknowledge the request. Simulator Operator Inform the control room that 1A410, "B" CRD pump breaker tripped on inverse time delay overcurrent. Simulator Operator Inform the control room that "B" CRD pump motor is abnormally hot. CREW Responds to annunciator 1C05A (A-7) "B" CRD PUMP TRIP OR MOTOR OVERLOAD CRS Directs starting "A" CRD pump in accordance with OI 255. If HPCI is required to be operable, verify HPCI suction is aligned to the CSTs Contacts organization for support. RO Implement actions of ARP 1C05A (A-7) "B" CRD PUMP TRIP OR MOTOR OVERLOAD Determine the cause of CRD 1P-209B trip as follows o Monitor alarm "B" CRD PUMP 1P-209B LO SUCT PRESSURE (1C05A, B-7). o If necessary send an Operator to Bus 1A4 to check targets on Breaker 1A410 o As soon as practical, monitor computer points W092 and W093 for any bearing temperature > 180F If due to CAUSES 1.1 through 1.5, start CRD Pump 1P-209A per OI 255 (CRD Hydraulic System). If 1P-209B tripped due to any electrical fault, initiate a Work Request to have the pump checked, meggered, and repaired as necessary. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 43 NRC Initial License Exam, Scenario #1 SEG Event 5: When directed to verify adequate oil level and close V-17-8 to 1/2 turn open: When contacted as the Reactor Engineer and informed of the High CRD Temperatures, When directed to slow open V-17-8, "A" CRD Pump Discharge Valve: After the ramp is complete and V-17-8 is full open: Simulator Operator Activate [ET 28]. This will position V-17-8 1/2 turn open. Inform the control room that there is adequate oil level in the "A" CRD pump motor and speed changer and the V-17-8, "A" CRD Pump Discharge Valve is 1/2 turn open. Simulator Operator Acknowledge the request for support. Simulator Operator Acknowledge the request. AND Activate [ET 27] This will position V-17-8 full open in 60 seconds. Simulator Operator Inform the control room that V-17-8 is full open. If the crew elects to start the 'A' CRD pump in accordance with OI 255 here are the expected student responses. The crew may address 1C05A (E-6) CRD MECHANISM HIGH TEMP, but the condition is expected for the loss of the CRD Pump. CREW Implements OI 255, Section regarding Startup of a CRD Pump CRS Directs starting "A" CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump. RO Prepare to start CRD Pump 1P-209A as follows: Verify adequate oil level in CRD Pump 1P-209A motor and speed changer Close 1P-209A Pump Discharge Isolation V-17-8 to approximately 1/2 turn open. Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL. At 1C05, verify MO-1833, INLET TO CRD RETURN LINE, is fully open Start CRD PUMP 1P-209A by momentarily placing handswitch HS-1807A on 1C05 in the START position Slowly open Discharge Isolation V-17-8 to pressurize downstream piping and to prevent CRD pump from tripping on low suction pressure. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 43 NRC Initial License Exam, Scenario #1 SEG When directed to vent both CRD Discharge Filters: Simulator Operator Acknowledge the request. Inform the control room that time compression is being used and that both CRD Discharge Filters have been vented. CREW Implements OI 255, Section regarding Startup of a CRD Pump CRS Directs starting "A" CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump. RO Vent both CRD Discharge Filters 1F-201A and B At 1C05, verify charging header pressurized > 1200 psig on PI-1816A CHARGING WATER PRESSURE Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on FI-1814 CRD SYSTEM FLOW When FC-1814 is properly controlling flow, then shift to AUTO Slowly adjust DRIVE WATER P CONTROL MO-1830 to obtain approximately 260 psid on PDI-1825A DRIVE WATER P Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 43 NRC Initial License Exam, Scenario #1 SEG If the crew elects to start the CRD pump in accordance with OI 255 QRC 1 here are the expected student responses. CREW Implements OI 255, QRC 1, CRD Rapid Start CRS Directs starting "A" CRD pump in accordance with OI 255, QRC 1, CRD Rapid Start. RO If one CRD Pump is running, proceed to step (2), otherwise start CRD Pump as follows: Close MO-1830, Drive Water P Control Verify FC-1814, CRD System Flow Control in Manual and Closed Start 1P-209A[B], CRD Pump Throttle MO-1830, Drive Water P Control partially open. Adjust FC-1814, CRD System Flow Control and throttle MO-1830, Drive Water P Control to achieve desired pressure and flow. Verify operating CRD Pump motors above 9 amps Restore FC-1814, CRD System Flow Control to Auto Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 43 NRC Initial License Exam, Scenario #1 SEG Accumulator Trouble annunciator response If contacted to determine if there are any "slow" control rods based on last scram time testing: Simulator Operator Inform the control room that there are NO slow control rods. CREW Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL CRS Comply with Technical Specification requirements for Control Rod Scram Accumulators. May enter TS LCO 3.1.5.Condition A (twice)- One control rod scram accumulator inoperable with reactor steam dome pressure >900 psig. o Declare the associated control rod scram time "slow" within 8 hours OR o Declare the associated control rod inoperable within 8 hours. Will Enter TS LCO 3.1.5 Condition B- Two or more control rod scram accumulators inoperable with reactor steam dome pressure >900 psig. o Restore charging water header pressure to > 940 psig within 1 hour of discovery of Condition B concurrent with charging header pressure < 940 psig. AND o Declare the associated control rod scram time "slow" within 1 hour OR o Declare the associated control rod inoperable within 1 hour. Must verify less than 6 control rods have been declared "slow" Must verify separation criteria for both "slow" control rods declaration and/or inoperable control rod declaration. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 43 NRC Initial License Exam, Scenario #1 SEG When directed to investigate accumulator trouble alarms: Three (3) minutes after being directed to investigate accumulator trouble alarms: Ten (10) minutes after being directed to recharge the accumulators: Ten (10) minutes after recharging 06-15: Simulator Operator Acknowledge the request. Simulator Operator Inform the control room that the alarms are due to low pressure. Control rod accumulator 06-15 is indicating 935 psig and 34-35 is indicating 930 psig. I will recharge the two accumulators in accordance with OI 255. Simulator Operator Activate [ET 14] This will remove MF RD070615. Inform the control room that accumulator 06-15 has been recharged. Final accumulator pressure is 1200 psig. Simulator Operator Activate [ET 15] This will remove MF RD073435. Inform the control room that accumulator 34-35 has been recharged. Final accumulator pressure is 1170 psig. CREW Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL CRS Directs recharging the accumulators in accordance with OI 255. RO Implement actions of ARP 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL Check the Full Core Display on 1C05 to determine which accumulators are in the trouble condition. o Determines that 06-15 and 34-35 are in trouble condition. Send an Operator to the accumulators to determine the cause of the alarm. Recharge accumulator per OI 255 (CRD HYDRAULIC SYSTEM). Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 43 NRC Initial License Exam, Scenario #1 SEG Event 6: When directed by the examiner: When contacted as organizational personnel to support HPCI auto initiation: If the operator checks status of relay E41A-K6: Simulator Operator: Activate [ET 7]. This causes an auto initiation of HPCI. Simulator Operator Acknowledge the information. Floor Instructor Inform the operator that the relay appears the same as C71A-K3D. This relay is energized to demonstrate the understanding of what it should look like. Crew Respond to auto initiation of HPCI. Implement OI 152, QRC 2, Tripping HPCI. CRS Directs tripping HPCI after verifying that HPCI operation is not required by assuring that by 2 independent indications adequate core cooling is assured. Enters AOP 255.2, Power/Reactivity Abnormal Change Comply with Technical Specification requirements for HPCI. TS LCO 3.5.1.Condition F- HPCI System INOPERABLE o F.1.- Verify by administrative means RCIC System is OPERABLE immediately o F.2.- Restore HPCI System to OPERABLE status within 14 days. BOP Implements actions of OI 152 QRC 2 to trip HPCI. Depresses and hold HS-2259, Remote Turbine Trip PB Verify HV-2201, HPCI Turbine Stop Valve Closes When HPCI speed is zero rpm, places 1P-218, Aux Oil Pump, in PTL. Verify HV-2200, HPCI Turbine Control Valve, closes Verify annunciator 1C03-3C (A6) is activated. Release HS-2259, HPCI Remote Turbine trip PB RO Continues to monitor reactor power, pressure and level May need to control level adjusting level setpoint. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 43 NRC Initial License Exam, Scenario #1 SEG AOP 255.2 due to HPCI auto start When contacted as organizational personnel to support HPCI auto initiation: Simulator Operator Acknowledge the information. Crew Respond to auto initiation of HPCI. Implement AOP 255.2, Power/ Reactivity Abnormal Change. CRS Directs AOP 255.2, Power/ Reactivity Abnormal Change. Establish critical parameter monitoring of Reactor Power, Reactor Pressure, and RPV Water Level, as priorities allow. Notify the Reactor Engineer and Operations Manager. After the cause has been determined and corrected, return to normal operation. BOP Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to: Assuming manual control of a malfunctioning system (completed when HPCI was tripped) Verify proper operation/indication of systems and/or indications. Monitor the Off-Gas System radiation levels on Panel 1C02 for any change in Off-Gas activity. RO Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal Verify control rod positions are correct for the established sequence, by using Rod Position Log Verify thermal limits on the Official 3D Case When power is stabilized, plot location on the Stability Power / Flow Map. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: LOOP, A DG Fails To Auto Start. (Will start in manual.) Small Recirc Leak Simulator Operator: Activate [ET 21] This will result in a Small Break LOCA immediately on a ramp and a LOOP after 60 seconds Simulator Operator: Critical Task #2 IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") LOSS OF POWER EVENT Crew Responds to Loss of Offsite Power CRS The crew may initially enter Station Black Out until the SBDG is restored to 1A3 -ESSENTIAL ELECTRICAL POWER" Directs starting the A DG and verifying it loads the Bus (CRITICAL TASK #2) RO Provides RPV level and pressure status BOP did not start t the "B" DG failed will not start and should be in Pull To Lock. BOP will start the 'A' SBDG with HS-3231A at 1C08 and verifies the output breaker closes. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Fails To Start but CAN be manually started. Small Recirc Leak CREW Responds to annunciator 1C05B-B1 - Primary Containment Pressure Hi/Lo Diagnoses rising containment pressure and lowering RPV water level. CRS Directs a reactor scram due to lowering RPV water level from SBLOCA. Direct the operator to Insert a manual reactor scram, and carry out IPOI 5 (Reactor Scram procedure) Confirms that the reactor is shutdown Direct the operator performance of the IPOI 5 immediate actions RO Perform the immediate operator responses to a reactor scram. Actions of IPOI 5 QRC-1: o Initiate a backup manual scram o Place the Mode Switch in SHUTDOWN o Verify all control rods fully inserted (single rod permissive) o Verify condenser backpressure is stable o If all control rods are not fully inserted, use the RIPs per CRS o Restore and maintain RPV level +170 to +211 (setback) o Verify recirc runback to 20% o Monitor RPV pressure o Verify Turbine/Generator trip o Verify neutron flux lowering o Insert SRM/IRM detectors o Announce scram via plant page o Proceeds to IPOI 5 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Fails To Start but CAN be manually started. Small Recirc Leak CRS Enters AOP 573 - Primary Containment Control RPV Control due to RPV low level (was entered when the scram occurred). -1 Alternate Level Control Leg is entered may direct: o Lockout of ADS o Start of CRD pump. o Start of SBLC pump Directs Reactor Water level band of 170" to 211" using available systems - (HPCI unavailable, will lead to ED) - This results DW Cooling Fans in FAST Primary Containment Control when containment pressure reaches 2 psig. ll Spray. - This results DW Cooling Fans in FAST Primary Containment Control when containment pressure reaches 2 psig. exceeds 11 psig, directs initiation of Drywell Spray. Event 8: HPCI starts but trips Simulator Operator: Verify [ET 23] is active Verify hp02 is on delay when the HPCI Turbine is started. After HPCI runs for 15 seconds the HPCI Turbine Trips. BOP Starts HPCI to maintain RPV level band. (HPCI will start but will trip) Reports to crew that HPCI has tripped. Attempts to restart (unsuccessful). Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Output BKR FAILS and will not close. B DG Fails To Start but CAN be manually started. Small Recirc Leak RO containment plant parameters BOP 1. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening 2. Throttle open MO-2006[MO-1933], Torus Spray Valve 1. Ensures Recirc Pumps are tripped 2. Repositions HS-1903C - Enable Containment Spray Valves to Manual 3. Depending on RPV level may take HS-1903B to 2/3 Core Coverage/LPCI INIT Interlock Override to MANUAL OVERRD 4. Open MO-2000[1902] , Inboard Drywell Spray Valve 5. Throttle open MO-2001[1903], Outboard Drywell Spray Valve. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements the mitigation strategies of EOP 1, RPV Control RO Inserts a manual reactor scram. Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend. Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure. Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. Directs lowering reactor pressure to lessen the driving head on the leak in the drywell. Shows concern for maintaining plant cooldown within the limits. Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Respond to and implement the actions of AOP 304.1, Loss of 4160V Non-Essential Power BOP Announces suspending all evolutions in progress associated with electrical switchgear and switching operations Verify two Well Water Pumps in service. Starts either A or C Well Water Pump and adjusts well water flow. Verify Well Water Pump 1P-58D secured. In AUTO, verifies FC-4414D, demand is zero. Verify GSW Pumps 1P-889A and B in service Place Bus 1A1 Transfer switch in MANUAL. Place Bus 1A2 Transfer switch in MANUAL. CRS Enters AOP 304.1, Loss of Both Non-Essential Buses Directs the BOP to take actions IAW AOP 304.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 43 NRC Initial License Exam, Scenario #1 SEG At the direction of the Lead Examiner once the crew completes the ED Brief and at the direction of the Lead Examiner Simulator Operator: Activate [ET 24] This will trip the 'A' CRD Pump Critical Task #22 BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. | |||
Simulator Operator: Activate [ET 9] This will trip the RCIC Pump Crew Implements the mitigation strategies of EOP 2, Primary Containment Control BOP Informs the CRS of containment parameters including parameter name, value and trend. Installs Defeat 4. Utilizes OI 149 QRC to spray the torus. Utilizes OI 149 QRC to spray the drywell.(Critical Task #22) Trips the running recirculation pump. CRS Performs a crew update of entry into EOP 2 due to Drywell Pressure. Obtains containment parameters. Directs installation of Defeat 4. Directs spraying the torus after confirmation that torus pressure is greater than 2 psig. Directs spraying the drywell before drywell temperature reaches 280F. Verifies torus water level less than 13.5 ft. Verifies plot of drywell temperature and drywell pressure on the DWSIL curve allows drywell sprays. Verifies recirculation pumps are secured. Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in T/L (T/L-3 and T/L 10), T/T (T/T-2), DW/T (DW/T-6) and PC/P (PC/P-7) legs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements that mitigation strategies of the ALC contingency of EOP 1 BOP Lockouts ADS. RO Attempts to restore and maintain RPV level above +15" Maximizes injection with CRD in accordance with AIP 407. Injects with SBLC in accordance with AIP 406. Verifies injection subsystems can be lined up for injection Verifies at least one injection subsystem lined up with a pump running. CRS Directs ADS lockout. Directs RPV level bands as RPV level lowers Directs maximizing injection with CRD in accordance with AIP 407. Directs injection with SBLC in accordance with AIP 406. Ensures injections subsystems can be lined up for injection. Waits for RPV level to drop to +15" Ensures at least one injection subsystem lined up with a pump running. Before RPV level reaches -25" performs an Emergency Depressurization. BOP: nitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 43 NRC Initial License Exam, Scenario #1 SEG Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". CRS Directs the performance of ED once RPV Water Level cannot be maintained > +15" (Critical #1) ED-1 Override open CV-4371A (Defeat 11) - Completed Earlier In The Scenario ED-2 Are all control rods inserted to at least position 00? (YES) ED-5 Does a drywell high pressure ECCS signal exist? (YES) ED-6 Prevent injection from Core Spray and RHR pumps not required to assure adequate core cooling. ED-7 Is torus water level above 4.5 ft? (YES) ED-8 Open the 4 ADS SRVs. OK to exceed Cooldown rate limit. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements mitigation strategies of EOP 1 after EOP ED to restore adequate core cooling RO Verifies low pressure ECCS systems start and align to inject into the RPV Reports when 1 Core Spray pump is injecting above 3000 gpm. and 1 other ECCS pump is injecting. Trips Core Spray pumps when RPV level indicates on the GEMACs Throttles RHR injection to restore and maintain RPV 170-211" CRS Verifies 1 Core Spray pump and 1 other ECCS pump available for injection Direct injection with one or more Preferred Injection Systems (Table 1A) and Alternate Injection Systems (Table 2A) Determines RPV level can be restored and maintained above +15" and returns to the normal RPV level control leg of EOP 1 Directs restoring and maintaining RPV level 170-211" using low pressure ECCS systems Directs tripping Core Spray pumps when RPV level indicates on the GEMACs Directs throttling RHR injection to maintain RPV level 170-211" CRS and Crew: Diagnoses HPCI failure to run Directs Emergency Depressurization. Directs Opening 4 SRVs (CRITICAL TASK #2) When Directed opens 4 ADS SRVs to emergency (CRITICAL TASK #2) Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 43 NRC Initial License Exam, Scenario #1 SEG *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 43 NRC Initial License Exam, Scenario #1 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES Malfunctions: Before EOP Entry: 1. Jacket Water Leak on "B" SBDG 2. Stuck Control Rod 3. "B" CRD Pump Trip 4. Low HCU Pressure 5. HPCI Spurious Start After EOP Entry: 1. Failure of "A" SBDG To Start 2. LOOP 3. "A" CRD Pump Trips 4. RCIC Trips 5. HPCI Trips Abnormal Events: 1. AOP 255.1, CONTROL ROD MOVEMENT/INDICATION ABNORMAL 2. AOP 255.2, POWER/REACTIVITY ABNORMAL CHANGE 3. AOP 301, LOSS OF ESSENTIAL ELECTRICAL POWER Major Transients: 1. LOOP 2. LOCA 3. ED Critical Tasks: 1. Critical Task #2 IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") 2. Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". 3. Critical Task #22 BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 43 NRC Initial License Exam, Scenario #1 SEG 2. IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") Safety Significance: Adequate core cooling is defined by EOPs as either: Core submergence (+15") Steam cooling with injection of makeup water to the RPV (-25") Required ECCS injection with RPV level above 2/3 core height (-39") Cue: RPV level will drop to <+15" and automatic system response will not restore RPV level for adequate core cooling. Performance Standard: If the crew performs actions that restore and maintain RPV level above +15", this critical task should be considered satisfactory because the crew has anticipated the potential loss of core cooling. If one CS is operating at 3000 gpm and another ECCS pump is injecting, RPV water level must be restored and maintained above -39". This would normally be expected after an Emergency RPV Depressurization. If ECCS is not injecting (less than 1 CS at 3000 gpm and another ECCS pump injecting), RPV water level must be restored and maintained above -25". This may be expected after an emergency RPV depressurization with ECCS problems Progression is to be made by the crew to use all available systems to restore RPV level above the directed level (-25" or -39"). Satisfactory performance of this CT does not require completion of starting all available systems if RPV level is restored above the directed level (-25" or -39"). If RPV injection is secured and RPV level is below +15" but above -25", the critical task is met, although remediation may be required. Feedback: Lowest valid RPV water level indicator is being maintained above directed value. EOP step(s): RC/L-10, L-11, L-12 BWROG: RPV-1.2 (1.2 is only after RPV pressure is lowered) Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 41 of 43 NRC Initial License Exam, Scenario #1 SEG 1. IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". Safety Significance: If the lowering RPV water level trend had not been reversed before RPV level drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping. Cue: RPV level lowered to +15". Performance Standard: The crew must "Initiate" emergency RPV depressurization after the lowest valid level indication shows <+15" and prior to the lowest valid level indicates -25". The critical task is not satisfactory if the actions for "Emergency RPV Depressurization" are not complete. (See definitions) Feedback: RPV pressure is rapidly lowering. EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 42 of 43 NRC Initial License Exam, Scenario #1 SEG 22. BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Safety Significance: If DW sprays were initiated when in the shaded area of the DWSIL, this could lead to an evaporative cooling pressure drop which could result in: Deinerting the containment or containment negative pressures below design. OR Drywell-below-torus differential pressure beyond design. Operation of DW sprays if DW temperature cannot be maintained below 280F, will ensure that the design temperatures of the components within the DW are not exceeded. If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV. Cue: DW temperature is rising and is below 280F. Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance Standard: DW sprays are initiated on at least one side of RHR prior to 280F DW temperature. If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure. If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required. Feedback: DW spray flow initiated and DW temperature is lowering. EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 43 of 43 SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 40 NRC Initial License Exam - Scenario #2 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team | |||
==References:== | |||
STP 3.3.1.1-17 Rev 08 AOP 358 Rev 31 ARP 1C05A Rev 78 AOP 255.1 Rev 44 AOP 255.2 Rev 42 AOP 302.1 Rev 54 AOP 691 Rev 8 OI 358 Rev 66 OI 149 Rev 146 OI 150 Rev 78 EOP 1 Rev 18 EOP 2 Rev 16 EOP ATWS Rev 21 TRM Tech Specs Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 40 NRC Initial License Exam - Scenario #2 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: The plant is operating at 80% power due to a downpower for maintenance. Thunderstorms are forecast for the area. "B" CRD pump was recently taken OOS for maintenance. Turnover: Start 'B' SBDG for ST after maintenance. Raise Reactor power recirculation flow. Event # Malf # Eventy Type* Event Description 1 None N BOP Perform MSIV test per STP 3.3.1.1-17 for "D" MSIV's 2 None R RO R SRO Raise Power with Recirculation Flow to 85% RTP 3 rp02a C BOP TS SRO Trip of RPS MG Set Tech Spec 3.3.8; 3.4.5, A & B & C; TRM 3.3.4 entry 4 rd01 3023 C ATC TS SRO Control Rod Drift (30-23) with AOP 255.1& 255.2 entry Tech Spec entry 3.1.3 5 ed13a C BOP TS SRO 125 VDC Div 1 panel 1D11 trip results in AOP entries Tech Spec entry 3.8.7, Condition B 6 rc08 BOP TS SRO Spurious start of RCIC, requires manually stopping RCIC Tech Spec Entry 3.5.3, Condition A 7 mc04b R RO C BOP Condenser Vacuum Leak (recoverable) Fast Power Reduction 8 mc04b M ALL Rising backpressure from Event 5 progression necessitates reactor scram. ATWS occurs 9 hp03 I BOP Failure of HPCI controller (complicates RPV level restoration). * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist. | |||
General Instructions 1. Reset to IC23 and raise power to ~80% RTP a. Load Events b. Load Malfunctions c. Load Overrides 2. OR Reset to the IC provided by the LOIT Exam Development Team 3. Verify Events validate FALSE 4. Reset APRM Gains and clear recorders 5. Complete the Exam Setup Checklist 6. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0 7. Fill in STP 3.3.1.1-17 Cover Matter through prerequisites, and have for turnover. 8. Verify MOL Pull Sheets are out. Trigger No. Trigger Logic Statement Trigger Word Description 3, 5, 7, 9, 11, 13, 15, 17 Manual Trigger 20 ZLOHPHS2202(2) == 1 HPCI MO 2404 Starts to open Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Value Final Value Setup rp02a RPS EPA BREAKER TRIP- RPS A EPA BKR 3 Inactive Active Setup rd013023 CONTROL ROD DRIFTS OUT- ROD 30-23 5 Inactive Active Setup ed13a 125 VDC DISTRIBUTION PANEL FAULT- PNL 1D11 7 Inactive Active Setup mc04b MAIN CONDENSER AIR INLEAKAGE- HP CONDENSER 6 min 9 0 .9 Setup rc08 INADVERTENT RCIC INITIATION 11 Inactive Active Setup mc04b MAIN CONDENSER AIR INLEAKAGE- HP CONDENSER 3 min 13 .9 1.2 Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 0 75 Setup hp03 HPCI FLOW CONTROLLER FAILS 1 min 20 As Is 30 Setup fw02a CONDENSATE PUMP TRIP- PUMP A 15 Inactive Active Setup fw02b CONDENSATE PUMP TRIP- PUMP B 15 Inactive Active Setup rc01 RCIC OVERSPEED TRIP 17 Inactive Active Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Setup mc01 MN COND 1E-7A VACUUM BREAKER V-03-73 (CLOSED,OPEN) 28 CLOSED OPEN Setup mc02 MN COND 1E-7B VACUUM BREAKER V-03-67 (CLOSED,OPEN) 28 CLOSED OPEN Setup rp02 ATWS TEST SWITCH (AKA DEFEAT 12) HS-1863A (RUN,TEST) 2:30 min 12 RUN TEST Setup rp03 ATWS TEST SWITCH (AKA DEFEAT 12) HS-1864A (RUN,TEST) 3 min 12 RUN TEST Time Override No. Override Title Delay Ramp ET Initial Value Final Value Setup DI-PC-037 HS-4321A GRP 7 CHAN A DW CLG AND FAN OVR NORMAL NORMAL DI-PC-038 HS-4321B GRP 7 CHAN B DW CLG AND FAN OVR NORMAL NORMAL Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist. | |||
If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Mild summer morning (Plant power levels) o Reactor Power Level 80% o Core Flow 40 Mlbm/hr Protected train o Protected Train is "B" Technical Specification Action statements in effect o None Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Perform STP 3.3.1.1-17, Main Steam Isolation Valve Functional Test for 'D' Main Steam Line ONLY. Retesting a relay. o Raise power with recirculation flow to achieve 85% RTP following a sequence exchange per RE direction. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline GREEN with one year to YELLOW o LERF Baseline GREEN with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, problems, operator workarounds, etc. o One Extra NLO Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Perform Main Steam Isolation Valve Testing CREW: Verifies Prerequisites for STP 3.3.1.1-17: No other testing on the RPS System All MSIV's are OPEN CRS: Authorizes performance of STP 3.3.1.1-17 for 'D' MSIVs. BOP: Verify energized at 1C15, RPS Trip Channel A1 B Line MSIV 90% OPEN relayC71A-K3E. Verify energized at 1C15, RPS Trip Channel B1 C Line MSIV 90% OPEN relayC71A-K3F. If the MODE SWITCH is in RUN, then visually confirm (at 1C15) the following CHAN A1 MSIV CLOSURE SCRAM BYP MODE SWITCH NOT IN RUN relay C71A-K11A contacts open (if MODE SWITCH is not in RUN, mark step 7.1.2.a and 7.1.2.b "N/A") Station personnel at 1C15 and 1C17 in preparation for observing test response of relays to the C71A-K3H and C71A-K3G, concurrent with cycling CV-4420 and CV-4421 At 1C03, take A INBD MSIV TEST CV-4420 handswitch HS-4412B to TEST and release. At 1C03, verify that CV-4420 goes partially closed and reopens fully. RO: Perform Peer Checks EXAMINER NOTE: After completion of STP, crew will move to raise reactor power Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Raise Power with Recirculation flow. If Contacted as the Reactor Engineer to provide guidance, Simulator Operator: Inform the crew to raise power with Recirc Flow to achieve approximately 85% power and hold power constant until a rod sequence is approved for further power ascension. | |||
Evaluator Note: Proceed to the next event when core flow reaches ~44 mlbm/hr (~83% RTP) or at the discretion of the Lead Examiner. CREW: The crew will brief the reactivity change prior to taking the shift. CRS: Directs power to be raised from 80 to 85% using recirculation pump flow. RO: Performs Recirculation Pump flow adjustments to raise power from 80% to 85%. Monitors plant parameters for expected response during reactivity manipulation. BOP: Monitor the plant. Perform Reactivity Peer Checks to the ATC while adjusting Recirculation flow. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Trip of RPS MG Set Tech Spec 3.3.8 entry At the direction of the Lead Examiner When called as the 2nd Asst. to investigate the loss of RPS, wait 2 minutes, When called as the 2nd Asst. to verify Alt power aligned to 1Y16, When contacted to verify the Cleanup Beds in hold, wait 3 minutes Simulator Operator: Activate [ET 3] Respond as plant personnel as necessary. Simulator Operator: Reports the A RPS MG Set is tripped and faint acrid smell and abnormally hot to touch, Both EPAs are tripped. 1Y30 looks ok. Simulator Operator: Report that 1Y16 is aligned to the alternate RPS power. [verify RF rp04 is in 1Y16] Simulator Operator: Report cleanup beds in hold. CRS: Directs Operators to IAW AOP 358 Technical Specifications for this condition are listed on the next page. RO: Report Power Pressure Level Report Report the Loss of A RPS BOP: Complete actions IAW AOP 358 o Direct an Operator to 1A3 Essential Switchgear Room to assist in troubleshooting the RPS Electrical Distribution system. o Suspend all evolutions in progress associated with electrical switchgear and switching operations. o Verify applicable automatic actions have occurred. Manually initiate those automatic actions that should have occurred but failed to occur. o Declare CIT-2738 inoperable, due to loss of RWCU flow to monitor. Refer to TRM 3.3.4 o Verify the fault is not suspected to be on the RPS bus prior to reenergizing the bus on the RPS Power Supply. o IF an alternate RPS power supply is available as indicted by observing A MG or ALT XFMR white light ON at 1C15 Place handswitch C71B S1A RPS ALTERNATE POWER TRANSFER to A MG OR ALT position as required and verify selected position white light remains on. o WHEN "A" RPS bus is energized then as directed by the CRS, perform OI 358 RPS Appendix 4, "RPS POWER SUPPLY TRANSFER HALF SCRAM RECOVERY CHECKLIST", and restore RWCU System. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to verify sat operation of the C EPA's, Wait 2 minutes and When contacted as Chemistry, Simulator Operator: inform the control room that everything appears normal. Simulator Operator: Acknowledge the request for support. CRS: TS Entries possible Enters TSs o TRM LCO 3.3.4 A RCS Conductivity monitor 4 hr to restore monitoring. o TS LCO 3.3.1.1 A One or more required channels inoperable. o 3.3.1.1 B One or more Functions with one or more required channels inoperable in both trip systems. actions met o TS LCO 3.4.5 A, Required Drywell Sump System inoperable. Restore required Drywell Sump System to OPERABLE status. o TS LCO 3.4.5 B, Required Primary Containment Air Sampling System inoperable. Initiate action to restore required Primary Containment Air Sampling System to OPERABLE status. o TS LCO 3.4.5 C, Required Drywell sump System and containment air sampling inoperable, Restore Drywell Sump System to Operable OR restore o TS LCO 3.3.3.1 One or more Functions with one required channel inoperable. o TS LCO 3.6.1.3 A (12 times) (If Overriden) - Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE Applicable to all the Group 3 Isolation vales repositioned in the Group 3 Isolation ARP actions Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE DSM Electricians Allow the crew to get to the 1/2 Scram Recovery Checklist prior to proceeding. Simulator Operator: Acknowledge to support. Simulator Operator: Acknowledge to support. OI 358 Appendix 4 Actions BOP: At 1C05, position REACTOR SCRAM RESET hand switch C71A-S5 to Group 1 and 4 [Group 2 and 3] and then to Group 2 and 3 [Group 1 and 4] to reset Half Scram. Verify "A"["B"] RPS AUTO SCRAM annunciator (1C05A[B], A-2[A-2]) reset. At 1C36, reset Main Steam Line radiation monitors RIS-4448A/C[B/D]. At 1C36, reset Fuel Pool Exhaust radiation monitor RIS-4131A[B]. At 1C36, reset Carbon Bed Vault radiation monitor RM-4138. At 1C05, momentarily press and release: PCIS DIV 1 RESET pushbutton A71B-S32 and PCIS DIV 2 RESET pushbutton A71B-S33 verifying the following annunciators reset: o PCIS GROUP "1" ISOLATION INITIATED (1C05B, A-8) o PCIS GROUP "2" ISOLATION INITIATED (1C05B, B-8) o PCIS GROUP "4" ISOLATION INITIATED (1C05B, D-8) o PCIS GROUP "5" ISOLATION INITIATED (1C05B, E-8) Verify reactor water sample valves are restored to their desired lineup per IPOI 7 Attachment 5, Group 1 Isolations. Notify Shift Chemistry Technician to restore Hydrogen Chemistry System CAVs analyzers to service if required. Reenergize the following RWCU isolation valve(s) as necessary [NA any non-applicable step(s)]: o MO-2700 (at 1B3219) Restart RWCU System as directed per OI 261 (Group 5). Exit Tech Spec as necessary for applicable PCIVs returned to operable status due to re-energizing the valve in the previous step. Actions Continued on the next page Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP: At 1C04, open A [B] PUMP MINI PURGE ISOL CV-1804A[CV-1804B] by taking HS-1804A[HS-1804B] to CLOSE, then to OPEN, allowing it to spring-return to AUTO. Verify the following GROUP 3 Isolations RESET per IPOI 7, unless CRS directs otherwise [NA any non-applicable step(s)]: o Standby Gas Treatment System per OI 170. o Drywell (Containment Atmosphere Control System) per OI 573. o Reactor Building HVAC System per OI 734. Verify PCIS GROUP "3" ISOLATION INITIATED annunciator (1C05B, C-8) reset. At 1C35, place CV-4371A GROUP 3 OVERRIDE switch S583B in NORM Verify the following GROUP 2 Isolations RESET per IPOI 7, unless CRS directs otherwise Examiner Note: When the crew is about to restore Cleanup to service and at the lead examiner's direction, move on to the next event. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: Control Rod Drift with AOP entry Tech Spec entry 3.1.3 At the direction of the lead examiner, If contacted as the second assistant Simulator Operator: Activate [ET 5] This will actuate RD013023, causing Rod 30-23 to drift out of the core. Simulator Operator: report that the HCU lineup is normal and HCU pressure is normal. . CREW: Diagnoses control rod 30-23 is drifting CRS: Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, Mispositioned control rod section. Directs entry into AOP 255.2 Power Reactivity Abnormal Change. Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, requirements are met. Evaluate the entry into TS LCO 3.1.3 C Control Rod Inoperable once the control rod is isolated. Direct the Organization to write a clearance to remove the Amphenoils to electrically disable the HCU after it is Isolated. Contacts RE and/or Duty Manager. RO: Recognizes Rod 30-23 is drifting and informs the SRO. 1C05A (D-6) Rod Drift Actions o At 1C05, select affected Control Rod, monitor 4 rod display to determine if a control rod is drifting, and if so in what direction. o Actions Continue on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to Mechanically Isolate HCU 30-23, wait 4 minutes and Simulator Operator: Acknowledge the request delete malfunction RD013023 and call back and inform the control room the hcu has been isolated with V-18-1008 (30-23), Insert Isolation, and V-18-1275 (30-23) Withdraw Isolation. o IF any control rod is drifting OUT, perform the following: If more than one rod is drifting OUT, manually scram the reactor per IPOI 5 (Reactor Scram). Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position momentarily (less than 1/2 second) to abort the rod sequence timer. If any control rod indicates withdrawal movement, attempt to drive the affected rods in to their required positions per the rod sequence by placing the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. If any control rod inserted per Step 3.2.c begins to drift out again, fully insert the affected rods by: If necessary, place the RWM Operators Display (RWM-OD) keylock mode switch to the BYPASS position. Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. If any control rod still indicates movement, place and hold the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the OFF position. Run an OFFICIAL 3D CASE for abnormal reactor power/control rod distributions. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: Control Rod Drift (Cont'd) When contacted as the Reactor Enginer, When contacted as the DSM/Operations Direstor Simulator Operator: Acknowledge and inform the control room that you will evaluate the current rod configuration. | |||
Simulator Operator: Acknowledge the request for support. BOP: Monitors balance of plant equipment/plant status. Contacts SANSOE to inspect control rod 30-23 HCU for abnormalities. EXAMINER NOTE: Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: 125 VDC Div 1 panel 1D11 trip results in AOP entries Tech Spec entry (3.8.7.B) At the direction of the Lead Examiner If reactor water level increases to a scram, then When contacted as the second assistant to go to the 1A3 switchgear room to in Simulator Operator: Activate [ET 7] This inserts ed13a causing a loss of 1D11 Simulator Operator: Activate [ET 9] move to next event. NOTE: If the RO does not place the level controller to "A" a scram will occur. Simulator Operator: report after 2 minutes that 1D10 CKT 6 has tripped free and there is no sign of smoke or fire at the breaker. CREW The crew will recognize the loss of 1D11 CRS: Possibly enters AOP 644 Enters AOP 302.1-Loss of 125 VDC Power, Tab 1-Loss of 125vdc Div 1 May direct, as time permits, the RO to transfer to "A" level control to control reactor level and try to maintain normal band. Enters TS LCO 3.8.7.B - 8 Hr LCO (1D11) Directs transferring non-essential power to the startup transformer. RO: Takes manual control of FW and attempts to restore reactor water level to the normal band. OR Place the "A" level controller in service with handswitch Place 3 Element to Single Element Monitor Power Pressure and Level at 1C05 BOP Actions Continued on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to investigate 1D11, wait 1 minute When contacted to provide organizational support, Simulator Operator: inform the control room that there are no abnormal indications and all breakers are Closed. Simulator Operator: Acknowledge the request for support. Actions continued from the previous page. BOP: Recognize the Loss of 1D11 Monitors BOP Equipment Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows. o Place the BUS 1A2 TRANSFER breaker mode selector switch in the MANUAL position. o Select Phase 1 with the BUS 1A2 STARTUP XFMR AMPERES meter switch and observe the ammeter reading. Select Phase 1 with the BUS 1A2 AUX XFMR AMPERES meter switch. o Place the control switch 4KV BREAKER 1A202 STARTUP XFMR TO BUS 1A2 momentarily in the CLOSE position. Observe that the red (breaker closed) and the white (closing spring charged) indicating lights are ON o Observe that the bus has parallel supplies by observing current on the supply ammeters. o Trip the supply breaker from the auxiliary transformer by placing the control switch 4KV BREAKER 1A101[201] AUX XFMR TO BUS 1A1[1A2] momentarily in the TRIP position. Observe that the white (closing spring charged) and the green (breaker open) indicating lights are ON. Actions Continued on the Next Page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions Continued from Previous Page. Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows. o Select individual phases with the BUS 1A1[1A2] STARTUP XFMR AMPERES meter switch to observe the current load and to verify approximately equal phase currents. o On the BUS 1A1[2] VOLTS meter, verify that all three phases indicate approximately 4160V by selecting each phase selector switch position. Observe that all three white (phase energized) indicating lights are ON. o Place the BUS 1A1[2] TRANSFER breaker mode switch in the AUTO position. o If both 1A1 and 1A2 non-essential buses are now powered from the Startup Transformer, notify ITC Midwest System Control Operator that the Auxiliary Transformer has been unloaded and to adjust the DAEC 161 KV bus low limit in EMS accordingly. - NA o Record the time ITC Midwest was notified the Auxiliary Transformer was unloaded in the Operating Log. Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6: Spurious start of RCIC, requires manually stopping RCIC Tech Spec Entry 3. At the discression the Lead Examiner When sent to investigate the Spurious start of RCIC, wait 3 minutes, Simulator Operator: Activate [ET 11] This will spuriously start RCIC Simulator Operator: Inform the control room that the Level Switch for the RCIC Turbine has actuated. Crew: Acknowledges annunciator 1C04c Announces alarm to the SRO CRS: Will direct the follow actions: Trip RCIC Reenter AOP 255.2 for Power Reactivity Abnormal Enter TS 3.5.3 Conditon A for RCIC Inoperable. May look at TS 3.3.5.3 for RCIC instrumentation. Establish critical parameter monitoring of Reactor Power, Reactor Pressure, and RPV Water Level, as priorities allow. RO: Verify control rod positions are correct for the established sequence, by using Rod Position Log. Verify thermal limits on the Official 3D Case. When power is stabilized, plot location on the Stability Power / | |||
Flow Map. Notify the Reactor Engineer and Operations Manager. BOP: Depress HS-2460, RCIC Manual Turbine Trip pushbutton. Verify MO-2405, RCIC Turbine Stop Valve, closes. Verify MO-2512, RCIC Inject Valve, closes. Verify MO 2510, RCIC Min Flow Bypass Valve, closes. Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Condenser Vacuum Leak (recoverable) Emergent Power Reduction HP Tech high rad brief If contacted as Aux Operator to perform a High Rad Entry to investigate. if the crew inserts a manual scram If contacted as the Aux Operator to go in to the condenser bay and investigate Simulator Operator: Activate [ET9] This will insert mc04b, result in degrading backpressure. Simulator Operator: Acknowledge the order Simulator Operator: Acknowledge the order Simulator Operator: Activate [ET 13] | |||
Simulator Operator: Acknowledge the order Crew: Recognizes the rising backpressure CRS: Will direct the follow actions: Enter AOP 691 Perform a fast power reduction to maintain condenser backpressure. Direct IPOI 4 Fast Power Reduction RO: Perform Fast Power Reduction (complete step sequence on the next page. o Lower Recirculation flow to 39 Mlbm/hr. o Insert control rods IAW the fast power reduction sequence sheet. Insert a manual reactor scram if condenser backpressure reaches 6" of Hg absolute. BOP: Establish critical parameter monitoring of condenser backpressure. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fast Power Reduction Steps IAW IPOI 4 RO: o IF core flow is greater than or equal to THEN at 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 39 Mlb/hr while maintaining level between +186" and +211". o Perform the following as required to reduce core flow and to insert rods per the Fast Power Reduction Sequence Sheet(s) Bypass the Rod Worth Minimizer. Station a second licensed operator in place as a peer checker for control rod movement. If necessary to achieve desired conditions, insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to Mlb/hr (equivalent to load line of less than 80%). At 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 27 Mlb/hr while maintaining level between +186" and +211". Insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to Mlb/hr (equivalent to load line of less than 52%). Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Back pressure gets worse. At the direction of the Lead Examiner, With the concurrence from the Lead Examiner When all rods are inserted, At the direction of the Lead Examiner, Simulator Operator: Activate [ET 13] This will worsen the condenser air inleakage driving the crew to insert a manual scram. *Simulator Operator:* Modify MC04B to 1.8 with a 30 Sec Ramp to drive the crew to scram if the fast power reduction is effective at maintaining back pressure. Simulator Operator: Activate [ET 15] this will trip both condensate pumps Crew The crew will determine that continued degradation in condenser backpressure will reach a turbine trip setpoint and take the unit offline. Enters and implements the actions of IPOI 5, Reactor Scram. Enters and implements the actions of EOP 1, RPV Control. RO: Scrams the reactor and performs the scram choreography. Reports a hydraulic ATWS and reactor power. Dials master feed water regulating valve controller to 158.5 in AUTO CRS: Directs scramming the reactor and performing IPOI 5, Reactor Scram. Enters EOP 1 due to a scram required with power above 5% or unknown. Verifies automatic isolations, ECCS initiations, and SBDG initiation. Transitions to EOP ATWS. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If directed to locally trip the 'A' Recirc MG Set Drive Motor Breaker When directed to install Defeat 12: Three (3) minutes after being directed to install Defeat 12: Simulator Operator: Acknowledge the request, wait 10 minutes and use [RF rr11] and open the drive motor breaker. Call the control room and inform them that the drive motor breaker is open. Floor Instructor Manually driving control rods, drifting rods, and repeated manual scram will insert all control rods. To perform repeated manual scram the crew will need to direct the 2nd Assistant to install EOP DEFEAT 12 Critical Task # 4 IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Inserting control rods using RIPs. Simulator Operator Acknowledge the request. Activate [ET 12]. This will install Defeat 12 after time delays. Simulator Operator Contact the control room and inform them that Defeat 12 is installed. Crew Implements the mitigation strategies of ATWS. RO: Reports a hydraulic ATWS and reactor power. Dials master feed water regulating valve controller to 158.5 in AUTO Performs the ATWS QRC. Reports completion of the ATWS QRC. Determines that ARI was NOT effective. Reports RPV level and reactor power. Coordinates with the BOP operator the performance of the Hydraulic Rod Insertion Procedures. BOP: Installs Defeat 15. Announces failure to scram and direct the 2nd Asst. to install EOP Defeat 12 for Repeated Manual Scram RIP 103. Installs Defeat 11. Locks out ADS Perform Hydraulic ATWS RIPs (CRITICAL) o RIP 103.2, Drifting Rods o Start a second CRD pump, if available. o Place CRD Flow Controller FC-1814 in MANUAL and run the output to maximum. o Observe increased cooling water flow on FI-1838 and cooling water dp increase on PDI-1832A. o Throttle open MO-1830, DRIVE WATER P CON s necessary to maximize cooling water flow and pressure. o Monitor for inward rod motion. Rods will drift in. | |||
CRS Actions continued on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Floor Instructor If the crew does not efficiently inject SBLC, enter power level control, restore power to at least one RPS bus, and/or reinitiate torus cooling (after the loss of offsite power) the crew may be required to emergency depressurize due to not being able to maintain torus water temperature and RPV pressure below the Heat Capacity Limit. | |||
CRS: Directs locking out ADS. Verifies at least one set of inboard and outboard MSIVs are open. Directs installation of Defeat 15. Directs performance of the ATWS QRC. Directs the injection of SBLC Recognizes the applicability of Continuous Recheck Statement in Level Leg of EOP ATWS and enters Power Level Control. Directs coordination of the Hydraulic ATWS Rod Insertion Procedures Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If directed to break main condenser vacuum: | |||
Three (3) minutes after the request: Critical Task # 10 IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. Critical Task #11 IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. | |||
Simulator Operator Activate [ET 28]. Acknowledge the request. Simulator Operator Inform the control room the main condenser vacuum breakers are open. Crew Implements AOP ATWS power level control actions. RO: Verifies HPCI is locked out. Terminates and prevents injection from condensate and feed. (CRITICAL) Reports reactor power when RPV level reaches 87" and lowering. Controls RPV level -25" to +87" using condensate and feedwater. (CRITICAL) As Time Permits, assist in RIPs BOP: Terminates and prevents injection from HPCI, CS, RHR when required. Continues to perform Hydraulic Rod Insertion Procedures CRS: Directs installation of Defeat 4. Directs terminating and preventing injection from HPCI, CS, RHR and Condensate and Feedwater. Directs reporting reactor power at 87" and lowering. Directs an RPV level band of -25" to +87" with condensate and feedwater. This band will be dependent on the level that is reported when power drops below 5% Directs an RPV pressure band of 800-1055 psig. using desired system (EHC). Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When all control rods are inserted: CRS: Recognize that all rods have inserted Evaluate Transitioning to EOP 1 from ATWS Direct the RO to secure Boron Injection Upon the report of SBLC Pumps secured, transition to EOP 1 RO: When directed by the CRS, Secure SBLC Pumps Inform the CRS that SBLC Pumps are secured Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the parameters of the Heat Capacity Limit are exceeded and an Emergency Depress. Is required with ATWS conditions present: Contingency Actions Crew Enters and implements the actions of an Emergency Depressurization with an ATWS condition present. RO: Terminates and prevents injection from Condensate and Feedwater. Slowly re-injects into the RPV to restore and maintain RPV level -25" to +15" using condensate and feedwater. BOP: Terminates and prevents injection from HPCI, Core Spray, RHR. Reports torus water level. Opens 4 ADS SRV's. Reports RPV level at 160 psig. and lowering CRS: Enters Emergency Depressurization. Directs terminating and preventing injection from HPCI, Core Spray, RHR, Condensate and Feedwater. Directs opening 4 ADS SRVs. Directs reporting of RPV level at 160 psig. and lowering Directs slowly re-injecting into the RPV to restore and maintain RPV level -25" to +15" using condensate and feedwater. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the parameters of the Heat Capacity Limit are exceeded and an Emergency Depress. Is required: Contingency Actions Crew Crew will enter and implement the actions of Emergency Depressurization. RO: Restores and maintains RPV 170-211" using condensate and feedwater. BOP: Reports torus water level. Opens 4 ADS SRV's. Restores and maintains RPV 170-211" using condensate and feedwater. CRS: Enters Emergency Depressurization. Directs opening 4 ADS SRVs. Directs restoring and maintaining RPV level 170-211" using condensate and feedwater. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew transitions to EOP 1 from EOP ATWS Crew Implements the mitigation strategies of EOP 1, RPV Control RO: Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS: Performs a crew update of entry into EOP 1 due to Exiting EOP ATWS Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 if not completed prior. Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. May Enter Alternate Level Control Leg of EOP 1 Lock Out ADS Restore and maintain RPV level above +15 in. with one or more Preferred Injection Systems (Table 1A) Wait Until RPV level drops to +15 in. Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions to start RCIC from a tripped conditions. At the direction of the Lead Examiner, Simulator Operator: Activate [ET 17] this will trip the RCIC Turbine on overspeed. CRS: Recognize Condensate and Feed no longer available. Direct the RO to inject with RCIC to restore Reactor Water Level RO: Verify MO-2511, RCIC Pump Discharge Valve, is open. Open MO 2426, RCIC Lube Oil Cooler Supply Valve. Start 1P 227, RCIC Vacuum Pump. Open MO-2404, RCIC Turbine Steam Supply Valve. For RPV injection, immediately open MO-2512, RCIC Inject Valve. Verify MO-2510, RCIC Min Flow Bypass Valve, closes as RCIC flow raises above 80 gpm. Start 1P-99A and B, ESW Pumps. Start 1V-AC-15A and B, RCIC Room Cooling Units. Recognize the Trip of RCIC, and inform the CRS. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Direct Crew Response for performance of the T/T leg of EOP 2. Directs operating all available torus cooling using only RHR pumps NOT required for adequate core cooling. Before torus water temperature reaches 110F enter EOP 1 and shutdown the reactor. Maintain torus water temperature below the Heat Capacity Limit (Graph 4). Wait until torus water temperature and RPV pressure cannot be maintained below the Heat Capacity Limit (Graph 4). Direct the reseting of the LO-LO-LO LPCI Logic to allow for restoration of Torus Cooling BOP: Place RHR in Torus Cooling IAW OI 149, QRC 2 Verify RHRSW in service per OI 416/OI 416 QRC 1. Verify 1P-99A and B, ESW Pumps, running. Place HS 2059 [HS 1959], A & C [B & D] RHRSW PUMPS LOCA TRIP OVERRIDE, in MANUAL OVERRD position. Verify MO-2046[1947], RHR HX Service Water Outlet Valve, CLOSED. Start RHRSW Pumps 1P-22 A[B] and/or 1P-22 C[D]. Throttle open MO-2046[1947], RHR HX Service Water Outlet Valve, to obtain 1200 - 2600 gpm per running pump. AS TIME ALLOWS, Perform the follow up actions Verify two or more River Water Supply Pumps running. Place LIC-4231[4232] in MANUAL. Adjust LIC-4231[4232] to achieve the desired River Water makeup flow. (Combined flow of ESW and RHRSW) Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP Actions continued from previous page. Place RHR in Torus Cooling IAW OI 149, QRC 2 Verify 1P229A[B, C, and/or D], RHR Pumps, running. If a LPCI HI Drywell pressure condition (2 # ) exists, place HS-2001C[1903C] Enable Containment Spray Valves in the MAN position. Open MO-2005[1932], Outboard Torus Cooling/Spray Valve. Throttle MO-2007[1934], Torus Cooling Test Valve, to maintain 4800 gpm per each operating RHR pump. Close MO-2030[1940], A[B] Heat Exch Bypass Valve. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Direct the BOP or ATC to restore Reactor Water Level with HPCI following the loss of Feed and Condensate once all rods are in. RO/ BOP: Start HPCI when Directed IAW OI 152 QRC 1 o If HPCI previously tripped on RPV High Water Level, depress HS-2299, RX HI WATER LEVEL HPCI TURBINE TRIP reset switch. o Open MO-2247, HPCI Lube Oil Cooler Supply Valve. o Start 1P-233, HPCI Vacuum Pump . o Open MO-2202, HPCI Turbine Steam Supply. o Start 1P-218, HPCI Aux Oil Pump . o Verify MO-2311, HPCI Pump Discharge Valve, open. o For RPV injection, immediately open MO-2312, HPCI Inject Valve. o Verify MO-2318, HPCI Min Flow Bypass Valve, closes as HPCI flow raises above 600 gpm. Recognize the HPCI Turbine fails to reach required speed and discharge pressure. Take manual control of the HPCI Turbine IAW ACP 1410.1 and place FIC 2309 in MANUAL and control the HPCI Turbine in MANUAL Report to the CRS that HPCI is injecting to the RPV in MANUAL due to a failed controller. *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 40 NRC Initial License Exam, Scenario #2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS DISCUSSION ITEMS No discussion points. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 40 NRC Initial License Exam, Scenario #2 SEG QUANTITATIVE ATTRIBUTES Malfunctions: Before EOP Entry: 1. Loss of "A" RPS 2. Drifting Control Rod 3. Loss of 1D11 4. RCIC Inadvertent Initiation 5. Condenser Air In leakage After EOP Entry: 1. ATWS 2. HPCI Controller Failure Abnormal Events: 1. AOP 255.1, Control Rod Drift 2. AOP 255.2, Power Reactivity Abnormal Change 3. AOP 358, Loss of RPS Power 4. AOP 691, Condenser High Back Pressure Major Transients: 1. ATWS 2. Power/Level Control 3. EOP 1 Alternate Level Control Leg Critical Tasks: 1. Critical Task # 4 IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Manual scram signal Inserting control rods using RIPs. Manual ARI signal Injection of Boron 2. Critical Task # 10 IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. 3. Critical Task #11 IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 40 NRC Initial License Exam, Scenario #2 SEG 4. IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Manual scram signal Inserting control rods using RIPs. Manual ARI signal Injection of Boron Safety Significance: The UFSAR and Safety Limits ensure that specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients and abnormal operational transients. The fuel cladding integrity safety limit is set such that no significant fuel damage is calculated to occur if the limit is not violated. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environs. The MCPR fuel cladding safety limit ensures that during normal operations and abnormal transients the fuel rods will not experience transition boiling and possible cladding damage. The MCPR analysis assumes that the control rods will insert in a specified time. If the control rods do not insert when a scram is required, the plant is beyond the fuel cladding MCPR analysis thus the fuel cladding safety limit is challenged and potential cladding damage may be occurring. Cue: A manual or automatic scram signal has been inserted and failed to lower reactor power below 5%. Performance Standard: The crew successfully initiates a manual scram signal after a automatic scram failed has occurred and/or, The crew initiates a manual ARI causing control rod insertion and/or, The crew successfully performs RIPs (the task of sending an operator to vent the scram air header should not be considered as "control room operator actions" and thus should not be considered as a method for this CT) and/or, The crew successfully performs RIPs as allowed by the scenario to insert control rods capable of being inserted and/or, The crew successfully injects boron into the RPV. If the crew performed the actions for Power/level control and that caused power to lower below 5% before any of the above actions were performed, this CT should be considered as N/A. If this CT was N/A due to Power/level control lowering power and the actions related with this CT were not competently performed, the responsible individual(s) and possible crew may fail or require remediation due to competencies. If the crew was performing the actions of Power/level control and was correctly performing actions for this CT, this CT should be considered satisfactory. If the crew is not performing the correct procedures for the given conditions and this results in the reactor remaining at power, this should be considered an individual failure and possible crew failure. Example: The crew is individually driving control rods during an electrical ATWS and ARI is available and has not been attempted. If ARI automatically initiates and results in power lowering below 5%, this CT should be N/A. Feedback: Control rod positions and/or boron injection. EOP step(s): ATWS Q-1, Q-3, Q-6, Q-8 BWROG: RPV 4.1, RPV 5.1, RPV 6.1 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 40 NRC Initial License Exam, Scenario #2 SEG 10. IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. Safety Significance: RPV water level must be lowered during ATWS to either lower reactor power or to prevent challenging the containment. If power is known to be below 5%, it is highly unlikely that the reactor is producing a significant power such that power/level control will effectively reduce power further, thus entering power/level control is not required or safety significant. If power is above 5%, or cannot be determined and RPV level is above 87", power level control is required to reduce reactor power in order to prevent or mitigate the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities. If power is known to be above 5%, or cannot be determined and RPV water level is above +15", and torus water temperature is above 110F, and either an SRV is open or will reopen or DW pressure is above 2 psig, then power level control is required to reduce power in order to preserve containment integrity. Thus terminating and preventing injection will aid in lowering power and can preclude failure of containment or equipment necessary for the safe shutdown of the plant. Cue: ATWS EOP entry required with reactor power above 5% or cannot be determined and either: RPV water level is above +87" or RPV water level is above +15" and torus water temperature is above 110F, and either an SRV is open or will reopen or DW pressure is above 2 psig. Performance Standard: Injection from all of the following is terminated until conditions allow reinjection: Condensate/Feedwater HPCI RHR Core Spray Alternate ATWS injection systems (Table 2B) Reinjection should not occur until RPV water level is below 87" and one of the Reactor power drops below 5% Reactor power drops below 5% All SRVs remain closed AND DW pressure remains below 2 psig. CRD, SBLC, and RCIC injection are allowed. If RCIC was not injecting but other systems were injecting outside the shroud at a flowrate below RCIC flowrate, the critical task is satisfactory although remediation may be necessary. If RPV level is not lowering to the required conditions, and the crew is not controlling RCIC injection, the critical task is satisfactory, although remediation may be required. Feedback: Injection flowrate for the listed systems remain at zero until reinjection is allowed. EOP step(s): ATWS/L two CRS, and L-1, -2. BWROG: RPV 6.3 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 40 NRC Initial License Exam, Scenario #2 SEG 11. IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. Safety Significance: Maintaining RPV water level above -25" will ensure that the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500F. The use of table 1B systems is to ensure the flowpath of the injection water is outside the shroud and mixes with the warmer water in the lower plenum prior to it reaching the core. Cue: Power level control has been entered in ATWS, RPV water level is below +87", and one or more of the following conditions have been met for reinjection: Reactor power drops below 5% RPV level reaches +15" All SRVs remain closed and DW pressure remains <2 psig. Performance Standard: Table 1B Injection systems are injecting to maintain RPV level above -25". Restarting of FW injection to maintain RPV level is satisfactory for this critical task. If injection with Table 1B systems are not required to maintain RPV level above -25", this critical task would be N/A. Example: RCIC has been operating and is maintaining RPV level. If the crew injects with Core Spray in an attempt to maintain RPV level above -25", this should be considered a critical task failure unless an ATWS ED has been performed. If an uncontrolled injection (above 2.8 Mlb/hr) causes a power rise above 5%, it should be considered a critical task failure. If an uncontrolled injection does not cause a power rise above 5%, but does cause RPV water level to go above the EOP ATWS maximum recorded RPV level, the critical task is satisfactory although remediation may be necessary. If RPV water level goes above the EOP ATWS maximum recorded RPV level due to CRD, SBLC and/or level swell, this should not require remediation. Feedback: RPV water level is being maintained above -25". EOP step(s): ATWS /L-3 BWROG: RPV 6.4 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 40 SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #3 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Jesse Seymour 2/18/15 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 31 NRC Initial License Exam - Scenario #3 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team | |||
==References:== | |||
AOP 255.2, Rev 42 AOP 410, Rev 28 ARP 1C04B, Rev 79 ARP 1C04C, Rev 45 ARP 1C05A, Rev 78 ARP 1C05B, Rev 98 ARP 1C06A, Rev 68 ARP 1C07B, Rev 87 ARP 1C23B, Rev 22 ED, Rev 9 EOP 2, Rev 16 EOP1, Rev 18 EOP3 EOP 4, Rev 20 IPOI 3, Rev 144 IPOI 5, Rev 58 OI 149, Rev 146 OI 150, Rev 78 OI 152, Rev 111 OI 264, Rev 134 OI 878.4, Rev 40 STP 3.6.2.1-01, Rev 8 Technical Specifications Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 31 NRC Initial License Exam - Scenario #3 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: Reactor power approximately 40% Power ascension in progress. Turnover: Continue power ascension in accordance with IPOI 3, POWER OPERATIONS (35% - 100% RATED POWER, Section 4.0. Steps are completed up to step 5. Raise power to approximately 50%. Stabilize power at approximately 50% and perform RCIC pump surveillance test Event # Malf # Eventy Type* Event Description 1 R ATC Raise power with recirculation flow. 2 rr17a C ATC C SRO 'A' Recirc Pump Speed Controller Failure. 2 nm08c I ATC TS SRO APRM 'C' fails (inoperable). Tech Spec review (3.3.1.1, 3.3.2.1) 3 N BOP RCIC Start IAW OI 150 4 rc06 sw14a sw14b C BOP TS SRO A RCIC system isolation signal is received due to steam leak; isolation is faulted. Tech Spec entry (3.5.3) 5 sw19b C BOP C SRO River Water Supply Pump trip. 6 M (ALL) Large break LOCA occurs (Recirc Pump suction break). Faulted LPCI initiation. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions 1. Reset to IC13 and lower power to ~40% RTP a. Lower reactor power using recirculation flow and control rods b. Load Events c. Load Malfunctions d. Load Overrides e. Place Torus Cooling in service with 1 RHR Pump and 1 RHRSW Pump operating on each side. 2. OR Reset to the IC provided by the LOIT Exam Development Team 3. Verify B and C APRM's are BYPASSED. 4. Mark up OI 150, Section 5.2 to step 7, and verify all steps to that point have been completed. 5. Mark up IPOI 3 up to and including step 7. NA step 8. 6. Obtain keys from key locker for Placing Torus Cooling in service. 7. Verify Events validate FALSE 8. Reset APRM Gains and clear recorders 9. Complete the Exam Setup Checklist 10. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0 11. Verify EOOS up-to-date. 12. Verify the SUFRV Lined up to the operating Feed Pump. 13. Have a copy of Daily Jets STP available to provide when requested. Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, 9 Manual Trigger Manual Trigger 20 YCAB002 >= 48 Power > 48% 21 1A1/1A2 Transfer 1A1/1A2 Transfer 22 HPCI Starts ZDIRPC71AS1(1) ==1 & ZLOHPHS2202(2) == 1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp (sec) ET Initial Value Final Value Setup rh10c RHR C PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10d RHR D PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10a RHR A PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10b RHR B PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup stdg01 TRIP OVERRIDE - 'A' SBDG 1G31 FAILS TO AUTO START Inactive Active Setup stdg02 TRIP OVERRIDE - 'B' SBDG 1G21 FAILS TO AUTO START Inactive Active Setup cs05a CORE SPRAY PUMP A - FAILURE TO AUTO-INITIATE Inactive Active Setup cs05b CORE SPRAY PUMP B - FAILURE TO AUTO-INITIATE Inactive Active Setup strh02 LPCI B INJECT VALVE FAILS TO AUTO OPEN - MO-1905 Inactive Active Setup ms31b GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- MO2401 Inactive Active Setup ms31a GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- MO2400 Inactive Active Setup strh01 LPCI A INJECT VALVE FAILS TO AUTO OPEN - MO-2003 Inactive Active Setup sthp01 HPCI SYSTEM AUTO INITIATION BLOCK Inactive Active Setup nm08c APRM CHANNEL FAILS- CHNL C 1 As Is 100 Setup rc06 RCIC STEAM SUPPLY LINE BREAK (RCIC ROOM) 6 min 3 0 30 Setup sw19b RIVER WATER SUPPLY PUMP TRIP- PUMP B, 1P117B 5 Inactive Active Setup rr15a RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP A 6 min 7 0 2 Setup rr17a RECIRC M-G FLOW CTRLR FAILS, AUTO/MAN MODES- M-G A 1 min 20 As Is 80 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp (sec) ET Initial Value Final Value Setup sw14a RCIC ROOM COOLER ESW FLOW BLOCKAGE- 1V-AC-15A 3 min 3 As Is 85 Setup sw14b RCIC ROOM COOLER ESW FLOW BLOCKAGE- 1V-AC-15B 3 min 3 As Is 85 Setup strc01 TRIP OVRD- RCIC FAILS TO AUTO START Write a sch file to block the initiation and valve light power 3 Inactive Active Setup fw02a CONDENSATE PUMP TRIP- PUMP A 21 Inactive Active Setup fw02b CONDENSATE PUMP TRIP- PUMP B 21 Inactive Active Setup hp02 HPCI TURBINE TRIP 22 Inactive Active Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 OVERRIDES Time Over. No. Override Title Delay Ramp ET Initial Value Final Value REMOTE FUNCTIONS Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Setup fp08 May need to look up RCIC DELUGE MAN ISOLATION VALVE V-33-84 (OPEN,CLOSE) Open Closed Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist. If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Warm Spring Day (Plant power levels) o Reactor Power Level 42% o Core Flow 30 Mlbm/hr Protected train o Protected Train is "B" Technical Specification Action statements in effect o TS LCO 3.5.1 Condition B- Day 1 of 7 One low pressure ECCS subsystem inoperable for reasons other than Condition A. Restore low pressure ECCS subsystem to operable status within 7 days. Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Raise Power with Recirc to approximately 50% RTP. o Perform RCIC post maintenance confidence run for maintenance performed a week ago IAW OI 150, Section 5.2. in CST to CST mode of operation. o RCIC Inop STP, 3.5.3-01 was completed just prior to turnover. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, problems, operator workarounds, etc. o One Extra NLO is in work control waiting for the RCIC Test Run and has been briefed. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Raise power with Recirc flow. If Contacted as the Reactor Engineer to provide guidance, Simulator Operator: Inform the crew to raise power with Recirc Flow to achieve approximately 50% power and hold power constant until a rod sequence is approved for further power ascension. CREW: CRS: Directs power to be raised from 40 to 50% using recirculation pump flow. RO: Performs Recirculation Pump flow adjustments to raise power from 40 to 50%. Monitors plant parameters for expected response during reactivity manipulation. BOP: Adjusts generator excitation manual regulator adjust to maintain the generator nulled. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: When power reaches ~48% | |||
When contacted as the 2nd Asst. to go to the MG Set Room to investigate the Recirc Pump Speed Changer, Wait 2 minutes and When Contacted as the DSM/OD When Contacted as the RE When contacted as procedures to deliver a copy of STP 3.4.1- Simulator Operator: Verify [ET 20] activates. This will cause "A" Recirc MG Set speed to rise. Simulator Operator: Report that the power switch is on and the thermal overload button on the motor is reset. Simulator Operator: Agree to support trouble shooting efforts. Simulator Operator: Acknowledge the situation and inform the CRS that you will develop a plan for recovery. Simulator Operator: Acknowledge the request and deliver the STP after 5 minutes. CREW: CRS: Will enter AOP 255.2 on the Power/Reactivity Abnormal. Contact the Duty Station Manager/Operations Director and/or the Reactor Engineer. May Enter TS 3.4.1 Condition C for the Mismatch in Recirc Pump Speeds. o Recirc Pump Speed Mismatch graph on the following page. If the "B" Scoop Tube was locked, the CRS may direct the crew to reset the "B" Scoop Tube in accordance with OI 264 RO: ARP 1C04A (C-5) Actions taken for the scoop lock. Will Lock the 'A' Recirc MG Set Scoop Tube from 1C04. The crew may lock the "B" Scoop tube if they do not diagnose the event properly Take actions IAW AOP 255.2 If directed, reset the "B" Scoop Tube in accordance with OI 264 BOP: Direct inplant operators to investigate the scoop tube malfunction Take actions for AOP 255.2 Run 3D Case Plot Power to Flow Resetting the scope tube lock on the next page. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Resetting the scoop tube lock on "B" Recirc Pump BOP: If directed, reset the "B" Scoop Tube in accordance with OI 264 o If A[B] Recirc MG Set is running, reset the Scoop Tube Lockout as follows o Verify Scoop Tube Position P-% o Adjust setpoint S-% to approximately match Scoop Tube Position P-%. o Verify controller output V-% approximately matches Scoop Tube Position P-%. o At 1C04, reset scoop tube lock by momentarily placing handswitch B31A-S3A[B] to RESET and then verify the following: o Annunciator 1C04A, C-5[1C04B, C-2], "A[B] RECIRC MG SCOOP TUBE LOCK" resets. o Amber SCOOP TUBE LOCKED Light located at 1C04 (above A[B] Scoop Tube Control handswitch B31A-S3A[B]) is OFF. o Verify that the Recirc pump speed is stable by observing the following parameters o SETPOINT (S), Percent Position (P), Percent Speed (X), Recirc pump discharge flow, Total core flow, Core pressure drop, APRM readings o Verify that SETPOINT (S) is selected for digital display. EXAMINER NOTE: After power has been raised to approximately 50%, commence Event 2. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3: | |||
If Contacted as a maintenance or support organization, Following the reset of the half-scram, crew should proceed to the RCIC surveillance test. If crew does not proceed, Simulator Operator: ACTIVATE [ET 1] This will cause "C" APRM to fail upscale. | |||
Simulator Operator: Acknowledge the issue, and/or to provide maintenance support for troubleshooting/repair. | |||
Simulator Operator: Call the CRS as the Operations Director and direct the crew to proceed with the RCIC Trouble Shooting Run to test the Flow Controller. Crew: Identifies the following: a half-scram has occurred. a rod out-block has occurred. BOP: OI 878.4 actions to Unbypass A APRM and take C APRM Out of operate. OI 878.4 actions to Bypass C APRM o If an APRM is currently bypassed, perform the following for the bypassed APRM, otherwise N/A this step: o Verify the APRM upscale, inoperative, and if greater than 5% | |||
reactor power, downscale trips on Panel 1C37 are reset. o Verify the IRM/APRM recorders on Panel 1C05 indicate approximately the same average power for the bypassed APRM as they do for the other APRM channels in operation. o Place the APRM BYPASS switch C51B-S3 or C51B-S6 on Panel 1C05 in the neutral (unbypassed) position. o Observe that the bypass light on Panel 1C05 and/or that the bypass light on Panel 1C37 is/are OFF. o Verify the two APRM channels in the RPS trip system which are to remain UNBYPASSED are OPERABLE, otherwise comply with Technical Specifications and TRM for inoperable RPS instrumentation. o Place the APRM BYPASS switch C51B-S3 (C51B-S6) on Panel 1C05 in the A, C, or E (B, D, or F) position for the channel to be bypassed. o Observe that the bypass lights for the bypassed channel on Panel 1C37 and/or Panel 1C05 is/are ON. Unbypass the D APRM Bypass the B APRM Actions are repeated for B and D APRMs RO and CRS Actions are on the following pages Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RO: Responds to failure of APRM 'C' Acknowledges 1C05A (B-2), APRM A, C, OR E UPSCALE TRIP OR INOP. o Check the SCRAM GROUP A and B lights on 1C05 to determine if a full Reactor scram has occurred. o If a full Reactor scram occurs, perform IPOI 5 (Reactor Scram). o Monitor APRM indications on Panels 1C05 and/or 1C37. o If only A RPS half scram has occurred: If any B RPS channel APRM is rapidly approaching or has exceeded its trip setpoint, manually scram the Reactor and perform IPOI 5 (Reactor Scram). o Suspend testing in progress on other RPS instrumentation. o If the trip is due to a loss of power, perform AOP 358 (Loss of RPS AC Power) and comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation. o If it is determined that an APRM has failed: Comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation and the Technical Requirements Manual requirements for Control Rod Block Instrumentation. With permission from the CRS, bypass the affected APRM o Reset the half scram. Acknowledges 1C05B (A-6), ROD OUT BLOCK. References ARP. Identifies that APRM 'C' has failed. When directed by the CRS, bypasses the 'C' APRM. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Directs crew response for failed APRM 'C' Reviews TS 3.3.1.1, Condition A for applicability Instrumentation. Reviews TS 3.3.2.1 for applicability. Reviews TRM LCO 3.3.2, Condition A for applicability. Directs 'C' APRM to be bypassed. Directs the half-scram to be reset. Briefs the crew on the effects of the Scoop Tube and APRM Failure. Direct the B APRM to be bypassed if not completed. EXAMINER NOTE: After the half-scram is reset and B APRM is BYPASSED, crew should proceed to RCIC Confidence Run (Event 3). Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 RCIC Confidence Run At the Direction of the Lead Examiner, When Contacted as the Extra Operator for the RCIC Run, Simulator Operator: Call the control room as Ray Wheaten and direct the crew to proceed with the RCIC Run, and that this is the crews priority. | |||
Simulator Operator: Wait 4 minutes and inform the control Room that Oil level has been verified satisfactory And standing by outside the RCIC Room. Air Flow Verified through the coolers. CRS: Directs crew to conduct the RCIC Run IAW OI 150, Section 5.2 in CST to CST Mode. Verify RCIC LCO has been entered, LCO 3.5.3, Condition A - RCIC System inoperable. Per the turnover, the RCIC Inop STP was previously completed, and restore to OPERABLE in 14 days. RO: Monitors plant parameters during RCIC Run. BOP: Starts RCIC in CST to CST mode in accordance with OI 150. Start 1V AC 15A and B RCIC ROOM CLG UNITS at 1C23 Open the REDUNDANT SHUTOFF valve MO 2316 on 1C03. Open the TEST BYPASS valve MO 2515 to 44-46% open as indicated on RCIC TEST BYP MO 2515 POSITION ZI 2515. Verify MO 2511 PUMP DISCHARGE valve is open. Start 1P 227 VACUUM PUMP by placing handswitch HS 2415 on 1C04 in the START position. Open MO 2426 LUBE OIL COOLER SUPPLY by placing HS 2426 in the OPEN position momentarily and observing proper valve position indication. If time permits, ensure unnecessary/unauthorized personnel are clear of the RCIC Room. Initiate Torus water temperature monitoring per STP 3.6.2.1-01. This is only required while heat is being added to the Torus. BOP Actions Continued Next Page Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When Contacted as Health Physics, When contacted as an operator to verify RCIC Running Sat, When Contacted as a member of the maintenance staff for trouble shooting Simulator Operator: Acknowledge the running of RCIC and the potential to change rad levels in the plant. Simulator Operator: Report that the pump is operating sat. Simulator Operator: Report that you will begin trouble shooting and to stand by for direction from the team. Open MO 2404 TURBINE STEAM SUPPLY by placing the handswitch in the OPEN position momentarily and observing proper valve position indication and that RCIC turbine speed, pump discharge pressure, and RCIC flow indicators indicate increases. Verify CV 2410, CV 2411, and CV 2436 Close Verify that MO 2510 MIN FLOW BYPASS opens when RCIC Flow is less than 80 gpm with pump discharge pressure greater than 125 psig. Verify HV 2406 TURBINE CONTROL VALVE Governor Valve is throttling to control turbine speed. In the CST to CST mode, throttle MO 2515 TEST BYPASS to achieve the desired discharge pressure. Verify that MO 2510 MIN FLOW BYPASS valve closes as RCIC flow rises above 80 gpm. Adjust FIC 2509 FLOW CONTROL until desired flow is achieved; do not throttle RCIC turbine speed below the minimum of 2000 rpm. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: When RCIC flow to the CST has been established, and with direction from the lead examiner: | |||
As the extra operator at the RCIC Room Door, once the High Amb Temp alarm sounds, Simulator Operator: ACTIVATE [ET 3] This will cause a small leak in the RCIC Room. Temperatures in the room will not exceed MAX SAFE limits. Simulator Operator: Inform the crew that a steam leak occurred in the RCIC Room, the RCIC room was evacuated, all personnel are accounted for, and that there are no injured personnel. CREW: identify that a RCIC isolation signal is present due to a steak leak in the RCIC room (e.g. high area temperature). RO: Monitor 1C05 indications for Power/Pressure/Level. If Required, attempt to Isolate the RCIC Steam Lines while the BOP is in the back panels area. Identifies that a valid RCIC isolation signal should be present due to a steam leak in the RCIC Room. Identifies that an automatic RCIC isolation has failed to occur. Manually initiates RCIC isolation by performing the following in accordance with OI-150, Section 7.1 or the applicable ARPs: o Closes MO-2400 RCIC INBD STEAM LINE ISOL, and MO-2401 RCIC OUTBD STEAM LINE ISOL. BOP: performs the following: May recognize the 1C23 Trouble Annunciator on 1C07, and investigate the Back Panel Area for the cause of the alarm. Upon investigation, the crew may take actions to Isolate RCIC. Acknowledges 1C04B (B-04) STEAM LEAK DET AMBIENT HI TEMP, 1C04C (A-07) References ARP(s). Goes to the back panel area to report temperatures. Established Ventilation in a 3-2-3 line up. RO/BOP/CRS Make Plant Announcement to alert personnel to the steam leak from RCIC CRS Actions continued on the next page. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 31 NRC Initial License Exam, Scenario #3 SEG Examiner Note: Once the RCIC test flow to the CST has been established, commence Event #4. When the crew has isolated the RCIC Steam Leak, If directed to deenergize MO-2401, If directed to deenergize MO-2400, SIMUATOR OPERATOR Delete ESW COOLER Blockage [sw14a and sw14b] Simulator Operator Insert OVER RIDES DO-RC-013 to off DO-RC-014 to off DI-RC-008 to auto And inform the crew that 1D14 Ckt 1, MO-2401 Power Supply is open. Simulator Operator Insert OVER RIDES DO-RC-010 to off DO-RC-011 to off DI-RC-006 to auto And inform the crew that MO-2400 Power Supply is open. CRS Actions continued from the previous page. CRS: performs the following: May enters EOP-3, Secondary Containment Control o Implements actions of EOP-3 SC/T leg for RCIC room temperature being greater than the Max Normal Operating Limit, but less than the Max Safe Operating Limit. o Directs manual isolation of the RCIC system if not already done. References Technical Specifications to address RCIC system inoperability: o TS 3.5.3, Condition A May declare TS 3.6.1.3, Condition B for two valves that failed to shut on the Isolation Signal in a single flow path. EXAMINER NOTE: Once RCIC manual isolation has occurred and SRO has completed TS call, commence event #5. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 31 NRC Initial License Exam, Scenario #3 SEG Event 6: River Water Supply Pump spurious trip When contacted as the AUX Operator to investigate the loss of the B RWS Pump, Wait 4 Minutes DSM Call Simulator Operator: when directed by lead examiner ACTIVATE [ET 5] to cause the 'B' RWS Pump to trip. | |||
Simulator Operator: and inform the control room that the B RWS Pump is hot to touch and that there is no smoke and no fire. Simulator Operator: Acknowledge the request for support. CREW: identifies a trip of the 'B' River Water Supply Pump. RO: Monitors plant parameters. BOP: Performs the following: Attempt to start standby pumps in both RWS Subsystems as necessary to restore needed makeup flow. Send an operator to the Intake Structure to verify alarms and check RWS pump breaker condition. Verify the Auto Start is not selected to the inop pump. CRS: directs crew response as follows: May Enter AOP-410, LOSS OF RIVER WATER SUPPLY o Update the Online Risk Monitor for the status of River Water Supply Pumps. May Direct actions IAW the ARP 1C06A (A-3) B RWS Pump Trip for the tripped RWS Pump LCO 3.7.2 met, Technical Specification Inoperable Log entry. EXAMINER NOTE: Commence event # 7 at the direction of the Lead Examiner. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 31 NRC Initial License Exam, Scenario #3 SEG Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). If Contacted as an operator in the plant, Simulator Operator: perform the following at the direction of the Lead Examiner: Activate [ET 7] and verify rr15a activates on ramp | |||
Simulator Operator: Agree to support required actions CREW: Will recognize the automatic reactor scram, lowering RPV level, lowering RPV pressure, and rising drywell pressure and Enter EOP 1 and 2 RO: performs the following: Performs IPOI 5 QRC 1, Reactor Scram Immediate Operator Actions: o Initiates a backup manual reactor scram. o Places THE MODE SWITCH in SHUTDOWN. o Verifies all control rods fully inserted. o Verifies main turbine trip o Verifies main generator lockout. o Verifies neutron flux is lowering. o Inserts all functional SRM and IRM detectors. Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). Simulator Operator: When Contacted to provide support Acknowledge the request CREW: Upon receipt of a 2# Drywell Pressure signal, The crew will recognize the failure of all ECCS Systems to automatically start and o Start A and B SBDG's o Start A, B, C, D RHR Pumps o Start A and B Core Spray Pumps o Start HPCI Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 31 NRC Initial License Exam, Scenario #3 SEG When directed by the Lead Examiner, Simulator Operator: Activate [ET 9] This will trip HPCI and prevent it from restarting. CREW: Implements the mitigation strategies of EOP 1, RPV Control RO: Inserts a manual reactor scram. Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend. Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS: Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure. Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. Directs lowering reactor pressure to lessen the driving head on the leak in the drywell. Shows concern for maintaining plant cooldown within the limits. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 31 NRC Initial License Exam, Scenario #3 SEG CRITICAL TASK #33 Maintain RPV level above TAF with operator actions CRITICAL TASK #22 DW spray on high DW temperature CREW: Implements the mitigation strategies of EOP 2, Primary Containment Control Recognizes the failed ECCS initiation (LPCI) and directs action to establish LPCI injection (CRITICAL TASK #33). BOP: Informs the CRS of containment parameters including parameter name, value and trend. Installs Defeat 4. Utilizes OI 149 QRC to spray the torus. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening Throttle open MO-2006[MO-1933], Torus Spray Valve Utilizes OI 149 QRC to spray the drywell.(CRITICAL Task #22) Ensures Recirc Pumps are tripped Repositions HS-1903C - Enable Containment Spray Valves to Manual Depending on RPV level may take HS-1903B to 2/3 Core Coverage/LPCI INIT Interlock Override to MANUAL OVERRD Open MO-2000[1902] , Inboard Drywell Spray Valve Throttle open MO-2001[1903], Outboard Drywell Spray Valve. Trips the running recirculation pump. CRS: Performs a crew update of entry into EOP 2 due to Drywell Pressure. Obtains containment parameters. Directs installation of Defeat 4. Directs spraying the torus after confirmation that torus pressure is greater than 2 psig. Directs spraying the drywell before drywell temperature reaches 280F. Verifies torus water level less than 13.5 ft. Verifies plot of drywell temperature and drywell pressure on the DWSIL curve allows drywell sprays. Verifies recirculation pumps are secured. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 31 NRC Initial License Exam, Scenario #3 SEG CREW: Implements that mitigation strategies of the ALC contingency of EOP 1 BOP: Lockouts ADS. RO: Attempts to restore and maintain RPV level above +15" Maximizes injection with CRD in accordance with AIP 407. Injects with SBLC in accordance with AIP 406. Verifies injection subsystems can be lined up for injection Verifies at least one injection subsystem lined up with a pump running. CRS: Directs ADS lockout. Directs RPV level bands as RPV level lowers Directs maximizing injection with CRD in accordance with AIP 407. Directs injection with SBLC in accordance with AIP 406. Ensures injections subsystems can be lined up for injection. Waits for RPV level to drop to +15" Ensures at least one injection subsystem lined up with a pump running. Before RPV level reaches -25" performs an Emergency Depressurization. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 31 NRC Initial License Exam, Scenario #3 SEG Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches (-25"). CREW: ED when Reactor Water Level is < +15" and before Reactor Water Level reaches -25"(CRITICAL) CRS: Diagnoses HPCI failure to run Directs Emergency Depressurization. Directs Opening 4 SRVs When Directed opens 4 ADS SRVs to emergency BOP: Informs SRO when 4 SRVs are open Monitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 31 NRC Initial License Exam, Scenario #3 SEG Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). Simulator Operator: ROLE PLAY: if contacted as Equipment Operator, perform required component manipulations and make appropriate reports to the Control Room. BOP: performs plant EOP operations as directed by the SRO. Aligns systems (RHRSW, RHR, etc.) and reports trends as required. Identifies failure of automatic LPCI alignment and injection and manually aligns LPCI injection by starting RHR pumps and opening valves as necessary (CRITICAL TASK). | |||
EXAMINER NOTE: when sufficient crew execution of the EOPs has been observed, then the scenario may be terminated. *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 31 NRC Initial License Exam, Scenario #3 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.) Malfunctions: Before EOP Entry: 1. Runaway Recirc Pump 2. "A" APRM Fails Upscale 3. RCIC Steam Leak with Failure to Automatically Isolate 4. RWS Pump Trips After EOP Entry: 1. LPCI Pumps Fail to Auto Start 2. Condensate Pump Trip 3. Failure of SBDG to Start 4. Trip of HPCI Abnormal Events: 1. Power Reactivity Abnormal Change 2. High Ambient Temperature 3. Loss of RWS, AOP or ARP Actions 4. Major Transients: 1. LOCA 2. Emergency Depressurization Critical Tasks: 1. Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". 2. Critical Task #22 DW spray on high DW temperature 3. Critical Task #33 Maintain RPV level above TAF with operator actions Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 31 NRC Initial License Exam, Scenario #3 SEG 1. IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". Safety Significance: If the lowering RPV water level trend had not been reversed before RPV level drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping. Cue: RPV level lowered to +15". Performance Standard: The crew must "Initiate" emergency RPV depressurization after the lowest valid level indication shows <+15" and prior to the lowest valid level indicates -25". The critical task is not satisfactory if the actions for "Emergency RPV Depressurization" are not complete. (See definitions) Feedback: RPV pressure is rapidly lowering. EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 31 NRC Initial License Exam, Scenario #3 SEG 22. BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Safety Significance: If DW sprays were initiated when in the shaded area of the DWSIL, this could lead to an evaporative cooling pressure drop which could result in: Deinerting the containment or containment negative pressures below design. OR Drywell-below-torus differential pressure beyond design. Operation of DW sprays if DW temperature cannot be maintained below 280F, will ensure that the design temperatures of the components within the DW are not exceeded. If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV. Cue: DW temperature is rising and is below 280F. Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance Standard: DW sprays are initiated on at least one side of RHR prior to 280F DW temperature. If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure. If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required. Feedback: DW spray flow initiated and DW temperature is lowering. EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 31 NRC Initial License Exam, Scenario #3 SEG 33. The Reactor is shutdown and RPV water level can be maintained above +15 inches with preferred and alternate injection systems, THEN inject to restore and maintain RPV level above +15 inches. Safety Significance: The preferred method of core cooling is core submergence. If this method is available, the crew is directed to inject with preferred and alternate systems to maintain the preferred method of core cooling. Although other methods will provide core cooling, such as Emergency Depressurization, the core temperatures will be higher. Cue: RPV level is lowering and preferred and/or alternate methods of injection are available to maintain RPV level above +15 inches, but will not maintain +15 inches without operator action. If automatic actions will maintain RPV level above +15 inches, this task should be N/A. Adequate time needs to be given to allow the crew to restart injection. The crew has indications that the system(s) is(are) available for injection. Performance Standard: The crew should start or align systems or power supplies to maintain RPV level above +15 inches. This could be taking manual control of a failed automatic controller, restoring power to a bus that has an available injection system, opening a valve that failed to auto open, or resetting a "trip" signal for an injection system. If starting of injection with operator actions will not maintain RPV level above +15 inches, this critical task should be N/A. If this is the situation, and the crew does not attempt any of these systems, resulting in RPV level reaching +15 inches sooner than if the injection systems were started, remediation may be necessary, although the CT is N/A. Feedback: Injection systems are maintaining RPV level above +15 inches. EOP step(s): RC/L-3 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 31 JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 1 | |||
TITLE: VENT THE SCRAM AIR HEADER TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: VENT THE SCRAM AIR HEADER JPM NUMBER: 201001 REV. 0 TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS: 201001 K1.09 K/A VALUE: 3.1/3.2 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: Lab: Time for Completion: 10 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material) {C001} TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SETUP INSTRUCTIONS: NONE SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE | |||
Required Materials: 1. RIP 101.3, Rev 1 2. Crescent Wrench General | |||
==References:== | |||
: 1. RIP 101.3, Rev. 1 Task Standards: 1. The operator simulates closing V-17-61. 2. The operator simulates removing pipe plug d/s of V-17-174. 3. Simulates opening V-17-174. 4. The operator simulates closing V-17-174. 5. Operator simulates installing pipe plug d/s of V-17-174. 6. Operator simulates opening V-17-61. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 6 of 13 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. INITIAL CONDITIONS: The plant is operating at 70% power. An ATWS has occurred. The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS. The RO has directed you to vent the scram air header. INITIATING CUES (IF APPLICABLE): Vent the scram air header in accordance with RIP 101.3 and inform the control room. This JPM is not Time Critical. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step:1 Critical Y RIP 101.3 Step 1 Close V-17-61 (Scram Pilot Air Header Isolation Vlv). Standard: The operator simulates closing V-17-61. Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator "The valve stem is in and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 8 of 13 Performance Step: 2 Critical Y RIP 101.3 Step 2 Remove the pipe plug located downstream of V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: The operator simulates removing pipe plug d/s of V-17-174. Evaluator Cue: When the operator has simulated turning the cap in the clockwise direction, tell the operator, "The pipe plug has been removed." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical Y RIP 101.3 Step 3 Open V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: Simulates opening V-17-174. Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, "The valve stem is up and handwheel stops moving. You hear a loud rush of air coming from the open pipe. The air flow diminishes over time." Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 9 of 13 Performance Step: 4 Critical N RIP 101.3 Per Cue Communicates actions to control room. Standard: The operator simulates calling the control room and informs RO that scram air header is depressurized. Evaluator Cue: When the operator simulates informing the control room that the Scram Air Header has been vented IAW RIP 101.3, tell the operator "That all control rods indicated inserted. Restore the Scram Air Header." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical N Q & A Question and Answer: What do you expect the position of the scram pilot valves to be before and after venting? Standard: The operator should respond that the scram pilot valves will be closed before venting and open after venting. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 10 of 13 Performance Step: 6 Critical Y RIP 101.3, Restoration, Step 1 Restoration: Close V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: The operator simulates closing V-17-174. Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator "The valve stem is in and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical Y RIP 101.3, Restoration, Step 2 Restoration: Reinstall the pipe plug downstream of V-17-174. Standard: Operator simulates installing pipe plug d/s of V-17-174. Evaluator Cue: When the operator simulates putting the pipe plug back on, tell the operator "The pipe plug is installed" Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 11 of 13 Performance Step: 8 Critical Y RIP 101.3, Restoration, Step 1 Restoration: Open V-17-61, Scram Pilot air header isolation valve. Standard: Operator simulates opening V-17-61. Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, "The valve stem is up and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the scram air header has been vented and restored, the JPM is complete. Direct the Operator to show the location of 1C208 to complete the RCIC Start JPM. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 12 of 13 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE: | |||
NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS: The plant is operating at 70% power. An ATWS has occurred. The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS. The RO has directed you to vent the scram air header. INITIATING CUES (IF APPLICABLE): Vent the scram air header in accordance with RIP 101.3 and inform the control room. This JPM is not Time Critical. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. | |||
TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 2 | |||
TITLE: OPERATE RCIC FROM 1C208 TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: OPERATE RCIC FROM 1C208 JPM NUMBER: 295016-01 REV. 0 TASK NUMBER(S) / TASK TITLE(S): 94.28/ Transfer Control to the Remote Shutdown Panel K/A NUMBERS: 295016 AK2.02 K/A VALUE: 4.0/4.1 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: X To be performed in the Training Building prior to the In Plant portion of the JPM, In Plant portion is required after the Task. Lab: Time for Completion: 40 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material) {C001} TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SETUP INSTRUCTIONS: 1. Reset to any IC that RCIC can be run in 2. Activate the Remote Shutdown Panel with REMOTE Function EXAM01 to NORM 3. Verify the simulator group has restored the RCIC Controller at 1C208 to service. 4. Start RCIC in CST to CST Mode at 415 gpm. 5. Set up radios on the same channel 6. Simulator Operator functions as the remote shutdown panel operator for the JPM. 7. Large Picture of the Instrument Rack located near 1C208 for level indications if used instead of verbal Cues. SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE | |||
Required Materials: 1. AOP 915, Rev. 53 General | |||
==References:== | |||
: 1. AOP 915, Rev. 53 Task Standards: 1. The Operator Unlocks the door. 2. The operator will place HS-2440 in REMOTE. 3. Reduce the rate of injection. 4. The operator will take the evaluator to the 1C208 Panel in the Plant or explain in enough detail as to demonstrate knowledge of the location in the plant. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 6 of 13 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. INITIAL CONDITIONS: A Plant Transient has occurred requiring a shutdown from outside the control room. The control room is being evacuated. RCIC is injecting to the vessel. INITIATING CUES (IF APPLICABLE): The CRS has directed you to take control of RCIC from 1C208, and restore reactor water level IAW AOP 915. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step:1 Critical N AOP 915, Section 2, Step 2 NOTE NOTE RCIC can be controlled from 1C208 but no flow or speed indication is available. Standard: Operator reads and place keeps the NOTE. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical Y AOP 915, Section 2, Step 2 a 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: a. Open key locked door protecting normal/remote handswitch HS-2440 RCIC TURB SPEED SELECT. Standard: The Operator Unlocks the door. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 8 of 13 Performance Step: 3 Critical N AOP 915, Section 2, Step 2 b 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: b. Verify HIC 2440 input (P) and output (V) are consistent with FIC 2509 output (V) if Control Room is manned. Otherwise, mark this step N/A. Standard: The operator will verify the values in the control room. Evaluator Cue: Simulator Operator: When the operator contacts the control room, provide the current readings for reactor water level in the simulator using Extreme View. Communications will be by phone number 7825 or by simulator radio if provided. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical Y AOP 915, Section 2, Step 2 c 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: c. Place HS-2440 in the REMOTE position. Standard: The operator will place HS-2440 in REMOTE. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 9 of 13 Performance Step: 5 Critical N AOP 915, Section 2, Step 2 d 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: d. Toggle the parameter displayed on HIC-2440 to V using the D pushbutton if needed. Standard: if required, the operator will toggle the display to V. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 6 Critical Y AOP 915, Section 2, Step 2 e 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: e. Control RCIC flow with HIC 2440 as necessary using the pulser knob. Standard: The operator will turn the pulsar knob in the counter clockwise direction to lower flow. Evaluator Cue: Inform the operator that RPV Water Level is RISING and to reduce the rate of injection a small amount. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 10 of 13 Performance Step: 7 Critical Y Continued on JPM In Plant 1, Vent the Scram Air Header. After the completion of the above portion of the task, the operator is required to demonstrate the knowledge of the location of the 1C208 Panel in the Plant. Standard: The operator will take the evaluator to the 1C208 Panel in the Plant or explain in enough detail as to demonstrate knowledge of the location in the plant. Evaluator Cue: Inform the operator that this portion of the task is complete. Inform the operator that they are to take you to the 1C208 Panel in the plant during a future JPM. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 11 of 13 Terminating Cues: When the operator has taken control of the RCIC Turbine at 1C208 AND When the operator has demonstrated knowledge of the location of the 1C208 Panel in the plant. - Completed as part of venting the scram air header. | |||
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 12 of 13 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE: | |||
NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS: A Plant Transient has occurred requiring a shutdown from outside the control room. The control room is being evacuated. RCIC is injecting to the vessel. INITIATING CUES (IF APPLICABLE): The CRS has directed you to take control of RCIC from 1C208, and restore reactor water level IAW AOP 915. | |||
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. | |||
TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 1 of 19 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 3 TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 19 JPM TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance JPM NUMBER: 262002-05 REV. 0 TASK NUMBER(S) / TASK TITLE(S): 28.10 (NSPEO)/ Support shutdown of Regulating Transformer 1Y1A for maintenance K/A NUMBERS: 262002 K/A VALUE: A4.01 3.1 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: X Perform: EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: Lab: Time for Completion: 15 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 3 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material) | |||
{C001} Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 4 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 5 of 19 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SET UP: NONE Simulator Setup Instructions: NONE SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE Required Materials: 1. OI 317.1 General | |||
==References:== | |||
: 1. OI 317.1, Rev. 59 Task Standards: 1. At 1D15[1D25] place inverter ALARM BYPASS SWITCH to BYPASS. 2. At 1Y15, turn circuit breaker 1Y1503 OFF 3. At 1Y1A, turn circuit breaker 1Y1A02 OFF 4. At 1Y1A, turn circuit breaker 1Y1A01 OFF 5. At 1B32, turn circuit breaker 1B3216A OFF Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 6 of 19 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. The initial conditions that I read may not exactly match the plant conditions, assume that the conditions that I read you are the correct plant conditions. INITIAL CONDITIONS: 1Y1A Regulating Transformer requires maintenance. 1D15 Instrument AC Inverter is in operation. All other Instrument AC equipment are operable and in their normal line-ups. RPS Alternate Power Source is on 1Y2A. INITIATING CUES (IF APPLICABLE): The CRS directs you, IAW OI 317.1, "120 VAC Instrument Control Power System," to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. | |||
Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 7 of 19 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step: 1 Critical N OI 317.1, Section 5.5, Step (1) At Panel 1Y36, verify the RPS alternate power supply source is not selected to 1Y16 [1Y26] Standard: Determines that RPS alternate power supply source is on 1Y2A in accordance with the Initial Conditions. Evaluator Cue: Show the operator Picture #1 to show the position of the Arrow. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 8 of 19 Performance Step: 2 Critical N OI 317.1, Section 5.5, Step (1)(a) If necessary, transfer the RPS alternate power supply source to 1Y2A [1Y1A] per OI 358. Standard: Based on the Initial Conditions, this action is not necessary. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical N OI 317.1, Section 5.5, Step (2) If necessary, start up and transfer load to Inverter 1D15 per Section 3.5, or transfer loads to an operating inverter per Section 4.2. Standard: This step is a turnover item. 1D15 is in service. Student marks the step as N/A'd. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 9 of 19 Performance Step: 4 Critical N OI 317.1, Section 5.5, Step (3) At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET pushbutton. Standard: Simulating pushing LAMP TEST/ALARM RESET pushbutton. Evaluator Cue: If asked what he/she sees when the pushbutton is depressed, CUE him/her that all of the lights are lit. When he/she simulates releasing the pushbutton, inform the student that the panel is the way he/she sees it now. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 10 of 19 Performance Step: 5 Critical Y OI 317.1, Section 5.5, Step (4) At 1D15[1D25] open right cabinet door and place inverter ALARM BYPASS SWITCH to BYPASS. Standard: Place the ALARM BYPASS SWITCH to BYPASS. Evaluator Note: The safety gear is located in a locker in the battery room hallway. To achieve this task, an FR Rating of 5 is required. Once the gear is pointed out and it is determined what he/she is going to wear, no further actions are necessary as the cabinet will NOT actually be opened. The ALARM BYPASS SWITCH is located inside 1D15. For the purposes of this JPM, opening this panel is not required. The student should simulate opening the right cabinet door and state that the bypass switch is on the right side of the cabinet and that he will simulate taking the switch to BYPASS. Evaluator Cue: CUE the student that the ALARM BYPASS SWITCH is in BYPASS by showing the operator Picture 2 in the back of the JPM. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 11 of 19 Performance Step: 6 Critical N OI 317.1, Section 5.5, Step (5) Confirm the FORWARD TRANSFER light is ON. Standard: FORWARD TRANSFER light is confirmed ON. Evaluator Cue: If asked, CUE him/her that the FORWARD TRANSFER light is ON. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical N OI 317.1, Section 5.5, Step (6) At 1Y15 [1Y25], confirm switch 1Y1504 [1Y2504] in the INVERTER position. (1Y15 [1Y25] MAINTENANCE SWITCH) Standard: Switch 1Y1504 confirmed in the INVERTER position. Evaluator Cue: CUE the student that Switch 1Y1504 is confirmed in the INVERTER position. There is a CAUTION on this page that states that a scoop tube lock-up is possible when closing 1Y1503, the Candidate may call the control room and inform them of the possibility of a scoop tube lock up. CUE the student that you understand that a scoop tube lock up may occur, and that he may continue. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 12 of 19 Performance Step: 8 Critical N OI 317.1, Section 5.5, Step (7) CAUTION CAUTION Opening or closing of breaker 1Y1503 [1Y2503] could result in a Reactor Recirc A[B] MG Set Scoop Tube lockup due to a problem in the scoop tube positioner circuitry. Standard: Reviews and placekeeps the CAUTION. Evaluator Cue: If the student calls the control room, CUE him that you understand that a scoop tube lock up may occur and that he may continue. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 9 Critical Y OI 317.1, Section 5.5, Step (7) Lock the Reactor Recirc A[B] MG Set Scoop Tube per OI 264 (Reactor Recirc System). Standard: Locks the "A" Reactor Recirc MG Scoop Tube. Evaluator Cue: Inform the student that another operator has locked the "A" Reactor Recirc MG Scoop Tube. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 13 of 19 Performance Step: 10 Critical Y OI 317.1, Section 5.5, Step (8) Turn circuit breaker 1Y1503 [1Y2503] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO JS1501 [JS2501]) Standard: Simulates turning off circuit breaker 1Y1503, REGULATING TRANSFORMER 1Y1A SUPPLY TO JS1501 by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1503 is in the OFF position after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 11 Critical Y OI 317.1, Section 5.5, Step (9) At 1Y1A [1Y2A], turn circuit breaker 1Y1A02 [1Y2A02] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO 1Y16 [1Y26]) Standard: Simulate turning off circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 is off after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 14 of 19 Performance Step: 12 Critical Y OI 317.1, Section 5.5, Step (10) Turn circuit breaker 1Y1A01 [1Y2A01] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] INPUT) Standard: Simulate turning off circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT is OFF after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 13 Critical Y OI 317.1, Section 5.5, Step (11) At 1B32 [1B42], turn circuit breaker 1B3216A [1B4203A] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] AC SUPPLY) Standard: Simulate turning off circuit breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY by simulating pushing the breaker switch down. Evaluator Cue: CUE him that breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is off after the action is simulated. The student may state that he will open the cabinet to verify breaker is in the OPEN position. CUE the student when he/she sees the breaker and it is in the OPEN position. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 15 of 19 Performance Step: 14 Critical N OI 317.1, Section 5.5, Step (12) Reset the Reactor Recirc A[B] MG Set Scoop Tube as directed by the OSM/CRS per OI 264 (Reactor Recirc System). Standard: Resets the "A" Reactor Recirc MG Scoop Tube. Evaluator Cue: Inform the student that another operator will reset the Reactor Recirc MG Scoop Tube and the JPM is complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is simulated to be OFF and the scoop tube is reset, the JPM is complete. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 16 of 19 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained. Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JPM Page 17 of 19 Picture 1 Handle is Horizontal Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JPM Page 18 of 19 Picture 2 Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS: 1Y1A Regulating Transformer requires maintenance. 1D15 Instrument AC Inverter is in operation. All other Instrument AC equipment are operable and in their normal line-ups. RPS Alternate Power Source is on 1Y2A. INITIATING CUES (IF APPLICABLE): The CRS directs you, IAW OI 317.1, "120 VAC Instrument Control Power System," to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2}} | |||
Revision as of 14:22, 6 June 2018
| ML15232A162 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/20/2015 |
| From: | Division of Reactor Safety III |
| To: | NextEra Energy Duane Arnold |
| Zoia, C D | |
| Shared Package | |
| ML15118A356 | List: |
| References | |
| Download: ML15232A162 (159) | |
Text
SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 43 NRC Initial License Exam - Scenario #1 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team
References:
AOP 255.1, Rev. 44 AOP 255.2, Rev. 42 ARP 1C05A, Rev. 78 ARP 1C94, Rev. 48 IPOI 3, Rev. 143 OI 152, QRC 2, Rev. 1 OI 255, Rev. 87 OI 255 QRC 1, Rev. 3 OI 324, Rev. 113 OI 454, Rev. 65 OI 856.1, Rev. 45 Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 43 NRC Initial License Exam - Scenario #1 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: The plant is operating at 80% power due to a downpour for maintenance. Thunderstorms are forecast for the area. "B" SBDG was recently returned from maintenance.
Turnover: Complete 'B' SBDG Testing per OI 324, SBDG, Section 6.4, synchronize and load. Raise Reactor power using control rods to a load line of 94-95%. Event # Malf # Eventy Type* Event Description 1 None N BOP Synchronize and load the 'B' SBDG IAW OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. 2 None C BOP TS SRO Report from field that 'B' SBDG has a jacket cooling water leak 'B' SBDG declared inoperable per TS 3.8.1 3 None R ATC Raise reactor power with control rods 4 rd02 3023 C ATC Stuck Control Rod 5 rd11b C RO CRD Pump trip 6 hp01 C BOP TS SRO HPCI spurious start requiring manual shutdown/isolation HPCI declared inoperable per TS 3.6. 7 ed01(a-e) rr15b stdg01 M ALL Loss of Offsite Power with Small break LOCA. Failure of 'A' SBDG to start in AUTO, will start in Manual. 8 hp02 C BOP HPCI starts in Manual but trips shortly after. Emergency Depressurization required. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions a. Reset to IC 23 or the Snap (1) Raise power to ~80% with Recirc and Rods. (2) Load Events (3) Load Malfunctions (4) Load Remote Functions b. Verify Events validate FALSE c. Ensure the following procedure is marked up prior to turnover and being provided to the candidates: (1) OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM a) Place a checkmark in the placekeeping area for the NOTE at the beginning of the section b) Place a checkmark in the first two steps of the section regarding bromination not occurring and the SBDG readiness checklist being completed. d. Build a schedule file to remove RD022223 on ET 20. (1) Verify the schedule file is RUNNING. e. Verify MOL Pull Sheets are out. EVENT TRIGGERS Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, 10, 11, 12, 13, 14, 15, 17, 30 Manual Trigger Manual Trigger 20 ZAORDPDI1825 >= .60 Drive Water DP > 295 psig 23 ZLOHPHS2312(2) == 1 & ZDIRPC71AS1(1) == 1 HPCI Inject Valve Opening after mode switch in SHUTDOWN Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 me Malf. No. Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN1C08B(26) 1C08B (C-02) B DIESEL GEN PANEL 1C 94 TROUBLE 1 Crywolf ON Setup rd022223 CONTROL ROD BLADE STUCK- ROD 22-23 3 Inactive Active Setup stdg01 TRIP OVERRIDE - 'A' SBDG 1G31 FAILS TO AUTO START Inactive Active Setup stdg02 TRIP OVERRIDE - 'B' SBDG 1G21 FAILS TO AUTO START Inactive Active Setup rd070615 CONTROL ROD ACCUMULATOR TROUBLE- ROD 06-15 45 sec 5 Inactive Active Setup Rd073435 CONTROL ROD ACCUMULATOR TROUBLE- ROD 34-35 1 min 5 Inactive Active Setup rd11b CRD HYDRAULIC PUMP TRIP- PUMP B 5 Inactive Active Setup hp01 HPCI INADVERTANT INITIATION 7 Inactive Active Setup rc01 RCIC PUMP TRIP 9 Inactive Active Setup ed01a LOSS OF OFF-SITE POWER SOURCES- BKR M 60 Sec 21 Inactive Active Setup ed01b LOSS OF OFF-SITE POWER SOURCES- BKR J 60 Sec 21 Inactive Active Setup ed01c LOSS OF OFF-SITE POWER SOURCES- BKR K 60 Sec 21 Inactive Active Setup ed01d LOSS OF OFF-SITE POWER SOURCES- BKR X5960 60 Sec 21 Inactive Active Setup ed01e LOSS OF OFF-SITE POWER SOURCES- BKR X5940 60 Sec 21 Inactive Active Setup rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP B 8 min 21 0 0.7 rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP B 3 min 23 As Is 1 Setup hp02 HPCI TURBINE TRIP 15 sec 23 Inactive Active Setup rd11a CRD HYDRAULIC PUMP TRIP- PUMP A 24 Inactive Active Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Schedule File for SEG. At Time On Event Action Description None 20 Delete malfunction rd022223 CONTROL ROD BLADE STUCK- ROD 22-23 None 22 Insert malfunction dg03b after 45 1G21 'B' DIESEL GENERATOR TRIP- DG B None 10 Insert remote dg19 to IDLE HS-3281B B DG 1G21 IDLE-RATED SWITCH (RATED,IDLE) None 11 Insert remote dg11 to PARALLEL 'B' DIESEL GEN 1G21 DROOP SWITCH (UNIT,PARALLEL) None 13 Insert remote dg19 to RATED HS-3281B B DG 1G21 IDLE-RATED SWITCH (RATED,IDLE) None 12 Insert remote dg11 to UNIT 'B' DIESEL GEN 1G21 DROOP SWITCH (UNIT,PARALLEL) None 28 Insert remote rd03 to 5.00000 CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 ISOLATION None 27 Insert remote rd03 to 100.00000 in 60 CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 ISOLATION None 14 Delete malfunction rd070615 CONTROL ROD ACCUMULATOR TROUBLE- ROD 06-15 None 15 Delete malfunction rd073435 CONTROL ROD ACCUMULATOR TROUBLE- ROD 34-35 None 17 Insert remote an05 to ACK REMOTE FUNC FEEDBACK AN05- ACK SWITCH 1C94 (NORM,ACK) None 17 Insert remote an05 to NORM after 5 REMOTE FUNC FEEDBACK AN05- ACK SWITCH 1C94 (NORM,ACK)
Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 43 Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Mild summer morning (Plant power levels) o Reactor Power Level % o Core Flow 40 Mlbm/hr Protected train o Protected Train is "A" Technical Specification Action statements in effect o None Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Start and load 'B' SBDG from the Control Room in accordance with OI 324, Section 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM for industry OE investigation. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> load run is required to be performed for maintenance. Offsite Sources STP was completed just prior to turnover (< 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago). o Power assention in progress following a sequence exchange. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment o Raise Power with rod withdrawal to 85% Power per RE Direction Comments, problems, operator workarounds, etc. o None Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Start 'B' ESW IAW OI 454 to support starting "B" SBDG: When directed to perform "B" ESW pump prestart checks: One (1) minute after the "B" ESW Pump is started: Simulator Operator: Inform the control room that time compression is being used and the "B" ESW Pump is ready for start. Simulator Operator Inform the control room that the "B"ESW Pump is running satisfactory. The strainer is rotating, auto vents are closed and that there is air flow in the room. The fan switch has been returned to auto. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. BOP Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. Start Emergency Service Water Pump 1P-99B per OI 454. Manually start either or both ESW pumps by performing either of the following: o Start B ESW PUMP 1P-99B by placing HS-4928B on 1C06 in the START position Verify B ESW PUMP 1P-99B running by observing the following on 1C06: o B ESW PUMP 1P-99B red indicating light is ON. o B ESW PUMP 1P-99B indicates normal running current of approximately 95-115 amps Verify adequate cooling for ESW Pump 1P-99B by observing that FI-4938B B ESW FLOW indicates greater than 300 gpm. As soon as possible after ESW pump start, perform the following: o Inspect the auto vent/vac breaker for evidence of excessive leakage. o Verify air flow from 1V-SF-56B, RHRSW/ESW Supply Fan. o After air flow is verified, operate 1V-SF-56B as directed by CRS. Control ESW/RHRSW pit level in accordance with OI 410. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the "B" SBDG Prelube pump is operating: Simulator Operator Inform the control room that the "B" SBDG Prelube Pump is running satisfactory. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.
CRS Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. BOP Start the B SBDG in accordance with OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. If starting the Standby Diesel Generator from the Control Room on 1C08 perform the following: Set Prelube Timer KS-3238B to 2.0 minutes. Start the B DIESEL GENERATOR 1G-21 PRELUBE pump by depressing the prelube pushbutton. After the Prelube Pump has been running for 1 minute, place B DIESEL GENERATOR 1G-21 CONTROL handswitch HS-3231B momentarily in the START position, and then return it to the AUTO position. Verify 1V-SF-21 Diesel Generator Supply Fan is running (verify red running light ON at 1C23). Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Paralleling the "B" SBDG to 1A4: When directed to place HS-3281, IDLE-RATED Switch in IDLE: One (1) minute after the request to place HS-3281B in IDLE: When requested to place HS-3234B, GOVERNOR MODE SWITCH in PARALLEL: One (1) minute after the request to place HS-3234B in PARALLEL:
Simulator Operator Acknowledge the request.
Simulator Operator Activate [ET 10]. Inform the control room that HS-3281B, IDLE-RATED SWITCH is in IDLE. Simulator Operator Acknowledge the request. Simulator Operator Activate [ET 11]. Inform the control room that HS3234B, GOVERNOR MODE SELECT SWITCH is in PARALLEL CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Verify SBDG 1G-21 started. At 1C94, verify HS-3281B, IDLE-RATED SWITCH, in IDLE. Perform the following on 1C08: o Adjusts "B" DIESEL GENERATOR 1G-21 VOLTAGE ADJUST control to maintain "B" DIESEL GENERATOR 1G-21 VOLTS meter at approximately 4160 volts. o Adjusts "B" DIESEL GENERATOR 1G-21 SPEED ADJUST control to maintain "B" DIESEL GENERATOR 1G-21 FREQUENCY meter at approximately 60 hertz. Place the GOVERNOR MODE SWITCH (DROOP) HS-3234B on 1C94 in the PARALLEL position. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Starting the "B" SBDG IAW OI 324 (cont): At the direction of the Lead Examiner: Communications for the leak are on page 14 Simulator Operator Activate [ET 17]. This will acknowledge the 1C94 Annunciator Alarms and clear the Control Room Annunciator on 1C08. This must occur prior to the next event. Simulator Operator: Activate [ET 1]. This will cause 1C08B (C-02), B Diesel Gen Panel 1C-94 Trouble to annunciate. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Enters AC Sources and SBDG LCOs. TS LCO 3.8.1 Condition A- One Offsite Circuit INOPERABLE. TS LCO 3.8.1. Condition B- One DG INOPERABLE BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Verifies AC Sources and SBDG LCOs have been entered. At 1C08, place BUS 1A4 Transfer handswitch to MANUAL. Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 "B" DIESEL GENERATOR 1G-21, to ON. Using the B DIESEL GENERATOR 1G-21 VOLTAGE ADJUST, raise INCOMING VOLTS SYNCHRONIZE to slightly more than RUNNING VOLTS SYNCHRONIZE. Using the B DIESEL GENERATOR 1G-21 SPEED ADJUST, adjust diesel generator speed to a slow, clockwise synchroscope rotation. When the synchroscope is at the 12 o'clock position, momentarily place the control switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 in the CLOSE position. Confirms the red (breaker closed) and white (closing spring charged) indicating lights are ON. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Starting the "B" SBDG IAW OI 324 (cont): When Contacted to verify 1A4 Switchgear Room Clear of Personnel, wait 1 minute and When directed to perform SBDG Operating Checklist OI 324A9 (Attachment 9): Simulator Operator inform the control room that 1A4 Switchgear Room is clear of personnel. Simulator Operator Acknowledge the request. CREW Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM. CRS Directs the operator to load the B SBDG in accordance with OI 324, Sect 6.6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Exits LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken to AUTO. BOP Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE "B" SBDG SYSTEM TO ESSENTIAL BUS 1A4. Loads the Diesel Generator to 250-300 KW using 1G21 speed adjust Place the SYNCHRONIZE switch for 4KV BREAKER 1A411 B DIESEL GENERATOR 1G-21 to OFF. Place BUS 1A4 TRANSFER handswitch in AUTO. Use B DIESEL GENERATOR 1G-21 SPEED ADJUST to load B DIESEL GENERATOR 1G-21 to 1,500 KW, observing B DIESEL GENERATOR 1G-21 KILOWATTS meter at 1C08 Adjust 'B' SBDG speed and voltage, as necessary to attain desired loading and power factor (0.9 power factor per Appendix 1). Complete the SBDG Operating Checklist OI 324A9 (Attachment 9). EXAMINER NOTE: After initially loading the 'B' SBDG, wait ~5 minutes then insert the next event. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: When directed to investigate the 1C94 Trouble Alarm: Three (3) minutes after being directed to investigate 1C94 Trouble Alarm: Simulator Operator Acknowledge the request. Simulator Operator: Inform the control room of the following: Coolant is on the floor around the SBDG, the expansion tank is empty. Annunciators in ALARM: 1C94 (A-3), Jacket Coolant Level Low 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Jacket coolant temp is 195°F, rising slowly. Crew Responds to 1C08B (C-2), B Diesel Gen Panel 1C-94 Trouble Alarm Responds to 1C94 (A-3), Jacket Coolant Level Low Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo BOP Send an Operator to 1C94 to determine the cause of the TROUBLE Alarm and take corrective action per ARP 1C-94. At 1C92 monitor TI-3258B to determine if Jacket Coolant temperature is high or low IF SBDG 1G-21 is running and NO LOOP or LOOP/LOCA emergency exists AND IF Jacket coolant temperature is above 195F on TI-3258B THEN Unload and trip SBDG and notify CRS. Unloads the 'B' SBDG (CRITICAL) Trips the 'B' SBDG (CRITICAL) Actions per the OI are on the next page. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 43 NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Jacket Coolant Leak on the 'B' SBDG. (cont'd)
When contacted as the DSM When contacted as Chemistry to investigate the leak, Floor Instructor The crew may elect to unload and remove the SBDG from service using OI 324. The steps documented to the right are the expected student response using OI 324. Simulator Operator: Acknowledge the request for support. Simulator Operator: Acknowledge the request for support. Crew Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo CRS Directs the operator to unload the B SBDG in accordance with OI 324, Sect 8.3, UNLOAD THE "B" SBDG. Enters LCOs 3.8.1.A and 3.8.1.B when the 1A4 Transfer handswitch is taken to MANUAL and exits 3.8.1.A when taken back to AUTO. BOP Implements OI 324, Sect 8.3, UNLOAD THE "B" SBDG If the SBDG is in PARALLEL OPERATION, then reduce the load on the Diesel Generator to 1500-1600 KW by using the DIESEL GENERATOR 1G-21 SPEED ADJUST CONTROL. Adjust A[B] DIESEL GENERATOR 1G-1G-21 VOLTAGE ADJUST to maintain 0.9 power factor per Appendix 1. Operate at 1500-1600 KW for 10 minutes to allow for cooldown. (Based on the current conditions, the 10 minute cooldown may be waived). Verify AC Sources LCO has been entered if applicable. Place the BUS 1A4 TRANSFER breaker mode selector switch is in MANUAL. (Critical for this evolution) Reduce the load on the Diesel Generator to 50 KW by using the DIESEL GENERATOR 1G-21 SPEED ADJUST CONTROL. Place the control switch for 4KV BREAKER 411 B DIESEL GENERATOR 1G-21 in the TRIP position. (Critical for this evolution) o Observe that the green (breaker tripped) and the white (closing spring charged) indicating lights are ON. Place the BUS 1A4 TRANSFER breaker mode selector switch in the AUTO position. (Critical for this evolution) At 1C08, confirm annunciator 4KV BUS AUTO TRANSFER INOP (1C08A, D-7) is reset. Actions continued on next page. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 43 NRC Initial License Exam, Scenario #1 SEG IF directed to place HS3234B in UNIT: If directed to place HS3281B in RATED: Simulator Operator Acknowledge the request. Activate [ET 12] This will insert RF dg11 to UNIT Inform the control room that HS3234B, B Governor Mode Switch is in UNIT. Simulator Operator Acknowledge the request. Activate [ET13] This will insert RF dg19 to RATED. Inform the control room that HS3281B, IDLE-RATED SWITCH is in RATED. Crew Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo CRS Directs the operator to unload the B SBDG in accordance with OI 324, Sect 8.3, UNLOAD THE "B" SBDG. Place the B GOVERNOR MODE SWITCH (DROOP) HS-3234B at 1C94 in UNIT. Directs placing the B DIESEL GENERATOR 1G-21 CONTROL handswitch HS-3231B on 1C08 in the PULL TO LOCK position. Declares the "B" SBDG INOPERABLE (already INOP potentially due to not exiting when 1A4 transfer switch was in MANUAL) TS LCO 3.8.1 Condition B- One DG INOPERABLE o Perform SR 3.8.1.1 for operable offsite circuits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. o Determine that the fault is not a common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. o Perform SR 3.8.1.2 for the operable EDG once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o Restore the inoperable EDG to operable within 7 days BOP Implements OI 324, Sect 8.3, UNLOAD THE "B" SBDG At 1C94, place HS-3281B, IDLE-RATED SWITCH, in RATED. EXAMINER NOTE: After the applicants shutdown the 'B' SBDG and after declaring the 'B' SBDG inoperable, the crew should proceed to withdrawing control rods. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 43 NRC Initial License Exam, Scenario #1 SEG Event 3 Increase Reactor Power with control rods If the crew does not transition to raising reactor power after the SBDG event: If called as organizational personnel to support the power rise: Simulator Operator: Contact the control room as the Reactor Engineer and inform them that raising reactor power is a priority. Simulator Operator Acknowledge the requests and provide needed support. CRS Directs Operators to increase power IAW IPOI and RE guidance RO Continues control rod withdrawal IAW OI 856.1 following the sequence. Monitor neutron monitoring instrumentation during control rod movements. Verifies the following indications: o White backlight on the Rod Select pushbutton turns ON o On the Full Core Display, the white "XX-XX" select light corresponding to the rod selected turns ON o On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod. Momentarily places the ROD MOVEMENT CONTROL in the OUT-NOTCH position and verifies: o The green ROD IN light turns ON momentarily and then turns OFF o The red ROD OUT light turns ON after the green ROD IN light turns OFF. o The red ROD OUT light turns OFF o The amber ROD SETTLE light turns ON and then turns OFF o The rod has been with drawn as indicated on the Four Rod Group Display BOP Provides Peer checks to RO during rod withdrawals. Monitors balance of plant equipment /plant status. Examiner Note: The 3rd control rod will stick. Go to Event 4. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 43 NRC Initial License Exam, Scenario #1 SEG Event 4: Stuck Control Rod At the direction of the Lead Examiner, When CRD drive water pressure is greater than 295 psig: If contacted as organizational personnel: Simulator Operator Activate [ET 3] This will stick Rod 22-23 at its current position. Simulator Operator Verify [ET 20] actuates. This will remove MF RD023023. This will allow rod 22-23 to move. Simulator Operator Acknowledge the information. Evaluator Note: It is satisfactory to adjust pressure greater than normal but less than 350# to limit stress on the CRD Evaluator Note: There is the potential to double notch a control rod with elevated drive water pressure. There is a large note in the AOP to direct the crew to recover from the double notch IAW OI 255 CREW Diagnoses control rod 22-23 is stuck CRS Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, when informed of stuck control rod. Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, requirements are met. Contacts RE and/or Duty Manager. RO While pulling control rods, recognizes 22-23 stuck and informs the SRO. Implements AOP 255.1, takes actions to address the stuck rod as follows: Verify power is available to RMCS. Verify the rod is actually selected. Demand a Rod Position Log and verify control rod positions. Verify the following parameters indicate approximately their normal values at 1C05 o CRD Pump flow at FC-1814 CRD System Flow Control (40 gpm) o CRD Charging Water header pressure at PI-1816A (CRD Pressure) Charging Water Press (1450 psi) o CRD Drive Water pressure at PDI-1825A (CRD Pressure) Drive Water P (260 psid) Raises drive water pressure to 310-350 psid by adjusting MO1830 until drive water pressure PI-1825A is 310-350 psid. Attempts to move the rod Recognizes rod movement and reports success to SRO Returns drive water pressure to its normal band Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 43 NRC Initial License Exam, Scenario #1 SEG Event 4: When directed to the HCU to perform local actions: Two (2) minutes after initial direction to verify condition at the HCU: If contacted to monitor HCU during control rod movement after RD022223 is removed: Simulator Operator Acknowledge the request.
Simulator Operator Inform the control room that the HCU lineup is normal and HCU pressure is normal. Simulator Operator Inform the control room that the HCU looked and sounded normal during the move. BOP Monitors balance of plant equipment/plant status. Contacts SANSOE to inspect control rod 22-23 HCU for abnormalities. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 43 NRC Initial License Exam, Scenario #1 SEG If the crew double notches the control rod, actions to recover are included. If contacted as the Reactor Engineer, Simulator Instructor Acknowledge the Double Notch and inform the crew that inserting the rod and continuing with the power change is permissible. Crew Recognize the Double Notch of the Control Rod. CRS Direct actions IAW OI 255, Section 10.1, Restoration from a Withdraw Double Notch. Notify Reactor Engineering. RO Verify thermal limits on an official or a predicted 3D case. Use the CONTROL ROD MOVEMENT SWITCH C11A-S2 at 1C05 to INSERT the rod one notch to its intended position. NA if the double notch is anticipated as part of a planned reactivity manipulation and thermal limits are not adversely affected. The crew should recommence the withdrawal of control rods IAW IPOI 3 once the double notched rod is restored. EXAMINER NOTE: Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 43 NRC Initial License Exam, Scenario #1 SEG Event 5: After the crew has performed AOP 255.1, raised power and at the direction of the examiner: When directed to investigate the cause of the "B" CRD pump trip. Two (2) minutes after being directed to investigate "B" CRD Pump breaker: Three (3) minutes after being directed to investigate "B" CRD pump locally: Simulator Operator ACTIVATE [ET 5]. This will cause a trip of the "B" CRD pump and accumulator alarms for 06-15 and 34-35.
Simulator Operator Acknowledge the request. Simulator Operator Inform the control room that 1A410, "B" CRD pump breaker tripped on inverse time delay overcurrent. Simulator Operator Inform the control room that "B" CRD pump motor is abnormally hot. CREW Responds to annunciator 1C05A (A-7) "B" CRD PUMP TRIP OR MOTOR OVERLOAD CRS Directs starting "A" CRD pump in accordance with OI 255. If HPCI is required to be operable, verify HPCI suction is aligned to the CSTs Contacts organization for support. RO Implement actions of ARP 1C05A (A-7) "B" CRD PUMP TRIP OR MOTOR OVERLOAD Determine the cause of CRD 1P-209B trip as follows o Monitor alarm "B" CRD PUMP 1P-209B LO SUCT PRESSURE (1C05A, B-7). o If necessary send an Operator to Bus 1A4 to check targets on Breaker 1A410 o As soon as practical, monitor computer points W092 and W093 for any bearing temperature > 180F If due to CAUSES 1.1 through 1.5, start CRD Pump 1P-209A per OI 255 (CRD Hydraulic System). If 1P-209B tripped due to any electrical fault, initiate a Work Request to have the pump checked, meggered, and repaired as necessary. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 43 NRC Initial License Exam, Scenario #1 SEG Event 5: When directed to verify adequate oil level and close V-17-8 to 1/2 turn open: When contacted as the Reactor Engineer and informed of the High CRD Temperatures, When directed to slow open V-17-8, "A" CRD Pump Discharge Valve: After the ramp is complete and V-17-8 is full open: Simulator Operator Activate [ET 28]. This will position V-17-8 1/2 turn open. Inform the control room that there is adequate oil level in the "A" CRD pump motor and speed changer and the V-17-8, "A" CRD Pump Discharge Valve is 1/2 turn open. Simulator Operator Acknowledge the request for support. Simulator Operator Acknowledge the request. AND Activate [ET 27] This will position V-17-8 full open in 60 seconds. Simulator Operator Inform the control room that V-17-8 is full open. If the crew elects to start the 'A' CRD pump in accordance with OI 255 here are the expected student responses. The crew may address 1C05A (E-6) CRD MECHANISM HIGH TEMP, but the condition is expected for the loss of the CRD Pump. CREW Implements OI 255, Section regarding Startup of a CRD Pump CRS Directs starting "A" CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump. RO Prepare to start CRD Pump 1P-209A as follows: Verify adequate oil level in CRD Pump 1P-209A motor and speed changer Close 1P-209A Pump Discharge Isolation V-17-8 to approximately 1/2 turn open. Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL. At 1C05, verify MO-1833, INLET TO CRD RETURN LINE, is fully open Start CRD PUMP 1P-209A by momentarily placing handswitch HS-1807A on 1C05 in the START position Slowly open Discharge Isolation V-17-8 to pressurize downstream piping and to prevent CRD pump from tripping on low suction pressure. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 43 NRC Initial License Exam, Scenario #1 SEG When directed to vent both CRD Discharge Filters: Simulator Operator Acknowledge the request. Inform the control room that time compression is being used and that both CRD Discharge Filters have been vented. CREW Implements OI 255, Section regarding Startup of a CRD Pump CRS Directs starting "A" CRD pump in accordance with OI 255, Section regarding Startup of a CRD Pump. RO Vent both CRD Discharge Filters 1F-201A and B At 1C05, verify charging header pressurized > 1200 psig on PI-1816A CHARGING WATER PRESSURE Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on FI-1814 CRD SYSTEM FLOW When FC-1814 is properly controlling flow, then shift to AUTO Slowly adjust DRIVE WATER P CONTROL MO-1830 to obtain approximately 260 psid on PDI-1825A DRIVE WATER P Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 43 NRC Initial License Exam, Scenario #1 SEG If the crew elects to start the CRD pump in accordance with OI 255 QRC 1 here are the expected student responses. CREW Implements OI 255, QRC 1, CRD Rapid Start CRS Directs starting "A" CRD pump in accordance with OI 255, QRC 1, CRD Rapid Start. RO If one CRD Pump is running, proceed to step (2), otherwise start CRD Pump as follows: Close MO-1830, Drive Water P Control Verify FC-1814, CRD System Flow Control in Manual and Closed Start 1P-209A[B], CRD Pump Throttle MO-1830, Drive Water P Control partially open. Adjust FC-1814, CRD System Flow Control and throttle MO-1830, Drive Water P Control to achieve desired pressure and flow. Verify operating CRD Pump motors above 9 amps Restore FC-1814, CRD System Flow Control to Auto Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 43 NRC Initial License Exam, Scenario #1 SEG Accumulator Trouble annunciator response If contacted to determine if there are any "slow" control rods based on last scram time testing: Simulator Operator Inform the control room that there are NO slow control rods. CREW Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL CRS Comply with Technical Specification requirements for Control Rod Scram Accumulators. May enter TS LCO 3.1.5.Condition A (twice)- One control rod scram accumulator inoperable with reactor steam dome pressure >900 psig. o Declare the associated control rod scram time "slow" within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR o Declare the associated control rod inoperable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Will Enter TS LCO 3.1.5 Condition B- Two or more control rod scram accumulators inoperable with reactor steam dome pressure >900 psig. o Restore charging water header pressure to > 940 psig within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of discovery of Condition B concurrent with charging header pressure < 940 psig. AND o Declare the associated control rod scram time "slow" within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR o Declare the associated control rod inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Must verify less than 6 control rods have been declared "slow" Must verify separation criteria for both "slow" control rods declaration and/or inoperable control rod declaration. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 43 NRC Initial License Exam, Scenario #1 SEG When directed to investigate accumulator trouble alarms: Three (3) minutes after being directed to investigate accumulator trouble alarms: Ten (10) minutes after being directed to recharge the accumulators: Ten (10) minutes after recharging 06-15: Simulator Operator Acknowledge the request. Simulator Operator Inform the control room that the alarms are due to low pressure. Control rod accumulator 06-15 is indicating 935 psig and 34-35 is indicating 930 psig. I will recharge the two accumulators in accordance with OI 255. Simulator Operator Activate [ET 14] This will remove MF RD070615. Inform the control room that accumulator 06-15 has been recharged. Final accumulator pressure is 1200 psig. Simulator Operator Activate [ET 15] This will remove MF RD073435. Inform the control room that accumulator 34-35 has been recharged. Final accumulator pressure is 1170 psig. CREW Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL CRS Directs recharging the accumulators in accordance with OI 255. RO Implement actions of ARP 1C05A (F-7), CRD ACCUMULATOR LO PRESSURE OR HI LEVEL Check the Full Core Display on 1C05 to determine which accumulators are in the trouble condition. o Determines that 06-15 and 34-35 are in trouble condition. Send an Operator to the accumulators to determine the cause of the alarm. Recharge accumulator per OI 255 (CRD HYDRAULIC SYSTEM). Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 43 NRC Initial License Exam, Scenario #1 SEG Event 6: When directed by the examiner: When contacted as organizational personnel to support HPCI auto initiation: If the operator checks status of relay E41A-K6: Simulator Operator: Activate [ET 7]. This causes an auto initiation of HPCI. Simulator Operator Acknowledge the information. Floor Instructor Inform the operator that the relay appears the same as C71A-K3D. This relay is energized to demonstrate the understanding of what it should look like. Crew Respond to auto initiation of HPCI. Implement OI 152, QRC 2, Tripping HPCI. CRS Directs tripping HPCI after verifying that HPCI operation is not required by assuring that by 2 independent indications adequate core cooling is assured. Enters AOP 255.2, Power/Reactivity Abnormal Change Comply with Technical Specification requirements for HPCI. TS LCO 3.5.1.Condition F- HPCI System INOPERABLE o F.1.- Verify by administrative means RCIC System is OPERABLE immediately o F.2.- Restore HPCI System to OPERABLE status within 14 days. BOP Implements actions of OI 152 QRC 2 to trip HPCI. Depresses and hold HS-2259, Remote Turbine Trip PB Verify HV-2201, HPCI Turbine Stop Valve Closes When HPCI speed is zero rpm, places 1P-218, Aux Oil Pump, in PTL. Verify HV-2200, HPCI Turbine Control Valve, closes Verify annunciator 1C03-3C (A6) is activated. Release HS-2259, HPCI Remote Turbine trip PB RO Continues to monitor reactor power, pressure and level May need to control level adjusting level setpoint. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 43 NRC Initial License Exam, Scenario #1 SEG AOP 255.2 due to HPCI auto start When contacted as organizational personnel to support HPCI auto initiation: Simulator Operator Acknowledge the information. Crew Respond to auto initiation of HPCI. Implement AOP 255.2, Power/ Reactivity Abnormal Change. CRS Directs AOP 255.2, Power/ Reactivity Abnormal Change. Establish critical parameter monitoring of Reactor Power, Reactor Pressure, and RPV Water Level, as priorities allow. Notify the Reactor Engineer and Operations Manager. After the cause has been determined and corrected, return to normal operation. BOP Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to: Assuming manual control of a malfunctioning system (completed when HPCI was tripped) Verify proper operation/indication of systems and/or indications. Monitor the Off-Gas System radiation levels on Panel 1C02 for any change in Off-Gas activity. RO Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal Verify control rod positions are correct for the established sequence, by using Rod Position Log Verify thermal limits on the Official 3D Case When power is stabilized, plot location on the Stability Power / Flow Map. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: LOOP, A DG Fails To Auto Start. (Will start in manual.) Small Recirc Leak Simulator Operator: Activate [ET 21] This will result in a Small Break LOCA immediately on a ramp and a LOOP after 60 seconds Simulator Operator: Critical Task #2 IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") LOSS OF POWER EVENT Crew Responds to Loss of Offsite Power CRS The crew may initially enter Station Black Out until the SBDG is restored to 1A3 -ESSENTIAL ELECTRICAL POWER" Directs starting the A DG and verifying it loads the Bus (CRITICAL TASK #2) RO Provides RPV level and pressure status BOP did not start t the "B" DG failed will not start and should be in Pull To Lock. BOP will start the 'A' SBDG with HS-3231A at 1C08 and verifies the output breaker closes. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Fails To Start but CAN be manually started. Small Recirc Leak CREW Responds to annunciator 1C05B-B1 - Primary Containment Pressure Hi/Lo Diagnoses rising containment pressure and lowering RPV water level. CRS Directs a reactor scram due to lowering RPV water level from SBLOCA. Direct the operator to Insert a manual reactor scram, and carry out IPOI 5 (Reactor Scram procedure) Confirms that the reactor is shutdown Direct the operator performance of the IPOI 5 immediate actions RO Perform the immediate operator responses to a reactor scram. Actions of IPOI 5 QRC-1: o Initiate a backup manual scram o Place the Mode Switch in SHUTDOWN o Verify all control rods fully inserted (single rod permissive) o Verify condenser backpressure is stable o If all control rods are not fully inserted, use the RIPs per CRS o Restore and maintain RPV level +170 to +211 (setback) o Verify recirc runback to 20% o Monitor RPV pressure o Verify Turbine/Generator trip o Verify neutron flux lowering o Insert SRM/IRM detectors o Announce scram via plant page o Proceeds to IPOI 5 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Fails To Start but CAN be manually started. Small Recirc Leak CRS Enters AOP 573 - Primary Containment Control RPV Control due to RPV low level (was entered when the scram occurred). -1 Alternate Level Control Leg is entered may direct: o Lockout of ADS o Start of CRD pump. o Start of SBLC pump Directs Reactor Water level band of 170" to 211" using available systems - (HPCI unavailable, will lead to ED) - This results DW Cooling Fans in FAST Primary Containment Control when containment pressure reaches 2 psig. ll Spray. - This results DW Cooling Fans in FAST Primary Containment Control when containment pressure reaches 2 psig. exceeds 11 psig, directs initiation of Drywell Spray. Event 8: HPCI starts but trips Simulator Operator: Verify [ET 23] is active Verify hp02 is on delay when the HPCI Turbine is started. After HPCI runs for 15 seconds the HPCI Turbine Trips. BOP Starts HPCI to maintain RPV level band. (HPCI will start but will trip) Reports to crew that HPCI has tripped. Attempts to restart (unsuccessful). Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 43 NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) LOOP, A DG Output BKR FAILS and will not close. B DG Fails To Start but CAN be manually started. Small Recirc Leak RO containment plant parameters BOP 1. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening 2. Throttle open MO-2006[MO-1933], Torus Spray Valve 1. Ensures Recirc Pumps are tripped 2. Repositions HS-1903C - Enable Containment Spray Valves to Manual 3. Depending on RPV level may take HS-1903B to 2/3 Core Coverage/LPCI INIT Interlock Override to MANUAL OVERRD 4. Open MO-2000[1902] , Inboard Drywell Spray Valve 5. Throttle open MO-2001[1903], Outboard Drywell Spray Valve. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements the mitigation strategies of EOP 1, RPV Control RO Inserts a manual reactor scram. Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend. Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure. Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. Directs lowering reactor pressure to lessen the driving head on the leak in the drywell. Shows concern for maintaining plant cooldown within the limits. Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Respond to and implement the actions of AOP 304.1, Loss of 4160V Non-Essential Power BOP Announces suspending all evolutions in progress associated with electrical switchgear and switching operations Verify two Well Water Pumps in service. Starts either A or C Well Water Pump and adjusts well water flow. Verify Well Water Pump 1P-58D secured. In AUTO, verifies FC-4414D, demand is zero. Verify GSW Pumps 1P-889A and B in service Place Bus 1A1 Transfer switch in MANUAL. Place Bus 1A2 Transfer switch in MANUAL. CRS Enters AOP 304.1, Loss of Both Non-Essential Buses Directs the BOP to take actions IAW AOP 304.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 43 NRC Initial License Exam, Scenario #1 SEG At the direction of the Lead Examiner once the crew completes the ED Brief and at the direction of the Lead Examiner Simulator Operator: Activate [ET 24] This will trip the 'A' CRD Pump Critical Task #22 BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays.
Simulator Operator: Activate [ET 9] This will trip the RCIC Pump Crew Implements the mitigation strategies of EOP 2, Primary Containment Control BOP Informs the CRS of containment parameters including parameter name, value and trend. Installs Defeat 4. Utilizes OI 149 QRC to spray the torus. Utilizes OI 149 QRC to spray the drywell.(Critical Task #22) Trips the running recirculation pump. CRS Performs a crew update of entry into EOP 2 due to Drywell Pressure. Obtains containment parameters. Directs installation of Defeat 4. Directs spraying the torus after confirmation that torus pressure is greater than 2 psig. Directs spraying the drywell before drywell temperature reaches 280F. Verifies torus water level less than 13.5 ft. Verifies plot of drywell temperature and drywell pressure on the DWSIL curve allows drywell sprays. Verifies recirculation pumps are secured. Placekeeps in EOP 2 to the applicable WAIT UNTIL steps in T/L (T/L-3 and T/L 10), T/T (T/T-2), DW/T (DW/T-6) and PC/P (PC/P-7) legs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements that mitigation strategies of the ALC contingency of EOP 1 BOP Lockouts ADS. RO Attempts to restore and maintain RPV level above +15" Maximizes injection with CRD in accordance with AIP 407. Injects with SBLC in accordance with AIP 406. Verifies injection subsystems can be lined up for injection Verifies at least one injection subsystem lined up with a pump running. CRS Directs ADS lockout. Directs RPV level bands as RPV level lowers Directs maximizing injection with CRD in accordance with AIP 407. Directs injection with SBLC in accordance with AIP 406. Ensures injections subsystems can be lined up for injection. Waits for RPV level to drop to +15" Ensures at least one injection subsystem lined up with a pump running. Before RPV level reaches -25" performs an Emergency Depressurization. BOP: nitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 43 NRC Initial License Exam, Scenario #1 SEG Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". CRS Directs the performance of ED once RPV Water Level cannot be maintained > +15" (Critical #1) ED-1 Override open CV-4371A (Defeat 11) - Completed Earlier In The Scenario ED-2 Are all control rods inserted to at least position 00? (YES) ED-5 Does a drywell high pressure ECCS signal exist? (YES) ED-6 Prevent injection from Core Spray and RHR pumps not required to assure adequate core cooling. ED-7 Is torus water level above 4.5 ft? (YES) ED-8 Open the 4 ADS SRVs. OK to exceed Cooldown rate limit. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 43 NRC Initial License Exam, Scenario #1 SEG Crew Implements mitigation strategies of EOP 1 after EOP ED to restore adequate core cooling RO Verifies low pressure ECCS systems start and align to inject into the RPV Reports when 1 Core Spray pump is injecting above 3000 gpm. and 1 other ECCS pump is injecting. Trips Core Spray pumps when RPV level indicates on the GEMACs Throttles RHR injection to restore and maintain RPV 170-211" CRS Verifies 1 Core Spray pump and 1 other ECCS pump available for injection Direct injection with one or more Preferred Injection Systems (Table 1A) and Alternate Injection Systems (Table 2A) Determines RPV level can be restored and maintained above +15" and returns to the normal RPV level control leg of EOP 1 Directs restoring and maintaining RPV level 170-211" using low pressure ECCS systems Directs tripping Core Spray pumps when RPV level indicates on the GEMACs Directs throttling RHR injection to maintain RPV level 170-211" CRS and Crew: Diagnoses HPCI failure to run Directs Emergency Depressurization. Directs Opening 4 SRVs (CRITICAL TASK #2) When Directed opens 4 ADS SRVs to emergency (CRITICAL TASK #2) Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 43 NRC Initial License Exam, Scenario #1 SEG *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 43 NRC Initial License Exam, Scenario #1 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES Malfunctions: Before EOP Entry: 1. Jacket Water Leak on "B" SBDG 2. Stuck Control Rod 3. "B" CRD Pump Trip 4. Low HCU Pressure 5. HPCI Spurious Start After EOP Entry: 1. Failure of "A" SBDG To Start 2. LOOP 3. "A" CRD Pump Trips 4. RCIC Trips 5. HPCI Trips Abnormal Events: 1. AOP 255.1, CONTROL ROD MOVEMENT/INDICATION ABNORMAL 2. AOP 255.2, POWER/REACTIVITY ABNORMAL CHANGE 3. AOP 301, LOSS OF ESSENTIAL ELECTRICAL POWER Major Transients: 1. LOOP 2. LOCA 3. ED Critical Tasks: 1. Critical Task #2 IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") 2. Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". 3. Critical Task #22 BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 43 NRC Initial License Exam, Scenario #1 SEG 2. IF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. (> -25" or -39") Safety Significance: Adequate core cooling is defined by EOPs as either: Core submergence (+15") Steam cooling with injection of makeup water to the RPV (-25") Required ECCS injection with RPV level above 2/3 core height (-39") Cue: RPV level will drop to <+15" and automatic system response will not restore RPV level for adequate core cooling. Performance Standard: If the crew performs actions that restore and maintain RPV level above +15", this critical task should be considered satisfactory because the crew has anticipated the potential loss of core cooling. If one CS is operating at 3000 gpm and another ECCS pump is injecting, RPV water level must be restored and maintained above -39". This would normally be expected after an Emergency RPV Depressurization. If ECCS is not injecting (less than 1 CS at 3000 gpm and another ECCS pump injecting), RPV water level must be restored and maintained above -25". This may be expected after an emergency RPV depressurization with ECCS problems Progression is to be made by the crew to use all available systems to restore RPV level above the directed level (-25" or -39"). Satisfactory performance of this CT does not require completion of starting all available systems if RPV level is restored above the directed level (-25" or -39"). If RPV injection is secured and RPV level is below +15" but above -25", the critical task is met, although remediation may be required. Feedback: Lowest valid RPV water level indicator is being maintained above directed value. EOP step(s): RC/L-10, L-11, L-12 BWROG: RPV-1.2 (1.2 is only after RPV pressure is lowered) Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 41 of 43 NRC Initial License Exam, Scenario #1 SEG 1. IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". Safety Significance: If the lowering RPV water level trend had not been reversed before RPV level drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping. Cue: RPV level lowered to +15". Performance Standard: The crew must "Initiate" emergency RPV depressurization after the lowest valid level indication shows <+15" and prior to the lowest valid level indicates -25". The critical task is not satisfactory if the actions for "Emergency RPV Depressurization" are not complete. (See definitions) Feedback: RPV pressure is rapidly lowering. EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 42 of 43 NRC Initial License Exam, Scenario #1 SEG 22. BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Safety Significance: If DW sprays were initiated when in the shaded area of the DWSIL, this could lead to an evaporative cooling pressure drop which could result in: Deinerting the containment or containment negative pressures below design. OR Drywell-below-torus differential pressure beyond design. Operation of DW sprays if DW temperature cannot be maintained below 280F, will ensure that the design temperatures of the components within the DW are not exceeded. If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV. Cue: DW temperature is rising and is below 280F. Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance Standard: DW sprays are initiated on at least one side of RHR prior to 280F DW temperature. If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure. If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required. Feedback: DW spray flow initiated and DW temperature is lowering. EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 1 rev 2 TR-AA-230-1003-F06 Revision 0 Page 43 of 43 SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Raymond Keith Walton 1/28/2015 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 40 NRC Initial License Exam - Scenario #2 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team
References:
STP 3.3.1.1-17 Rev 08 AOP 358 Rev 31 ARP 1C05A Rev 78 AOP 255.1 Rev 44 AOP 255.2 Rev 42 AOP 302.1 Rev 54 AOP 691 Rev 8 OI 358 Rev 66 OI 149 Rev 146 OI 150 Rev 78 EOP 1 Rev 18 EOP 2 Rev 16 EOP ATWS Rev 21 TRM Tech Specs Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 40 NRC Initial License Exam - Scenario #2 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: The plant is operating at 80% power due to a downpower for maintenance. Thunderstorms are forecast for the area. "B" CRD pump was recently taken OOS for maintenance. Turnover: Start 'B' SBDG for ST after maintenance. Raise Reactor power recirculation flow. Event # Malf # Eventy Type* Event Description 1 None N BOP Perform MSIV test per STP 3.3.1.1-17 for "D" MSIV's 2 None R RO R SRO Raise Power with Recirculation Flow to 85% RTP 3 rp02a C BOP TS SRO Trip of RPS MG Set Tech Spec 3.3.8; 3.4.5, A & B & C; TRM 3.3.4 entry 4 rd01 3023 C ATC TS SRO Control Rod Drift (30-23) with AOP 255.1& 255.2 entry Tech Spec entry 3.1.3 5 ed13a C BOP TS SRO 125 VDC Div 1 panel 1D11 trip results in AOP entries Tech Spec entry 3.8.7, Condition B 6 rc08 BOP TS SRO Spurious start of RCIC, requires manually stopping RCIC Tech Spec Entry 3.5.3, Condition A 7 mc04b R RO C BOP Condenser Vacuum Leak (recoverable) Fast Power Reduction 8 mc04b M ALL Rising backpressure from Event 5 progression necessitates reactor scram. ATWS occurs 9 hp03 I BOP Failure of HPCI controller (complicates RPV level restoration). * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
General Instructions 1. Reset to IC23 and raise power to ~80% RTP a. Load Events b. Load Malfunctions c. Load Overrides 2. OR Reset to the IC provided by the LOIT Exam Development Team 3. Verify Events validate FALSE 4. Reset APRM Gains and clear recorders 5. Complete the Exam Setup Checklist 6. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0 7. Fill in STP 3.3.1.1-17 Cover Matter through prerequisites, and have for turnover. 8. Verify MOL Pull Sheets are out. Trigger No. Trigger Logic Statement Trigger Word Description 3, 5, 7, 9, 11, 13, 15, 17 Manual Trigger 20 ZLOHPHS2202(2) == 1 HPCI MO 2404 Starts to open Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Value Final Value Setup rp02a RPS EPA BREAKER TRIP- RPS A EPA BKR 3 Inactive Active Setup rd013023 CONTROL ROD DRIFTS OUT- ROD 30-23 5 Inactive Active Setup ed13a 125 VDC DISTRIBUTION PANEL FAULT- PNL 1D11 7 Inactive Active Setup mc04b MAIN CONDENSER AIR INLEAKAGE- HP CONDENSER 6 min 9 0 .9 Setup rc08 INADVERTENT RCIC INITIATION 11 Inactive Active Setup mc04b MAIN CONDENSER AIR INLEAKAGE- HP CONDENSER 3 min 13 .9 1.2 Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME (VARIABLE) 0 75 Setup hp03 HPCI FLOW CONTROLLER FAILS 1 min 20 As Is 30 Setup fw02a CONDENSATE PUMP TRIP- PUMP A 15 Inactive Active Setup fw02b CONDENSATE PUMP TRIP- PUMP B 15 Inactive Active Setup rc01 RCIC OVERSPEED TRIP 17 Inactive Active Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Setup mc01 MN COND 1E-7A VACUUM BREAKER V-03-73 (CLOSED,OPEN) 28 CLOSED OPEN Setup mc02 MN COND 1E-7B VACUUM BREAKER V-03-67 (CLOSED,OPEN) 28 CLOSED OPEN Setup rp02 ATWS TEST SWITCH (AKA DEFEAT 12) HS-1863A (RUN,TEST) 2:30 min 12 RUN TEST Setup rp03 ATWS TEST SWITCH (AKA DEFEAT 12) HS-1864A (RUN,TEST) 3 min 12 RUN TEST Time Override No. Override Title Delay Ramp ET Initial Value Final Value Setup DI-PC-037 HS-4321A GRP 7 CHAN A DW CLG AND FAN OVR NORMAL NORMAL DI-PC-038 HS-4321B GRP 7 CHAN B DW CLG AND FAN OVR NORMAL NORMAL Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 40 Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Mild summer morning (Plant power levels) o Reactor Power Level 80% o Core Flow 40 Mlbm/hr Protected train o Protected Train is "B" Technical Specification Action statements in effect o None Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Perform STP 3.3.1.1-17, Main Steam Isolation Valve Functional Test for 'D' Main Steam Line ONLY. Retesting a relay. o Raise power with recirculation flow to achieve 85% RTP following a sequence exchange per RE direction. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline GREEN with one year to YELLOW o LERF Baseline GREEN with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, problems, operator workarounds, etc. o One Extra NLO Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Perform Main Steam Isolation Valve Testing CREW: Verifies Prerequisites for STP 3.3.1.1-17: No other testing on the RPS System All MSIV's are OPEN CRS: Authorizes performance of STP 3.3.1.1-17 for 'D' MSIVs. BOP: Verify energized at 1C15, RPS Trip Channel A1 B Line MSIV 90% OPEN relayC71A-K3E. Verify energized at 1C15, RPS Trip Channel B1 C Line MSIV 90% OPEN relayC71A-K3F. If the MODE SWITCH is in RUN, then visually confirm (at 1C15) the following CHAN A1 MSIV CLOSURE SCRAM BYP MODE SWITCH NOT IN RUN relay C71A-K11A contacts open (if MODE SWITCH is not in RUN, mark step 7.1.2.a and 7.1.2.b "N/A") Station personnel at 1C15 and 1C17 in preparation for observing test response of relays to the C71A-K3H and C71A-K3G, concurrent with cycling CV-4420 and CV-4421 At 1C03, take A INBD MSIV TEST CV-4420 handswitch HS-4412B to TEST and release. At 1C03, verify that CV-4420 goes partially closed and reopens fully. RO: Perform Peer Checks EXAMINER NOTE: After completion of STP, crew will move to raise reactor power Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Raise Power with Recirculation flow. If Contacted as the Reactor Engineer to provide guidance, Simulator Operator: Inform the crew to raise power with Recirc Flow to achieve approximately 85% power and hold power constant until a rod sequence is approved for further power ascension.
Evaluator Note: Proceed to the next event when core flow reaches ~44 mlbm/hr (~83% RTP) or at the discretion of the Lead Examiner. CREW: The crew will brief the reactivity change prior to taking the shift. CRS: Directs power to be raised from 80 to 85% using recirculation pump flow. RO: Performs Recirculation Pump flow adjustments to raise power from 80% to 85%. Monitors plant parameters for expected response during reactivity manipulation. BOP: Monitor the plant. Perform Reactivity Peer Checks to the ATC while adjusting Recirculation flow. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Trip of RPS MG Set Tech Spec 3.3.8 entry At the direction of the Lead Examiner When called as the 2nd Asst. to investigate the loss of RPS, wait 2 minutes, When called as the 2nd Asst. to verify Alt power aligned to 1Y16, When contacted to verify the Cleanup Beds in hold, wait 3 minutes Simulator Operator: Activate [ET 3] Respond as plant personnel as necessary. Simulator Operator: Reports the A RPS MG Set is tripped and faint acrid smell and abnormally hot to touch, Both EPAs are tripped. 1Y30 looks ok. Simulator Operator: Report that 1Y16 is aligned to the alternate RPS power. [verify RF rp04 is in 1Y16] Simulator Operator: Report cleanup beds in hold. CRS: Directs Operators to IAW AOP 358 Technical Specifications for this condition are listed on the next page. RO: Report Power Pressure Level Report Report the Loss of A RPS BOP: Complete actions IAW AOP 358 o Direct an Operator to 1A3 Essential Switchgear Room to assist in troubleshooting the RPS Electrical Distribution system. o Suspend all evolutions in progress associated with electrical switchgear and switching operations. o Verify applicable automatic actions have occurred. Manually initiate those automatic actions that should have occurred but failed to occur. o Declare CIT-2738 inoperable, due to loss of RWCU flow to monitor. Refer to TRM 3.3.4 o Verify the fault is not suspected to be on the RPS bus prior to reenergizing the bus on the RPS Power Supply. o IF an alternate RPS power supply is available as indicted by observing A MG or ALT XFMR white light ON at 1C15 Place handswitch C71B S1A RPS ALTERNATE POWER TRANSFER to A MG OR ALT position as required and verify selected position white light remains on. o WHEN "A" RPS bus is energized then as directed by the CRS, perform OI 358 RPS Appendix 4, "RPS POWER SUPPLY TRANSFER HALF SCRAM RECOVERY CHECKLIST", and restore RWCU System. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to verify sat operation of the C EPA's, Wait 2 minutes and When contacted as Chemistry, Simulator Operator: inform the control room that everything appears normal. Simulator Operator: Acknowledge the request for support. CRS: TS Entries possible Enters TSs o TRM LCO 3.3.4 A RCS Conductivity monitor 4 hr to restore monitoring. o TS LCO 3.3.1.1 A One or more required channels inoperable. o 3.3.1.1 B One or more Functions with one or more required channels inoperable in both trip systems. actions met o TS LCO 3.4.5 A, Required Drywell Sump System inoperable. Restore required Drywell Sump System to OPERABLE status. o TS LCO 3.4.5 B, Required Primary Containment Air Sampling System inoperable. Initiate action to restore required Primary Containment Air Sampling System to OPERABLE status. o TS LCO 3.4.5 C, Required Drywell sump System and containment air sampling inoperable, Restore Drywell Sump System to Operable OR restore o TS LCO 3.3.3.1 One or more Functions with one required channel inoperable. o TS LCO 3.6.1.3 A (12 times) (If Overriden) - Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE Applicable to all the Group 3 Isolation vales repositioned in the Group 3 Isolation ARP actions Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE DSM Electricians Allow the crew to get to the 1/2 Scram Recovery Checklist prior to proceeding. Simulator Operator: Acknowledge to support. Simulator Operator: Acknowledge to support. OI 358 Appendix 4 Actions BOP: At 1C05, position REACTOR SCRAM RESET hand switch C71A-S5 to Group 1 and 4 [Group 2 and 3] and then to Group 2 and 3 [Group 1 and 4] to reset Half Scram. Verify "A"["B"] RPS AUTO SCRAM annunciator (1C05A[B], A-2[A-2]) reset. At 1C36, reset Main Steam Line radiation monitors RIS-4448A/C[B/D]. At 1C36, reset Fuel Pool Exhaust radiation monitor RIS-4131A[B]. At 1C36, reset Carbon Bed Vault radiation monitor RM-4138. At 1C05, momentarily press and release: PCIS DIV 1 RESET pushbutton A71B-S32 and PCIS DIV 2 RESET pushbutton A71B-S33 verifying the following annunciators reset: o PCIS GROUP "1" ISOLATION INITIATED (1C05B, A-8) o PCIS GROUP "2" ISOLATION INITIATED (1C05B, B-8) o PCIS GROUP "4" ISOLATION INITIATED (1C05B, D-8) o PCIS GROUP "5" ISOLATION INITIATED (1C05B, E-8) Verify reactor water sample valves are restored to their desired lineup per IPOI 7 Attachment 5, Group 1 Isolations. Notify Shift Chemistry Technician to restore Hydrogen Chemistry System CAVs analyzers to service if required. Reenergize the following RWCU isolation valve(s) as necessary [NA any non-applicable step(s)]: o MO-2700 (at 1B3219) Restart RWCU System as directed per OI 261 (Group 5). Exit Tech Spec as necessary for applicable PCIVs returned to operable status due to re-energizing the valve in the previous step. Actions Continued on the next page Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP: At 1C04, open A [B] PUMP MINI PURGE ISOL CV-1804A[CV-1804B] by taking HS-1804A[HS-1804B] to CLOSE, then to OPEN, allowing it to spring-return to AUTO. Verify the following GROUP 3 Isolations RESET per IPOI 7, unless CRS directs otherwise [NA any non-applicable step(s)]: o Standby Gas Treatment System per OI 170. o Drywell (Containment Atmosphere Control System) per OI 573. o Reactor Building HVAC System per OI 734. Verify PCIS GROUP "3" ISOLATION INITIATED annunciator (1C05B, C-8) reset. At 1C35, place CV-4371A GROUP 3 OVERRIDE switch S583B in NORM Verify the following GROUP 2 Isolations RESET per IPOI 7, unless CRS directs otherwise Examiner Note: When the crew is about to restore Cleanup to service and at the lead examiner's direction, move on to the next event. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: Control Rod Drift with AOP entry Tech Spec entry 3.1.3 At the direction of the lead examiner, If contacted as the second assistant Simulator Operator: Activate [ET 5] This will actuate RD013023, causing Rod 30-23 to drift out of the core. Simulator Operator: report that the HCU lineup is normal and HCU pressure is normal. . CREW: Diagnoses control rod 30-23 is drifting CRS: Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, Mispositioned control rod section. Directs entry into AOP 255.2 Power Reactivity Abnormal Change. Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, requirements are met. Evaluate the entry into TS LCO 3.1.3 C Control Rod Inoperable once the control rod is isolated. Direct the Organization to write a clearance to remove the Amphenoils to electrically disable the HCU after it is Isolated. Contacts RE and/or Duty Manager. RO: Recognizes Rod 30-23 is drifting and informs the SRO. 1C05A (D-6) Rod Drift Actions o At 1C05, select affected Control Rod, monitor 4 rod display to determine if a control rod is drifting, and if so in what direction. o Actions Continue on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to Mechanically Isolate HCU 30-23, wait 4 minutes and Simulator Operator: Acknowledge the request delete malfunction RD013023 and call back and inform the control room the hcu has been isolated with V-18-1008 (30-23), Insert Isolation, and V-18-1275 (30-23) Withdraw Isolation. o IF any control rod is drifting OUT, perform the following: If more than one rod is drifting OUT, manually scram the reactor per IPOI 5 (Reactor Scram). Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position momentarily (less than 1/2 second) to abort the rod sequence timer. If any control rod indicates withdrawal movement, attempt to drive the affected rods in to their required positions per the rod sequence by placing the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. If any control rod inserted per Step 3.2.c begins to drift out again, fully insert the affected rods by: If necessary, place the RWM Operators Display (RWM-OD) keylock mode switch to the BYPASS position. Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. If any control rod still indicates movement, place and hold the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD IN position. Place the C11A S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the OFF position. Run an OFFICIAL 3D CASE for abnormal reactor power/control rod distributions. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: Control Rod Drift (Cont'd) When contacted as the Reactor Enginer, When contacted as the DSM/Operations Direstor Simulator Operator: Acknowledge and inform the control room that you will evaluate the current rod configuration.
Simulator Operator: Acknowledge the request for support. BOP: Monitors balance of plant equipment/plant status. Contacts SANSOE to inspect control rod 30-23 HCU for abnormalities. EXAMINER NOTE: Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: 125 VDC Div 1 panel 1D11 trip results in AOP entries Tech Spec entry (3.8.7.B) At the direction of the Lead Examiner If reactor water level increases to a scram, then When contacted as the second assistant to go to the 1A3 switchgear room to in Simulator Operator: Activate [ET 7] This inserts ed13a causing a loss of 1D11 Simulator Operator: Activate [ET 9] move to next event. NOTE: If the RO does not place the level controller to "A" a scram will occur. Simulator Operator: report after 2 minutes that 1D10 CKT 6 has tripped free and there is no sign of smoke or fire at the breaker. CREW The crew will recognize the loss of 1D11 CRS: Possibly enters AOP 644 Enters AOP 302.1-Loss of 125 VDC Power, Tab 1-Loss of 125vdc Div 1 May direct, as time permits, the RO to transfer to "A" level control to control reactor level and try to maintain normal band. Enters TS LCO 3.8.7.B - 8 Hr LCO (1D11) Directs transferring non-essential power to the startup transformer. RO: Takes manual control of FW and attempts to restore reactor water level to the normal band. OR Place the "A" level controller in service with handswitch Place 3 Element to Single Element Monitor Power Pressure and Level at 1C05 BOP Actions Continued on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed to investigate 1D11, wait 1 minute When contacted to provide organizational support, Simulator Operator: inform the control room that there are no abnormal indications and all breakers are Closed. Simulator Operator: Acknowledge the request for support. Actions continued from the previous page. BOP: Recognize the Loss of 1D11 Monitors BOP Equipment Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows. o Place the BUS 1A2 TRANSFER breaker mode selector switch in the MANUAL position. o Select Phase 1 with the BUS 1A2 STARTUP XFMR AMPERES meter switch and observe the ammeter reading. Select Phase 1 with the BUS 1A2 AUX XFMR AMPERES meter switch. o Place the control switch 4KV BREAKER 1A202 STARTUP XFMR TO BUS 1A2 momentarily in the CLOSE position. Observe that the red (breaker closed) and the white (closing spring charged) indicating lights are ON o Observe that the bus has parallel supplies by observing current on the supply ammeters. o Trip the supply breaker from the auxiliary transformer by placing the control switch 4KV BREAKER 1A101[201] AUX XFMR TO BUS 1A1[1A2] momentarily in the TRIP position. Observe that the white (closing spring charged) and the green (breaker open) indicating lights are ON. Actions Continued on the Next Page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions Continued from Previous Page. Transfers non-essential power to the startup transformer per OI 304.1, section 4.2. as follows. o Select individual phases with the BUS 1A1[1A2] STARTUP XFMR AMPERES meter switch to observe the current load and to verify approximately equal phase currents. o On the BUS 1A1[2] VOLTS meter, verify that all three phases indicate approximately 4160V by selecting each phase selector switch position. Observe that all three white (phase energized) indicating lights are ON. o Place the BUS 1A1[2] TRANSFER breaker mode switch in the AUTO position. o If both 1A1 and 1A2 non-essential buses are now powered from the Startup Transformer, notify ITC Midwest System Control Operator that the Auxiliary Transformer has been unloaded and to adjust the DAEC 161 KV bus low limit in EMS accordingly. - NA o Record the time ITC Midwest was notified the Auxiliary Transformer was unloaded in the Operating Log. Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6: Spurious start of RCIC, requires manually stopping RCIC Tech Spec Entry 3. At the discression the Lead Examiner When sent to investigate the Spurious start of RCIC, wait 3 minutes, Simulator Operator: Activate [ET 11] This will spuriously start RCIC Simulator Operator: Inform the control room that the Level Switch for the RCIC Turbine has actuated. Crew: Acknowledges annunciator 1C04c Announces alarm to the SRO CRS: Will direct the follow actions: Trip RCIC Reenter AOP 255.2 for Power Reactivity Abnormal Enter TS 3.5.3 Conditon A for RCIC Inoperable. May look at TS 3.3.5.3 for RCIC instrumentation. Establish critical parameter monitoring of Reactor Power, Reactor Pressure, and RPV Water Level, as priorities allow. RO: Verify control rod positions are correct for the established sequence, by using Rod Position Log. Verify thermal limits on the Official 3D Case. When power is stabilized, plot location on the Stability Power /
Flow Map. Notify the Reactor Engineer and Operations Manager. BOP: Depress HS-2460, RCIC Manual Turbine Trip pushbutton. Verify MO-2405, RCIC Turbine Stop Valve, closes. Verify MO-2512, RCIC Inject Valve, closes. Verify MO 2510, RCIC Min Flow Bypass Valve, closes. Continue to next event at examiner's direction. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 Condenser Vacuum Leak (recoverable) Emergent Power Reduction HP Tech high rad brief If contacted as Aux Operator to perform a High Rad Entry to investigate. if the crew inserts a manual scram If contacted as the Aux Operator to go in to the condenser bay and investigate Simulator Operator: Activate [ET9] This will insert mc04b, result in degrading backpressure. Simulator Operator: Acknowledge the order Simulator Operator: Acknowledge the order Simulator Operator: Activate [ET 13]
Simulator Operator: Acknowledge the order Crew: Recognizes the rising backpressure CRS: Will direct the follow actions: Enter AOP 691 Perform a fast power reduction to maintain condenser backpressure. Direct IPOI 4 Fast Power Reduction RO: Perform Fast Power Reduction (complete step sequence on the next page. o Lower Recirculation flow to 39 Mlbm/hr. o Insert control rods IAW the fast power reduction sequence sheet. Insert a manual reactor scram if condenser backpressure reaches 6" of Hg absolute. BOP: Establish critical parameter monitoring of condenser backpressure. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fast Power Reduction Steps IAW IPOI 4 RO: o IF core flow is greater than or equal to THEN at 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 39 Mlb/hr while maintaining level between +186" and +211". o Perform the following as required to reduce core flow and to insert rods per the Fast Power Reduction Sequence Sheet(s) Bypass the Rod Worth Minimizer. Station a second licensed operator in place as a peer checker for control rod movement. If necessary to achieve desired conditions, insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to Mlb/hr (equivalent to load line of less than 80%). At 1C04, reduce A and B MG SET SPEED CONTROL to lower core flow to 27 Mlb/hr while maintaining level between +186" and +211". Insert control rods using the Fast Power Reduction Sequence Sheet(s) until power is less than or equal to Mlb/hr (equivalent to load line of less than 52%). Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Back pressure gets worse. At the direction of the Lead Examiner, With the concurrence from the Lead Examiner When all rods are inserted, At the direction of the Lead Examiner, Simulator Operator: Activate [ET 13] This will worsen the condenser air inleakage driving the crew to insert a manual scram. *Simulator Operator:* Modify MC04B to 1.8 with a 30 Sec Ramp to drive the crew to scram if the fast power reduction is effective at maintaining back pressure. Simulator Operator: Activate [ET 15] this will trip both condensate pumps Crew The crew will determine that continued degradation in condenser backpressure will reach a turbine trip setpoint and take the unit offline. Enters and implements the actions of IPOI 5, Reactor Scram. Enters and implements the actions of EOP 1, RPV Control. RO: Scrams the reactor and performs the scram choreography. Reports a hydraulic ATWS and reactor power. Dials master feed water regulating valve controller to 158.5 in AUTO CRS: Directs scramming the reactor and performing IPOI 5, Reactor Scram. Enters EOP 1 due to a scram required with power above 5% or unknown. Verifies automatic isolations, ECCS initiations, and SBDG initiation. Transitions to EOP ATWS. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If directed to locally trip the 'A' Recirc MG Set Drive Motor Breaker When directed to install Defeat 12: Three (3) minutes after being directed to install Defeat 12: Simulator Operator: Acknowledge the request, wait 10 minutes and use [RF rr11] and open the drive motor breaker. Call the control room and inform them that the drive motor breaker is open. Floor Instructor Manually driving control rods, drifting rods, and repeated manual scram will insert all control rods. To perform repeated manual scram the crew will need to direct the 2nd Assistant to install EOP DEFEAT 12 Critical Task # 4 IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Inserting control rods using RIPs. Simulator Operator Acknowledge the request. Activate [ET 12]. This will install Defeat 12 after time delays. Simulator Operator Contact the control room and inform them that Defeat 12 is installed. Crew Implements the mitigation strategies of ATWS. RO: Reports a hydraulic ATWS and reactor power. Dials master feed water regulating valve controller to 158.5 in AUTO Performs the ATWS QRC. Reports completion of the ATWS QRC. Determines that ARI was NOT effective. Reports RPV level and reactor power. Coordinates with the BOP operator the performance of the Hydraulic Rod Insertion Procedures. BOP: Installs Defeat 15. Announces failure to scram and direct the 2nd Asst. to install EOP Defeat 12 for Repeated Manual Scram RIP 103. Installs Defeat 11. Locks out ADS Perform Hydraulic ATWS RIPs (CRITICAL) o RIP 103.2, Drifting Rods o Start a second CRD pump, if available. o Place CRD Flow Controller FC-1814 in MANUAL and run the output to maximum. o Observe increased cooling water flow on FI-1838 and cooling water dp increase on PDI-1832A. o Throttle open MO-1830, DRIVE WATER P CON s necessary to maximize cooling water flow and pressure. o Monitor for inward rod motion. Rods will drift in.
CRS Actions continued on the next page. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Floor Instructor If the crew does not efficiently inject SBLC, enter power level control, restore power to at least one RPS bus, and/or reinitiate torus cooling (after the loss of offsite power) the crew may be required to emergency depressurize due to not being able to maintain torus water temperature and RPV pressure below the Heat Capacity Limit.
CRS: Directs locking out ADS. Verifies at least one set of inboard and outboard MSIVs are open. Directs installation of Defeat 15. Directs performance of the ATWS QRC. Directs the injection of SBLC Recognizes the applicability of Continuous Recheck Statement in Level Leg of EOP ATWS and enters Power Level Control. Directs coordination of the Hydraulic ATWS Rod Insertion Procedures Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If directed to break main condenser vacuum:
Three (3) minutes after the request: Critical Task # 10 IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. Critical Task #11 IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems.
Simulator Operator Activate [ET 28]. Acknowledge the request. Simulator Operator Inform the control room the main condenser vacuum breakers are open. Crew Implements AOP ATWS power level control actions. RO: Verifies HPCI is locked out. Terminates and prevents injection from condensate and feed. (CRITICAL) Reports reactor power when RPV level reaches 87" and lowering. Controls RPV level -25" to +87" using condensate and feedwater. (CRITICAL) As Time Permits, assist in RIPs BOP: Terminates and prevents injection from HPCI, CS, RHR when required. Continues to perform Hydraulic Rod Insertion Procedures CRS: Directs installation of Defeat 4. Directs terminating and preventing injection from HPCI, CS, RHR and Condensate and Feedwater. Directs reporting reactor power at 87" and lowering. Directs an RPV level band of -25" to +87" with condensate and feedwater. This band will be dependent on the level that is reported when power drops below 5% Directs an RPV pressure band of 800-1055 psig. using desired system (EHC). Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When all control rods are inserted: CRS: Recognize that all rods have inserted Evaluate Transitioning to EOP 1 from ATWS Direct the RO to secure Boron Injection Upon the report of SBLC Pumps secured, transition to EOP 1 RO: When directed by the CRS, Secure SBLC Pumps Inform the CRS that SBLC Pumps are secured Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the parameters of the Heat Capacity Limit are exceeded and an Emergency Depress. Is required with ATWS conditions present: Contingency Actions Crew Enters and implements the actions of an Emergency Depressurization with an ATWS condition present. RO: Terminates and prevents injection from Condensate and Feedwater. Slowly re-injects into the RPV to restore and maintain RPV level -25" to +15" using condensate and feedwater. BOP: Terminates and prevents injection from HPCI, Core Spray, RHR. Reports torus water level. Opens 4 ADS SRV's. Reports RPV level at 160 psig. and lowering CRS: Enters Emergency Depressurization. Directs terminating and preventing injection from HPCI, Core Spray, RHR, Condensate and Feedwater. Directs opening 4 ADS SRVs. Directs reporting of RPV level at 160 psig. and lowering Directs slowly re-injecting into the RPV to restore and maintain RPV level -25" to +15" using condensate and feedwater. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the parameters of the Heat Capacity Limit are exceeded and an Emergency Depress. Is required: Contingency Actions Crew Crew will enter and implement the actions of Emergency Depressurization. RO: Restores and maintains RPV 170-211" using condensate and feedwater. BOP: Reports torus water level. Opens 4 ADS SRV's. Restores and maintains RPV 170-211" using condensate and feedwater. CRS: Enters Emergency Depressurization. Directs opening 4 ADS SRVs. Directs restoring and maintaining RPV level 170-211" using condensate and feedwater. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew transitions to EOP 1 from EOP ATWS Crew Implements the mitigation strategies of EOP 1, RPV Control RO: Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS: Performs a crew update of entry into EOP 1 due to Exiting EOP ATWS Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 if not completed prior. Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. May Enter Alternate Level Control Leg of EOP 1 Lock Out ADS Restore and maintain RPV level above +15 in. with one or more Preferred Injection Systems (Table 1A) Wait Until RPV level drops to +15 in. Placekeeps in EOP 1 to the applicable WAIT UNTIL step in RC/P (RC/P-6) leg Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions to start RCIC from a tripped conditions. At the direction of the Lead Examiner, Simulator Operator: Activate [ET 17] this will trip the RCIC Turbine on overspeed. CRS: Recognize Condensate and Feed no longer available. Direct the RO to inject with RCIC to restore Reactor Water Level RO: Verify MO-2511, RCIC Pump Discharge Valve, is open. Open MO 2426, RCIC Lube Oil Cooler Supply Valve. Start 1P 227, RCIC Vacuum Pump. Open MO-2404, RCIC Turbine Steam Supply Valve. For RPV injection, immediately open MO-2512, RCIC Inject Valve. Verify MO-2510, RCIC Min Flow Bypass Valve, closes as RCIC flow raises above 80 gpm. Start 1P-99A and B, ESW Pumps. Start 1V-AC-15A and B, RCIC Room Cooling Units. Recognize the Trip of RCIC, and inform the CRS. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 32 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Direct Crew Response for performance of the T/T leg of EOP 2. Directs operating all available torus cooling using only RHR pumps NOT required for adequate core cooling. Before torus water temperature reaches 110F enter EOP 1 and shutdown the reactor. Maintain torus water temperature below the Heat Capacity Limit (Graph 4). Wait until torus water temperature and RPV pressure cannot be maintained below the Heat Capacity Limit (Graph 4). Direct the reseting of the LO-LO-LO LPCI Logic to allow for restoration of Torus Cooling BOP: Place RHR in Torus Cooling IAW OI 149, QRC 2 Verify RHRSW in service per OI 416/OI 416 QRC 1. Verify 1P-99A and B, ESW Pumps, running. Place HS 2059 [HS 1959], A & C [B & D] RHRSW PUMPS LOCA TRIP OVERRIDE, in MANUAL OVERRD position. Verify MO-2046[1947], RHR HX Service Water Outlet Valve, CLOSED. Start RHRSW Pumps 1P-22 A[B] and/or 1P-22 C[D]. Throttle open MO-2046[1947], RHR HX Service Water Outlet Valve, to obtain 1200 - 2600 gpm per running pump. AS TIME ALLOWS, Perform the follow up actions Verify two or more River Water Supply Pumps running. Place LIC-4231[4232] in MANUAL. Adjust LIC-4231[4232] to achieve the desired River Water makeup flow. (Combined flow of ESW and RHRSW) Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 33 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE BOP Actions continued from previous page. Place RHR in Torus Cooling IAW OI 149, QRC 2 Verify 1P229A[B, C, and/or D], RHR Pumps, running. If a LPCI HI Drywell pressure condition (2 # ) exists, place HS-2001C[1903C] Enable Containment Spray Valves in the MAN position. Open MO-2005[1932], Outboard Torus Cooling/Spray Valve. Throttle MO-2007[1934], Torus Cooling Test Valve, to maintain 4800 gpm per each operating RHR pump. Close MO-2030[1940], A[B] Heat Exch Bypass Valve. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 34 of 40 NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Direct the BOP or ATC to restore Reactor Water Level with HPCI following the loss of Feed and Condensate once all rods are in. RO/ BOP: Start HPCI when Directed IAW OI 152 QRC 1 o If HPCI previously tripped on RPV High Water Level, depress HS-2299, RX HI WATER LEVEL HPCI TURBINE TRIP reset switch. o Open MO-2247, HPCI Lube Oil Cooler Supply Valve. o Start 1P-233, HPCI Vacuum Pump . o Open MO-2202, HPCI Turbine Steam Supply. o Start 1P-218, HPCI Aux Oil Pump . o Verify MO-2311, HPCI Pump Discharge Valve, open. o For RPV injection, immediately open MO-2312, HPCI Inject Valve. o Verify MO-2318, HPCI Min Flow Bypass Valve, closes as HPCI flow raises above 600 gpm. Recognize the HPCI Turbine fails to reach required speed and discharge pressure. Take manual control of the HPCI Turbine IAW ACP 1410.1 and place FIC 2309 in MANUAL and control the HPCI Turbine in MANUAL Report to the CRS that HPCI is injecting to the RPV in MANUAL due to a failed controller. *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 35 of 40 NRC Initial License Exam, Scenario #2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS DISCUSSION ITEMS No discussion points. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 36 of 40 NRC Initial License Exam, Scenario #2 SEG QUANTITATIVE ATTRIBUTES Malfunctions: Before EOP Entry: 1. Loss of "A" RPS 2. Drifting Control Rod 3. Loss of 1D11 4. RCIC Inadvertent Initiation 5. Condenser Air In leakage After EOP Entry: 1. ATWS 2. HPCI Controller Failure Abnormal Events: 1. AOP 255.1, Control Rod Drift 2. AOP 255.2, Power Reactivity Abnormal Change 3. AOP 358, Loss of RPS Power 4. AOP 691, Condenser High Back Pressure Major Transients: 1. ATWS 2. Power/Level Control 3. EOP 1 Alternate Level Control Leg Critical Tasks: 1. Critical Task # 4 IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Manual scram signal Inserting control rods using RIPs. Manual ARI signal Injection of Boron 2. Critical Task # 10 IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. 3. Critical Task #11 IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 37 of 40 NRC Initial License Exam, Scenario #2 SEG 4. IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods: Manual scram signal Inserting control rods using RIPs. Manual ARI signal Injection of Boron Safety Significance: The UFSAR and Safety Limits ensure that specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients and abnormal operational transients. The fuel cladding integrity safety limit is set such that no significant fuel damage is calculated to occur if the limit is not violated. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environs. The MCPR fuel cladding safety limit ensures that during normal operations and abnormal transients the fuel rods will not experience transition boiling and possible cladding damage. The MCPR analysis assumes that the control rods will insert in a specified time. If the control rods do not insert when a scram is required, the plant is beyond the fuel cladding MCPR analysis thus the fuel cladding safety limit is challenged and potential cladding damage may be occurring. Cue: A manual or automatic scram signal has been inserted and failed to lower reactor power below 5%. Performance Standard: The crew successfully initiates a manual scram signal after a automatic scram failed has occurred and/or, The crew initiates a manual ARI causing control rod insertion and/or, The crew successfully performs RIPs (the task of sending an operator to vent the scram air header should not be considered as "control room operator actions" and thus should not be considered as a method for this CT) and/or, The crew successfully performs RIPs as allowed by the scenario to insert control rods capable of being inserted and/or, The crew successfully injects boron into the RPV. If the crew performed the actions for Power/level control and that caused power to lower below 5% before any of the above actions were performed, this CT should be considered as N/A. If this CT was N/A due to Power/level control lowering power and the actions related with this CT were not competently performed, the responsible individual(s) and possible crew may fail or require remediation due to competencies. If the crew was performing the actions of Power/level control and was correctly performing actions for this CT, this CT should be considered satisfactory. If the crew is not performing the correct procedures for the given conditions and this results in the reactor remaining at power, this should be considered an individual failure and possible crew failure. Example: The crew is individually driving control rods during an electrical ATWS and ARI is available and has not been attempted. If ARI automatically initiates and results in power lowering below 5%, this CT should be N/A. Feedback: Control rod positions and/or boron injection. EOP step(s): ATWS Q-1, Q-3, Q-6, Q-8 BWROG: RPV 4.1, RPV 5.1, RPV 6.1 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 38 of 40 NRC Initial License Exam, Scenario #2 SEG 10. IF a reactor scram is required, and Reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. Safety Significance: RPV water level must be lowered during ATWS to either lower reactor power or to prevent challenging the containment. If power is known to be below 5%, it is highly unlikely that the reactor is producing a significant power such that power/level control will effectively reduce power further, thus entering power/level control is not required or safety significant. If power is above 5%, or cannot be determined and RPV level is above 87", power level control is required to reduce reactor power in order to prevent or mitigate the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities. If power is known to be above 5%, or cannot be determined and RPV water level is above +15", and torus water temperature is above 110F, and either an SRV is open or will reopen or DW pressure is above 2 psig, then power level control is required to reduce power in order to preserve containment integrity. Thus terminating and preventing injection will aid in lowering power and can preclude failure of containment or equipment necessary for the safe shutdown of the plant. Cue: ATWS EOP entry required with reactor power above 5% or cannot be determined and either: RPV water level is above +87" or RPV water level is above +15" and torus water temperature is above 110F, and either an SRV is open or will reopen or DW pressure is above 2 psig. Performance Standard: Injection from all of the following is terminated until conditions allow reinjection: Condensate/Feedwater HPCI RHR Core Spray Alternate ATWS injection systems (Table 2B) Reinjection should not occur until RPV water level is below 87" and one of the Reactor power drops below 5% Reactor power drops below 5% All SRVs remain closed AND DW pressure remains below 2 psig. CRD, SBLC, and RCIC injection are allowed. If RCIC was not injecting but other systems were injecting outside the shroud at a flowrate below RCIC flowrate, the critical task is satisfactory although remediation may be necessary. If RPV level is not lowering to the required conditions, and the crew is not controlling RCIC injection, the critical task is satisfactory, although remediation may be required. Feedback: Injection flowrate for the listed systems remain at zero until reinjection is allowed. EOP step(s): ATWS/L two CRS, and L-1, -2. BWROG: RPV 6.3 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 39 of 40 NRC Initial License Exam, Scenario #2 SEG 11. IF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. Safety Significance: Maintaining RPV water level above -25" will ensure that the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500F. The use of table 1B systems is to ensure the flowpath of the injection water is outside the shroud and mixes with the warmer water in the lower plenum prior to it reaching the core. Cue: Power level control has been entered in ATWS, RPV water level is below +87", and one or more of the following conditions have been met for reinjection: Reactor power drops below 5% RPV level reaches +15" All SRVs remain closed and DW pressure remains <2 psig. Performance Standard: Table 1B Injection systems are injecting to maintain RPV level above -25". Restarting of FW injection to maintain RPV level is satisfactory for this critical task. If injection with Table 1B systems are not required to maintain RPV level above -25", this critical task would be N/A. Example: RCIC has been operating and is maintaining RPV level. If the crew injects with Core Spray in an attempt to maintain RPV level above -25", this should be considered a critical task failure unless an ATWS ED has been performed. If an uncontrolled injection (above 2.8 Mlb/hr) causes a power rise above 5%, it should be considered a critical task failure. If an uncontrolled injection does not cause a power rise above 5%, but does cause RPV water level to go above the EOP ATWS maximum recorded RPV level, the critical task is satisfactory although remediation may be necessary. If RPV water level goes above the EOP ATWS maximum recorded RPV level due to CRD, SBLC and/or level swell, this should not require remediation. Feedback: RPV water level is being maintained above -25". EOP step(s): ATWS /L-3 BWROG: RPV 6.4 Filename: 2015 NRC Exam Scenario 2 rev 2 TR-AA-230-1003-F06 Revision 0 Page 40 of 40 SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #: 0 LMS ID: LMS Rev. Date: SEG TITLE: NRC Initial License Exam, Scenario #3 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other: DURATION: ~ 90 minutes Developed by: Jesse Seymour 2/18/15 Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 1 of 31 NRC Initial License Exam - Scenario #3 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given the specific malfunctions presented in the evaluated scenario guide, the students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures: Enabling Objectives: There are no formal learning objectives for this evaluation. Prerequisites: None Training Resources: Simulator Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team
References:
AOP 255.2, Rev 42 AOP 410, Rev 28 ARP 1C04B, Rev 79 ARP 1C04C, Rev 45 ARP 1C05A, Rev 78 ARP 1C05B, Rev 98 ARP 1C06A, Rev 68 ARP 1C07B, Rev 87 ARP 1C23B, Rev 22 ED, Rev 9 EOP 2, Rev 16 EOP1, Rev 18 EOP3 EOP 4, Rev 20 IPOI 3, Rev 144 IPOI 5, Rev 58 OI 149, Rev 146 OI 150, Rev 78 OI 152, Rev 111 OI 264, Rev 134 OI 878.4, Rev 40 STP 3.6.2.1-01, Rev 8 Technical Specifications Protected Content: Identify here and in training material as {C001}; See Comment for details. None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance. Operating Experience: None Risk Significant Operator Actions: Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 2 of 31 NRC Initial License Exam - Scenario #3 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title None None UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 3 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Facility: Duane Arnold Energy Center Op-Test # 2015-301 Examiners: _____________________________ Operators: _____________________________ _____________________________ _____________________________ _____________________________ _____________________________ Initial Conditions: Reactor power approximately 40% Power ascension in progress. Turnover: Continue power ascension in accordance with IPOI 3, POWER OPERATIONS (35% - 100% RATED POWER, Section 4.0. Steps are completed up to step 5. Raise power to approximately 50%. Stabilize power at approximately 50% and perform RCIC pump surveillance test Event # Malf # Eventy Type* Event Description 1 R ATC Raise power with recirculation flow. 2 rr17a C ATC C SRO 'A' Recirc Pump Speed Controller Failure. 2 nm08c I ATC TS SRO APRM 'C' fails (inoperable). Tech Spec review (3.3.1.1, 3.3.2.1) 3 N BOP RCIC Start IAW OI 150 4 rc06 sw14a sw14b C BOP TS SRO A RCIC system isolation signal is received due to steam leak; isolation is faulted. Tech Spec entry (3.5.3) 5 sw19b C BOP C SRO River Water Supply Pump trip. 6 M (ALL) Large break LOCA occurs (Recirc Pump suction break). Faulted LPCI initiation. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 4 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SIMULATOR SET UP INSTRUCTIONS General Instructions 1. Reset to IC13 and lower power to ~40% RTP a. Lower reactor power using recirculation flow and control rods b. Load Events c. Load Malfunctions d. Load Overrides e. Place Torus Cooling in service with 1 RHR Pump and 1 RHRSW Pump operating on each side. 2. OR Reset to the IC provided by the LOIT Exam Development Team 3. Verify B and C APRM's are BYPASSED. 4. Mark up OI 150, Section 5.2 to step 7, and verify all steps to that point have been completed. 5. Mark up IPOI 3 up to and including step 7. NA step 8. 6. Obtain keys from key locker for Placing Torus Cooling in service. 7. Verify Events validate FALSE 8. Reset APRM Gains and clear recorders 9. Complete the Exam Setup Checklist 10. Ensure no BIAS is inserted on the FRV Controllers by verifying Y at 0.0 11. Verify EOOS up-to-date. 12. Verify the SUFRV Lined up to the operating Feed Pump. 13. Have a copy of Daily Jets STP available to provide when requested. Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7, 9 Manual Trigger Manual Trigger 20 YCAB002 >= 48 Power > 48% 21 1A1/1A2 Transfer 1A1/1A2 Transfer 22 HPCI Starts ZDIRPC71AS1(1) ==1 & ZLOHPHS2202(2) == 1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 5 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp (sec) ET Initial Value Final Value Setup rh10c RHR C PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10d RHR D PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10a RHR A PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup rh10b RHR B PUMP FAIL TO AUTO-ACTUATE Inactive Active Setup stdg01 TRIP OVERRIDE - 'A' SBDG 1G31 FAILS TO AUTO START Inactive Active Setup stdg02 TRIP OVERRIDE - 'B' SBDG 1G21 FAILS TO AUTO START Inactive Active Setup cs05a CORE SPRAY PUMP A - FAILURE TO AUTO-INITIATE Inactive Active Setup cs05b CORE SPRAY PUMP B - FAILURE TO AUTO-INITIATE Inactive Active Setup strh02 LPCI B INJECT VALVE FAILS TO AUTO OPEN - MO-1905 Inactive Active Setup ms31b GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- MO2401 Inactive Active Setup ms31a GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- MO2400 Inactive Active Setup strh01 LPCI A INJECT VALVE FAILS TO AUTO OPEN - MO-2003 Inactive Active Setup sthp01 HPCI SYSTEM AUTO INITIATION BLOCK Inactive Active Setup nm08c APRM CHANNEL FAILS- CHNL C 1 As Is 100 Setup rc06 RCIC STEAM SUPPLY LINE BREAK (RCIC ROOM) 6 min 3 0 30 Setup sw19b RIVER WATER SUPPLY PUMP TRIP- PUMP B, 1P117B 5 Inactive Active Setup rr15a RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP A 6 min 7 0 2 Setup rr17a RECIRC M-G FLOW CTRLR FAILS, AUTO/MAN MODES- M-G A 1 min 20 As Is 80 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 6 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp (sec) ET Initial Value Final Value Setup sw14a RCIC ROOM COOLER ESW FLOW BLOCKAGE- 1V-AC-15A 3 min 3 As Is 85 Setup sw14b RCIC ROOM COOLER ESW FLOW BLOCKAGE- 1V-AC-15B 3 min 3 As Is 85 Setup strc01 TRIP OVRD- RCIC FAILS TO AUTO START Write a sch file to block the initiation and valve light power 3 Inactive Active Setup fw02a CONDENSATE PUMP TRIP- PUMP A 21 Inactive Active Setup fw02b CONDENSATE PUMP TRIP- PUMP B 21 Inactive Active Setup hp02 HPCI TURBINE TRIP 22 Inactive Active Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 7 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 OVERRIDES Time Over. No. Override Title Delay Ramp ET Initial Value Final Value REMOTE FUNCTIONS Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Setup fp08 May need to look up RCIC DELUGE MAN ISOLATION VALVE V-33-84 (OPEN,CLOSE) Open Closed Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist. If surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 8 of 31 Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 SHIFT TURNOVER INFORMATION Day of week and shift o Today o Day Shift Weather conditions o Warm Spring Day (Plant power levels) o Reactor Power Level 42% o Core Flow 30 Mlbm/hr Protected train o Protected Train is "B" Technical Specification Action statements in effect o TS LCO 3.5.1 Condition B- Day 1 of 7 One low pressure ECCS subsystem inoperable for reasons other than Condition A. Restore low pressure ECCS subsystem to operable status within 7 days. Locked in / failed annunciators and alarms o None Evolutions in progress or planned for upcoming shift o Raise Power with Recirc to approximately 50% RTP. o Perform RCIC post maintenance confidence run for maintenance performed a week ago IAW OI 150, Section 5.2. in CST to CST mode of operation. o RCIC Inop STP, 3.5.3-01 was completed just prior to turnover. Plant PRA/PSA Status including CDF/LERF & color o CDF Baseline with one year to YELLOW o LERF Baseline with one year to YELLOW Existing LCOs, date of next surveillance o None. Procedures or major maintenance in progress o None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, problems, operator workarounds, etc. o One Extra NLO is in work control waiting for the RCIC Test Run and has been briefed. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 9 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Raise power with Recirc flow. If Contacted as the Reactor Engineer to provide guidance, Simulator Operator: Inform the crew to raise power with Recirc Flow to achieve approximately 50% power and hold power constant until a rod sequence is approved for further power ascension. CREW: CRS: Directs power to be raised from 40 to 50% using recirculation pump flow. RO: Performs Recirculation Pump flow adjustments to raise power from 40 to 50%. Monitors plant parameters for expected response during reactivity manipulation. BOP: Adjusts generator excitation manual regulator adjust to maintain the generator nulled. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 10 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: When power reaches ~48%
When contacted as the 2nd Asst. to go to the MG Set Room to investigate the Recirc Pump Speed Changer, Wait 2 minutes and When Contacted as the DSM/OD When Contacted as the RE When contacted as procedures to deliver a copy of STP 3.4.1- Simulator Operator: Verify [ET 20] activates. This will cause "A" Recirc MG Set speed to rise. Simulator Operator: Report that the power switch is on and the thermal overload button on the motor is reset. Simulator Operator: Agree to support trouble shooting efforts. Simulator Operator: Acknowledge the situation and inform the CRS that you will develop a plan for recovery. Simulator Operator: Acknowledge the request and deliver the STP after 5 minutes. CREW: CRS: Will enter AOP 255.2 on the Power/Reactivity Abnormal. Contact the Duty Station Manager/Operations Director and/or the Reactor Engineer. May Enter TS 3.4.1 Condition C for the Mismatch in Recirc Pump Speeds. o Recirc Pump Speed Mismatch graph on the following page. If the "B" Scoop Tube was locked, the CRS may direct the crew to reset the "B" Scoop Tube in accordance with OI 264 RO: ARP 1C04A (C-5) Actions taken for the scoop lock. Will Lock the 'A' Recirc MG Set Scoop Tube from 1C04. The crew may lock the "B" Scoop tube if they do not diagnose the event properly Take actions IAW AOP 255.2 If directed, reset the "B" Scoop Tube in accordance with OI 264 BOP: Direct inplant operators to investigate the scoop tube malfunction Take actions for AOP 255.2 Run 3D Case Plot Power to Flow Resetting the scope tube lock on the next page. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 11 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 12 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Resetting the scoop tube lock on "B" Recirc Pump BOP: If directed, reset the "B" Scoop Tube in accordance with OI 264 o If A[B] Recirc MG Set is running, reset the Scoop Tube Lockout as follows o Verify Scoop Tube Position P-% o Adjust setpoint S-% to approximately match Scoop Tube Position P-%. o Verify controller output V-% approximately matches Scoop Tube Position P-%. o At 1C04, reset scoop tube lock by momentarily placing handswitch B31A-S3A[B] to RESET and then verify the following: o Annunciator 1C04A, C-5[1C04B, C-2], "A[B] RECIRC MG SCOOP TUBE LOCK" resets. o Amber SCOOP TUBE LOCKED Light located at 1C04 (above A[B] Scoop Tube Control handswitch B31A-S3A[B]) is OFF. o Verify that the Recirc pump speed is stable by observing the following parameters o SETPOINT (S), Percent Position (P), Percent Speed (X), Recirc pump discharge flow, Total core flow, Core pressure drop, APRM readings o Verify that SETPOINT (S) is selected for digital display. EXAMINER NOTE: After power has been raised to approximately 50%, commence Event 2. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 13 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3:
If Contacted as a maintenance or support organization, Following the reset of the half-scram, crew should proceed to the RCIC surveillance test. If crew does not proceed, Simulator Operator: ACTIVATE [ET 1] This will cause "C" APRM to fail upscale.
Simulator Operator: Acknowledge the issue, and/or to provide maintenance support for troubleshooting/repair.
Simulator Operator: Call the CRS as the Operations Director and direct the crew to proceed with the RCIC Trouble Shooting Run to test the Flow Controller. Crew: Identifies the following: a half-scram has occurred. a rod out-block has occurred. BOP: OI 878.4 actions to Unbypass A APRM and take C APRM Out of operate. OI 878.4 actions to Bypass C APRM o If an APRM is currently bypassed, perform the following for the bypassed APRM, otherwise N/A this step: o Verify the APRM upscale, inoperative, and if greater than 5%
reactor power, downscale trips on Panel 1C37 are reset. o Verify the IRM/APRM recorders on Panel 1C05 indicate approximately the same average power for the bypassed APRM as they do for the other APRM channels in operation. o Place the APRM BYPASS switch C51B-S3 or C51B-S6 on Panel 1C05 in the neutral (unbypassed) position. o Observe that the bypass light on Panel 1C05 and/or that the bypass light on Panel 1C37 is/are OFF. o Verify the two APRM channels in the RPS trip system which are to remain UNBYPASSED are OPERABLE, otherwise comply with Technical Specifications and TRM for inoperable RPS instrumentation. o Place the APRM BYPASS switch C51B-S3 (C51B-S6) on Panel 1C05 in the A, C, or E (B, D, or F) position for the channel to be bypassed. o Observe that the bypass lights for the bypassed channel on Panel 1C37 and/or Panel 1C05 is/are ON. Unbypass the D APRM Bypass the B APRM Actions are repeated for B and D APRMs RO and CRS Actions are on the following pages Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 14 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RO: Responds to failure of APRM 'C' Acknowledges 1C05A (B-2), APRM A, C, OR E UPSCALE TRIP OR INOP. o Check the SCRAM GROUP A and B lights on 1C05 to determine if a full Reactor scram has occurred. o If a full Reactor scram occurs, perform IPOI 5 (Reactor Scram). o Monitor APRM indications on Panels 1C05 and/or 1C37. o If only A RPS half scram has occurred: If any B RPS channel APRM is rapidly approaching or has exceeded its trip setpoint, manually scram the Reactor and perform IPOI 5 (Reactor Scram). o Suspend testing in progress on other RPS instrumentation. o If the trip is due to a loss of power, perform AOP 358 (Loss of RPS AC Power) and comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation. o If it is determined that an APRM has failed: Comply with Technical Specification requirements for Reactor Protection System (RPS) Instrumentation and the Technical Requirements Manual requirements for Control Rod Block Instrumentation. With permission from the CRS, bypass the affected APRM o Reset the half scram. Acknowledges 1C05B (A-6), ROD OUT BLOCK. References ARP. Identifies that APRM 'C' has failed. When directed by the CRS, bypasses the 'C' APRM. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 15 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRS: Directs crew response for failed APRM 'C' Reviews TS 3.3.1.1, Condition A for applicability Instrumentation. Reviews TS 3.3.2.1 for applicability. Reviews TRM LCO 3.3.2, Condition A for applicability. Directs 'C' APRM to be bypassed. Directs the half-scram to be reset. Briefs the crew on the effects of the Scoop Tube and APRM Failure. Direct the B APRM to be bypassed if not completed. EXAMINER NOTE: After the half-scram is reset and B APRM is BYPASSED, crew should proceed to RCIC Confidence Run (Event 3). Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 16 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 RCIC Confidence Run At the Direction of the Lead Examiner, When Contacted as the Extra Operator for the RCIC Run, Simulator Operator: Call the control room as Ray Wheaten and direct the crew to proceed with the RCIC Run, and that this is the crews priority.
Simulator Operator: Wait 4 minutes and inform the control Room that Oil level has been verified satisfactory And standing by outside the RCIC Room. Air Flow Verified through the coolers. CRS: Directs crew to conduct the RCIC Run IAW OI 150, Section 5.2 in CST to CST Mode. Verify RCIC LCO has been entered, LCO 3.5.3, Condition A - RCIC System inoperable. Per the turnover, the RCIC Inop STP was previously completed, and restore to OPERABLE in 14 days. RO: Monitors plant parameters during RCIC Run. BOP: Starts RCIC in CST to CST mode in accordance with OI 150. Start 1V AC 15A and B RCIC ROOM CLG UNITS at 1C23 Open the REDUNDANT SHUTOFF valve MO 2316 on 1C03. Open the TEST BYPASS valve MO 2515 to 44-46% open as indicated on RCIC TEST BYP MO 2515 POSITION ZI 2515. Verify MO 2511 PUMP DISCHARGE valve is open. Start 1P 227 VACUUM PUMP by placing handswitch HS 2415 on 1C04 in the START position. Open MO 2426 LUBE OIL COOLER SUPPLY by placing HS 2426 in the OPEN position momentarily and observing proper valve position indication. If time permits, ensure unnecessary/unauthorized personnel are clear of the RCIC Room. Initiate Torus water temperature monitoring per STP 3.6.2.1-01. This is only required while heat is being added to the Torus. BOP Actions Continued Next Page Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 17 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When Contacted as Health Physics, When contacted as an operator to verify RCIC Running Sat, When Contacted as a member of the maintenance staff for trouble shooting Simulator Operator: Acknowledge the running of RCIC and the potential to change rad levels in the plant. Simulator Operator: Report that the pump is operating sat. Simulator Operator: Report that you will begin trouble shooting and to stand by for direction from the team. Open MO 2404 TURBINE STEAM SUPPLY by placing the handswitch in the OPEN position momentarily and observing proper valve position indication and that RCIC turbine speed, pump discharge pressure, and RCIC flow indicators indicate increases. Verify CV 2410, CV 2411, and CV 2436 Close Verify that MO 2510 MIN FLOW BYPASS opens when RCIC Flow is less than 80 gpm with pump discharge pressure greater than 125 psig. Verify HV 2406 TURBINE CONTROL VALVE Governor Valve is throttling to control turbine speed. In the CST to CST mode, throttle MO 2515 TEST BYPASS to achieve the desired discharge pressure. Verify that MO 2510 MIN FLOW BYPASS valve closes as RCIC flow rises above 80 gpm. Adjust FIC 2509 FLOW CONTROL until desired flow is achieved; do not throttle RCIC turbine speed below the minimum of 2000 rpm. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 18 of 31 NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: When RCIC flow to the CST has been established, and with direction from the lead examiner:
As the extra operator at the RCIC Room Door, once the High Amb Temp alarm sounds, Simulator Operator: ACTIVATE [ET 3] This will cause a small leak in the RCIC Room. Temperatures in the room will not exceed MAX SAFE limits. Simulator Operator: Inform the crew that a steam leak occurred in the RCIC Room, the RCIC room was evacuated, all personnel are accounted for, and that there are no injured personnel. CREW: identify that a RCIC isolation signal is present due to a steak leak in the RCIC room (e.g. high area temperature). RO: Monitor 1C05 indications for Power/Pressure/Level. If Required, attempt to Isolate the RCIC Steam Lines while the BOP is in the back panels area. Identifies that a valid RCIC isolation signal should be present due to a steam leak in the RCIC Room. Identifies that an automatic RCIC isolation has failed to occur. Manually initiates RCIC isolation by performing the following in accordance with OI-150, Section 7.1 or the applicable ARPs: o Closes MO-2400 RCIC INBD STEAM LINE ISOL, and MO-2401 RCIC OUTBD STEAM LINE ISOL. BOP: performs the following: May recognize the 1C23 Trouble Annunciator on 1C07, and investigate the Back Panel Area for the cause of the alarm. Upon investigation, the crew may take actions to Isolate RCIC. Acknowledges 1C04B (B-04) STEAM LEAK DET AMBIENT HI TEMP, 1C04C (A-07) References ARP(s). Goes to the back panel area to report temperatures. Established Ventilation in a 3-2-3 line up. RO/BOP/CRS Make Plant Announcement to alert personnel to the steam leak from RCIC CRS Actions continued on the next page. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 19 of 31 NRC Initial License Exam, Scenario #3 SEG Examiner Note: Once the RCIC test flow to the CST has been established, commence Event #4. When the crew has isolated the RCIC Steam Leak, If directed to deenergize MO-2401, If directed to deenergize MO-2400, SIMUATOR OPERATOR Delete ESW COOLER Blockage [sw14a and sw14b] Simulator Operator Insert OVER RIDES DO-RC-013 to off DO-RC-014 to off DI-RC-008 to auto And inform the crew that 1D14 Ckt 1, MO-2401 Power Supply is open. Simulator Operator Insert OVER RIDES DO-RC-010 to off DO-RC-011 to off DI-RC-006 to auto And inform the crew that MO-2400 Power Supply is open. CRS Actions continued from the previous page. CRS: performs the following: May enters EOP-3, Secondary Containment Control o Implements actions of EOP-3 SC/T leg for RCIC room temperature being greater than the Max Normal Operating Limit, but less than the Max Safe Operating Limit. o Directs manual isolation of the RCIC system if not already done. References Technical Specifications to address RCIC system inoperability: o TS 3.5.3, Condition A May declare TS 3.6.1.3, Condition B for two valves that failed to shut on the Isolation Signal in a single flow path. EXAMINER NOTE: Once RCIC manual isolation has occurred and SRO has completed TS call, commence event #5. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 20 of 31 NRC Initial License Exam, Scenario #3 SEG Event 6: River Water Supply Pump spurious trip When contacted as the AUX Operator to investigate the loss of the B RWS Pump, Wait 4 Minutes DSM Call Simulator Operator: when directed by lead examiner ACTIVATE [ET 5] to cause the 'B' RWS Pump to trip.
Simulator Operator: and inform the control room that the B RWS Pump is hot to touch and that there is no smoke and no fire. Simulator Operator: Acknowledge the request for support. CREW: identifies a trip of the 'B' River Water Supply Pump. RO: Monitors plant parameters. BOP: Performs the following: Attempt to start standby pumps in both RWS Subsystems as necessary to restore needed makeup flow. Send an operator to the Intake Structure to verify alarms and check RWS pump breaker condition. Verify the Auto Start is not selected to the inop pump. CRS: directs crew response as follows: May Enter AOP-410, LOSS OF RIVER WATER SUPPLY o Update the Online Risk Monitor for the status of River Water Supply Pumps. May Direct actions IAW the ARP 1C06A (A-3) B RWS Pump Trip for the tripped RWS Pump LCO 3.7.2 met, Technical Specification Inoperable Log entry. EXAMINER NOTE: Commence event # 7 at the direction of the Lead Examiner. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 21 of 31 NRC Initial License Exam, Scenario #3 SEG Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). If Contacted as an operator in the plant, Simulator Operator: perform the following at the direction of the Lead Examiner: Activate [ET 7] and verify rr15a activates on ramp
Simulator Operator: Agree to support required actions CREW: Will recognize the automatic reactor scram, lowering RPV level, lowering RPV pressure, and rising drywell pressure and Enter EOP 1 and 2 RO: performs the following: Performs IPOI 5 QRC 1, Reactor Scram Immediate Operator Actions: o Initiates a backup manual reactor scram. o Places THE MODE SWITCH in SHUTDOWN. o Verifies all control rods fully inserted. o Verifies main turbine trip o Verifies main generator lockout. o Verifies neutron flux is lowering. o Inserts all functional SRM and IRM detectors. Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). Simulator Operator: When Contacted to provide support Acknowledge the request CREW: Upon receipt of a 2# Drywell Pressure signal, The crew will recognize the failure of all ECCS Systems to automatically start and o Start A and B SBDG's o Start A, B, C, D RHR Pumps o Start A and B Core Spray Pumps o Start HPCI Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 22 of 31 NRC Initial License Exam, Scenario #3 SEG When directed by the Lead Examiner, Simulator Operator: Activate [ET 9] This will trip HPCI and prevent it from restarting. CREW: Implements the mitigation strategies of EOP 1, RPV Control RO: Inserts a manual reactor scram. Completes a scram report that includes all rods in, reactor pressure and trend and reactor water level and trend. Restores and maintains RC/L 170-211" using RCIC and other alternate injection systems. Maintains RC/P 800-1055 psig. using directed pressure control systems. Lowers reactor pressure to the directed control band using the directed control system. CRS: Performs a crew update of entry into EOP 1 due to RPV level or Drywell Pressure. Directs an RPV level band of 170-211" using RCIC and other alternate injection systems. Directs installation of Defeat 11 Directs an RPV pressure band of 800-1055 psig using directed pressure control systems. Directs lowering reactor pressure to lessen the driving head on the leak in the drywell. Shows concern for maintaining plant cooldown within the limits. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 23 of 31 NRC Initial License Exam, Scenario #3 SEG CRITICAL TASK #33 Maintain RPV level above TAF with operator actions CRITICAL TASK #22 DW spray on high DW temperature CREW: Implements the mitigation strategies of EOP 2, Primary Containment Control Recognizes the failed ECCS initiation (LPCI) and directs action to establish LPCI injection (CRITICAL TASK #33). BOP: Informs the CRS of containment parameters including parameter name, value and trend. Installs Defeat 4. Utilizes OI 149 QRC to spray the torus. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening Throttle open MO-2006[MO-1933], Torus Spray Valve Utilizes OI 149 QRC to spray the drywell.(CRITICAL Task #22) Ensures Recirc Pumps are tripped Repositions HS-1903C - Enable Containment Spray Valves to Manual Depending on RPV level may take HS-1903B to 2/3 Core Coverage/LPCI INIT Interlock Override to MANUAL OVERRD Open MO-2000[1902] , Inboard Drywell Spray Valve Throttle open MO-2001[1903], Outboard Drywell Spray Valve. Trips the running recirculation pump. CRS: Performs a crew update of entry into EOP 2 due to Drywell Pressure. Obtains containment parameters. Directs installation of Defeat 4. Directs spraying the torus after confirmation that torus pressure is greater than 2 psig. Directs spraying the drywell before drywell temperature reaches 280F. Verifies torus water level less than 13.5 ft. Verifies plot of drywell temperature and drywell pressure on the DWSIL curve allows drywell sprays. Verifies recirculation pumps are secured. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 24 of 31 NRC Initial License Exam, Scenario #3 SEG CREW: Implements that mitigation strategies of the ALC contingency of EOP 1 BOP: Lockouts ADS. RO: Attempts to restore and maintain RPV level above +15" Maximizes injection with CRD in accordance with AIP 407. Injects with SBLC in accordance with AIP 406. Verifies injection subsystems can be lined up for injection Verifies at least one injection subsystem lined up with a pump running. CRS: Directs ADS lockout. Directs RPV level bands as RPV level lowers Directs maximizing injection with CRD in accordance with AIP 407. Directs injection with SBLC in accordance with AIP 406. Ensures injections subsystems can be lined up for injection. Waits for RPV level to drop to +15" Ensures at least one injection subsystem lined up with a pump running. Before RPV level reaches -25" performs an Emergency Depressurization. Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 25 of 31 NRC Initial License Exam, Scenario #3 SEG Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches (-25"). CREW: ED when Reactor Water Level is < +15" and before Reactor Water Level reaches -25"(CRITICAL) CRS: Diagnoses HPCI failure to run Directs Emergency Depressurization. Directs Opening 4 SRVs When Directed opens 4 ADS SRVs to emergency BOP: Informs SRO when 4 SRVs are open Monitors and controls RPV level as he depressurization occurs Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 26 of 31 NRC Initial License Exam, Scenario #3 SEG Event 7: Large Break LOCA (Recirc Suction break) with faulted LPCI auto initiation (manual alignment required). Simulator Operator: ROLE PLAY: if contacted as Equipment Operator, perform required component manipulations and make appropriate reports to the Control Room. BOP: performs plant EOP operations as directed by the SRO. Aligns systems (RHRSW, RHR, etc.) and reports trends as required. Identifies failure of automatic LPCI alignment and injection and manually aligns LPCI injection by starting RHR pumps and opening valves as necessary (CRITICAL TASK).
EXAMINER NOTE: when sufficient crew execution of the EOPs has been observed, then the scenario may be terminated. *** END OF SCENARIO *** Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 27 of 31 NRC Initial License Exam, Scenario #3 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.) Malfunctions: Before EOP Entry: 1. Runaway Recirc Pump 2. "A" APRM Fails Upscale 3. RCIC Steam Leak with Failure to Automatically Isolate 4. RWS Pump Trips After EOP Entry: 1. LPCI Pumps Fail to Auto Start 2. Condensate Pump Trip 3. Failure of SBDG to Start 4. Trip of HPCI Abnormal Events: 1. Power Reactivity Abnormal Change 2. High Ambient Temperature 3. Loss of RWS, AOP or ARP Actions 4. Major Transients: 1. LOCA 2. Emergency Depressurization Critical Tasks: 1. Critical Task #1 IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". 2. Critical Task #22 DW spray on high DW temperature 3. Critical Task #33 Maintain RPV level above TAF with operator actions Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 28 of 31 NRC Initial License Exam, Scenario #3 SEG 1. IF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25". Safety Significance: If the lowering RPV water level trend had not been reversed before RPV level drops to +15", emergency RPV depressurization should be performed prior to RPV level reaching -25". The consequence of not depressurizing the RPV when level is below -25" is a loss of adequate core cooling. Depressurizing prematurely may unnecessarily cause unneeded stress on the RPV and piping. Cue: RPV level lowered to +15". Performance Standard: The crew must "Initiate" emergency RPV depressurization after the lowest valid level indication shows <+15" and prior to the lowest valid level indicates -25". The critical task is not satisfactory if the actions for "Emergency RPV Depressurization" are not complete. (See definitions) Feedback: RPV pressure is rapidly lowering. EOP step(s): RC/L-4, L-7, L-8 BWROG: RPV 1.1 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 29 of 31 NRC Initial License Exam, Scenario #3 SEG 22. BEFORE drywell temperature reaches 280F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. Safety Significance: If DW sprays were initiated when in the shaded area of the DWSIL, this could lead to an evaporative cooling pressure drop which could result in: Deinerting the containment or containment negative pressures below design. OR Drywell-below-torus differential pressure beyond design. Operation of DW sprays if DW temperature cannot be maintained below 280F, will ensure that the design temperatures of the components within the DW are not exceeded. If DW sprays are not utilized when available, the next EOP actions will be to Emergency RPV Depressurize, which will lower the amount of ambient heat to the DW, but will cause additional pressure/temperature stress on the RPV. Cue: DW temperature is rising and is below 280F. Average DW temperature and DW pressure conditions allow DW spray per the DWSIL curve Performance Standard: DW sprays are initiated on at least one side of RHR prior to 280F DW temperature. If DW sprays are initiated while in the shaded area of the Drywell Spray Initiation Limit (DWSIL), this would be a critical task failure. If the crew does not secure Recirculation pumps prior to initiating DW sprays, the critical task is considered satisfactory although remediation may be required. Feedback: DW spray flow initiated and DW temperature is lowering. EOP step(s): DW/T-4, -5 BWROG: N/A Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 30 of 31 NRC Initial License Exam, Scenario #3 SEG 33. The Reactor is shutdown and RPV water level can be maintained above +15 inches with preferred and alternate injection systems, THEN inject to restore and maintain RPV level above +15 inches. Safety Significance: The preferred method of core cooling is core submergence. If this method is available, the crew is directed to inject with preferred and alternate systems to maintain the preferred method of core cooling. Although other methods will provide core cooling, such as Emergency Depressurization, the core temperatures will be higher. Cue: RPV level is lowering and preferred and/or alternate methods of injection are available to maintain RPV level above +15 inches, but will not maintain +15 inches without operator action. If automatic actions will maintain RPV level above +15 inches, this task should be N/A. Adequate time needs to be given to allow the crew to restart injection. The crew has indications that the system(s) is(are) available for injection. Performance Standard: The crew should start or align systems or power supplies to maintain RPV level above +15 inches. This could be taking manual control of a failed automatic controller, restoring power to a bus that has an available injection system, opening a valve that failed to auto open, or resetting a "trip" signal for an injection system. If starting of injection with operator actions will not maintain RPV level above +15 inches, this critical task should be N/A. If this is the situation, and the crew does not attempt any of these systems, resulting in RPV level reaching +15 inches sooner than if the injection systems were started, remediation may be necessary, although the CT is N/A. Feedback: Injection systems are maintaining RPV level above +15 inches. EOP step(s): RC/L-3 Filename: 2015 NRC Exam Scenario 3 rev 2 TR-AA-230-1003-F06 Revision 0 Page 31 of 31 JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 1
TITLE: VENT THE SCRAM AIR HEADER TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: VENT THE SCRAM AIR HEADER JPM NUMBER: 201001 REV. 0 TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS: 201001 K1.09 K/A VALUE: 3.1/3.2 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: Lab: Time for Completion: 10 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material) {C001} TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SETUP INSTRUCTIONS: NONE SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE
Required Materials: 1. RIP 101.3, Rev 1 2. Crescent Wrench General
References:
- 1. RIP 101.3, Rev. 1 Task Standards: 1. The operator simulates closing V-17-61. 2. The operator simulates removing pipe plug d/s of V-17-174. 3. Simulates opening V-17-174. 4. The operator simulates closing V-17-174. 5. Operator simulates installing pipe plug d/s of V-17-174. 6. Operator simulates opening V-17-61. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 6 of 13 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. INITIAL CONDITIONS: The plant is operating at 70% power. An ATWS has occurred. The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS. The RO has directed you to vent the scram air header. INITIATING CUES (IF APPLICABLE): Vent the scram air header in accordance with RIP 101.3 and inform the control room. This JPM is not Time Critical. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step:1 Critical Y RIP 101.3 Step 1 Close V-17-61 (Scram Pilot Air Header Isolation Vlv). Standard: The operator simulates closing V-17-61. Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator "The valve stem is in and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 8 of 13 Performance Step: 2 Critical Y RIP 101.3 Step 2 Remove the pipe plug located downstream of V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: The operator simulates removing pipe plug d/s of V-17-174. Evaluator Cue: When the operator has simulated turning the cap in the clockwise direction, tell the operator, "The pipe plug has been removed." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical Y RIP 101.3 Step 3 Open V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: Simulates opening V-17-174. Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, "The valve stem is up and handwheel stops moving. You hear a loud rush of air coming from the open pipe. The air flow diminishes over time." Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 9 of 13 Performance Step: 4 Critical N RIP 101.3 Per Cue Communicates actions to control room. Standard: The operator simulates calling the control room and informs RO that scram air header is depressurized. Evaluator Cue: When the operator simulates informing the control room that the Scram Air Header has been vented IAW RIP 101.3, tell the operator "That all control rods indicated inserted. Restore the Scram Air Header." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical N Q & A Question and Answer: What do you expect the position of the scram pilot valves to be before and after venting? Standard: The operator should respond that the scram pilot valves will be closed before venting and open after venting. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 10 of 13 Performance Step: 6 Critical Y RIP 101.3, Restoration, Step 1 Restoration: Close V-17-174, (PI-184/PS1842 Test Connection Isolation valve). Standard: The operator simulates closing V-17-174. Evaluator Cue: When the operator has simulated turning the handwheel in the clockwise direction, tell the operator "The valve stem is in and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical Y RIP 101.3, Restoration, Step 2 Restoration: Reinstall the pipe plug downstream of V-17-174. Standard: Operator simulates installing pipe plug d/s of V-17-174. Evaluator Cue: When the operator simulates putting the pipe plug back on, tell the operator "The pipe plug is installed" Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 11 of 13 Performance Step: 8 Critical Y RIP 101.3, Restoration, Step 1 Restoration: Open V-17-61, Scram Pilot air header isolation valve. Standard: Operator simulates opening V-17-61. Evaluator Cue: When the operator has simulated turning the handwheel in the counter clockwise direction, tell the operator, "The valve stem is up and handwheel stops moving." Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the scram air header has been vented and restored, the JPM is complete. Direct the Operator to show the location of 1C208 to complete the RCIC Start JPM. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 1 VENT THE SCRAM AIR HEADER JPM Page 12 of 13 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS: The plant is operating at 70% power. An ATWS has occurred. The Shift Manager has directed the RO to perform IPOI 5 QRC 2, ATWS. The RO has directed you to vent the scram air header. INITIATING CUES (IF APPLICABLE): Vent the scram air header in accordance with RIP 101.3 and inform the control room. This JPM is not Time Critical. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 2
TITLE: OPERATE RCIC FROM 1C208 TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 13 JPM TITLE: OPERATE RCIC FROM 1C208 JPM NUMBER: 295016-01 REV. 0 TASK NUMBER(S) / TASK TITLE(S): 94.28/ Transfer Control to the Remote Shutdown Panel K/A NUMBERS: 295016 AK2.02 K/A VALUE: 4.0/4.1 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: X To be performed in the Training Building prior to the In Plant portion of the JPM, In Plant portion is required after the Task. Lab: Time for Completion: 40 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material) {C001} TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SETUP INSTRUCTIONS: 1. Reset to any IC that RCIC can be run in 2. Activate the Remote Shutdown Panel with REMOTE Function EXAM01 to NORM 3. Verify the simulator group has restored the RCIC Controller at 1C208 to service. 4. Start RCIC in CST to CST Mode at 415 gpm. 5. Set up radios on the same channel 6. Simulator Operator functions as the remote shutdown panel operator for the JPM. 7. Large Picture of the Instrument Rack located near 1C208 for level indications if used instead of verbal Cues. SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE
Required Materials: 1. AOP 915, Rev. 53 General
References:
- 1. AOP 915, Rev. 53 Task Standards: 1. The Operator Unlocks the door. 2. The operator will place HS-2440 in REMOTE. 3. Reduce the rate of injection. 4. The operator will take the evaluator to the 1C208 Panel in the Plant or explain in enough detail as to demonstrate knowledge of the location in the plant. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 6 of 13 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. INITIAL CONDITIONS: A Plant Transient has occurred requiring a shutdown from outside the control room. The control room is being evacuated. RCIC is injecting to the vessel. INITIATING CUES (IF APPLICABLE): The CRS has directed you to take control of RCIC from 1C208, and restore reactor water level IAW AOP 915. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step:1 Critical N AOP 915, Section 2, Step 2 NOTE NOTE RCIC can be controlled from 1C208 but no flow or speed indication is available. Standard: Operator reads and place keeps the NOTE. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical Y AOP 915, Section 2, Step 2 a 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: a. Open key locked door protecting normal/remote handswitch HS-2440 RCIC TURB SPEED SELECT. Standard: The Operator Unlocks the door. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 8 of 13 Performance Step: 3 Critical N AOP 915, Section 2, Step 2 b 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: b. Verify HIC 2440 input (P) and output (V) are consistent with FIC 2509 output (V) if Control Room is manned. Otherwise, mark this step N/A. Standard: The operator will verify the values in the control room. Evaluator Cue: Simulator Operator: When the operator contacts the control room, provide the current readings for reactor water level in the simulator using Extreme View. Communications will be by phone number 7825 or by simulator radio if provided. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical Y AOP 915, Section 2, Step 2 c 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: c. Place HS-2440 in the REMOTE position. Standard: The operator will place HS-2440 in REMOTE. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 9 of 13 Performance Step: 5 Critical N AOP 915, Section 2, Step 2 d 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: d. Toggle the parameter displayed on HIC-2440 to V using the D pushbutton if needed. Standard: if required, the operator will toggle the display to V. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 6 Critical Y AOP 915, Section 2, Step 2 e 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 perform the following: e. Control RCIC flow with HIC 2440 as necessary using the pulser knob. Standard: The operator will turn the pulsar knob in the counter clockwise direction to lower flow. Evaluator Cue: Inform the operator that RPV Water Level is RISING and to reduce the rate of injection a small amount. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 10 of 13 Performance Step: 7 Critical Y Continued on JPM In Plant 1, Vent the Scram Air Header. After the completion of the above portion of the task, the operator is required to demonstrate the knowledge of the location of the 1C208 Panel in the Plant. Standard: The operator will take the evaluator to the 1C208 Panel in the Plant or explain in enough detail as to demonstrate knowledge of the location in the plant. Evaluator Cue: Inform the operator that this portion of the task is complete. Inform the operator that they are to take you to the 1C208 Panel in the plant during a future JPM. Performance: SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 11 of 13 Terminating Cues: When the operator has taken control of the RCIC Turbine at 1C208 AND When the operator has demonstrated knowledge of the location of the 1C208 Panel in the plant. - Completed as part of venting the scram air header.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: TR-AA-230-1003-F10, Revision 2 2015 NRC In Plant 2 OPERATE RCIC FROM 1C208 JPM Page 12 of 13 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS: A Plant Transient has occurred requiring a shutdown from outside the control room. The control room is being evacuated. RCIC is injecting to the vessel. INITIATING CUES (IF APPLICABLE): The CRS has directed you to take control of RCIC from 1C208, and restore reactor water level IAW AOP 915.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2 JOB PERFORMANCE MEASURE JPM Page 1 of 19 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant 3 TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JOB PERFORMANCE MEASURE JPM Page 2 of 19 JPM TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance JPM NUMBER: 262002-05 REV. 0 TASK NUMBER(S) / TASK TITLE(S): 28.10 (NSPEO)/ Support shutdown of Regulating Transformer 1Y1A for maintenance K/A NUMBERS: 262002 K/A VALUE: A4.01 3.1 Justification (FOR K/A VALUES <3.0): TASK APPLICABILITY: RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: X Perform: EVALUATION LOCATION: In-Plant: X Control Room: Simulator: Other: Lab: Time for Completion: 15 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by: Signature On File (NRC Developed) Instructor/Developer Date Reviewed by: Signature On File (NRC Developed) Instructor (Instructional Review) Date Validated by: Signature On File (NRC Developed) SME (Technical Review) Date Approved by: Signature On File (NRC Developed) Training Supervision Date Approved by: Signature On File (NRC Developed) Training Program Owner Date Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 3 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE. REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly? 2. Has the JPM been reviewed and validated by SMEs? 3. Can the required conditions for the JPM be appropriately established in the simulator if required? 4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures? 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step? 6. Has the completion time been established based on validation data or incumbent experience? 7. If the task is time critical, is the time critical portion based upon actual task performance requirements? 8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required? 10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately? 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee? 13. Are all references identified, current, accurate, and available to the trainee? 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion? 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.) 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001} Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 4 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0 Initial development for 2015 NRC LOIT examination. Initial development for 2015 NRC LOIT examination. N/A See Cover See Cover Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 5 of 19 SIMULATOR SET-UP: (Only required for simulator JPMs) SIMULATOR SET UP: NONE Simulator Setup Instructions: NONE SIMULATOR MALFUNCTIONS: NONE SIMULATOR OVERRIDES: NONE SIMULATOR REMOTE FUNCTIONS: NONE Required Materials: 1. OI 317.1 General
References:
- 1. OI 317.1, Rev. 59 Task Standards: 1. At 1D15[1D25] place inverter ALARM BYPASS SWITCH to BYPASS. 2. At 1Y15, turn circuit breaker 1Y1503 OFF 3. At 1Y1A, turn circuit breaker 1Y1A02 OFF 4. At 1Y1A, turn circuit breaker 1Y1A01 OFF 5. At 1B32, turn circuit breaker 1B3216A OFF Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 6 of 19 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED. The initial conditions that I read may not exactly match the plant conditions, assume that the conditions that I read you are the correct plant conditions. INITIAL CONDITIONS: 1Y1A Regulating Transformer requires maintenance. 1D15 Instrument AC Inverter is in operation. All other Instrument AC equipment are operable and in their normal line-ups. RPS Alternate Power Source is on 1Y2A. INITIATING CUES (IF APPLICABLE): The CRS directs you, IAW OI 317.1, "120 VAC Instrument Control Power System," to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 7 of 19 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication). NOTE: Critical steps are marked with a "Y" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. Performance Step: 1 Critical N OI 317.1, Section 5.5, Step (1) At Panel 1Y36, verify the RPS alternate power supply source is not selected to 1Y16 [1Y26] Standard: Determines that RPS alternate power supply source is on 1Y2A in accordance with the Initial Conditions. Evaluator Cue: Show the operator Picture #1 to show the position of the Arrow. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 8 of 19 Performance Step: 2 Critical N OI 317.1, Section 5.5, Step (1)(a) If necessary, transfer the RPS alternate power supply source to 1Y2A [1Y1A] per OI 358. Standard: Based on the Initial Conditions, this action is not necessary. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical N OI 317.1, Section 5.5, Step (2) If necessary, start up and transfer load to Inverter 1D15 per Section 3.5, or transfer loads to an operating inverter per Section 4.2. Standard: This step is a turnover item. 1D15 is in service. Student marks the step as N/A'd. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 9 of 19 Performance Step: 4 Critical N OI 317.1, Section 5.5, Step (3) At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET pushbutton. Standard: Simulating pushing LAMP TEST/ALARM RESET pushbutton. Evaluator Cue: If asked what he/she sees when the pushbutton is depressed, CUE him/her that all of the lights are lit. When he/she simulates releasing the pushbutton, inform the student that the panel is the way he/she sees it now. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 10 of 19 Performance Step: 5 Critical Y OI 317.1, Section 5.5, Step (4) At 1D15[1D25] open right cabinet door and place inverter ALARM BYPASS SWITCH to BYPASS. Standard: Place the ALARM BYPASS SWITCH to BYPASS. Evaluator Note: The safety gear is located in a locker in the battery room hallway. To achieve this task, an FR Rating of 5 is required. Once the gear is pointed out and it is determined what he/she is going to wear, no further actions are necessary as the cabinet will NOT actually be opened. The ALARM BYPASS SWITCH is located inside 1D15. For the purposes of this JPM, opening this panel is not required. The student should simulate opening the right cabinet door and state that the bypass switch is on the right side of the cabinet and that he will simulate taking the switch to BYPASS. Evaluator Cue: CUE the student that the ALARM BYPASS SWITCH is in BYPASS by showing the operator Picture 2 in the back of the JPM. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 11 of 19 Performance Step: 6 Critical N OI 317.1, Section 5.5, Step (5) Confirm the FORWARD TRANSFER light is ON. Standard: FORWARD TRANSFER light is confirmed ON. Evaluator Cue: If asked, CUE him/her that the FORWARD TRANSFER light is ON. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical N OI 317.1, Section 5.5, Step (6) At 1Y15 [1Y25], confirm switch 1Y1504 [1Y2504] in the INVERTER position. (1Y15 [1Y25] MAINTENANCE SWITCH) Standard: Switch 1Y1504 confirmed in the INVERTER position. Evaluator Cue: CUE the student that Switch 1Y1504 is confirmed in the INVERTER position. There is a CAUTION on this page that states that a scoop tube lock-up is possible when closing 1Y1503, the Candidate may call the control room and inform them of the possibility of a scoop tube lock up. CUE the student that you understand that a scoop tube lock up may occur, and that he may continue. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 12 of 19 Performance Step: 8 Critical N OI 317.1, Section 5.5, Step (7) CAUTION CAUTION Opening or closing of breaker 1Y1503 [1Y2503] could result in a Reactor Recirc A[B] MG Set Scoop Tube lockup due to a problem in the scoop tube positioner circuitry. Standard: Reviews and placekeeps the CAUTION. Evaluator Cue: If the student calls the control room, CUE him that you understand that a scoop tube lock up may occur and that he may continue. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 9 Critical Y OI 317.1, Section 5.5, Step (7) Lock the Reactor Recirc A[B] MG Set Scoop Tube per OI 264 (Reactor Recirc System). Standard: Locks the "A" Reactor Recirc MG Scoop Tube. Evaluator Cue: Inform the student that another operator has locked the "A" Reactor Recirc MG Scoop Tube. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 13 of 19 Performance Step: 10 Critical Y OI 317.1, Section 5.5, Step (8) Turn circuit breaker 1Y1503 [1Y2503] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO JS1501 [JS2501]) Standard: Simulates turning off circuit breaker 1Y1503, REGULATING TRANSFORMER 1Y1A SUPPLY TO JS1501 by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1503 is in the OFF position after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 11 Critical Y OI 317.1, Section 5.5, Step (9) At 1Y1A [1Y2A], turn circuit breaker 1Y1A02 [1Y2A02] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO 1Y16 [1Y26]) Standard: Simulate turning off circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 is off after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 14 of 19 Performance Step: 12 Critical Y OI 317.1, Section 5.5, Step (10) Turn circuit breaker 1Y1A01 [1Y2A01] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] INPUT) Standard: Simulate turning off circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT by simulating pushing the breaker switch down. Evaluator Cue: CUE the student that circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT is OFF after the action is simulated. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 13 Critical Y OI 317.1, Section 5.5, Step (11) At 1B32 [1B42], turn circuit breaker 1B3216A [1B4203A] OFF. (REGULATING TRANSFORMER 1Y1A [1Y2A] AC SUPPLY) Standard: Simulate turning off circuit breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY by simulating pushing the breaker switch down. Evaluator Cue: CUE him that breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is off after the action is simulated. The student may state that he will open the cabinet to verify breaker is in the OPEN position. CUE the student when he/she sees the breaker and it is in the OPEN position. Performance: SATISFACTORY UNSATISFACTORY Comments: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 15 of 19 Performance Step: 14 Critical N OI 317.1, Section 5.5, Step (12) Reset the Reactor Recirc A[B] MG Set Scoop Tube as directed by the OSM/CRS per OI 264 (Reactor Recirc System). Standard: Resets the "A" Reactor Recirc MG Scoop Tube. Evaluator Cue: Inform the student that another operator will reset the Reactor Recirc MG Scoop Tube and the JPM is complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is simulated to be OFF and the scoop tube is reset, the JPM is complete. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Stop Time: Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 2015 NRC In Plant 3 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR MAINTENANCE JPM Page 16 of 19 Examinee: Evaluator: RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT: Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE. EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained. Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JPM Page 17 of 19 Picture 1 Handle is Horizontal Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 JPM Page 18 of 19 Picture 2 Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2 Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS: 1Y1A Regulating Transformer requires maintenance. 1D15 Instrument AC Inverter is in operation. All other Instrument AC equipment are operable and in their normal line-ups. RPS Alternate Power Source is on 1Y2A. INITIATING CUES (IF APPLICABLE): The CRS directs you, IAW OI 317.1, "120 VAC Instrument Control Power System," to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. Filename: 2015 NRC Exam In Plant 3 Rev 2 TR-AA-230-1003-F10 Revision 2