ML15258A665
| ML15258A665 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/20/2015 |
| From: | NRC/RGN-III |
| To: | NextEra Energy Duane Arnold |
| Zoia, C D | |
| Shared Package | |
| ML15118A364 | List: |
| References | |
| Download: ML15258A665 (130) | |
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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 1 of 40
NRC Initial License Exam - Scenario #1 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given the specific malfunctions presented in the evaluated scenario guide, the Objective: students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures:
Enabling There are no formal learning objectives for this evaluation.
Objectives:
Prerequisites: None Training Simulator Resources: Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team
References:
OI 324, Rev. 113 OI 454, Rev. 65 ARP 1C94, Rev. 48 IPOI 3, Rev. 143 OI 856.1, Rev. 45 AOP 255.1, Rev. 44 ARP 1C05A, Rev. 78 OI 255, Rev. 87 OI 255 QRC 1, Rev. 3 OI 152, QRC 2, Rev. 1 AOP 255.2, Rev. 42 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 None Experience:
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 2 of 40
Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Risk Significant Operator Actions:
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 3 of 40
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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 4 of 40
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 downpower 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 Event # Malf # Eventy Description Type*
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 Report from field that B SBDG has a jacket cooling water leak TS SRO B SBDG declared inoperable per TS 3.8.1 3 None R ATC Raise reactor power with control rods 4 rd02 C ATC Stuck Control Rod 3023 5 rd11b C RO CRD Pump trip 6 hp01 C BOP HPCI spurious start requiring manual shutdown/isolation TS SRO HPCI declared inoperable per TS 3.6.
7 ed01( M ALL Loss of Offsite Power with Small break LOCA.
a-e) rr15b Failure of A SBDG to start in AUTO, will start in Manual.
stdg01 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 5 of 40
Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 THIS PAGE IS USED FOR THE PRE-SCENARIO BRIEFING. IT CAN BE DELETED IF NOT REQUIRED.
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 RD021423 on ET 20.
(1) Verify the schedule file is RUNNING.
EVENT TRIGGERS Trigger No. Trigger Logic Statement Trigger Word Description 1, 5, 7, 10, Manual Trigger Manual Trigger 11, 12, 13, 14, 15, 17, 30 20 ZAORDPDI1825 >= .60 Drive Water DP > 295 psig 23 ZLOHPHS2312(2) == 1 & HPCI Inject Valve Opening after mode switch ZDIRPC71AS1(1) == 1 in SHUTDOWN Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 6 of 40
Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 me Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup AN1C08B(26) 1C08B (C-02) B DIESEL GEN 1 Crywolf ON PANEL 1C 94 TROUBLE Setup rd023023 CONTROL ROD BLADE Inactive Active STUCK- ROD 30-23 Setup stdg01 TRIP OVERRIDE - 'A' SBDG Inactive Active 1G31 FAILS TO AUTO START Setup stdg02 TRIP OVERRIDE - 'B' SBDG Inactive Active 1G21 FAILS TO AUTO START Setup rd070615 CONTROL ROD ACCUMULATOR TROUBLE- 45 sec 5 Inactive Active ROD 06-15 Setup Rd073435 CONTROL ROD ACCUMULATOR TROUBLE- 1 min 5 Inactive Active ROD 34-35 Setup rd11b CRD HYDRAULIC PUMP TRIP-5 Inactive Active PUMP B Setup hp01 HPCI INADVERTANT 7 Inactive Active INITIATION Setup ed01a LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR M Setup ed01b LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR J Setup ed01c LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR K Setup ed01d LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR X5960 Setup ed01e LOSS OF OFF-SITE POWER 60 Sec 21 Inactive Active SOURCES- BKR X5940 Setup rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 8 min 21 0 0.7 B
rr15b RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 3 min 23 As Is 1 B
Setup hp02 HPCI TURBINE TRIP 15 sec 23 Inactive Active Setup rd11a CRD HYDRAULIC PUMP TRIP-24 Inactive Active PUMP A Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 7 of 40
Appendix D NRC Initial License Exam - Scenario #1 Form ES-D-1 Schedule File for SEG.
At On Action Description Time Event Delete malfunction None 20 CONTROL ROD BLADE STUCK- ROD 30-23 rd023023 Insert malfunction dg03b None 22 1G21 'B' DIESEL GENERATOR TRIP- DG B after 45 HS-3281B B DG 1G21 IDLE-RATED SWITCH None 10 Insert remote dg19 to IDLE (RATED,IDLE)
Insert remote dg11 to 'B' DIESEL GEN 1G21 DROOP SWITCH None 11 PARALLEL (UNIT,PARALLEL)
Insert remote dg19 to HS-3281B B DG 1G21 IDLE-RATED SWITCH None 13 RATED (RATED,IDLE)
'B' DIESEL GEN 1G21 DROOP SWITCH None 12 Insert remote dg11 to UNIT (UNIT,PARALLEL)
Insert remote rd03 to CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 None 28 5.00000 ISOLATION Insert remote rd03 to CRD PUMP 1P-209A DISCHARGE VALVE V-17-08 None 27 100.00000 in 60 ISOLATION Delete malfunction CONTROL ROD ACCUMULATOR TROUBLE-None 14 rd070615 ROD 06-15 Delete malfunction CONTROL ROD ACCUMULATOR TROUBLE-None 15 rd073435 ROD 34-35 REMOTE FUNC FEEDBACK AN05- ACK SWITCH None 17 Insert remote an05 to ACK 1C94 (NORM,ACK)
Insert remote an05 to REMOTE FUNC FEEDBACK AN05- ACK SWITCH None 17 NORM after 5 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 8 of 40
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 80%
o Core Flow 41 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 post maintenance testing.
(Ensure reason we are starting using this method is okay)
- 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 Recirculation Flow to 85% Power per RE Direction
- Comments, problems, operator workarounds, etc.
o None Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 9 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:
Start B ESW
support starting B SBDG: SRO:
Simulator Operator:
- Directs the operator to start the B SBDG in accordance with OI 324, Sect 6.4, When directed FAST MANUAL STARTUP OF THE B SBDG SYSTEM.
to perform B Inform the control room that time ESW pump compression is being used and the B BOP:
prestart checks: ESW Pump is ready for start.
- 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
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 Simulator Operator
- Verify adequate cooling for ESW Pump 1P-99B by observing that FI-4938B One (1) minute B ESW FLOW indicates greater than 300 gpm.
after the B Inform the control room that the BESW Pump is running satisfactory. The strainer
- As soon as possible after ESW pump start, perform the following:
ESW Pump is started: is rotating, auto vents are closed and that o Inspect the auto vent/vac breaker for evidence of excessive leakage.
there is air flow in the room. 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 10 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CREW:
- Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG SYSTEM.
SRO:
- 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: If starting the Standby Diesel Generator from the After the B Simulator Operator Control Room on 1C08 perform the following:
SBDG Prelube Inform the control room that the B
- Set Prelube Timer KS-3238B to 2.0 minutes.
pump is SBDG Prelube Pump is running
- Start the B DIESEL GENERATOR 1G-21 PRELUBE pump by depressing operating: satisfactory. 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 11 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Paralleling the CREW:
B SBDG to
- Implements OI 324, Sect 6.4, FAST MANUAL STARTUP OF THE B SBDG 1A4: SYSTEM.
SRO:
- 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.
When directed BOP:
Simulator Operator to place HS-
- Load the B SBDG in accordance with OI 324, Sect 6. 6, PARALLELING THE B 3281, IDLE- Acknowledge the request. SBDG SYSTEM TO ESSENTIAL BUS 1A4.
RATED Switch
- Verify SBDG 1G-21 started per Sections Error! Reference source not in IDLE: found., Error! Reference source not found., Error! Reference source not found. or Error! Reference source not found..
One (1) minute Simulator Operator
- At 1C94, verify HS-3281B, IDLE-RATED SWITCH, in IDLE.
after the Activate ET 10.
- Perform the following on 1C08:
request to place o Adjusts B DIESEL GENERATOR 1G-21 VOLTAGE ADJUST HS-3281 in Inform the control room that HS-3281, control to maintain B DIESEL GENERATOR 1G-21 VOLTS meter IDLE: IDLE-RATED SWITCH is in IDLE.
at approximately 4160 volts.
o Adjusts B DIESEL GENERATOR 1G-21 SPEED ADJUST control When Simulator Operator to maintain B DIESEL GENERATOR 1G-21 FREQUENCY meter Acknowledge the request. at approximately 60 hertz.
requested to place HS-
- Place the GOVERNOR MODE SWITCH (DROOP) HS-3234B on 1C94 in the 3234B, PARALLEL position.
GOVERNOR MODE SWITCH in PARALLEL:
One (1) minute Simulator Operator after the Activate ET 11.
request to place Inform the control room that HS3234B, HS-3234B in GOVERNOR MODE SELECT SWITCH is PARALLEL: in PARALLEL Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 12 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:
Starting the B
324 (cont): SRO:
- 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.
Simulator Operator
- Enters AC Sources and SBDG LCOs.
Activate ET 17.
- TS LCO 3.8.1 Condition A- One Offsite Circuit INOPERABLE.
This will acknowledge the 1C94
- TS LCO 3.8.1. Condition B- One DG INOPERABLE Annunciator Alarms and clear the Control Room Annunciator on 1C08. This must BOP:
occur prior to the next event.
- 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.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 13 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:
Starting the B
324 (cont): SRO:
- 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 BUS 1A4 TRANSFER handswitch in AUTO.
When directed
- Use B DIESEL GENERATOR 1G-21 SPEED ADJUST to load B DIESEL Simulator Operator to perform GENERATOR 1G-21 to 1,500 KW, observing B DIESEL GENERATOR SBDG Acknowledge the request. 1G-21 KILOWATTS meter at 1C08 Operating
- Adjust B SBDG speed and voltage, as necessary to attain desired loading Checklist OI and power factor (0.9 power factor per Appendix 1).
324A9
- Complete the SBDG Operating Checklist OI 324A9 (Attachment 9).
(Attachment 9):
EXAMINER NOTE: After initially loading the B SBDG, wait ~5 minutes then insert Event 2.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 14 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Simulator Operator: Crew:
Five (5) minutes Activate ET 1.
- Responds to 1C08B (C-2), B Diesel Gen Panel 1C-94 Trouble Alarm after initially
- Responds to 1C94 (A-3), Jacket Coolant Level Low This will cause 1C08B (C-02), B Diesel starting to load
- Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Gen Panel 1C-94 Trouble to annunciate.
the B SBDG and at the direction of the Examiner:
BOP:
Simulator Operator
- Send an Operator to 1C94 to determine the cause of the TROUBLE When directed to investigate Acknowledge the request. Alarm and take corrective action per ARP 1C-94.
the 1C94
- At 1C92 monitor TI-3258B to determine if Jacket Coolant temperature is Trouble Alarm: high or low
- IF SBDG 1G-21 is running and NO LOOP or LOOP/LOCA emergency exists AND IF Jacket coolant temperature is above 195°F on TI-3258B Three (3) THEN Unload and trip SBDG and notify CRS.
minutes after Simulator Operator:
being directed
- Unloads the B SBDG (CRITICAL)
Inform the control room of the to investigate
- Trips the B SBDG (CRITICAL) following:
1C94 Trouble Alarm:
- 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.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 15 of 40
NRC Initial License Exam, Scenario #1 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2: Floor Instructor Crew:
Jacket Coolant The crew may elect to unload and remove
- Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Leak on the B the SBDG from service using OI 324. The SRO:
SBDG. steps documented to the left are the
- Directs the operator to unload the B SBDG in accordance with OI 324, Sect expected student response using OI 324. 8.3, UNLOAD THE B SBDG.
(contd)
- 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.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 16 of 40
NRC Initial License Exam, Scenario #1 SEG IF directed to Simulator Operator Crew:
place HS3234B
- Responds to 1C94 (A-4), Jacket Coolant Temperature Hi/Lo Acknowledge the request.
in UNIT:
Activate ET 12 SRO:
- Directs the operator to unload the B SBDG in accordance with OI 324, Sect This will insert RF dg11 to UNIT 8.3, UNLOAD THE B SBDG.
Inform the control room that HS3234B,
- Place the B GOVERNOR MODE SWITCH (DROOP) HS-3234B at B Governor Mode Switch is in UNIT. 1C94 in UNIT.
If directed to
- Directs placing the B DIESEL GENERATOR 1G-21 CONTROL place HS3281B Simulator Operator handswitch HS-3231B on 1C08 in the PULL TO LOCK position.
in RATED:
- Declares the B SBDG INOPERABLE (already INOP potentially due to Acknowledge the request. not exiting when 1A4 transfer switch was in MANUAL)
Activate ET13
- TS LCO 3.8.1 Condition B- One DG INOPERABLE This will insert RF dg19 to RATED. 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.
Inform the control room that HS3281B, IDLE-RATED SWITCH is in RATED. 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 17 of 40
NRC Initial License Exam, Scenario #1 SEG Event 3 SRO Increase Directs Operators to increase power IAW IPOI and RE guidance Reactor Power with control RO:
rods Continues control rod withdrawal IAW OI 856.1 following the sequence.
- Monitor neutron monitoring instrumentation during control rod movements.
If the crew does not transition to Simulator Operator:
- Verifies the following indications:
raising reactor Contact the control room as the Shift o White backlight on the Rod Select pushbutton turns ON power after the Manager and inform them that raising o On the Full Core Display, the white XX-XX select light corresponding SBDG event: reactor power is a priority. to the rod selected turns ON o On the Four Rod Group Display, the white SELECT light turns ON If called as Simulator Operator denoting the position display for the selectred rod.
organizational Acknowledge the requests and provide
- Momentarily places the ROD MOVEMENT CONTROL in the OUT-personnel to needed support. NOTCH position and verifies:
support the power rise: 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 withdrawls.
- Monitors balance of plant equipment /plant status.
Examiner Note: Prior to moving 3rd control rod, rod will stick. Go to Event 4.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 18 of 40
NRC Initial License Exam, Scenario #1 SEG Event 4: CREW Stuck Control Diagnoses control rod 14-23 is stuck Rod SRO
- Directs entry to AOP 255.1, Control Rod Movement/Indication Abnormal, when informed of stuck control rod.
When CRD Simulator Operator drive water
- Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, Verify ET 20 actuates. requirements are met.
pressure is greater than This will remove MF RD021423. This will
- Contacts RE and/or Duty Manager.
295 psig: allow rod 14-23 to move.
- While pulling control rods, recognizes 14-23 stuck and informs the SRO.
- Implements AOP 255.1, takes actions to address the stuck rod as follows:
If contacted as organizational Simulator Operator
- Verify power is available to RMCS.
personnel: Acknowledge the information.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 19 of 40
NRC Initial License Exam, Scenario #1 SEG Event 4: BOP:
When directed Simulator Operator
- Monitors balance of plant equipment/plant status.
to the HCU to Acknowledge the request.
perform local
- Contacts SANSOE to inspect control rod 14-23 HCU for abnormalities.
actions:
Two (2) minutes after initial Simulator Operator direction to Inform the control room that the HCU verify condition lineup is normal and HCU pressure is at the HCU: normal.
If contacted to monitor HCU Simulator Operator during control Inform the control room that the HCU rod movement looked and sounded normal during the after RD021423 move.
is removed:
EXAMINER NOTE: Continue to next event at examiners direction.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 20 of 40
NRC Initial License Exam, Scenario #1 SEG Event 5: Simulator Operator CREW:
After the crew ACTIVATE ET 5.
- Responds to annunciator 1C05A (A-7) B CRD PUMP TRIP OR MOTOR has performed OVERLOAD This will cause a trip of the B CRD pump AOP 255.1, and an accumulator alarms for 06-15 and SRO:
raised power 34-35.
and at the direction of the
- Contacts organization for support.
When directed Simulator Operator RO:
to investigate the cause of the Acknowledge the request.
- Determine the cause of CRD 1P-209B trip as follows o Monitor alarm "B" CRD PUMP 1P-209B LO SUCT PRESSURE (1C05A, B-7).
Two (2) minutes o If necessary send an Operator to Bus 1A4 to check targets on after being Simulator Operator Breaker 1A410 directed to Inform the control room that 1A410, B investigate B o As soon as practical, monitor computer points W092 and CRD pump breaker tripped on inverse W093 for any bearing temperature > 180°F CRD Pump time delay overcurrent.
breaker:
- If 1P-209B tripped due to any electrical fault, initiate a Work Request Three (3) to have the pump checked, meggered, and repaired as necessary.
minutes after Simulator Operator being directed Inform the control room that B CRD to investigate pump motor is abnormally hot.
B CRD pump locally:
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 21 of 40
NRC Initial License Exam, Scenario #1 SEG Event 5: Simulator Operator If the crew elects to start the CRD pump in accordance with OI 255 here are the expected student responses.
When directed Activate ET 28.
to verify CREW:
This will position V-17-8 1/2 turn open.
adequate oil
- Implements OI 255, Sect regarding Startup of a CRD Pump level and close Inform the control room that there is SRO:
V-17-8 to 1/2 turn adequate oil level in the A CRD pump open: motor and speed changer and the V
- Directs starting A CRD pump in accordance with OI 255, Section 8, A CRD Pump Discharge Valve is 1/2 regarding Startup of a CRD Pump.
turn open. RO:
When contacted
- Verify adequate oil level in CRD Pump 1P-209A motor and speed Simulator Operator as the Reactor changer Engineer and Acknowledge the request for support.
- Close 1P-209A Pump Discharge Isolation V-17-8 to approximately informed of the 1/2 turn open.
High CRD Temperatures,
Simulator Operator
- At 1C05, verify MO-1833, INLET TO CRD RETURN LINE, is fully open When directed Acknowledge the request.
- Start CRD PUMP 1P-209A by momentarily placing handswitch to slow open V- AND HS-1807A on 1C05 in the START position 17-8, A CRD Pump Activate ET 27
- Slowly open Discharge Isolation V-17-8 to pressurize downstream Discharge piping and to prevent CRD pump from tripping on low suction pressure.
This will position V-17-8 full open in 60 Valve: seconds.
After the ramp Simulator Operator is complete and V-17-8 is full Inform the control room that V-17-8 is open: full open.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 22 of 40
NRC Initial License Exam, Scenario #1 SEG CREW:
When directed Simulator Operator RO:
to vent both Acknowledge the request.
- Vent both CRD Discharge Filters 1F-201A and B CRD Discharge Filters: Inform the control room that time
- At 1C05, verify charging header pressurized > 1200 psig on PI-1816A compression is being used and that CHARGING WATER PRESSURE both CRD Discharge Filters have been
- Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain vented. 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 23 of 40
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:
RO:
- Close MO-1830, Drive Water P Control
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 24 of 40
NRC Initial License Exam, Scenario #1 SEG Accumulator CREW:
Trouble
- Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO annunciator PRESSURE OR HI LEVEL response SRO:
- Comply with Technical Specification requirements for Control Rod Scram If contacted to Simulator Operator Accumulators.
determine if Inform the control room that there are there are any
- TS LCO 3.1.5.Condition A (twice)- One control rod scram NO slow control rods. accumulator inoperable with reactor steam dome pressure >900 psig.
slow control rods based on o Declare the associated control rod scram time slow within 8 last scram time hours OR testing: 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 />.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 25 of 40
NRC Initial License Exam, Scenario #1 SEG When directed Simulator Operator CREW:
to investigate
- Responds to annunciator 1C05A (F-7), CRD ACCUMULATOR LO Acknowledge the request.
accumulator PRESSURE OR HI LEVEL trouble alarms: SRO:
- Directs recharging the accumulators in accordance with OI 255.
RO:
Three (3) Simulator Operator
- Implement actions of ARP 1C05A (F-7), CRD ACCUMULATOR LO minutes after Inform the control room that the alarms PRESSURE OR HI LEVEL being directed are due to low pressure. Control rod to investigate
- Check the Full Core Display on 1C05 to determine which accumulator 06-15 is indicating 935 accumulators are in the trouble condition.
accumulator psig and 34-35 is indicating 930 psig.
trouble alarms: o Determines that 06-15 and 34-35 are in trouble condition.
I will recharge the two accumulators in
- Send an Operator to the accumulators to determine the cause of the accordance with OI 255. alarm.
- Recharge accumulator per OI 255 (CRD HYDRAULIC SYSTEM).
Ten (10) Simulator Operator minutes after being directed Activate ET 14 to recharge the This will remove MF RD070615.
Inform the control room that accumulator 06-15 has been recharged.
Final accumulator pressure is 1200 psig.
Ten (10) minutes after Simulator Operator recharging 06- Activate ET 15 15:
This will remove MF RD073435.
Inform the control room that accumulator 34-35 has been recharged.
Final accumulator pressure is 1170 psig.
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 26 of 40
NRC Initial License Exam, Scenario #1 SEG Continue to next event at examiners direction.
Event 6: Simulator Operator: Crew When directed Activate ET 7.
- Respond to auto initiation of HPCI.
by the This causes an auto initiation of HPCI.
examiner:
SRO Simulator Operator
- Directs tripping HPCI after verifying that HPCI operation is not required When contacted as Acknowledge the information. by assuring that by 2 independent indications adequate core cooling is organizational assured.
personnel to
- Comply with Technical Specification requirements for HPCI.
auto initiation:
- TS LCO 3.5.1.Condition F- HPCI System INOPERABLE o F.1.- Verify by administrative means RCIC System is OPERABLE If the operator immediately checks status of Floor Instructor Inform the operator that the relay o F.2.- Restore HPCI System to OPERABLE status within 14 days.
relay E41A-K6:
appears the same as C71A-K3D. BOP
This relay is energized to demonstrate the understanding of what it should look like.
- Depresses and hold HS-2259, Remote Turbine Trip PB
- Verify HV-2201, HPCI Turbine Stop Valve Closes
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 27 of 40
NRC Initial License Exam, Scenario #1 SEG AOP 255.2 due Crew to HPCI auto
- Respond to auto initiation of HPCI.
start
- Implement AOP 255.2, Power/ Reactivity Abnormal Change.
When contacted Simulator Operator SRO as
- Directs AOP 255.2, Power/ Reactivity Abnormal Change.
organizational Acknowledge the information.
personnel to
- Establish critical parameter monitoring of Reactor Power, Reactor support HPCI Pressure, and RPV Water Level, as priorities allow.
auto initiation:
- Notify the Reactor Engineer and Operations Manager.
- After the cause has been determined and corrected, return to normal operation.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 28 of 40
NRC Initial License Exam, Scenario #1 SEG Event 7: Simulator Operator: LOSS OF POWER EVENT LOOP, A DG Activate ET 21 Crew Fails To Auto This will result in a Small Break LOCA Responds to Loss of Offsite Power Indications Start. (Will start immediately on a ramp and a LOOP after SRO in manual.)
60 seconds
- Directs Reactor pressure control using SRVs
- Enters AOP 304.1 LOSS OF 4160V NON-ESSENTIAL ELECTRICAL Small Recirc Simulator Operator: POWER Leak
- Enters AOP 301 LOSS OF ESSENTIAL ELECTRICAL POWER Directs starting the A DG and verifying it loads the Bus (CRITICAL TASK #1)
- Directs RPV level band 170 to 211 using available systems RO Provides RPV level and pressure status BOP
- May report MSIV closure (Group I Isolation)
- Diagnoses that the A DG started but did not pick up the bus
- Diagnoses that the A DG is running with output breaker open.
- Acknowledges that the B DG failed will not start STARTS A DG and verifies it loads BUS 1A3 (CRITICAL TASK #1)
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 29 of 40
NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) CREW:
LOOP, A DG Responds to annunciator 1C05B-B1 - Primary Containment Pressure Hi/Lo Output BKR Diagnoses rising containment pressure and lowering RPV water level.
FAILS and will not close. B DG SRO:
Fails To Start but CAN be Directs a reactor scram due to lowering RPV water level from SBLOCA.
manually
- Direct the operator to Insert a manual reactor scram, and carry out IPOI 5 started. (Reactor Scram procedure)
Small Recirc
- Confirms that the reactor is shutdown Leak
- 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 If forced circulation is lost, enter AOP 264 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 30 of 40
NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) SRO:
Enters AOP 573 - Primary Containment Control LOOP, A DG
- Directs operators to monitor containment parameters Output BKR
not close. B DG
- IF EOP-1 Alternate Level Control Leg is entered may direct:
Fails To Start o Lockout of ADS but CAN be o Start of CRD pump. (A CRD Pump unavailable) manually o Start of SBLC pump started.
Directs Reactor Water level band of 170 to 211 using available Small Recirc systems - (HPCI unavailable, will lead to ED)
Leak
- Directs Defeat 4 - This results DW Cooling Fans in FAST
- Enters EOP Primary Containment Control when containment pressure reaches 2 psig.
- Directs initiation of Torus Spray prior to Torus Pressure exceeding 11 psig
- IF Torus Pressure exceeds 11 psig, directs initiation of Drywell Spray.
- Directs Defeat 4 - This results DW Cooling Fans in FAST
- Enters EOP Primary Containment Control when containment pressure reaches 2 psig.
- Directs initiation of Torus Spray prior to Torus Pressure exceeding 11 psig
- IF Torus Pressure exceeds 11 psig, directs initiation of Drywell Spray.
Event 8: Booth Operator: BOP:
HPCI starts but After HPCI runs for <1 minute, insert Starts HPCI to maintain RPV level band. (HPCI will start but will trip) trips Malfunction XXFF, Trips HPCI. Reports to crew that HPCI has tripped.
Attempts to restart (unsuccessful).
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 31 of 40
NRC Initial License Exam, Scenario #1 SEG Event 7: (Cont) RO:
- Assists BOP in controlling RPV level and monitoring other critical primary Output BKR containment plant parameters FAILS and will not close. B DG BOP:
Fails To Start
- If directed, performs Defeat 4 to maximize drywell cooling but CAN be
- Places Torus Spray in service as follows:
manually started. 1. Places keylock HS-2005[HS-1932] Outboard Torus Cooling/Spray Valve Small Recirc handswitch in OPEN and verify valve opening Leak 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 32 of 40
NRC Initial License Exam, Scenario #1 SEG Crew
- 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.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 33 of 40
NRC Initial License Exam, Scenario #1 SEG Crew
- Announces suspending all evolutions in progress associated with electrical switchgear and switching operations
- Verify two Well Water Pumps in service. Starts either B or C Well Water Pump and adjusts well water flow.
- 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 Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 34 of 40
NRC Initial License Exam, Scenario #1 SEG Crew
- Implements the mitigation strategies of EOP 2, Primary Containment Control RO
- 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.
- Trips the running recirculation pump.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 35 of 40
NRC Initial License Exam, Scenario #1 SEG Crew
- Lockouts ADS.
- 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.
- Directs ADS lockout.
- 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: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 36 of 40
NRC Initial License Exam, Scenario #1 SEG Crew
- 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
- 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 tripping Core Spray pumps when RPV level indicates on the GEMACs Directs throttling RHR injection to maintain RPV level 170-211 Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 37 of 40
NRC Initial License Exam, Scenario #1 SEG SRO 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)
BOP:
- Monitors and controls RPV level as he depressurization occurs
- END OF SCENARIO ***
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 38 of 40
[SEG #], [Title], [Rev. ] SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS THIS SECTION IS ONLY REQUIRED FOR EVALUATED SCENARIOS.
DISCUSSION ITEMS Insert any additional Discussion Points to be made after scenario completion. See Discussion Point discussion in the Expected Student Response column of the Simulator Exercise Guide Scenario Instructions three-column template above.
QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
1.
2.
After EOP Entry:
1.
2.
Abnormal Events:
1.
2.
Major Transients:
1.
2.
Critical Tasks:
- 2. Starts the A SBDG manually to power only safety-related electrical bus
Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 39 of 40
[SEG #], [Title], [Rev. ] SEG Filename: Scenario 1 rev1 TR-AA-230-1003-F06 Revision 0 Page 40 of 40
SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #:
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: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 1 of 24
NRC Initial License Exam - Scenario #2 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given specific plant conditions, the students will be able to in Objective: accordance with plant procedures.
Enabling Given specific plant conditions, the student will be able to perform:
Objectives: 1.
2.
3.
Prerequisites:
Training Resources:
References:
Protected Content: Identify here and in training material as {C001}; See Comment for details.
Evaluation Method:
Operating Experience:
Risk Significant Operator Actions:
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 2 of 24
NRC Initial License Exam - Scenario #2 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Annotate risk significant tasks as applicable 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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 3 of 24
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 using control rods.
Event Event # Malf # Eventy Description Type*
1 None N BOP Perform MSIV test per STP 3.3.1.1-17 2 rp02a C BOP Trip of RPS MG Set TS SRO Tech Spec 3.3.8 entry 3 rd01 C ATC Control Rod Drift with AOP entry 3023 TS SRO Tech Spec entry 3.1.3 4
ed13a C BOP 125 VDC Div 1 panel 1D11 trip results in AOP entries TS SRO Tech Spec entry 3.8.7, Condition B 5 mc04b R RO Condenser Vacuum Leak (recoverable)
C BOP Fast Power Reduction 6 rc08 BOP Spurious start of RCIC, requires manually stopping RCIC TS SRO Tech Spec Entry 3.5.3, Condition A 7 mc04b M ALL Rising backpressure from Event 5 progression necessitates reactor scram.
ATWS occurs 8 hp03 I BOP Failure of HPCI controller (complicates RPV level restoration).
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 4 of 24
Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 THIS PAGE IS USED FOR THE PRE-SCENARIO BRIEFING. IT CAN BE DELETED IF NOT REQUIRED.
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
- 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
- 8. Fill in STP 3.3.1.1-17 Cover Matter, and have for turnover.
Trigger No. Trigger Logic Statement Trigger Word Description 3 Manual Trigger Trips A EPA 5 Manual Trigger Drifts Rod 30-23 Out 7 Manual Trigger Loss of 1D11 9 Manual Trigger Condenser Air Leak 11 Manual Trigger RCIC Spurious Start 13 Manual Trigger Condenser Air Leakage Rises 20 ZLOHPHS2202(2) == 1 HPCI MO 2404 Starts to open Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 5 of 24
Appendix D NRC Initial License Exam - Scenario #2 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value rp02a RPS EPA BREAKER TRIP-3 Inactive Active RPS A EPA BKR rd013023 CONTROL ROD DRIFTS OUT-5 Inactive Active ROD 30-23 ed13a 125 VDC DISTRIBUTION 7 Inactive Active PANEL FAULT- PNL 1D11 mc04b MAIN CONDENSER AIR 6 min 9 0 .9 INLEAKAGE- HP CONDENSER rc08 INADVERTENT RCIC 11 Inactive Active INITIATION mc04b MAIN CONDENSER AIR 3 min 13 .9 1.2 INLEAKAGE- HP CONDENSER Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE VOLUME 0 75 (VARIABLE) hp03 HPCI FLOW CONTROLLER 1 min 20 As Is 30 FAILS Fw02a Cond Pump Trip 15 Active Fw02b Cond Pump Trip 15 Active 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: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 6 of 24
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 41 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.
Retesting a relay.
The STA will assist with the back panel verifications during the performance of the STP.
- 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 Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 7 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 8 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: CREW:
Perform Main Verifies Prerequisites for STP 3.3.1.1-17:
Steam Isolation
- No other testing on the RPS System Valve Testing
- All MSIVs are OPEN Floor Instructor: SRO:
Station person at C71A-K3A and C71A-
K3B and role play when relays cycle.
Use the cordless phones in the simulator to communicate. These BOP:
relays are actual relays in the simulator.
OPEN relayC71A-K3E.
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)
Recommend performing one set (D MSIV INBD and OTBD)
- Station personnel at 1C15 and 1C17 in preparation for observing test response of relays to the C71A-K3A and C71A-K3B, concurrent with cycling CV-4412 and CV-4413
- At 1C03, verify that CV-4412 goes partially closed and reopens fully.
- Repeat actions for the remaining valves.
RO:
- Perform Peer Checks Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 9 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EXAMINER NOTE: After completion of ST, crew will move to raise reactor power Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 10 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2 SRO Trip of RPS MG Directs Operators to IAW AOP 358 Set
- Enters TSs Tech Spec o 3.3.4 A 4 hr 3.3.8 entry o 3.3.1.1 A All Required actions met Simulator Operator: o 3.3.1.1 B All Required actions met At the direction Activate [ET 3] o 3.4.5 B of the Lead Examiner Respond as plant personnel as necessary. o 3.4.5 C o 3.3.3.1 PAM Simulator Operator: o 3.6.1.3 - (12 times) All the Group 3 Isolation vales When called as Reports the A RPS MG Set is tripped and repositioned in the Group 3 Isolation ARP the 2nd Asst. to faint acrid smell and abnormally hot to RO:
investigate the touch, Both EPAs are tripped. 1Y30 looks loss of RPS,
- Report Power Pressure Level Report ok.
wait 2 minutes,
- Report the Loss of A RPS BOP:
When called as the 2nd Asst. to Report that 1Y16 is aligned to the alternate verify Alt power rps power.
aligned to 1Y16, Simulator Operator:
When contacted to verify the Report cleanup beds in hold.
Cleanup Beds in hold, wait 3 minutes Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 11 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE OI 358 Appendix 4 Actions - Insert Here DSM Simulator Operator:
Acknowledge to support.
Electricians Simulator Operator:
Acknowledge to support.
Allow the crew to get to the 1/2 Scram Recovery Checklist prior to proceeding.
Examiner Note: When the crew is about to restore Cleanup to service and at the lead examiners direction, move on to the next event..
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 12 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3: CREW:
Control Rod Diagnoses control rod 30-23 is drifting Drift with AOP SRO:
entry
- Directs entry to AOP 255.1, Control Rod Movement/Indication Tech Spec Abnormal, Mispositioned control rod section.
entry 3.1.3
- Directs entry into AOP 255.2 Power Reactivity Abnormal Change.
Simulator Operator:
- Determines that the TS 3.3.2.1, Control Rod Block Instrumentation, At the direction requirements are met.
of the lead Activate [ET 5]
examiner, This will actuate RD013023, causing Rod
- Evaluate the entry into TS LCO 3.1.3 C Control Rod Inoperable 30-23 to drift out of the core.
- 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.
If contacted as Simulator Operator:
RO:
the second report that the HCU lineup is normal and assistant HCU pressure is normal.
- 1C05A (D-6) Rod Drift Actions
Simulator Operator:
- As directed and IAW AOP 255.1, takes actions to address the stuck rod Acknowledge the request as follows:
When directed to Mechanically delete malfunction RD013023 and call Isolate HCU 30- back and inform the control room the hcu 23, wait 4 has been isolated with (valve numbers) Section 8.1 of OI 255, Isolation of HCU added to the writeup for actions.
minutes and Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 13 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3: BOP:
- Monitors balance of plant equipment/plant status.
Drift
- Contacts SANSOE to inspect control rod 30-23 HCU for abnormalities.
(Contd)
Simulator Operator:
When contacted as the Reactor Acknowledge and inform the control Enginer, room that you will evaluate the current rod configuration.
When contacted Simulator Operator:
as the Acknowledge the request for support.
DSM/Operation s Direstor EXAMINER NOTE: Continue to next event at examiners direction.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 14 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: CREW 125 VDC Div 1 The crew will recognize the loss of 1D11 panel 1D11 trip SRO results in AOP entries
- Possibly enters AOP 644
- Enters AOP 302.1-Loss of 125 VDC Power, Tab 1-Loss of 125vdc Tech Spec Div 1 entry (3.8.7.B)
- May direct, as time permits, the RO to transfer to A level control to control reactor level and try to maintain normal band.
Simulator Operator:
- Enters TS LCO 3.8.7.B - 8 Hr LCO (1D11)
At the direction of the Lead Activate [ET 7]
- Directs transferring non-essential power to the startup transformer.
Examiner This inserts ed13a causing a loss of 1D11 RO
- Takes manual control of FW and attempts to restore reactor water level to the normal band.
Simulator Operator: OR If level increases to a scram, then set
- Place the A level controller in service with handswitch Event Trigger 9 to TRUE and move to
- Place 3 Element to Single Element next event.
- Monitor Power Pressure and Level at 1C05 NOTE: If the RO does not place the level controller to A a scram will occur.
When contacted as the second Simulator Operator:
assistant to go report after 2 minutes that 1D10 CKT 6 to the 1A3 has tripped free and there is no sign of switchgear smoke or fire at the breaker. BOP Actions Continued on the next page.
room to in Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 15 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Actions continued from the previous page.
- Recognize the Loss of 1D11 Simulator Operator:
- 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 Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 16 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5: Crew:
Acknowledges annunciator 1C04c Spurious start of RCIC, Announces alarm to the SRO requires manually SRO:
stopping RCIC Will direct the follow actions:
Tech Spec o Trip rcic Entry 3.
o Enter AOP 255.2 for Power Reactivity Abnormal o Enter TS 3.5.3 Conditon A for RCIC Inoperable.
o May look at TS 3.3.5.3 for rcic instrumentation.
At the Simulator Operator:
discression the Activate [ET 11]
Lead Examiner This will spuriously start RCIC When sent to investigate the Simulator Operator:
Spurious start Inform the control room that the Level of RCIC, wait 3 Switch for the RCIC Turbine has minutes, actuated.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 17 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4: RO: (Continued)
(Contd) o BOP:
- Provides peer check when required Continue to next event at examiners direction.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 18 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 o Enter AOP 691, High Condenser Backpressure.
Simulator Operator: Fast power reduction \ 39mlbm Condenser Vacuum Leak Activate [ET9]
- Fast power reduction rod insertion (recoverable)
This will insert mc04b, result in degrading
- Reduce recirc to 27 mlbm Emergent backpressure.
Power Reduction Insert rods to 30-35% power o
HP Tech high Simulator Operator:
rad brief Acknoledge the order If contacted as Simulator Operator:
Aux Operator to Acknoledge the order perform a High Rad Entry to investigate.
Simulator Operator:
Activate [ET 13] if the crew inserts a manual scram Go in to the condenser bay and investigate Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 19 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Back pressure EOP1 ATWS gets worse.
Manually trip generator field breaker Simulator Operator: ATWS EOP1 after drifting rods iaw rips At the direction of the Lead Activate [ET 13]
Examiner, This will worsen the condenser air inleakage driving the crew to insert a Trip C/F when the crew gets all rods in.
manual scram.
OI 149 to resetr lpci logic on lo lo lo trip.
Simulator Operator:
Acknoledge the order and activate ET Torus cooling When Directed to install defeat 12 to install Defeat 12 Restore water level with HPCI 12 Simulator Operator:
When all rods are inserted, Activate [ET 15]
Restore drywell cooling iaw defeat 4 with group 7 JPM for this Override the Key Locks for defeat 4 Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 20 of 24
NRC Initial License Exam, Scenario #2 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Follow up question for the SRO With a loss of A RPS, What is reportable IAW LI-AA-102-1001?
- END OF SCENARIO ***
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 21 of 24
[SEG #], [Title], [Rev. ] SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS THIS SECTION IS ONLY REQUIRED FOR EVALUATED SCENARIOS.
DISCUSSION ITEMS Insert any additional Discussion Points to be made after scenario completion. See Discussion Point discussion in the Expected Student Response column of the Simulator Exercise Guide Scenario Instructions three-column template above.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 22 of 24
[SEG #], [Title], [Rev. ] SEG POST SCENARIO REVIEW LICENSED OPERATOR CONTINUING TRAINING REVIEW
- Conduct Post-Scenario Review in accordance with Attachment 2 to TR-AA-230-1007 using TR-AA-230-1007-F07, Simulator Instructor LOCT Post-Exercise Checklist.
LICENSED OPERATOR INITIAL TRAINING REVIEW
- Conduct Post-Scenario Review in accordance with Attachment 2 to TR-AA-230-1007 using TR-AA-230-1007-F08, Simulator Instructor LOIT Post-Exercise Checklist.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 23 of 24
[SEG #], [Title], [Rev. ] SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
1.
2.
After EOP Entry:
1.
2.
Abnormal Events:
1.
2.
Major Transients:
1.
2.
Critical Tasks:
1.
2.
Filename: Scenario 2 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 24 of 24
SIMULATOR EXERCISE GUIDE SEG SITE: Duane Arnold Energy Center Revision #:
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: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 1 of 22
NRC Initial License Exam - Scenario #3 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given the specific malfunctions presented in the evaluated scenario guide, the Objective: students will be able to protect the public, protect plant personnel and protect plant equipment, in accordance with plant procedures:
Enabling There are no formal learning objectives for this evaluation.
Objectives:
Prerequisites: None Training Simulator Resources: Simulator Operator Phone Talker Simulator Floor Instructor Evaluation Team
References:
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 None Experience:
Risk Significant Operator Actions:
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 2 of 22
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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE See Cover Initial development for Initial development for 2015 NRC 0 2015 NRC LOIT N/A LOIT examination. See Cover examination.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 3 of 22
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 HPCI pump surveillance test Event Event # Malf # Eventy Description Type*
AO-RR-1 069 R ATC Raise power with recirculation flow.
I ATC APRM A fails (inoperable).
2 TS SRO Tech Spec review (3.3.1.1, 3.3.2.1) 3 N BOP RCIC surveillance test.
A RCIC system isolation signal is received due to steam leak; isolation is C BOP 4 faulted.
TS SRO Tech Spec entry (3.5.3)
C BOP 5 River Water Supply Pump trip.
C SRO 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: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 4 of 22
Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 THIS PAGE IS USED FOR THE PRE-SCENARIO BRIEFING. IT CAN BE DELETED IF NOT REQUIRED.
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
- 3. Verify B and C APRMs 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.
Trigger No. Trigger Logic Statement Trigger Word Description 1, 3, 5, 7 Manual Trigger Manual Trigger 20 YCAB002 >= 48 Power > 48%
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 5 of 22
Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value (sec)
Setup rh10c RHR C PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10d RHR D PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10a RHR A PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup rh10b RHR B PUMP FAIL TO AUTO-Inactive Active ACTUATE Setup stdg01 TRIP OVERRIDE - 'A' SBDG Inactive Active 1G31 FAILS TO AUTO START Setup stdg02 TRIP OVERRIDE - 'B' SBDG Inactive Active 1G21 FAILS TO AUTO START Setup cs05a CORE SPRAY PUMP A -
Inactive Active FAILURE TO AUTO-INITIATE Setup cs05b CORE SPRAY PUMP B -
Inactive Active FAILURE TO AUTO-INITIATE Setup strh02 LPCI B INJECT VALVE FAILS Inactive Active TO AUTO OPEN - MO-1905 Setup ms31b GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- Inactive Active MO2401 Setup ms31a GROUP 6 ISOLATION VALVE(S) FAIL(S) TO CLOSE- Inactive Active MO2400 Setup strh01 LPCI A INJECT VALVE FAILS Inactive Active TO AUTO OPEN - MO-2003 Setup sthp01 HPCI SYSTEM AUTO Inactive Active INITIATION BLOCK Setup nm08a APRM CHANNEL FAILS- CHNL REMOVE 1 As Is 100 A
Setup rc06 RCIC STEAM SUPPLY LINE 6 min 3 0 30 BREAK (RCIC ROOM)
Setup sw19b RIVER WATER SUPPLY PUMP 5 Inactive Active TRIP- PUMP B, 1P117B Setup rr15a RECIRC LOOP RUPT- DESIGN BASES LOCA AT 100%- LOOP 7 0 2 A
Setup Rr17a 1 min 20 As Is 80 Setup Sw14a 3 min 85 Setup Sw14b 3 min 85 Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 6 of 22
Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value (sec)
Setup Strc01 Write a sch file to block the initiation and valve light power Add Condensate Pump Trip on 1A1/2 transfer.
HP0 HPCI TRIP on 15 seconds running.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 7 of 22
Appendix D NRC Initial License Exam - Scenario #3 Form ES-D-1 OVERRIDES Time Over. No. Override Title Delay Ramp ET Initial Final Value Value REMOTE FUNCTIONS Time Remote No. Remote Title Delay Ramp ET Initial Final Value Value Setup fp08 RCIC DELUGE MAN May need to ISOLATION VALVE V-33-84 Open Closed look up (OPEN,CLOSE)
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: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 8 of 22
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-XX was completed last shift and is in routing.
- 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: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 9 of 22
NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Have the crews brief the evolutions on the CREW:
Raise power turnover sheet. Provide the crews with OI with Recirc flow. 264, OI 150, IPOI 3, and STP XXXXX SRO:
- Directs power to be raised from 40 to 50% using recirculation pump If Contacted as flow.
the Reactor Simulator Operator:
Engineer to ATC:
provide Inform the crew to raise power with Recirc
- Performs Recirculation Pump flow adjustments to raise power from
- guidance, Flow to achieve approximately 50% power 40 to 50%.
and hold power constant until a rod sequence is approved for further power
- Monitors plant parameters for expected response during reactivity ascension. manipulation.
BOP:
- Adjusts generator excitation as necessary to maintain KVAR loading and power factor as specified by the system load dispatcher per OI 698, Main Generator.
- Starts additional cooling tower fans in forward as necessary to maintain condenser absolute pressure less than 5 in. Hg., as indicated at LP COND 1E-7A[B] BACK PRESSURE indication PI-1476[1477] on 1C07.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 10 of 22
NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1: Simulator Operator: CREW:
When power Verify ET 20 activates.
reaches 48% This will cause A Recirc MG Set speed to SRO:
rise.
- Will enter AOP 255.2 on the Power/Reactivity Abnormal.
- Contact the Duty Station Manager/Operations Director and/or the Reactor When contacted Engineer.
Simulator Operator:
as the 2nd Asst.
Report that the power switch is on and the
- May Enter TS 3.4.1 Condition C for the Mismatch in Recirc Pump Speeds.
to go to the MG Set Room to thermal overload button on the motor is
- If the B Scoop Tube was locked, the CRS may direct the crew to reset the reset. B Scoop Tube in accordance with OI 264 investigate the Recirc Pump Speed ATC:
Changer, Wait 2
minutes and
- 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
- If directed, reset the B Scoop Tube in accordance with OI 264 Contacted as Agree to support trouble shooting efforts.
the DSM/OD BOP:
When
- Direct inplant operators to investigate the scoop tube malfunction Contacted as Simulator Operator:
Acknowledge the situation and inform the
- Run 3D Case recovery.
- Plot Power to Flow
- If directed, reset the B Scoop Tube in accordance with OI 264 Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 11 of 22
NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EXAMINER NOTE: After power has been raised to approximately 50%, commence Event 2.
Event 2: Simulator Operator: Crew:
ACTIVATE ET 1. Identifies the following:
This will cause A APRM to fail upscale.
- a half-scram has occurred.
- a rod out-block has occurred.
BOP:
Simulator Operator:
- Unbypass the B APRM Acknowledge the issue, and/or to provide or support
- Bypass the D APRM maintenance support for organization, ATC:
troubleshooting/repair.
Responds to failure of APRM A
Following the Simulator Operator:
- Acknowledges 1C05B (A-6), ROD OUT BLOCK. References ARP.
reset of the half-scram, crew Call the CRS as the Operations Director
- Identifies that APRM A has failed.
should proceed and direct the crew to proceed with the
to the RCIC RCIC Trouble Shooting Run to test the surveillance Flow Controller.
- Resets the half scram.
test. If crew
- does not
- proceed, SRO Actions are continued on the next page.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 12 of 22
NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Continued from previous page.
SRO:
Directs crew response for failed APRM A
- Reviews TS 3.3.1.1, Condition A for applicability Instrumentation.
- Reviews TS 3.3.2.1 for applicability.
- Directs A APRM to be bypassed.
Directs the half-scram to be reset.
- Direct the D APRM to be bypassed if not completed.
EXAMINER NOTE: After the half-scram is reset, crew should proceed to RCIC Trouble Shooting (Event 3).
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 13 of 22
NRC Initial License Exam, Scenario #3 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 If the vacuum pump does not initially RCIC start or trips, direct the crew to attempt SRO:
Confidence Run it again at the direction of the Electrical
Maintenance Supervisor in the RCIC Room.
- Verify RCIC LCO has been entered When Simulator Operator:
Contacted as Wait 4 minutes and inform the control the Extra Room that ATC:
Operator for the
- Oil level has been verified
- Monitors plant parameters during RCIC Run.
RCIC Run, satisfactory
- And standing by outside the RCIC BOP:
Room.
Starts RCIC in CST to CST mode in accordance with OI 150.
- Open the REDUNDANT SHUTOFF valve MO 2316 on 1C03.
Simulator Operator:
Contacted as
- Open the TEST BYPASS valve MO 2515 to 44-46% open as Health Physics, Acknowledge the running of RCIC and the indicated on RCIC TEST BYP MO 2515 POSITION ZI 2515.
potential to change rad levels in the plant.
- Verify MO 2511 PUMP DISCHARGE valve is open.
When contacted Simulator Operator:
- Start 1P 227 VACUUM PUMP by placing handswitch HS 2415 on as an operator 1C04 in the START position.
Report that the pump is operating sat.
to verify RCIC
- Open MO 2426 LUBE OIL COOLER SUPPLY by placing HS 2426 in Running Sat, the OPEN position momentarily and observing proper valve position indication.
When
- If time permits, ensure unnecessary/unauthorized personnel are clear Contacted as a Simulator Operator: of the RCIC Room.
member of the Report that you will begin trouble shooting maintenance and to stand by for direction from the team.
- Initiate Torus water temperature monitoring per STP 3.6.2.1-01. This staff for trouble is only required while heat is being added to the Torus.
shooting BOP Actions Continued Next Page Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 14 of 22
NRC Initial License Exam, Scenario #3 SEG
- 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.
Floor Instructor:
- Verify CV 2410, CV 2411, and CV 2436 Close When the crew determines the One member of the exam team shall wear
- Verify that MO 2510 MIN FLOW BYPASS opens when RCIC Flow is need to perform an STA Badge and take over the STP as less than 80 gpm with pump discharge pressure greater than 125 STP 3.6.2.1-01, the STA. psig.
- Verify HV 2406 TURBINE CONTROL VALVE Governor Valve is throttling to control turbine speed.
- 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.
Examiner Note: Once the RCIC test flow to the CST has been established, commence Event #4.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 15 of 22
NRC Initial License Exam, Scenario #3 SEG Event 4: Simulator Operator: CREW: identify that a RCIC isolation signal is present due to a steak leak in the RCIC room (e.g. high area temperature).
When RCIC ACTIVATE ET 3 flow to the CST This will cause a small leak in the RCIC ATC:
has been Room. Temperatures in the room will not
- Monitor 1C05 indications for Power/Pressure/Level.
established, exceed MAX SAFE limits.
and with
- If Required, attempt to Isolate the RCIC Steam Lines while the BOP is in the direction from back panels area.
the lead BOP: performs the following:
examiner:
- May recognize the
- Acknowledges 1C04B (B-04) STEAM LEAK DET AMBIENT HI TEMP, 1C04C (A-07) References ARP(s).
Simulator Operator:
- Identifies that a valid RCIC isolation signal should be present due to a steam As the extra Inform the crew that a steam leak occurred leak in the RCIC Room.
operator at the in the RCIC Room, the RCIC room was
- Identifies that an automatic RCIC isolation has failed to occur.
RCIC Room evacuated, all personnel are accounted Door, once the for, and that there are no injured
- Manually initiates RCIC isolation by performing the following in accordance with OI-150, Section 7.1 or the applicable ARPs:
High Amb Temp personnel.
alarm sounds, o Closes MO-2400 RCIC INBD STEAM LINE ISOL, and MO-2401 RCIC OUTBD STEAM LINE ISOL.
SRO Actions continued on the next page.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 16 of 22
NRC Initial License Exam, Scenario #3 SEG SRO Actions continued from the previous page.
SIMUATOR OPERATOR SRO: performs the following:
Delete ESW COOLER Blockage
- 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.
If the Chief Examiner request the Entry in to EOP 3, Add malfunctions to prevent o Directs manual isolation of the RCIC system if not already done.
closing the Isolation valves until inplant
- References Technical Specifications to address RCIC system inoperability:
operator actions are taken to reset a o TS 3.5.3, Condition A breaker or thermal overload.
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: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 17 of 22
NRC Initial License Exam, Scenario #3 SEG Event 5: Simulator Operator: when directed by CREW: identifies a trip of the B River Water Supply Pump.
lead examiner River Water Supply Pump ACTIVATE [ET 5] ATC: monitors plant parameters.
spurious trip to cause the B RWS Pump to trip. 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 When contacted Simulator Operator: RWS pump breaker condition.
as the AUX Operator to and inform the control room that the B SRO: directs crew response as follows:
investigate the RWS Pump is hot to touch and that there loss of the B is no smoke and no fire.
- May Enter AOP-410, LOSS OF RIVER WATER SUPPLY RWS Pump, o Update the Online Risk Monitor for the status of River Water Wait 4 Minutes Supply Pumps.
- LCO 3.7.2 met, TS Inop Log entry.
DSM Call Simulator Operator:
Acknowledge the request for support.
EXAMINER NOTE:
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 18 of 22
NRC Initial License Exam, Scenario #3 SEG Event 6: Simulator Operator: perform the following CREW: Will recognize the automatic reactor scram, lowering RPV level, at the direction of the Lead Examiner: lowering RPV pressure, and rising drywell pressure and Enter EOP 1 Large Break and 2 LOCA (Recirc Activate [ET 7]
Suction break) ATC: performs the following:
and verify rr15a activates on ramp with faulted
- Performs IPOI 5 QRC 1, Reactor Scram Immediate Operator Actions:
LPCI auto initiation o Initiates a backup manual reactor scram.
(manual o Places THE MODE SWITCH in SHUTDOWN.
alignment required). o Verifies all control rods fully inserted.
o Verifies main turbine trip Simulator Operator:
o Verifies main generator lockout.
If Contacted as Agree to support required actions an operator in o Verifies neutron flux is lowering.
the plant, o Inserts all functional SRM and IRM detectors.
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 19 of 22
NRC Initial License Exam, Scenario #3 SEG Event 6: Simulator Operator: SRO: directs crew actions as follows:
Large Break ROLE PLAY: if contacted as Equipment
LOCA (Recirc Operator, perform required component o Recognizes the failed ECCS initiation (LPCI) and directs Suction break) manipulations and make appropriate action to establish LPCI injection (CRITICAL TASK).
with faulted reports to the Control Room.
o Implements the ALC Leg of EOP 1 RC/L:
LPCI auto initiation Recognizes that RPV water level cannot be (manual maintained >+15 inches (TAF).
alignment Assesses available ECCS injection sources required). appropriately and transitions correctly.
o Implements RC/P.
- Implements EOP 2, Primary Containment Control:
o Implements T/L.
o Implements T/T:
Aligns RHR for Suppression Pool Cooling as required.
o Implements DW/T:
Determines that Drywell cannot be maintained <150°F and maximizes drywell cooling.
o Implements PC/P:
Determines that Primary Containment pressure cannot be maintained less than 2.0 psig and ensures that Drywell and Torus sprays are operated appropriately.
Add ED?
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 20 of 22
NRC Initial License Exam, Scenario #3 SEG Event 6: Simulator Operator: BOP: performs plant EOP operations as directed by the SRO. Aligns systems (RHRSW, RHR, etc.) and reports trends as required.
Large Break ROLE PLAY: if contacted as Equipment LOCA (Recirc Operator, perform required component Suction break) manipulations and make appropriate
- Identifies failure of automatic LPCI alignment and injection and with faulted reports to the Control Room. manually aligns LPCI injection by starting RHR pumps and LPCI auto opening valves as necessary (CRITICAL TASK).
initiation (manual alignment required).
EXAMINER NOTE: when sufficient crew execution of the EOPs has been observed, then the scenario may be terminated.
- END OF SCENARIO ***
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 21 of 22
[SEG #], [Title], [Rev. ] SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS THIS SECTION IS ONLY REQUIRED FOR EVALUATED SCENARIOS.
DISCUSSION ITEMS Insert any additional Discussion Points to be made after scenario completion. See Discussion Point discussion in the Expected Student Response column of the Simulator Exercise Guide Scenario Instructions three-column template above.
QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
1.
2.
After EOP Entry:
1.
2.
Abnormal Events:
1.
2.
Major Transients:
1.
2.
Critical Tasks:
- 2. Starts the A SBDG manually to power only safety-related electrical bus
Filename: Scenario 3 rev 1-1 TR-AA-230-1003-F06 Revision 0 Page 22 of 22
JOB PERFORMANCE MEASURE JPM Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant I 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:
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 Date TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant I
[J VENT THE SCRAM AIR HEADER 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?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees 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 I
[J VENT THE SCRAM AIR HEADER 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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant I
[J VENT THE SCRAM AIR HEADER 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 I
[J VENT THE SCRAM AIR HEADER 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.
INITIATING CUES (IF APPLICABLE):
- 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 I
[J VENT THE SCRAM AIR HEADER 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 examinees 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 Close V-17-61 (Scram Pilot Air Header Isolation Vlv).
Critical Y (SEQ-)
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 I
[J VENT THE SCRAM AIR HEADER Performance Step: 2 Remove the pipe plug located downstream of V-17-174, (PI-Critical Y (SEQ-) 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 Open V-17-174, (PI-184/PS1842 Test Connection Isolation valve).
Critical Y (SEQ-)
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 I
[J VENT THE SCRAM AIR HEADER Performance Step: 4 Communicates actions to control room.
Critical N (SEQ-)
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 Question and Answer:
Critical N (SEQ-) 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 I
[J VENT THE SCRAM AIR HEADER Performance Step: 6 Restoration: Close V-17-174, (PI-184/PS1842 Test Connection Isolation Critical Y (SEQ-) 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 Restoration: Reinstall the pipe plug downstream of V-17-174.
Critical Y (SEQ-)
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 I
[J VENT THE SCRAM AIR HEADER Performance Step: 8 Restoration: Open V-17-61, Scram Pilot air header isolation valve.
Critical Y (SEQ-)
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.
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 I JPM VENT THE SCRAM AIR HEADER 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.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees 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.
INITIATING CUES (IF APPLICABLE):
- 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 J 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: 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: X To be performed in the Training Building prior to the In Plant portion of the JPM, In Plant Lab:
portion is required after the Task.
Time for Completion: 40 Minutes Time Critical: NO Alternate Path [NRC]: NO Alternate Path [INPO]: NO Developed by:
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 Date TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant J JPM OPERATE RCIC FROM 1C208 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?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees 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 J JPM OPERATE RCIC FROM 1C208 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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant J JPM OPERATE RCIC FROM 1C208 Page 5 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
- 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.
- 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 J JPM OPERATE RCIC FROM 1C208 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 J JPM OPERATE RCIC FROM 1C208 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 examinees 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 NOTE Critical N (SEQ-) 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 2. If directed by CRS to take manual control of RCIC (if running) at Critical Y (SEQ-) 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 J JPM OPERATE RCIC FROM 1C208 Page 8 of 13 Performance Step: 3 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 Critical N (SEQ-) 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 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 Critical Y (SEQ-) 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 J JPM OPERATE RCIC FROM 1C208 Page 9 of 13 Performance Step: 5 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 Critical N (SEQ-) 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:
TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant J JPM OPERATE RCIC FROM 1C208 Page 10 of 13 Performance Step: 6 2. If directed by CRS to take manual control of RCIC (if running) at 1C208 Critical Y (SEQ-) perform the following:
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:
Performance Step: 7 After the completion of the above portion of the task, the operator is Critical Y (SEQ-) 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 or describe its location.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
2015 NRC In Plant J JPM OPERATE RCIC FROM 1C208 Page 11 of 13 When the operator has taken control of the RCIC Turbine at 1C208 Terminating Cues: AND When the operator has demonstrated knowledge of the location of the 1C208 Panel in the plant.
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 J JPM OPERATE RCIC FROM 1C208 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.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees 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 18 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2015 NRC In Plant K TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
JOB PERFORMANCE MEASURE JPM Page 2 of 18 JPM TITLE: Shutdown of Regulating Transformer 1Y1A for Maintenance JPM NUMBER: 262002-05 REV. 0 TASK NUMBER(S) / 28.10 (NSPEO)/
TASK TITLE(S): 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:
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 Date Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 3 of 18 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?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees 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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 4 of 18 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.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 5 of 18 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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 6 of 18 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.
- 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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 7 of 18 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 examinees 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 At Panel 1Y36, verify the RPS alternate power supply source is not selected to Critical N 1Y16 [1Y26]
OI 317.1, Section 5.5, Step (1)
Standard: Determines that RPS alternate power supply source is on 1Y2A in accordance with the Initial Conditions.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 If necessary, transfer the RPS alternate power supply source to 1Y2A [1Y1A]
Critical N per OI 358.
OI 317.1, Section 5.5, Step (1)(a)
Standard: Based on the Initial Conditions, this action is not necessary.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 8 of 18 Performance Step: 3 If necessary, start up and transfer load to Inverter 1D15 per Critical N Section 3.5, or transfer loads to an operating inverter per Section 4.2.
OI 317.1, Section 5.5, Step (2)
Standard: This step is a turnover item. 1D15 is in service. Student marks the step as N/Ad.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET Critical N pushbutton.
OI 317.1, Section 5.5, Step (3)
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 9 of 18 Performance Step: 5 At 1D15[1D25] open right cabinet door and place inverter ALARM BYPASS Critical Y SWITCH to BYPASS.
OI 317.1, Section 5.5, Step (4)
Standard: Place the ALARM BYPASS SWITCH to BYPASS.
Evaluator Note: The safety gear is located in a locker in the battery room hallway. The Aux man has a key on a ring that gets him/her into the locker.
To achieve this task, a face shield and gloves are adequate, more may be chosen to wear.
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 10 of 18 Performance Step: 6 Confirm the FORWARD TRANSFER light is ON.
Critical N OI 317.1, Section 5.5, Step (5)
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 At 1Y15 [1Y25], confirm switch 1Y1504 [1Y2504] in the INVERTER position.
Critical N (1Y15 [1Y25] MAINTENANCE SWITCH)
OI 317.1, Section 5.5, Step (6)
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 11 of 18 Performance Step: 8 CAUTION Critical N Opening or closing of breaker 1Y1503 [1Y2503] could result in a Reactor Recirc OI 317.1, Section 5.5, A[B] MG Set Scoop Tube lockup due to a problem in the scoop tube positioner Step (7) CAUTION 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 Lock the Reactor Recirc A[B] MG Set Scoop Tube per OI 264 (Reactor Recirc Critical Y System).
OI 317.1, Section 5.5, Step (7)
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 12 of 18 Performance Step: 10 Turn circuit breaker 1Y1503 [1Y2503] OFF. (REGULATING TRANSFORMER Critical Y 1Y1A [1Y2A] SUPPLY TO JS1501 [JS2501])
OI 317.1, Section 5.5, Step (8)
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 At 1Y1A [1Y2A], turn circuit breaker 1Y1A02 [1Y2A02] OFF.
Critical Y (REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO 1Y16 [1Y26])
OI 317.1, Section 5.5, Step (9)
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 13 of 18 Performance Step: 12 Turn circuit breaker 1Y1A01 [1Y2A01] OFF.
Critical Y (REGULATING TRANSFORMER 1Y1A [1Y2A] INPUT)
OI 317.1, Section 5.5, Step (10)
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 At 1B32 [1B42], turn circuit breaker 1B3216A [1B4203A] OFF.
Critical Y (REGULATING TRANSFORMER 1Y1A [1Y2A] AC SUPPLY)
OI 317.1, Section 5.5, Step (11)
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 14 of 18 Performance Step: 14 Reset the Reactor Recirc A[B] MG Set Scoop Tube as directed by the Critical Y OSM/CRS per OI 264 (Reactor Recirc System).
OI 317.1, Section 5.5, Step (12)
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:
When breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, Terminating Cues:
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 k TR-AA-230-1003-F10 Revision 2
2015 NRC In Plant K SHUTDOWN OF REGULATING TRANSFORMER 1Y1A FOR JPM MAINTENANCE Page 15 of 18 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.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
JPM Page 16 of 18 Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
JPM Page 17 of 18 Picture 2 Filename: 2015 NRC Exam In Plant k TR-AA-230-1003-F10 Revision 2
Page 18 of 18 TURNOVER SHEET INITIAL CONDITIONS:
- 1Y1A Regulating Transformer requires maintenance.
- 1D15 Instrument AC Inverter is in operation.
- 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 k TR-AA-230-1003-F10 Revision 2