ML092860258
| ML092860258 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/13/2009 |
| From: | NRC/RGN-II |
| To: | Carolina Power & Light Co |
| References | |
| 50-261/09-301 50-261/09-301 | |
| Download: ML092860258 (31) | |
Text
FACILITY NAM E: _ _..:.R;:,;:o;,:b;.:,:in.:.:s:,:o:.:.,:n:.....-_ _ __ Section 9 REPORTNUMBER: __-=20~O~9~-3~O~1_________________
FINAL SRO WRITTEN EXAM CONTENTS:
[5 Final SRO Written Exam (25 'as given' questions with changes made during administration annotated)
~Reference Handouts Provided To Applicants o AI,sWer ttey Z,.J !2-0 S ~
Location of Electronic Files:
Submitted By: ~ Verified By: ~
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: Facility/Unit:
Region: I 0 II 0 III 0 IV 0 Reactor Type: WD CE D BWDGE D Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values / -- / -- Points Applicant's Scores / -- / -- Points Applicant's Grade / -- / -- Percent
(
ES-401, Page 31 of 33
ILC-09 NRC Exam 76.
Given the following:
- Unit is in Mode 3 at 547°F.
- PZR PORV, PCV-456 fails partially open and when it's control switch was taken to CLOSE, nothing happened.
- AOP-019, Malfunction of RCS Pressure Control, has been entered and RCS pressure has been stabilized.
Which ONE (1) of the following describes the actions and status of PZR PORV operability?
Isolate the PZR PORV by closing PZR PORV Block valve RC-535 AND ..... .
A. remove power.
PZR PORV is inoperable with the plant in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.
B. remove power.
PZR PORV is operable since safety function is maintained.
C. leave energized.
PZR PORV is inoperable with the plant in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.
D. leave energized.
PZR PORV is operable since safety function is maintained.
76
ILC-09 NRC Exam 77.
Given the following:
- Plant was at 100% RTP.
- All Main Feedwater was lost.
- The crew is monitoring RTGB indications associated with the loss of feedwater.
Which ONE (1) of the following lists of instrumentation can be relied upon for monitoring lAW Reg. Guide 1.97 and are Type A, Category 1 variables?
Edgewise indicator(s) for the following:
A. NR S/G level Condensate header pressure B. WR S/G level Condensate header pressure C. NR S/G level CST Level D. WR S/G level CST Level 77
ILC-09 NRC Exam 78.
Given the following:
- A Station Blackout has occurred from 100% RTP.
- The crew is performing actions of EPP-1, Loss of All AC Power. Immediate actions are complete.
- "A" CCW pump is running.
- Offsite power is restored and the START UP TRANSF ENERGIZED white light is ILLUMINATED.
Which ONE (1) of the following describes the procedural guidance for restoring power from offsite AND which lockout(s) will have to be reset to accomplish this electrical lineup?
A. OP-602, Dedicated Shutdown System. VERIFY Main Generator Lockouts 86P and 86BU have been reset.
B. OP-602, Dedicated Shutdown System. VERIFY the 115 KV Span Bus Lockout has been reset.
C. OP-603, Electrical Distribution. VERIFY Main Generator Lockouts 86P and 86BU have been reset.
D. OP-603, Electrical Distribution. VERIFY the 115 KV Span Bus Lockout has been reset.
78
ILC-09 NRC Exam 79.
Given the following:
- Unit operating in Mode 1 at 35% RTP.
- 125V DC Bus B has been lost due to faulty straps between the bus and batteries.
- PATH-1 has been entered for Reactor Trip.
Which ONE (1) of the following describes the plant control power that is lost and the procedure transition required?
Control power has been lost to 4KV Buses (1) . Entry to EPP-27, Loss of DC Bus B will be from (2)
A. 3 &4 EPP-4, Reactor Trip Response B. 3 &4 EPP-7, SI Termination C. 1 &2 EPP-4, Reactor Trip Response D. 1 &2 EPP-7, SI Termination 79
ILC-09 NRC Exam 80.
Given the following:
- Plant is operating under a Reliability Alert due to numerous base load plants being out of service.
- APP-009-D7, GEN LO FREQ, is in alarm.
- The Load Dispatcher has notified the Control Room crew that all spinning reserves have been loaded.
- Main generator frequency is 59.1 Hz and stable.
- Reactor power had increased to 101 % and the BOP operator reduced turbine load using the limiter. Reactor power is currently at 98.5% and stable.
- Generator parameters are currently as follows: GEN Phase A Phase B Volts =
22KV, GEN Phase CAmps = 21.9KA.
- The Load Dispatcher has requested maximum power generation.
Which ONE (1) of the following describes the appropriate response to the Load Dispatcher? (Reference Provided)
At the current main generator frequency, ..... .
A. load must be reduced on the generator, but will be able to remain on line.
B. load must be reduced on the generator, but Reactor Trip will be required in 5 minutes.
C. generator capability is available, and power could be increased to 100% load.
D. generator capability is available, but Reactor Trip will be required in 5 minutes.
80
ILC-09 NRC Exam 81.
Given the following:
- Reactor trip has occurred due to both Main Feedwater Pump motors being grounded out.
- All AFW Pumps fail to start.
- PATH-1 has been entered and transition to EPP-4, Reactor Trip Response, has been made.
- SPDS has been reset, CSFST monitoring has been initiated and the crew has been directed to enter FRP-H.1, Response to Loss of Secondary Heat Sink.
- Wide Range S/G levels are at 28% and lowering.
Which ONE (1) of the following describes the actions required to restore a heat sink lAW FRP-H.1?
A. Initiate SI, then open ONLY ONE (1) PZR PORV to establish RCS bleed and feed operation.
B. Initiate SI, then open BOTH PZR PORVs to establish RCS bleed and feed operation.
C. Depressurize ALL S/Gs to between 240 - 600 psig to allow the Condensate System to refill the S/Gs.
D. Depressurize ONLY ONE (1) S/G to between 240 - 600 psig to allow the Condensate System to refill the S/G.
81
ILC-09 NRC Exam 82.
Given the following:
- Plant is in MODE 1.
- OST-011, Rod Cluster Control Exercise and Rod Position Indication, is in progress with testing of Control Bank D.
- The RO is withdrawing Control Bank 0 rods to restore them to their pretest position.
- The RO releases the IN-HOLD-OUT lever.
Which ONE (1) of the following would indicate an uncontrolled rod withdrawal event is in progress AND the maximum initial power level required for the performance of this test lAW OST-011?
A turbine runback would occur due to (1) . Reactor power less than (2)
A. (1 ) Overpower Delta T bistables actuating from the Tave increase (2) 98%
B. (1 ) Overtemperature Delta T bistables actuating from the PZR Pressure increase
( (2) 98%
C. (1 ) Overpower Delta T bistables actuating from the Tave increase (2) 90%
D. (1 ) Overtemperature Delta T bistables actuating from the PZR Pressure increase (2) 90%
82
ILC-09 NRC Exam 83.
Given the following:
- Plant in MODE 1 at 100% RTP.
- R-20, Fuel Handling Building Lower Level annunciates.
- Inside AO has been dispatched to investigate.
- The Inside AO reports that the "in service" WGDT is depressurizing.
Which ONE (1) of the following describes the procedural entry required and actions that must be accomplished to mitigate this event?
A. AOP-009, Accidental Gas Release from a WGDT.
Start HVE-15A, FUEL HANDLING BUILDING EXHAUST FAN and place leaking WGDT in Standby.
B. AOP-009, Accidental Gas Release from a WGDT.
Start HVE-5A OR HVE-5B, AUX BLDG CHARCOAL EXH FAN and place leaking WGDT on Cover Gas.
C. AOP-005, Radiation Monitoring System.
Start HVE-15A, FUEL HANDLING BUILDING EXHAUST FAN and place leaking WGDT in Standby.
D. AOP-005, Radiation Monitoring System.
Start HVE-5A OR HVE-5B, AUX BLDG CHARCOAL EXH FAN and place leaking WGDT on Cover Gas.
83
ILC-09 NRC Exam 84.
Given the following:
- Plant is operating in Mode 1 at 100% RTP.
- Fuel failure of> 0.1 % and < 1.0% has been detected through the RCS chemistry sample.
Which ONE (1) of the following describes the proper R-9 radiation monitor response to the given conditions?
R-9 monitor should read ........... .
A. 0.25 R/hr.
B. 1.0 R/hr.
C. 25 R/hr.
D. 100 R/hr.
84
ILC-09 NRC Exam 85.
Given the following:
- PATH-1 has been implemented following a steam line break inside the CV.
- The step has been reached which requires stopping CV Spray pumps.
Which ONE (1) of the following describes the reason for stopping CV Spray pumps and the basis for the actions required for the CV Spray Pump Discharge Valves lAW PATH-1?
Securing the pumps prevents .....
A. RWST depletion.
Positions the valves for immediate re-initiation of Spray if required.
B. pump runout.
Ensures CV isolation and prevents gas binding of the pumps.
C. pump runout.
Positions the valves for immediate re-initiation of Spray if required.
D. RWST depletion.
Ensures CV isolation and prevents gas binding of the pumps.
85
ILC-09 NRC Exam 86.
Given the following:
- Plant is operating in Mode 1 at 98% RTP.
- RCS Loop 3 Tave I Delta T has been removed from service lAW OWP-028, T I Delta T-3 due to a failure of the cold leg RTD.
- I&C personnel are currently working on repairs and project that the work will not be completed for another 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> due to the RTD testing in a bath at the I&C lab.
- I&C Supervisor has just notified the CRSS that a recently completed calibration on Power Range channel N-41 has a module that fell outside of its tolerance band and N-41 is inoperable.
Which ONE (1) of the following minimum actions is required to maintain compliance with ITS?
A. Reduce reactor power to ~ 75% RTP within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
- 8. Place the plant in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
C. Reduce reactor power to ~ 75% RTP within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. Place the plant in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
86
ILC-09 NRC Exam 87.
Given the following:
- Mode 1 at 100% RTP.
- The reactor has been tripped and SI initiated due to a steam line break inside Containment on the "A" S/G.
- Transition has been made to EPP-11, Faulted Steam Generator Isolation.
Which ONE (1) of the following statements is a bases for steps that isolate feed flow to and steam flow from the faulted S/G lAW EPP-11 SO?
A. Allows maximum cooldown capability of the non-faulted S/Gs.
S. Minimizes mass and energy releases to Containment.
C. Minimizes radiological releases to Containment.
O. Allows a faster repressurization of the RCS.
87
ILC-09 NRC Exam 88.
Given the following:
- Mode 6 with core offload in progress to the Spent Fuel Pit.
- Maintenance has requested permission to change 4 battery cells on Station Battery A.
Which ONE (1) of the following describes the operational limitations and ITS LCO requirements for this maintenance activity?
A. Fuel movement must be stopped.
DC Train A will be inoperable when the battery cell is disconnected.
B. Fuel movement must be stopped.
The unit will be in a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO action statement during the cell changeout.
C. Fuel movement may continue.
No LCO applies provided that an A Train Battery Charger is supplying DC Bus A.
D. Fuel movement may continue.
No LCO applies provided that DC Bus B is operable.
88
ILC-09 NRC Exam 89.
Given the following:
- Plant in Mode 1 at 100% RTP.
- A hostile attack has resulted in damage to the intake structure and the loss of ALL SeNice Water Pumps.
- EPP-4, Reactor Trip Response, was entered.
Which ONE (1) of the following describes the required procedure transition and what actions are taken to support critical equipment?
A. EPP-28, Loss of Ultimate Heat Sink Oeepwell Pump 0 is aligned to ONE (1) EOG.
B. EPP-28, Loss of Ultimate Heat Sink Oeepwell Pump 0 is aligned to BOTH EOGs.
C. AOP-022, Loss of SeNice Water Align Unit #1 Deepwell Pump to supply seal and bearing cooling to the Circulating Water Pumps.
D. AOP-022, Loss of SeNice Water Align emergency cooling to the Motor Driven AFW Pump oil coolers.
89
ILC-09 NRC Exam 90.
Given the following:
- Unit is currently in Mode 3 with GP-007, Plant Cooldown from Hot Shutdown to Cold Shutdown, in progress.
Which ONE (1) of the following describes the procedural controls for CV entries and any restrictions that apply to the scope of the activities?
A. PLP-006, Containment Vessel Inspection / Closeout, controls the entries.
Prestaging of equipment must meet the requirements of PLP-006 until Mode 5 is entered.
B. PLP-006, Containment Vessel Inspection / Closeout, controls the entries.
Prestaging of equipment is NOT allowed until the unit has entered Mode 5.
C. OMM-033, Implementation of CV Closure, controls the entries.
Prestaging of equipment must meet the requirements of OMM-033 until Mode 5 is entered.
D. OMM-033, Implementation of CV Closure, controls the entries.
Prestaging of equipment is NOT allowed until the unit has entered Mode 5.
90
ILC-09 NRC Exam 91.
Given the following:
- Unit in Mode 1 at 100% RTP.
- R-12, Containment Radioactive Gas Monitor, is in service.
- OWP-002, CV-2, for Containment Purge Supply Inner Valve, was implemented to repair an Instrument Air fitting leak on V12-7, Containment Purge Supply Inner Valve, discovered during a Containment entry.
- Maintenance has now been completed and PMT requires a Containment Purge to return the valve to service.
R-11, Containment Particulate R-14C, Main Vent Stack (Low Range Noble Gas)
Which ONE (1) of the following describes additional instrumentation required to be in operation to meet the minimum required instrumentation to place the CV Purge in service lAW OP-921, Containment Air Handling?
A. None. R-12 is sufficient.
B. R-11 ONLY.
C. R-14C ONLY.
D. R-11 and R-14C.
91
ILC-09 NRC Exam 92.
Given the following:
- Waste Condensate Tank "A" is being prepared for release.
- Tank pH was sampled and found to be too low.
Which ONE (1) of the following describes the impact of this sample on the recirculation requirements and the adjustments necessary for tank pH prior to release lAW OP-705, Waste Liquid Release and Recirculation, and the National Pollutant Discharge Elimination System (NPDES)?
The Tank must be recirced for .....
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the pH adjusted to > 6.0.
B. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and the pH adjusted to > 6.0.
C. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the pH adjusted to > 5.0.
D. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and the pH adjusted to > 5.0.
92
ILC-09 NRC Exam 93.
Given the following:
- The Waste Gas System is aligned with Waste Gas Decay Tank (WGDT) B in Standby.
- The Inservice WGDT pressure is increasing due to current sluicing operations with the Spent Resin Storage Tank.
- Oxygen sample results are 4.5%.
Which ONE (1) of the following describes the method pressure will be controlled in the "In Service" WGDT and what action is required for the oxygen concentration lAW TRM 3.20?
A. Standby WGDT will be automatically placed in service at 110 psig.
Restore oxygen concentration to less than 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
B. Standby WGDT will be automatically placed in service at 80 psig.
Restore oxygen concentration to less than 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
C. Standby WGDT must be manually placed in service at 110 psig.
Restore oxygen concentration to less than 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
D. Standby WGDT must be manually placed in service at 80 psig.
Restore oxygen concentration to less than 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
93
ILC-09 NRC Exam 94.
Given the following:
- Plant in MODE 1 at 100% RTP.
- EDG A is being tested lAW OST-401-1, EDG A Slow Speed Start.
- The EDG is loaded to maximum continuous load.
- The first set of data for Attachment 10.2, Emergency Diesel Generator Data Sheet, has the cylinder temperatures listed below:
- 1. 10BooF 2. 10950 F 3. 11000 F 4. 11070 F 5. 11200 F 6. 11420 F
- 7. 10750 F B. 10900 F 9. 11450 F 10. 11300 F 11. 11100 F 12. 113BoF As the data is being reviewed for acceptance criteria, Service Water Pump C trips.
Which ONE (1) of the following describes the operability of the EDG based on the cylinder temperatures and ITS requirements? (Reference provided)
EDG A. ..........
A. shall be declared INOPERABLE based on these cylinder temperatures. Remain in LCO 3.B.1 Condition B and restore operability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. shall be declared INOPERABLE based on these cylinder temperatures. Remain in LCO 3.B.1 Condition B and declare redundant features supported by the inoperable EDG inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
C. is OPERABLE based on these cylinder temperatures. Remain in LCO 3.B.1 Condition B and restore operability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. is OPERABLE based on these cylinder temperatures. Remain in LCO 3.B.1 Condition B and declare redundant features supported by the inoperable EDG inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
94
ILC-09 NRC Exam 95.
Given the following:
- Unit in Mode 6 for refueling outage.
- The letdown line has been removed from service and cleared for maintenance.
- Maintenance personnel have welded several new vent valves in the letdown line.
- An approved procedure has been provided with the work order package to perform the line hydrostatic test following installation.
- A clearance boundary change must be implemented to initiate the system hydrostatic test.
Complete the statement below to remain in compliance with procedure OPS-NGGC-1301, Equipment Clearance.
The Principal Clearance Holder and (1) will determine the Affected Employees for the clearance boundary change and (2) will provide concurrence for the Maintenance personnel to introduce fluids into the clearance boundary for the system hydrostatic test.
A. (1) an SRO (2) a WCC SRO B. (1) a Maintenance Supervisor (2) a CRSS C. (1) an SRO (2) a CRSS D. (1) a Maintenance Supervisor (2) a WCC SRO 95
ILC-09 NRC Exam 96.
Given the following:
- The plant is in No Mode with all fuel offloaded to the SFP.
- Cooling has been lost to the SFP Heat Exchanger.
Which ONE (1) of the following procedures provides available contingency procedures to implement for this loss of decay heat removal AND which procedure is referenced for this condition?
A. OMM-048, Work Coordination and Risk Assessment AOP-014, CCW System Malfunction B. OMM-046, Control of Key Safety Functions During Shutdown AOP-014, CCW System Malfunction C. OMM-048, Work Coordination and Risk Assessment AOP-036, SFP Events D. OMM-046, Control of Key Safety Functions During Shutdown AOP-036, SFP Events 96
ILC-09 NRC Exam 97.
Given the following:
- Waste Condensate Tank "A" is going to be released.
- R-18, Liquid Waste Disposal Effluent, is in service and it's setpoint is set for the value on the Liquid Waste Release Permit.
- WD-1785, Liquid Waste Release Manual Isolation, has been unlocked and opened.
- WD-17858, FIT-1064 throttle valve, has been throttled lAW the Waste Release Permit and the WCT Pump has been started.
- Estimated release time for this release is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
Which ONE (1) of the following describes ODCM Section 2.6 required actions if FIT-1064, Waste Discharge Flowmeter, becomes inoperable during the release?
The release ..... .
A. may continue as long as flowrate is estimated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during release. .
- 8. may continue as long as flowrate is estimated at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during release.
C. must be terminated. 2 independent samples required prior to release via this pathway.
D. must be terminated. 2 personnel must independently verify the lineup prior to release via th is pathway.
97
ILC-09 NRC Exam 98.
Given the following:
- A General Emergency has been declared.
- All Emergency Response Facilities have been activated.
- A mechanic must be dispatched from the Operations Support Center to the Pipe Alley into a radiation field of 120 Rem/hr to isolate the pathway from the CV to terminate the release point.
- The Pipe Alley entry is projected to take 15 minutes.
- 80th available volunteers have been briefed on the risks involved.
Mechanic "A" is 49 years old Mechanic "8" is 35 years old Which ONE (1) of the following describes the individual that should be selected to perform the assigned task lAW EPOSC-04, Emergency Work Control, and who will authorize the entry?
Mechanic (1) should be chosen. The (2) will authorize the entry.
A. (1 ) "All (2) Emergency Response Manager (ERM)
B. (1 ) IIA" (2) Site Emergency Coordinator (SEC)
C. (1 ) 118" (2) Emergency Response Manager (ERM)
D. (1 ) "8" (2) Site Emergency Coordinator (SEC) 98
ILC-09 NRC Exam 99.
During the implementation of the EOP network foldout procedures, which ONE (1) of the following describes the responsibilities and required actions of the CRSS lAW OMM-022, Emergency Operating Procedures User's Guide?
As a minimum, the CRSS is required to review the ..... .
A. headers of the criteria contained in each foldout with the crew when the foldout becomes applicable. ONLY 1 foldout is applicable at any given time.
B. headers of the criteria contained in each foldout with the crew when the foldout becomes applicable. Once a foldout is applicable, it and all subsequent foldouts remain in effect until the EOP network is exited.
C. individual criteria contained in each foldout with the crew when the foldout becomes applicable. ONLY 1 foldout is applicable at any given time.
D. individual criteria contained in each foldout with the crew when the foldout becomes applicable. Once a foldout is applicable, it and all subsequent foldouts remain in effect until the EOP network is exited.
99
ILC-09 NRC Exam 100.
Given the following:
- Plant in Mode 1 at 100% RTP.
- RCS leakage of 80 gpm has been determined.
- Loss of Offsite Power in coincidence with a steam line break in the CV occurred 20 minutes ago.
- EDG B failed to start and CANNOT be started.
- Due to a flange leak, flow for the CV Air Recirc Coolers is as follows:
- HVH-1 is 900 GPM
- HVH-2 is 650 GPM
- HVH-3 is 875 GPM
- HVH-4 is 900 GPM
- CV Pressure is 15 psig.
- RVLlS Full Range level is 91 %.
- CSFST status: Subcriticality - GREEN Core Cooling - YELLOW Heat Sink - YELLOW RCS Integrity - GREEN Containment - YELLOW Inventory - YELLOW Which ONE (1) of the following describes the current Emergency Action Level (EAL) classification? (Reference Provided)
A. Site Area Emergency - Loss of power.
B. Site Area Emergency - Loss or potential loss of any 2 Fission Product Barriers.
C. Alert - Loss of power.
D. Alert - Loss or potential loss of either Fuel Clad or RCS.
(
100
References:
ILC09 NRC Written Exam
Rev. 9 AOP-026 GRID INSTABILITY Page 12 of 14 ATTACHMENT 1 (Page 1 of 1)
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1.011
, .010
~ ** ~.R***~..m~mU~i~II~IIII.8Iml~mll~m~IIII~II~1 IIItIHI/lf 2200 2220 2240 22.0 UIO 2200 2UO 2340 UIO 2310 2400 2420 2440 2410 2410 nOO 2520 21'
.. 0 2110 2110 2100 I OST-401-1 Rev. 39 Page 48 of 51
Emergency Action Level Matrixes
- HOT Conditions - Rev. 2
- ALL Conditions - Rev. 2
. Provided as Separate Handouts