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{{#Wiki_filter:}} | {{#Wiki_filter:Question:(1 point)1ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The "A" Reactor Trip Bypass Breaker has been placed in service for testing*The "A" Reactor Trip Breaker has been removed from service*A transient condition exists requiring a reactor trip*The OAC depresses the manual reactor trip pushbutton prior to an RPS setpoint beingreachedWhich ONE of the following describes the plant response? The "A" Reactor Trip Bypass Breaker opens due to actuation of its ____(1)____ and the "B" Reactor Trip Breaker opens due to actuation of its ____(2)____. A. (1) UV trip, ONLY (2) UV trip, ONLYB. (1) UV trip, ONLY (2) UV and shunt trip C. (1) UV and shunt trip (2) UV trip, ONLY D. (1) UV and shunt trip (2) UV and shunt trip Page 1 of 75 Question:(1 point)2ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | ||
* The plant is operating at 100% power | |||
* A transient results in both Pressurizer PORVs opening and sticking OPEN after pressure lowers below the OPEN setpoint | |||
* When the operator attempts to close the Block Valves for each PORV, the OATC observes that the status lights for Block Valves RC-535 and RC-536 are all EXTINGUISHED Subsequently, the CRS directs that the power to each Block Valve be restored. RC-535, Block Valve to Pressurizer PORV PCV-456 RC-536, Block Valve to Pressurizer PORV PCV-455C Which ONE of the following identifies the location(s) to which the operator must be dispatched to close the breakers for the Block Valves? The operator must proceed to-- A. MCC-5 for BOTH RC-535 and RC-536 B. MCC-5 for RC-535; and MCC-6 for RC-536 C. MCC-5 for RC-536; and MCC-6 for RC-535 D. MCC-6 for BOTH RC-535 and RC-536 Page 2 of 75 Question:(1 point)3ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*"A" CV Spray pump is out of service for maintenanceSubsequently: *A SBLOCA occurred at 0930 coincident with a Loss of Offsite Power*"B" EDG tripped immediately after starting*At 1000, the crew is performing the actions of EOP-E-1, LOSS OF REACTOR ORSECONDARY COOLANT with the following current plant conditions:*CV pressure: 11 psig and rising slowly*CV Sump level: 178 inches and rising*CV radiation level: 0.5 R/hr*"A" Loop Cold Leg temperature: 338 °F*"B" Loop Cold Leg temperature: 425 °F*"C" Loop Cold Leg temperature: 427 °FWhich ONE of the following correctly completes the statements below? CSF-4 Integrity critical safety function status tree color is ____(1)____. CSF-5 Containment critical safety function status tree color is ____(2)____. A. (1) Yellow (2) Yellow B. (1) Orange (2) Yellow C. (1) Yellow (2) Orange D. (1) Orange (2) Orange Page 3 of 75 Question:(1 point)4ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power a Large Break LOCA occursWhich ONE of the following correctly completes the statements below? IAW EOP-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION entry conditions, the HIGHEST allowable RWST level before transfer to Cold Leg Recirculation is required is ____(1)____. The reason that the above switchover criteria is established is to ensure that core flow can be maintained using one ____(2)____ pump taking suction on the RWST during realignment to the CV sump. A. (1) 19% (2) SI B. (1) 19% | |||
(2) RHR C. (1) 27% (2) SI D. (1) 27% | |||
(2) RHR Page 4 of 75 Question:(1 point)5ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The "A" Charging pump is operating in AUTO | |||
* The following annunciators alarm in the control room, all within 30 seconds: | |||
* APP-001-B4, RCP SEAL INJECTION HI/LO FLOW | |||
* APP-001-B6, LP LTDN LN HI TEMP | |||
* APP-001-D6, LP LTDN HI PRESS | |||
* APP-001-E6, LP LTDN RELIEF HI TEMP Which ONE of the following identifies the cause of these alarms? A. Seal Injection Filter clogged B. HCV-121, Charging Flow Valve failed closed C. TCV-144, NRHX Temperature Control Valve failed closed D. CVC-204A, Letdown Line Isolation Stop Valve failed closed Page 5 of 75 Question:(1 point)6ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant cooldown is in progress | |||
* The "A" RHR Train is in service | |||
* At 0700 RCS temperature was 130°F Subsequently, cooling water flow is interrupted to the "A" RHR Heat Exchanger and the following is observed: Time RCS Temp 0715 146 0730 162 0745 178 Which ONE of the following correctly completes the statements below? If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 Mode 4 ____(1)____ be entered. | |||
If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 the Technical Specification Heat up limit ____(2)____ be exceeded. (REFERENCES PROVIDED)A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 6 of 75 Question:(1 point)7ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* A Pressurizer pressure instrument has failed resulting in the following: | |||
* All Pressurizer heaters are energized | |||
* RCS pressure is 2270 psig and rising Which ONE of the following correctly completes the statement below? Pressurizer Pressure channel ____(1)____ has failed LOW. | |||
Pressurizer PORV ____(2)____ will cycle open and closed to limit the RCS pressure rise. A. (1) PT-444 (2) PCV-455C B. (1) PT-444 (2) PCV-456 C. (1) PT-445 (2) PCV-456 D. (1) PT-445 (2) PCV-455C Page 7 of 75 Question:(1 point)8ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An ATWS has occurred | |||
* Immediate Actions of FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, are in progress Which ONE of the following correctly completes the statements below? Opening a MINIMUM of ____(1)____ breaker(s) in the Rod Drive MG Set Room will result in a reactor trip. OR Opening a MINIMUM of ____(2)____ breaker(s) in the 4 KV Room will result in a reactor trip. A. (1) one (2) one B. (1) one (2) two C. (1) two (2) one D. (1) two (2) two Page 8 of 75 Question:(1 point)9ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A SGTR has occurred | |||
* The crew has entered EOP-E-3, STEAM GENERATOR TUBE RUPTURE | |||
* The Subcooled Margin Monitor is OOS | |||
* The crew has initiated an RCS cooldown using the Steam Dumps to a target CET temperature Which ONE of the following correctly completes the statements below? The operator will open the steam dumps to cooldown at ____(1)____. | |||
Subsequently: | |||
* The RCS cooldown is completed | |||
* CET Temperature is being maintained at 510°F | |||
* Ruptured S/G pressure is 1000 psig | |||
* RCS pressure has stabilized at 1400 psig | |||
* The CRS directs you to report RCS Subcooling Based on current plant conditions RCS Subcooling is approximately ____(2)____°F. A. (1) a maximum of 100°F/hour (2) 30-40 B. (1) the maximum achievable rate (2) 30-40 C. (1) a maximum of 100°F/hour (2) 70-80 D. (1) the maximum achievable rate (2) 70-80 Page 9 of 75 Question:(1 point)10ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant tripped from 100% power | |||
* The crew is implementing EOP-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS | |||
* RCS Boration has been initiated | |||
* RCS temperature is 348°F and lowering | |||
* The current time in Core Life is 20,000 MWD/MTU | |||
* The current boron concentration is 100 ppm Which ONE of the following correctly completes the statements below? IAW EOP-ECA-2.1, the operator must raise the RCS boron concentration to a MINIMUM of approximately ____(1)____ to establish the Cold Shutdown boron concentration. The reactivity effects due to this event are more severe while operating at the ____(2)____-Of-Life. (REFERENCES PROVIDED) A. (1) 680-690 ppm (2) Beginning B. (1) 680-690 ppm (2) End C. (1) 760-770 ppm (2) End D. (1) 760-770 ppm (2) Beginning Page 10 of 75 Question:(1 point)11ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a loss of both MFW pumps occurred | |||
* All Service Water pumps have lost power and cannot be restored | |||
* CST level is 12% and rapidly lowering | |||
* The SDAFW pump is out of service IAW OP-402, AUXILIARY FEEDWATER SYSTEM, which ONE of the following is required to supply the OIL COOLER for operation of the "B" MDAFW pump under these conditions? A. Fire Water B. Potable Water C. Deepwell Water D. Fukushima AFW Suction Tank water Page 11 of 75 Question:(1 point)12ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating anExtended Loss of AC Power (ELAP)*A depressurization of all S/G's was initiated at 10:00*The following timeline of events is observed:Time S/G Pressures Pzr Level 10:15 500 psig 13% 10:45 190 psig 0% Which ONE of the following correctly completes the statements below? The EARLIEST time at which the depressurization is required to be stopped IAW EOP-ECA-0.0, is ____(1)____. The reason the depressurization is stopped is to ____(2)____. A. (1) 1015 (2) prevent injection of accumulator nitrogen into the RCS B. (1) 1045 (2) ensure that no reactor head voiding will occur C. (1) 1015 (2) ensure that no reactor head voiding will occur D. (1) 1045 (2) prevent injection of accumulator nitrogen into the RCS Page 12 of 75 Question:(1 point)13ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power when a loss of off-site power occurs*Fifteen seconds later an SI actuation occurred due to a Large Break LOCAWhich ONE of the following correctly completes the statements below? The BOP will expect to see the SW Booster Pumps started on the ____(1)____. SW Booster Pump suction pressure ____(2)____ have to be at least 30 psig for the SW Booster Pump to start. A. (1) Blackout Sequencer (2) does B. (1) Blackout Sequencer (2) does NOT C. (1) SI Sequencer (2) does D. (1) SI Sequencer (2) does NOT Page 13 of 75 Question:(1 point)14ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* A Startup Transformer lockout occurs Which ONE of the following describes how Instrument Buses 1 and 4 will respond to this event? A. Both Instrument Buses 1 and 4 will de-energize B. Instrument Bus 1 will remain energized; Instrument Bus 4 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus C. Instrument Bus 4 will remain energized; Instrument Bus 1 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus D. Both Instrument Buses 1 and 4 will remain energized Page 14 of 75 Question:(1 point)15ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* APP-036-D1, BATT CHARGER A/A-1 TROUBLE, annunciated. | |||
* The OAO reports the following indications from Battery Charger "A-1": * +40 Volts on the Ground Detection Voltmeter. | |||
* 135 Volts DC on Charger Voltage. Which ONE of the following correctly completes the statements below? IAW OMM-035, GROUND ISOLATION, the FIRST action the operator will take to attempt to identify the cause of the ground is ____(1)____. Subsequently, MCC-A spuriously de-energizes. Instrument Bus 2 and 7 will ____(2)____. A. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) de-energize B. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) remain energized C. (1) cycle selected breakers on Distribution Panel A (2) de-energize D. (1) cycle selected breakers on Distribution Panel A (2) remain energized Page 15 of 75 Question:(1 point)16ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a reactor trip and SI occurred | |||
* The crew has entered EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT | |||
* APP-036-D7, AREA MONITOR HI RAD, has just alarmed | |||
* APP-036-H1, WDBRP TROUBLE, has just alarmed Which ONE of the following correctly completes the statements below? IAW EOP-E-1, radiation monitor ____(1)____ would be used to diagnose a LOCA outside containment. The WDBRP TROUBLE alarm ____(2)____ consistent with a LOCA outside Containment in the Auxiliary Building. A. (1) R-3, PASS Panel Area (2) is B. (1) R-3, PASS Panel Area (2) is NOT C. (1) R-8, Drumming Room (2) is D. (1) R-8, Drumming Room (2) is NOT Page 16 of 75 Question:(1 point)17ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The reactor was tripped from 100% power due to a loss of MFW | |||
* A spurious SI has actuated | |||
* RCS Pressure - 2300 psig | |||
* All S/G pressures - 1050 psig | |||
* S/G WIDE RANGE levels are as follows: | |||
* WIDE RANGE: A - 10%, | |||
* WIDE RANGE: B - 15%, | |||
* WIDE RANGE: C - 9% | |||
* AFW flow is indicating 0 gpm | |||
* EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Immediate Actions are complete and have just been verified Which ONE (1) of the following correctly completes the statement below? The crew should ____(1)____ because ____(2)____. A. (1) remain in EOP-E-0 until directed to transition out (2) the "B" S/G is still a viable Heat Sink B. (1) remain in EOP-E-0 until directed to transition out (2) rules of usage require continuing in EOP-E-0 C. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed is required D. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed can still be avoided Page 17 of 75 Question:(1 point)18ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant has tripped from 100% power due to a LOCA | |||
* The crew is operating in EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION | |||
* RWST level is at 16% | |||
* RWST Makeup has been established in accordance with Supplement P, Emergency Makeup To The RWST | |||
* The only ECCS Pump drawing on the RWST is the "A" SI Pump and pump flow has been adjusted to 150 gpm. Which ONE of the following correctly completes the statements below? IAW EOP-ECA-1.1, the EARLIEST that the "A" SI Pump must be stopped is when the RWST Level lowers to ____(1)____. Assuming these conditions remain the same, four hours from now the RWST level will be ____(2)____. A. (1) 9% (2) higher B. (1) 9% (2) lower C. (1) 13% (2) higher D. (1) 13% | |||
(2) lower Page 18 of 75 Question:(1 point)19ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 50% power | |||
* During the performance of OST-011, ROD CLUSTER CONTROL EXERCISE & ROD POSITION INDICATION, ONE Control Bank "B" rod is 17 steps below the rest of the bank | |||
* The crew is performing the steps to realign the rod IAW AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM Which ONE of the following correctly completes the statements below? 1) IAW AOP-001, OPEN the Control Bank "B" lift coil switch(es) for ____(1)____. 2) Realign the rod using the ____(2)____ position of the rod bank selector switch. A. (1) the misaligned rod ONLY (2) CB B B. (1) the misaligned rod ONLY (2) M (MANUAL) C. (1) all but the misaligned rod (2) CB B D. (1) all but the misaligned rod (2) M (MANUAL) Page 19 of 75 Question:(1 point)20ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The Pressurizer Level Channel Selector Switch is selected to NORMAL*The reference leg for Pressurizer level Transmitter LT-459 develops a slow leak*The "A" Charging Pump is running in AUTOWhich ONE of the following describes the instrument response? LT-459 __LT-460__ A. rises lowers B. lowers remains the same C. rises remains the same D. lowers rises Page 20 of 75 Question:(1 point)21ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A reactor startup is being commenced | |||
* Source Range count rate (CR0) prior to control bank rod withdrawal is as follows: | |||
* N31: 3.0E+001 cps | |||
* N32: 3.0E+001 cps Subsequently: | |||
* The crew has completed the MINIMUM number of doublings required to allow the crew to withdraw control rods as necessary to achieve criticality IAW GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL | |||
* The following indications are observed: | |||
* N31: 2.4E+002 cps | |||
* N32: 1.2E+002 cps Which ONE of the following correctly completes the statement below? IAW GP-003, Source Range Channel ____(1)____ is indicating AS EXPECTED. When the Source Range Channel with the unexpected reading is removed from service per the appropriate OWP, the reactor startup ____(2)____ continue. A. (1) N31 (2) may B. (1) N31 (2) may not C. (1) N32 (2) may D. (1) N32 (2) may not Page 21 of 75 Question:(1 point)22ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A Reactor startup is in progress | |||
* The following indications are observed: | |||
* N31/32 = 900 cps | |||
* N35/36 = 5 x 10-11 amps Subsequently: | |||
* Intermediate Range (IR) channel N36 fails LOW | |||
* The crew places the Reactor startup on HOLD Which ONE of the following correctly completes the following statement? The reason that the reactor startup is placed on HOLD is because a Reactor Protection Trip Function for the ________ accident is degraded. A. rod ejection B. boron dilution C. steam line break D. uncontrolled RCCA bank rod withdrawal Page 22 of 75 Question:(1 point)23ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An accidental gaseous radwaste release is in progress | |||
* R-1, Control Room Area Radiation Monitor, alarms | |||
* R-1 is indicating 8.62E-2 mR/hr and stable Which ONE of the following correctly completes the statements below? R-1 ____(1)____ operating properly. | |||
When R-1 alarms, the CR HVAC will automatically shift to the Emergency ____(2)____ Mode. A. (1) is (2) Recirculation B. (1) is (2) Pressurization C. (1) is NOT (2) Recirculation D. (1) is NOT (2) Pressurization Page 23 of 75 Question:(1 point)24ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* The following is observed on the Fire Alarm Console: (SEE REFERENCE CONDITIONS ON NEXT PAGE) Which ONE of the following correctly completes the statements below? It is expected that the automatic water suppression system ____(1)____ actuate for these conditions. Based on this information, the entry conditions ____(2)____ met for AOP-041, RESPONSE TO FIRE EVENTS. A. (1) will (2) are B. (1) will (2) are NOT C. (1) will NOT (2) are D. (1) will NOT (2) are NOT Page 24 of 75 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* With the plant at 100%, a confirmed bomb threat has been received | |||
* The caller specified that the bomb was located in the Control Room | |||
* The following timeline of events is recorded: 2110 The Control Room was evacuated after all appropriate actions were taken 2145 A Control operator in the Charging Pump Room informs the SM that: | |||
* N51 reads 3.0E5 cps and is slowly lowering | |||
* Pressurizer pressure is 2225 psig | |||
* Pressurizer level is 35% | |||
* The "A" Charging Pump is operating Which ONE of the following correctly completes the statements below? IAW Attachment 1 of AOP-004, CONTROL ROOM INACCESSIBILITY, the operator will raise Pressurizer level to at LEAST greater than ____(1)____, and then stop the running Charging Pump. | |||
The basis for this action is to ____(2)____. A. (1) 60% (2) prevent exceeding the Charging Pump starting duty limitations B. (1) 60% (2) ensure that the reactor is subcritical C. (1) 86% | |||
(2) ensure that the reactor is subcritical D. (1) 86% | |||
(2) prevent exceeding the Charging Pump starting duty limitations Page 25 of 75 Question:(1 point)26ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The R-9, Letdown Line Area, indication on Radiation Monitoring System Recorder RR-1 is rising Which ONE of the following correctly completes the statements below? If the trend continues, it is expected that ____(1)____. The basis for the R-9 setpoint is to detect ____(2)____. A. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) small leaks in fuel rods B. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) release of resin from the in-service demineralizers C. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) small leaks in fuel rods D. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) release of resin from the in-service demineralizers Page 26 of 75 Question:(1 point)27ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* EOP-ECA-0.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED has been implemented | |||
* The crew is checking for Natural Circulation with the following conditions: | |||
* Containment pressure is 0.5 psig | |||
* Steam dump using the S/G PORVs is in progress | |||
* RCS subcooling based on CETs are 33°F and stable | |||
* CETC are 555°F and stable | |||
* S/G pressures are stable at 900 psig | |||
* RCS Hot Leg temperatures are 555°F and stable | |||
* RCS Cold Leg temperatures are 545°F and slowly rising | |||
* S/G NR levels are 21% and stable Which ONE of the following correctly completes the statements below? Based on the indications above, Natural Circulation (NC) flow ____(1)____ been established. IAW EOP-ECA-0.1, the crew will ____(2)____. A. (1) has NOT (2) raise S/G levels to promote the establishment of NC flow B. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 9% C. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 18% D. (1) has NOT (2) raise the rate of dumping steam to promote the establishment of NC flow Page 27 of 75 Question:(1 point)28ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power when a transient occurs | |||
* Over 15-20 seconds a load rejection lowers and then stabilizes power at 80% Which ONE of the following correctly completes the statements below? Seal water injection flow will INITIALLY ____(1)____. Subsequently, | |||
* APP-001-B4, RCP SEAL INJ HI/LO FLOW, has alarmed | |||
* The CRS has directed use of the expanded seal water injection flow control band The expanded seal water injection flow control band is ____(2)____. A. (1) rise (2) 6-20 gpm B. (1) rise (2) 7-18 gpm C. (1) lower (2) 6-20 gpm D. (1) lower (2) 7-18 gpm Page 28 of 75 Question:(1 point)29ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is in Mode 3 | |||
* APP-003-E2, VCT HI/LO PRESS, has alarmed | |||
* Actual VCT pressure is 15 psig Which ONE of the following correctly completes the statement below? If VCT pressure continues to lower, RCP #1 Seal Leakoff flow will ____(1)____ and RCP #2 Seal leakoff flow will ____(2)____. A. (1) lower (2) rise B. (1) rise (2) lower C. (1) rise (2) rise D. (1) lower (2) lower Page 29 of 75 Question:(1 point)30ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*Due to RTGB indications the crew has entered AOP-024, LOSS OF INSTRUMENT BUS*An Auto Makeup to the VCT has initiated on the loss of instrument busWhich ONE of the following correctly completes the statement below? The Auto makeup has occurred because VCT Level transmitter ____(1)____ has de-energized on a loss of Instrument Bus ____(2)____. A. (1) LT-112 (2) 7 B. (1) LT-112 (2) 9 C. (1) LT-115 (2) 7 D. (1) LT-115 (2) 9 Page 30 of 75 Question:(1 point)31ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *A plant cooldown is in progress*The "A" RHR Train is in service*RCS temperature is 190°F*RCS Pressure is 350 psig*The RCS is in Solid Plant Operation with LTOPP in serviceSubsequently, a transient occurs resulting in the following: *RCS temperature is 195°F*RCS Pressure is 420 psig*PZR PORV PCV-456 indicates OPEN*PZR PORV PCV-455C indicates CLOSEDThe crew has entered AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Which ONE of the following correctly completes the statements below? Based on plant conditions, both PORVs should have ____(1)____. IAW AOP-019 immediate actions, the operator will FIRST ____(2)____ to control or mitigate the consequences of this event. A. (1) remained closed (2) close PCV-456 B. (1) opened (2) stop all Charging Pumps and RCPs C. (1) opened (2) ensure the block valve for PCV-456 is OPEN D. (1) remained closed (2) place the PCV-456 LTOPP Arming Switch to NORMAL Page 31 of 75 Question:(1 point)32ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: * "A" Train RHR is in service | |||
* Instrument Air pressure lowers to 30 psig Which ONE of the following correctly completes the statement below? RCS temperature will INITIALLY ____(1)____, and RHR System Flow will INITIALLY ____(2)____. A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Lower (2) Lower D. (1) Lower (2) Rise Page 32 of 75 Question:(1 point)33ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% RTP | |||
* The following timeline is observed: TIME "A" SI accumulator pressure"A" SI accumulator level1108 637 psig 68 percent 1111 646 psig 70 percent 1114 660 psig 75 percent Which ONE of the following correctly completes the statement below? The EARLIEST time at which an RTGB annunciator alarm would occur is at time ____(1)____, due to ____(2)____ reaching its alarm setpoint. A. (1) 1111 (2) APP-002-A4, SI ACCUM A HI/LO LVL B. (1) 1114 (2) APP-002-B4, SI ACCUM A HI/LO PRESS C. (1) 1111 (2) APP-002-B4, SI ACCUM A HI/LO PRESS D. (1) 1114 (2) APP-002-A4, SI ACCUM A HI/LO LVL Page 33 of 75 Question:(1 point)34ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a LOCA occurs inside Containment Which ONE of the following correctly completes the statements below? While operating in the EOP Network, the LOWEST pressure in which "Adverse" containment values are applicable is ____(1)____. Based on the increased containment temperature, level detectors with wet reference legs will indicate ____(2)____ than the actual level. A. (1) 4 psig (2) lower B. (1) 4 psig (2) higher C. (1) 10 psig (2) lower D. (1) 10 psig (2) higher Page 34 of 75 Question:(1 point)35ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* Containment pressure is 0.2 psig | |||
* Containment temperature is 94°F Subsequently: | |||
* A load rejection results in a reactor trip | |||
* Following the trip, a Pressurizer Safety valve opens, and will NOT reseat | |||
* The PRT rupture disks function as designed | |||
* Containment pressure is rising at 0.1 psig every 5 minutes | |||
* Containment temperature is rising at 2°F every 5 minutes Assuming these conditions remain constant, which ONE of the following identifies the Containment Technical Specifications LCOs that will be affected one hour from now? A. Both LCO 3.6.4, Containment Pressure, and LCO 3.6.5, Containment Air Temperature, will be exceeded. B. Only LCO 3.6.4, Containment Pressure, will be exceeded. C. Only LCO 3.6.5, Containment Air Temperature, will be exceeded. D. Neither LCO 3.6.4, Containment Pressure, nor LCO 3.6.5, Containment Air Temperature, will be exceeded. Page 35 of 75 Question:(1 point)36ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
T= 1305:10 | |||
* A loss of off-site power has occurred concurrent with a Reactor trip | |||
* The crew enters EOP-E-0, Reactor Trip or Safety Injection T=1307:40 | |||
* Immediate actions of EOP-E-0 are complete | |||
* The following parameters are noted: | |||
* RCS pressure is 2110 psig and stable | |||
* SG pressures are all 910 psig and lowering slowly | |||
* CV pressure is 0.7 psig and rising slowly At time 1307:40, which ONE of the following describes the CCW Pump indication available in the control room? A. "B" and "C" CCW Pump RED indicating lights are LIT. "A" CCW Pump GREEN indicating light is LIT. B. All 3 CCW Pump control switch GREEN indicating lights are LIT. C. "B" and "C" CCW Pump GREEN indicating lights are LIT; "A" CCW Pump RED indicating light is LIT. D. "B" and "C" CCW Pump RED indicating lights are LIT; "A" CCW Pump GREEN and RED indicating lights are EXTINGUISHED. Page 36 of 75 Question:(1 point)37ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant The plant is at 100% power when the following occurs: | |||
* A load rejection results in a PZR PORV actuation | |||
* The PZR PORV will not fully seat | |||
* The depressurization led to a Reactor Trip and Safety Injection | |||
* PZR pressure reduces to 1400 psig and stabilizes | |||
* The PRT rupture discs rupture at their design setpoint | |||
* Containment pressure peaks at 15 psig Which ONE of the following is the MAXIMUM temperature indicated by the Safety Valve tailpiece RTD during the entire event? A. 213°F B. 250°F C. 298°F D. 338°F Page 37 of 75 Question:(1 point)38ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following identifies a condition which will cause an automatic reactor trip? A. RCP bus frequency reads 58.0 Hz when THREE Power Range channels read 5% RTP. B. Flow in ONE Reactor Coolant Loop reads 91% when ALL Power Range channels read 35% RTP. C. ONE Intermediate Range NI channel reads 1 x10E-6 AMPS when TWO Power Range channels read 15% RTP. D. ONE Source Range NI channel reads 5 x10E5 CPS when TWO Intermediate Range NI channels read 9 x10E-11 AMPS. Page 38 of 75 Question:(1 point)39ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant was at 100% when a SI occurredWhich ONE of the following correctly completes the statements below regarding the Feed Reg Valves and the Feed Reg Bypass Valves? Following the SI signal, the Feed Reg Bypass Valves ____(1)____ receive a CLOSE signal. The Feed Reg Valves ____(2)_____ be available when the SI is RESET and the Feedwater Isolation OVRD/RESET key switches are placed in OVRD/RESET. A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 39 of 75 Question:(1 point)40ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below regarding the Containment Spray Actuation logic scheme? | |||
The MINIMUM number of Containment Pressure channels that must sense pressure greater than the Hi-Hi pressure setpoint to generate an automatic Containment Spray Actuation is ____(1)____. The Containment Spray Actuation bistables are ____(2)____ to actuate. A. (1) Two (2) Energize B. (1) Two (2) De-energize C. (1) Four (2) Energize D. (1) Four (2) De-energize Page 40 of 75 Question:(1 point)41ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*A realignment has just occurred and the operator observes the following Service Watervalve alignments for HVH-1 (CV Recirc Fan A) and HVH-2 (CV Recirc Fan B):Assuming no conditions change, which ONE of the following identifies the operational restrictions, if any, placed on HVH-1? A. HVH-1 may run continuously, there are no restrictions. B. HVH-1 may continue to run for up to 15 additional minutes. C. HVH-1 must be immediately secured and cannot be run under these conditions. D. HVH-1 must be immediately secured and can ONLY be started during emergencies. Page 41 of 75 Question:(1 point)42ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% | |||
* A LOCA inside containment occurs and the following timeline is observed: TIME OBSERVATION 1200 LOCA occurs 1201 CV Spray system actuates 1211 CV Pressure peaks at 22 PSIG 1235 CV Pressure lowers to less than 10 PSIG 1245 CV Pressure lowers to less than 4 PSIG Which ONE of the following correctly completes the statements below? IAW EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, the EARLIEST TIME that the Containment Spray Pumps may be secured is ____(1)____. | |||
In order to successfully reset the Phase B Containment Isolation signal, the Containment Spray Signal ____(2)____ required to be reset FIRST. A. (1) 1235 (2) is B. (1) 1235 (2) is NOT C. (1) 1245 (2) is D. (1) 1245 (2) is NOT Page 42 of 75 Question:(1 point)43ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*R-15, Air Ejector Radiation Monitor, alarms*The crew entered AOP-035, S/G TUBE LEAK*The crew has initiated Attachment 5, R-15 Monitoring*Chemistry reports the following leakrates:Time "A" S/G Tube leakrate 0800 31 gpd 0900 51 gpd 1000 81 gpd 1100 111 gpd IAW AOP-035, which ONE of the following identifies the EARLIEST time that a plant shutdown is required? A. 0800 B. 0900 C. 1000 D. 1100 Page 43 of 75 Question:(1 point)44ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occursWhich ONE of the following describes how this actuation affects the Reactor and the Main Turbine? A. BOTH the Reactor and the Main Turbine receive trip signals directly from the FWIS. B. The Reactor receives a trip signal directly from the FWIS, and causes a Main Turbine trip. C. The Main Turbine receives a trip signal directly from the FWIS and the Reactor will trip because the Main Turbine tripped with power above P-8. D. NEITHER the Reactor nor the Main Turbine receive trip signals directly from the FWIS. However, the Reactor will trip on plant conditions created by the FWIS actuation and cause a Main Turbine trip. Page 44 of 75 Question:(1 point)45ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power, an ATWS event occurred*The crew entered FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION ATWS*All SG Narrow Range levels are OFF-Scale LOWWhich ONE of the following correctly completes the statement below? IAW FRP-S.1, AFW flow must be greater than a MINIMUM value of ________ to establish a Secondary Heat Sink? A. 300 gpm B. 500 gpm C. 600 gpm D. 1000 gpm Page 45 of 75 Question:(1 point)46ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* A reactor trip has occurred Which ONE of the following identifies the breakers which will automatically CLOSE one minuteafter the reactor trip? Breaker nomenclature: 52/10 4KV BUS 1-2 TIE BKR 52/12 START-UP TRANSFORMER TO 4KV BUS 2 52/17 START-UP TRANSFORMER TO 4KV BUS 3 52/19 4KV BUS 3-4 TIE BKR A. 52/10 and 52/12 B. 52/10 and 52/17 C. 52/12 and 52/19 D. 52/17 and 52/19 Page 46 of 75 Question:(1 point)47ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on faultWhich ONE of the following correctly completes the statement below? Circulating Water pump(s) _________ lost power. A. "A" & "B" have B. "B" & "C" have C. "A" & "C" have D. "B" ONLY has Page 47 of 75 Question:(1 point)48ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is in Mode 3*The "B" Battery Charger is in service*The "B-1" Battery Charger is in standbySubsequently: *MCC-6 is de-energized*APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms*Two minutes later MCC-6 is re-energizedWhich ONE of the following identifies when APP-036-D2 will clear? APP-036-D2 will clear-- A. when the "B" Battery Charger automatically restarts. B. only after the operator manually restarts the "B" Battery Charger. C. only after the operator manually places the "B-1" Battery Charger back in the STANDBY mode. D. only after the operator manually restarts the "B" Battery Charger and places the "B-1" Battery Charger back in the STANDBY mode. Page 48 of 75 Question:(1 point)49ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*OST-401-1, EDG "A" SLOW SPEED START testing is in progress*Current "A" EDG load is 2500 KWSubsequently: *The Normal Supply Breaker to E-1, 52/18B, opens*EDG "A" Output Breaker 52/17B, opensWhich ONE of the following correctly completes the statements below? IAW OP-604 CAUTION statement, the consequence of opening the EDG "A" Output Breaker under load is ____(1)____. IAW OP-604 when attempting to recover, the local Generator Parallel/Isolate Switch must be placed in the ____(2)____ position. OP-604, DIESEL GENERATORS "A" AND "B" A. (1) the diesel engine may trip due to overspeed (2) ISOL B. (1) excessive carbon buildup in the engine could occur (2) PARALLEL C. (1) the diesel engine may trip due to overspeed (2) PARALLEL D. (1) excessive carbon buildup in the engine could occur (2) ISOL Page 49 of 75 Question:(1 point)50ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following supplies power to the "A" and "B" EDG Fuel Oil Transfer Pumps? A. MCC-10 and MCC-9 respectively B. MCC-9 and MCC-10 respectively C. MCC-6 and MCC-5 respectively D. MCC-5 and MCC-6 respectively Page 50 of 75 Question:(1 point)51ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The reactor is at 100%*The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIRHANDLING*R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarmsV12-12, CV VAC RELIEF V12-13, CV VAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE of the following correctly completes the statements below? The crew would expect to see ____(1)____ annunciator flashing. Due to the conditions above, ____(2)____ will automatically close. A. (1) APP-036-D7 (2) V12-12 & V12-13 ONLY B. (1) APP-036-D8 (2) V12-12 & V12-13 ONLY C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Page 51 of 75 Question:(1 point)52ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*R-19A, STM GEN BLOW DN SG-A, enters the alarm conditionWhich ONE of the following correctly completes the statements below? In regards to the Blowdown Isolation Valves and the Blowdown Sample Isolation Valves, an alarm condition on R-19A will automatically close the ____(1)____. IAW AOP-005, RADIATION MONITORING SYSTEM, if the automatic actions fail to occur, the crew ____(2)____ de-energize R-19A in an attempt to cause the automatic actions to occur. A. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will D. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will NOT Page 52 of 75 Question:(1 point)53ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following correctly completes the statements below regarding components normally cooled by Service Water? The Circulating Water Pumps ____(1)____ be cooled by the Fire Water System during an emergency. The Control Room HVAC Cooling Units ____(2)____ be cooled by the Fire Water System during an emergency. A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can NOT D. (1) can NOT (2) can Page 53 of 75 Question:(1 point)54ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power * "D" IA Compressor is running | |||
* Station Air Compressor is running Subsequently: | |||
* IA Header pressure is 79 PSIG and lowering | |||
* The crew is implementing AOP-017, LOSS OF INSTRUMENT AIR SA-5, STATION AIR TO INST AIR CROSS CONNECT SA-220, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION SA-221, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION Which ONE of the following correctly completes the statements below? IAW AOP-017, the PREFERRED method to cross connect IA from Station Air is by opening ____(1)____ . | |||
IA will no longer be used to supply Breathing Air to ____(2)____. A. (1) SA-5 (2) minimize IA loads ONLY B. (1) SA-5 (2) minimize IA loads and prevent harm to users of Breathing Air C. (1) SA-220 and SA-221 (2) minimize IA loads ONLY D. (1) SA-220 and SA-221 (2) minimize IA loads and prevent harm to users of Breathing Air Page 54 of 75 Question:(1 point)55ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A LOCA occurred 45 minutes ago | |||
* The crew is implementing the Emergency Operating Procedures | |||
* The following conditions exist: | |||
* CET temperature is 340°F | |||
* RCS pressure is 60 psig and lowering | |||
* Full Range RVLIS is 40% | |||
* RCS Cold Leg temperature is 320°F and lowering | |||
* S/G NR levels are off-scale LOW | |||
* S/G pressures are 550 psig and trending down | |||
* AFW flow is 450 gpm | |||
* All RCPs are OFF | |||
* CV pressure is 43 psig and rising | |||
* SPDS has been reset Which ONE of the following identifies the MOST challenged Critical Safety Function? A. Integrity B. Heat Sink C. Containment D. Core Cooling Page 55 of 75 Question:(1 point)56ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power Subsequently, all IRPI indication is lost except a green LED is illuminated on each rod indicator Which ONE of the following correctly completes the statements below? The cause of this condition is the ____(1)____ has tripped. | |||
For this condition entry into AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, ____(2)____ required. A. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is B. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is D. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is NOT Page 56 of 75 Question:(1 point)57ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* GP-008, DRAINING THE REACTOR COOLANT SYSTEM, is in progress | |||
* The crew has positioned HIC-142, PURFICATION FLOW, to establish required drain rate Which ONE of the following correctly completes the statements below? LCV-115A, VCT/HLDP TK DIV, will begin to divert at ____(1)____ in the VCT. | |||
IAW GP-008, ____(2)____ level change can be used to determine the volume drained from the RCS. A. (1) 30" (2) WHUT B. (1) 30" (2) CVCS HUT C. (1) 51.6" (2) CVCS HUT D. (1) 51.6" (2) WHUT Page 57 of 75 Question:(1 point)58ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 35% power and stable | |||
* The "A" Charging Pump is running in AUTO | |||
* The "B" Charging Pump is running in MANUAL and adjusted to 50% output on Charging Pump Speed Controller SC-151 | |||
* Letdown flow is 105 gpm Subsequently: | |||
* Letdown flow is lowered 45 gpm | |||
* Reactor power is lowered to 30% and stabilized | |||
* Pressurizer Level lowers to, and has stabilized at 31.5% Which ONE of the following correctly completes the statements below? The Pressurizer Level Control System ____(1)____ operating as expected for these plant conditions. While Letdown was being lowered, APP-003-F3, CHG PMP LO SPEED, alarmed. According to OP-301, CHEMICAL AND VOLUME CONTROL SYSTEM, the operator will be required to ____(2)____ Charging Pump to clear the alarm. A. (1) is (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" B. (1) is (2) adjust the speed of the "B" C. (1) is NOT (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" D. (1) is NOT (2) adjust the speed of the "B" Page 58 of 75 Question:(1 point)59ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The Plant is in Mode 1, following a control rod manipulation | |||
* The RTGB IRPI indication for Control Bank "D" Rod M-8 indicates 120 inches | |||
* The RTGB IRPI indication for Control Bank "D" Rod H-4 indicates 110 inches | |||
* Control Bank "D" step counter position is 192 steps Which ONE of the following correctly completes the statements below? Based on the given conditions, control rod ____(1)____ is stuck. Assuming the average of the individual rod positions in the affected bank indicate 120 inches, entry into ITS LCO 3.1.4, ROD GROUP ALIGNMENT LIMITS, ____(2)____ required. A. (1) M-8 (2) is B. (1) M-8 (2) is NOT C. (1) H-4 (2) is D. (1) H-4 (2) is NOT Page 59 of 75 Question:(1 point)60ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The operator is reviewing the T/C TREND pages on both the Train "A" and Train "B" ICCM displays Which ONE of the following correctly completes the statements below? The TOTAL number of Core Exit Thermocouples (CET) that monitor the core is ____(1)____. The T/C TREND page displays the average of ____(2)____ CET indications over the last 30 minutes. A. (1) 23 (2) the five highest B. (1) 23 (2) all C. (1) 46 (2) all D. (1) 46 (2) the five highest Page 60 of 75 Question:(1 point)61ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE (1) of the following is the power supply for HVE-3, CV Air Iodine Removal Fan? A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-10 Page 61 of 75 Question:(1 point)62ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW GP-010, REFUELING, the Containment Purge System ____(1)____ required be in operation during Core Alterations with the Equipment Hatch removed. | |||
The Containment Purge System ____(2)____ required be in operation if a Containment entry is being made with the plant in Mode 1. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 62 of 75 Question:(1 point)63ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* Spent fuel handling activities are NOT in progress Subsequently: | |||
* SFP level starts to rapidly lower due to a large structural and piping failure | |||
* The crew has entered AOP-036, SFP EVENTS R-14, Plant Vent Effluent Monitor R-21, Fuel Handling Building Upper Level, Noble Gas HVE-15, Fuel Handling Building Exhaust Fan Which ONE of the following correctly completes the statements below? IAW AOP-036, R-14 ____(1)____ monitored for indications of fuel damage. | |||
If R-21 were to subsequently alarm, HVE-15 ____(2)____ automatically trip. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 63 of 75 Question:(1 point)64ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* The SDAFW Pump is OOS Subsequently: | |||
* The crew trips the reactor and initiates safety injection due to a SGTR on the "B" Steam Generator | |||
* V2-16A, AFW Header Discharge Valve, has failed CLOSED | |||
* The "B" MDAFW Pump trips on auto-start * "B" SG NR level is 6% and rising slowly * "A" and "C" SG NR levels are off-scale low Which ONE of the following correctly completes the statements below? Without operator action, a Secondary Heat Sink ____(1)____ established. | |||
Based on the current conditions, the operator ____(2)____ immediately isolate feed to the "B" S/G. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 64 of 75 Question:(1 point)65ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following discharges to the Reactor Coolant Drain Tank? A. RCV-609, CC SURGE TANK VENT B. CVC-203 A/B, LETDOWN RELIEF VALVES C. CVC-389, EXCESS LETDOWN DIVERSION D. CVC-400 A/B/C, CHARGING PUMP "A/B/C" LEAKAGE ISOLATION Page 65 of 75 Question:(1 point)66ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW OPS-NGGC-1303, VERIFICATION PRACTICES, guidance for waiving Independent Verification (IV) requirements states that the IV may be waived if the operators were expected to ____(1)____ to complete the verification. | |||
In these cases, ____(2)____ Verification will be used as an alternative to Independent Verification. A. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Concurrent B. (1) receive a total exposure of greater than 10 mrem (2) Concurrent C. (1) receive a total exposure of greater than 10 mrem (2) Functional D. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Functional Page 66 of 75 Question:(1 point)67ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions: | |||
* The plant is in MODE 6 for refueling operations | |||
* Core alterations are in progress Which ONE of the following correctly completes the statements below? IAW LCO 3.9.2, NUCLEAR INSTRUMENTATION, ____(1)____ shall be OPERABLE. N-51 and N-52, ____(2)____ capable of providing audible indication inside Containment. N-31, N-32, SOURCE RANGE NUCLEAR INSTRUMENTS N-51, N-52, REG. GUIDE 1.97 NEUTRON FLUX (SOURCE RANGE, WIDE RANGE) A. (1) either N-31 OR N-32 (2) are B. (1) both N-31 AND N-32 (2) are C. (1) either N-31 OR N-32 (2) are NOT D. (1) both N-31 AND N-32 (2) are NOT Page 67 of 75 Question:(1 point)68ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant startup is in progress | |||
* NIS Power Indication is 50% | |||
* The STA is recording data IAW GP-005, POWER OPERATION, Attachment 1, REACTOR POWER ASCENSION INDICATOR LOG Which ONE of the following correctly completes the statements below? IAW GP-005, if Core T indicates 33°F, the crew ____(1)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). IAW GP-005, if Calorimetric power indicates 51.5%, the crew ____(2)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Page 68 of 75 Question:(1 point)69ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The FWUFM System has been OOS for five days Subsequently: | |||
* An AO reports a steam leak near the Main Steam Isolation Valves | |||
* The following indications are noted in the Control Room: | |||
* Tavg is LOWERING | |||
* Steam flow and feed flow have RISEN | |||
* A Power Limit Warning alarm on ERFIS has been received | |||
* Reactor power is slowly RISING Which ONE of the following identifies the MAXIMUM thermal power limit allowed by the operating license under these conditions? A. 2300 MWt B. 2307 MWt C. 2339 MWt D. 2346 MWt Page 69 of 75 Question:(1 point)70ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band. Which ONE of the following correctly completes the statement below? IAW Technical Specification LCO 3.2.3 ACTION--. Restore AFD to within target band within ___(1)___. If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___. A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour Page 70 of 75 Question:(1 point)71ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* Letdown flow is 45 gpm | |||
* The "A" Charging Pump is operating in AUTO | |||
* The "B" Charging Pump is operating in MANUAL Subsequently: | |||
* R-9, Letdown Line Area Monitor, alarms | |||
* The alarm is determined to be valid | |||
* The crew enters AOP-005, RADIATION MONITORING SYSTEM Which ONE of the following correctly completes the statements below? IAW with Attachment 9 of AOP-005, the operator ____(1)____ required to evacuate the Aux Building of non-essential personnel. | |||
IAW with Attachment 9 of AOP-005, the operator ____(2)____ required to isolate letdown flow. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 71 of 75 Question:(1 point)72ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An operator has been assigned work in the radiologically controlled area | |||
* The dose rate in the area is 500 mR/hr | |||
* The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension? A. 1 hour B. 3 hours C. 4 hours D. 7 hours Page 72 of 75 Question:(1 point)73ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant cooldown is in progress | |||
* RCS Temperature is 430°F | |||
* RCS pressure is 725 psig | |||
* The SI Accumulators have been isolated Subsequently, an RCS leak occurs and the operating crew enters AOP-016, EXCESSIVE RCS LEAKAGE. | |||
Which ONE of the following correctly completes the statements below? AOP-016 will ensure that a MINIMUM of ____(1)____ Charging Pumps are running with their speed adjusted to maximum. | |||
With the current plant conditions, if Pressurizer level continues to lower uncontrollably with maximum charging flow, the crew would transition to ____(2)____. A. (1) two (2) AOP-033, SHUTDOWN LOCA B. (1) two (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION C. (1) three (2) AOP-033, SHUTDOWN LOCA D. (1) three (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 73 of 75 Question:(1 point)74ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The Control Room receives a confirmed report of a fire in the Unit 2 Cable Spread Room (Fire Zone 19) at 0730 Which ONE of the following correctly completes the statements below? IAW AOP-041, RESPONSE TO FIRE EVENT, the operator must ____(1)____. The LATEST time that this action may be complete is ____(2)____. A. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0740 B. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0745 C. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (2) 0745 D. (3) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (4) 0740 Page 74 of 75 Question:(1 point)75ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power Subsequently, the following time line of events occur: TIME EVENT 1200 APP-009-C5, MAIN TRANSF TROUBLE, alarms 1203 The Outside AO reports that all Main Transformer Fans and Pumps are NOT operating 1204 The crew enters AOP-037, LARGE TRANSFORMER MALFUNCTIONS 1208 TIME NOW IAW AOP-037, which ONE of the following identifies the EARLIEST time that the reactor must be tripped? A. IMMEDIATELY B. 1211 C. 1214 D. 1231 Page 75 of 75 RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-7 Amendment No.218 0 2550751000 1250 1500 1750 2000 2250 2500 2750 0 5100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) MATERIALS PROPERTIES BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Curves applicable for heatup rates up to 60 ºF/Hr for Service period up to 35 EFPY. Heatup Curves include +10ºF and -60 psig allowance For instrumentation error. Acceptable Operation Unacceptable Operation Leak Test Limit Heatup Rate to 60 ° F/Hr Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 35 EFPY Indicated Pressure (psig) Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-8 Amendment No. 218 0 250 500 750 1000 1250 1500 1750 2000 2250 2500 2750 0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) Unacceptable Operation Acceptable Operation 100°F/ Hr Cooldown Rates ( ° F/Hr) 0 ° F/Hr. Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY 60°F/ Hr 40°F/ Hr 20°F/ Hr 100 60 40 0 and 20 Curves applicable for cooldown rates up to 100°F/Hr for the service period up to 35 EFPY. Curves include +10°F and -60 PSIG allowance for instrument error. Indicated Pressure (PSIG) MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 and Girth Weld 10-273 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F 3/4T, 147°F and 172°F REV. REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR5007009001100 1300150017000200040006000800010000120001400016000180002000022000CYCLE EXPOSURE (MWD/MTU)CURVE 1.14BORON CONCENTRATION REQUIRED TO MAINTAINSHUTDOWN MARGIN BORON (PPM)HBR2 CYCLE 30200 F300 F350 FA MINIMUM OF 2.6% SHUTDOWN MARGIN(ARI-MRR)38 FRNP Cycle 30 Curve Book Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve BookRNP-F/NFSA-0237, Rev. 0 Page A46 of A86 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer1B2D3C4C5B6B7B8B9D10C11A12D13D14B15A16A17B18B19C20A21B22D23D24D25CPrinted 2/11/2016 2:53:31 PMPage 1 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer26A27D28C29B30C31B32B33C34B35B36A37D38D39C40C41B42C43C44C45C46C47B48A49A50DPrinted 2/11/2016 2:53:32 PMPage 2 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer51D52C53D54D55C56C57B58B59C60D61A62B63A64B65C66C67D68B69A70A71B72B73A74D75BPrinted 2/11/2016 2:53:32 PMPage 3 of 3 Question:(1 point)1ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The "A" Reactor Trip Bypass Breaker has been placed in service for testing*The "A" Reactor Trip Breaker has been removed from service*A transient condition exists requiring a reactor trip*The OAC depresses the manual reactor trip pushbutton prior to an RPS setpoint beingreachedWhich ONE of the following describes the plant response? The "A" Reactor Trip Bypass Breaker opens due to actuation of its ____(1)____ and the "B" Reactor Trip Breaker opens due to actuation of its ____(2)____. A. (1) UV trip, ONLY (2) UV trip, ONLYB. (1) UV trip, ONLY (2) UV and shunt trip C. (1) UV and shunt trip (2) UV trip, ONLY D. (1) UV and shunt trip (2) UV and shunt trip Page 1 of 75 Question:(1 point)2ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* A transient results in both Pressurizer PORVs opening and sticking OPEN after pressure lowers below the OPEN setpoint | |||
* When the operator attempts to close the Block Valves for each PORV, the OATC observes that the status lights for Block Valves RC-535 and RC-536 are all EXTINGUISHED Subsequently, the CRS directs that the power to each Block Valve be restored. RC-535, Block Valve to Pressurizer PORV PCV-456 RC-536, Block Valve to Pressurizer PORV PCV-455C Which ONE of the following identifies the location(s) to which the operator must be dispatched to close the breakers for the Block Valves? The operator must proceed to-- A. MCC-5 for BOTH RC-535 and RC-536 B. MCC-5 for RC-535; and MCC-6 for RC-536 C. MCC-5 for RC-536; and MCC-6 for RC-535 D. MCC-6 for BOTH RC-535 and RC-536 Page 2 of 75 Question:(1 point)3ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*"A" CV Spray pump is out of service for maintenanceSubsequently: *A SBLOCA occurred at 0930 coincident with a Loss of Offsite Power*"B" EDG tripped immediately after starting*At 1000, the crew is performing the actions of EOP-E-1, LOSS OF REACTOR ORSECONDARY COOLANT with the following current plant conditions:*CV pressure: 11 psig and rising slowly*CV Sump level: 178 inches and rising*CV radiation level: 0.5 R/hr*"A" Loop Cold Leg temperature: 338 °F*"B" Loop Cold Leg temperature: 425 °F*"C" Loop Cold Leg temperature: 427 °FWhich ONE of the following correctly completes the statements below? CSF-4 Integrity critical safety function status tree color is ____(1)____. CSF-5 Containment critical safety function status tree color is ____(2)____. A. (1) Yellow (2) Yellow B. (1) Orange (2) Yellow C. (1) Yellow (2) Orange D. (1) Orange (2) Orange Page 3 of 75 Question:(1 point)4ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power a Large Break LOCA occursWhich ONE of the following correctly completes the statements below? IAW EOP-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION entry conditions, the HIGHEST allowable RWST level before transfer to Cold Leg Recirculation is required is ____(1)____. The reason that the above switchover criteria is established is to ensure that core flow can be maintained using one ____(2)____ pump taking suction on the RWST during realignment to the CV sump. A. (1) 19% (2) SI B. (1) 19% | |||
(2) RHR C. (1) 27% (2) SI D. (1) 27% | |||
(2) RHR Page 4 of 75 Question:(1 point)5ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The "A" Charging pump is operating in AUTO | |||
* The following annunciators alarm in the control room, all within 30 seconds: | |||
* APP-001-B4, RCP SEAL INJECTION HI/LO FLOW | |||
* APP-001-B6, LP LTDN LN HI TEMP | |||
* APP-001-D6, LP LTDN HI PRESS | |||
* APP-001-E6, LP LTDN RELIEF HI TEMP Which ONE of the following identifies the cause of these alarms? A. Seal Injection Filter clogged B. HCV-121, Charging Flow Valve failed closed C. TCV-144, NRHX Temperature Control Valve failed closed D. CVC-204A, Letdown Line Isolation Stop Valve failed closed Page 5 of 75 Question:(1 point)6ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant cooldown is in progress | |||
* The "A" RHR Train is in service | |||
* At 0700 RCS temperature was 130°F Subsequently, cooling water flow is interrupted to the "A" RHR Heat Exchanger and the following is observed: Time RCS Temp 0715 146 0730 162 0745 178 Which ONE of the following correctly completes the statements below? If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 Mode 4 ____(1)____ be entered. | |||
If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 the Technical Specification Heat up limit ____(2)____ be exceeded. (REFERENCES PROVIDED)A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 6 of 75 Question:(1 point)7ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* A Pressurizer pressure instrument has failed resulting in the following: | |||
* All Pressurizer heaters are energized | |||
* RCS pressure is 2270 psig and rising Which ONE of the following correctly completes the statement below? Pressurizer Pressure channel ____(1)____ has failed LOW. | |||
Pressurizer PORV ____(2)____ will cycle open and closed to limit the RCS pressure rise. A. (1) PT-444 (2) PCV-455C B. (1) PT-444 (2) PCV-456 C. (1) PT-445 (2) PCV-456 D. (1) PT-445 (2) PCV-455C Page 7 of 75 Question:(1 point)8ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An ATWS has occurred | |||
* Immediate Actions of FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, are in progress Which ONE of the following correctly completes the statements below? Opening a MINIMUM of ____(1)____ breaker(s) in the Rod Drive MG Set Room will result in a reactor trip. OR Opening a MINIMUM of ____(2)____ breaker(s) in the 4 KV Room will result in a reactor trip. A. (1) one (2) one B. (1) one (2) two C. (1) two (2) one D. (1) two (2) two Page 8 of 75 Question:(1 point)9ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A SGTR has occurred | |||
* The crew has entered EOP-E-3, STEAM GENERATOR TUBE RUPTURE | |||
* The Subcooled Margin Monitor is OOS | |||
* The crew has initiated an RCS cooldown using the Steam Dumps to a target CET temperature Which ONE of the following correctly completes the statements below? The operator will open the steam dumps to cooldown at ____(1)____. | |||
Subsequently: | |||
* The RCS cooldown is completed | |||
* CET Temperature is being maintained at 510°F | |||
* Ruptured S/G pressure is 1000 psig | |||
* RCS pressure has stabilized at 1400 psig | |||
* The CRS directs you to report RCS Subcooling Based on current plant conditions RCS Subcooling is approximately ____(2)____°F. A. (1) a maximum of 100°F/hour (2) 30-40 B. (1) the maximum achievable rate (2) 30-40 C. (1) a maximum of 100°F/hour (2) 70-80 D. (1) the maximum achievable rate (2) 70-80 Page 9 of 75 Question:(1 point)10ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant tripped from 100% power | |||
* The crew is implementing EOP-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS | |||
* RCS Boration has been initiated | |||
* RCS temperature is 348°F and lowering | |||
* The current time in Core Life is 20,000 MWD/MTU | |||
* The current boron concentration is 100 ppm Which ONE of the following correctly completes the statements below? IAW EOP-ECA-2.1, the operator must raise the RCS boron concentration to a MINIMUM of approximately ____(1)____ to establish the Cold Shutdown boron concentration. The reactivity effects due to this event are more severe while operating at the ____(2)____-Of-Life. (REFERENCES PROVIDED) A. (1) 680-690 ppm (2) Beginning B. (1) 680-690 ppm (2) End C. (1) 760-770 ppm (2) End D. (1) 760-770 ppm (2) Beginning Page 10 of 75 Question:(1 point)11ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a loss of both MFW pumps occurred | |||
* All Service Water pumps have lost power and cannot be restored | |||
* CST level is 12% and rapidly lowering | |||
* The SDAFW pump is out of service IAW OP-402, AUXILIARY FEEDWATER SYSTEM, which ONE of the following is required to supply the OIL COOLER for operation of the "B" MDAFW pump under these conditions? A. Fire Water B. Potable Water C. Deepwell Water D. Fukushima AFW Suction Tank water Page 11 of 75 Question:(1 point)12ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating anExtended Loss of AC Power (ELAP)*A depressurization of all S/G's was initiated at 10:00*The following timeline of events is observed:Time S/G Pressures Pzr Level 10:15 500 psig 13% 10:45 190 psig 0% Which ONE of the following correctly completes the statements below? The EARLIEST time at which the depressurization is required to be stopped IAW EOP-ECA-0.0, is ____(1)____. The reason the depressurization is stopped is to ____(2)____. A. (1) 1015 (2) prevent injection of accumulator nitrogen into the RCS B. (1) 1045 (2) ensure that no reactor head voiding will occur C. (1) 1015 (2) ensure that no reactor head voiding will occur D. (1) 1045 (2) prevent injection of accumulator nitrogen into the RCS Page 12 of 75 Question:(1 point)13ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power when a loss of off-site power occurs*Fifteen seconds later an SI actuation occurred due to a Large Break LOCAWhich ONE of the following correctly completes the statements below? The BOP will expect to see the SW Booster Pumps started on the ____(1)____. SW Booster Pump suction pressure ____(2)____ have to be at least 30 psig for the SW Booster Pump to start. A. (1) Blackout Sequencer (2) does B. (1) Blackout Sequencer (2) does NOT C. (1) SI Sequencer (2) does D. (1) SI Sequencer (2) does NOT Page 13 of 75 Question:(1 point)14ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* A Startup Transformer lockout occurs Which ONE of the following describes how Instrument Buses 1 and 4 will respond to this event? A. Both Instrument Buses 1 and 4 will de-energize B. Instrument Bus 1 will remain energized; Instrument Bus 4 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus C. Instrument Bus 4 will remain energized; Instrument Bus 1 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus D. Both Instrument Buses 1 and 4 will remain energized Page 14 of 75 Question:(1 point)15ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* APP-036-D1, BATT CHARGER A/A-1 TROUBLE, annunciated. | |||
* The OAO reports the following indications from Battery Charger "A-1": * +40 Volts on the Ground Detection Voltmeter. | |||
* 135 Volts DC on Charger Voltage. Which ONE of the following correctly completes the statements below? IAW OMM-035, GROUND ISOLATION, the FIRST action the operator will take to attempt to identify the cause of the ground is ____(1)____. Subsequently, MCC-A spuriously de-energizes. Instrument Bus 2 and 7 will ____(2)____. A. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) de-energize B. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) remain energized C. (1) cycle selected breakers on Distribution Panel A (2) de-energize D. (1) cycle selected breakers on Distribution Panel A (2) remain energized Page 15 of 75 Question:(1 point)16ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a reactor trip and SI occurred | |||
* The crew has entered EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT | |||
* APP-036-D7, AREA MONITOR HI RAD, has just alarmed | |||
* APP-036-H1, WDBRP TROUBLE, has just alarmed Which ONE of the following correctly completes the statements below? IAW EOP-E-1, radiation monitor ____(1)____ would be used to diagnose a LOCA outside containment. The WDBRP TROUBLE alarm ____(2)____ consistent with a LOCA outside Containment in the Auxiliary Building. A. (1) R-3, PASS Panel Area (2) is B. (1) R-3, PASS Panel Area (2) is NOT C. (1) R-8, Drumming Room (2) is D. (1) R-8, Drumming Room (2) is NOT Page 16 of 75 Question:(1 point)17ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The reactor was tripped from 100% power due to a loss of MFW | |||
* A spurious SI has actuated | |||
* RCS Pressure - 2300 psig | |||
* All S/G pressures - 1050 psig | |||
* S/G WIDE RANGE levels are as follows: | |||
* WIDE RANGE: A - 10%, | |||
* WIDE RANGE: B - 15%, | |||
* WIDE RANGE: C - 9% | |||
* AFW flow is indicating 0 gpm | |||
* EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Immediate Actions are complete and have just been verified Which ONE (1) of the following correctly completes the statement below? The crew should ____(1)____ because ____(2)____. A. (1) remain in EOP-E-0 until directed to transition out (2) the "B" S/G is still a viable Heat Sink B. (1) remain in EOP-E-0 until directed to transition out (2) rules of usage require continuing in EOP-E-0 C. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed is required D. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed can still be avoided Page 17 of 75 Question:(1 point)18ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant has tripped from 100% power due to a LOCA | |||
* The crew is operating in EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION | |||
* RWST level is at 16% | |||
* RWST Makeup has been established in accordance with Supplement P, Emergency Makeup To The RWST | |||
* The only ECCS Pump drawing on the RWST is the "A" SI Pump and pump flow has been adjusted to 150 gpm. Which ONE of the following correctly completes the statements below? IAW EOP-ECA-1.1, the EARLIEST that the "A" SI Pump must be stopped is when the RWST Level lowers to ____(1)____. Assuming these conditions remain the same, four hours from now the RWST level will be ____(2)____. A. (1) 9% (2) higher B. (1) 9% (2) lower C. (1) 13% (2) higher D. (1) 13% | |||
(2) lower Page 18 of 75 Question:(1 point)19ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 50% power | |||
* During the performance of OST-011, ROD CLUSTER CONTROL EXERCISE & ROD POSITION INDICATION, ONE Control Bank "B" rod is 17 steps below the rest of the bank | |||
* The crew is performing the steps to realign the rod IAW AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM Which ONE of the following correctly completes the statements below? 1) IAW AOP-001, OPEN the Control Bank "B" lift coil switch(es) for ____(1)____. 2) Realign the rod using the ____(2)____ position of the rod bank selector switch. A. (1) the misaligned rod ONLY (2) CB B B. (1) the misaligned rod ONLY (2) M (MANUAL) C. (1) all but the misaligned rod (2) CB B D. (1) all but the misaligned rod (2) M (MANUAL) Page 19 of 75 Question:(1 point)20ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The Pressurizer Level Channel Selector Switch is selected to NORMAL*The reference leg for Pressurizer level Transmitter LT-459 develops a slow leak*The "A" Charging Pump is running in AUTOWhich ONE of the following describes the instrument response? LT-459 __LT-460__ A. rises lowers B. lowers remains the same C. rises remains the same D. lowers rises Page 20 of 75 Question:(1 point)21ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A reactor startup is being commenced | |||
* Source Range count rate (CR0) prior to control bank rod withdrawal is as follows: | |||
* N31: 3.0E+001 cps | |||
* N32: 3.0E+001 cps Subsequently: | |||
* The crew has completed the MINIMUM number of doublings required to allow the crew to withdraw control rods as necessary to achieve criticality IAW GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL | |||
* The following indications are observed: | |||
* N31: 2.4E+002 cps | |||
* N32: 1.2E+002 cps Which ONE of the following correctly completes the statement below? IAW GP-003, Source Range Channel ____(1)____ is indicating AS EXPECTED. When the Source Range Channel with the unexpected reading is removed from service per the appropriate OWP, the reactor startup ____(2)____ continue. A. (1) N31 (2) may B. (1) N31 (2) may not C. (1) N32 (2) may D. (1) N32 (2) may not Page 21 of 75 Question:(1 point)22ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A Reactor startup is in progress | |||
* The following indications are observed: | |||
* N31/32 = 900 cps | |||
* N35/36 = 5 x 10-11 amps Subsequently: | |||
* Intermediate Range (IR) channel N36 fails LOW | |||
* The crew places the Reactor startup on HOLD Which ONE of the following correctly completes the following statement? The reason that the reactor startup is placed on HOLD is because a Reactor Protection Trip Function for the ________ accident is degraded. A. rod ejection B. boron dilution C. steam line break D. uncontrolled RCCA bank rod withdrawal Page 22 of 75 Question:(1 point)23ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An accidental gaseous radwaste release is in progress | |||
* R-1, Control Room Area Radiation Monitor, alarms | |||
* R-1 is indicating 8.62E-2 mR/hr and stable Which ONE of the following correctly completes the statements below? R-1 ____(1)____ operating properly. | |||
When R-1 alarms, the CR HVAC will automatically shift to the Emergency ____(2)____ Mode. A. (1) is (2) Recirculation B. (1) is (2) Pressurization C. (1) is NOT (2) Recirculation D. (1) is NOT (2) Pressurization Page 23 of 75 Question:(1 point)24ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* The following is observed on the Fire Alarm Console: (SEE REFERENCE CONDITIONS ON NEXT PAGE) Which ONE of the following correctly completes the statements below? It is expected that the automatic water suppression system ____(1)____ actuate for these conditions. Based on this information, the entry conditions ____(2)____ met for AOP-041, RESPONSE TO FIRE EVENTS. A. (1) will (2) are B. (1) will (2) are NOT C. (1) will NOT (2) are D. (1) will NOT (2) are NOT Page 24 of 75 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* With the plant at 100%, a confirmed bomb threat has been received | |||
* The caller specified that the bomb was located in the Control Room | |||
* The following timeline of events is recorded: 2110 The Control Room was evacuated after all appropriate actions were taken 2145 A Control operator in the Charging Pump Room informs the SM that: | |||
* N51 reads 3.0E5 cps and is slowly lowering | |||
* Pressurizer pressure is 2225 psig | |||
* Pressurizer level is 35% | |||
* The "A" Charging Pump is operating Which ONE of the following correctly completes the statements below? IAW Attachment 1 of AOP-004, CONTROL ROOM INACCESSIBILITY, the operator will raise Pressurizer level to at LEAST greater than ____(1)____, and then stop the running Charging Pump. | |||
The basis for this action is to ____(2)____. A. (1) 60% (2) prevent exceeding the Charging Pump starting duty limitations B. (1) 60% (2) ensure that the reactor is subcritical C. (1) 86% | |||
(2) ensure that the reactor is subcritical D. (1) 86% | |||
(2) prevent exceeding the Charging Pump starting duty limitations Page 25 of 75 Question:(1 point)26ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The R-9, Letdown Line Area, indication on Radiation Monitoring System Recorder RR-1 is rising Which ONE of the following correctly completes the statements below? If the trend continues, it is expected that ____(1)____. The basis for the R-9 setpoint is to detect ____(2)____. A. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) small leaks in fuel rods B. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) release of resin from the in-service demineralizers C. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) small leaks in fuel rods D. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) release of resin from the in-service demineralizers Page 26 of 75 Question:(1 point)27ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* EOP-ECA-0.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED has been implemented | |||
* The crew is checking for Natural Circulation with the following conditions: | |||
* Containment pressure is 0.5 psig | |||
* Steam dump using the S/G PORVs is in progress | |||
* RCS subcooling based on CETs are 33°F and stable | |||
* CETC are 555°F and stable | |||
* S/G pressures are stable at 900 psig | |||
* RCS Hot Leg temperatures are 555°F and stable | |||
* RCS Cold Leg temperatures are 545°F and slowly rising | |||
* S/G NR levels are 21% and stable Which ONE of the following correctly completes the statements below? Based on the indications above, Natural Circulation (NC) flow ____(1)____ been established. IAW EOP-ECA-0.1, the crew will ____(2)____. A. (1) has NOT (2) raise S/G levels to promote the establishment of NC flow B. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 9% C. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 18% D. (1) has NOT (2) raise the rate of dumping steam to promote the establishment of NC flow Page 27 of 75 Question:(1 point)28ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power when a transient occurs | |||
* Over 15-20 seconds a load rejection lowers and then stabilizes power at 80% Which ONE of the following correctly completes the statements below? Seal water injection flow will INITIALLY ____(1)____. Subsequently, | |||
* APP-001-B4, RCP SEAL INJ HI/LO FLOW, has alarmed | |||
* The CRS has directed use of the expanded seal water injection flow control band The expanded seal water injection flow control band is ____(2)____. A. (1) rise (2) 6-20 gpm B. (1) rise (2) 7-18 gpm C. (1) lower (2) 6-20 gpm D. (1) lower (2) 7-18 gpm Page 28 of 75 Question:(1 point)29ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is in Mode 3 | |||
* APP-003-E2, VCT HI/LO PRESS, has alarmed | |||
* Actual VCT pressure is 15 psig Which ONE of the following correctly completes the statement below? If VCT pressure continues to lower, RCP #1 Seal Leakoff flow will ____(1)____ and RCP #2 Seal leakoff flow will ____(2)____. A. (1) lower (2) rise B. (1) rise (2) lower C. (1) rise (2) rise D. (1) lower (2) lower Page 29 of 75 Question:(1 point)30ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*Due to RTGB indications the crew has entered AOP-024, LOSS OF INSTRUMENT BUS*An Auto Makeup to the VCT has initiated on the loss of instrument busWhich ONE of the following correctly completes the statement below? The Auto makeup has occurred because VCT Level transmitter ____(1)____ has de-energized on a loss of Instrument Bus ____(2)____. A. (1) LT-112 (2) 7 B. (1) LT-112 (2) 9 C. (1) LT-115 (2) 7 D. (1) LT-115 (2) 9 Page 30 of 75 Question:(1 point)31ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *A plant cooldown is in progress*The "A" RHR Train is in service*RCS temperature is 190°F*RCS Pressure is 350 psig*The RCS is in Solid Plant Operation with LTOPP in serviceSubsequently, a transient occurs resulting in the following: *RCS temperature is 195°F*RCS Pressure is 420 psig*PZR PORV PCV-456 indicates OPEN*PZR PORV PCV-455C indicates CLOSEDThe crew has entered AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Which ONE of the following correctly completes the statements below? Based on plant conditions, both PORVs should have ____(1)____. IAW AOP-019 immediate actions, the operator will FIRST ____(2)____ to control or mitigate the consequences of this event. A. (1) remained closed (2) close PCV-456 B. (1) opened (2) stop all Charging Pumps and RCPs C. (1) opened (2) ensure the block valve for PCV-456 is OPEN D. (1) remained closed (2) place the PCV-456 LTOPP Arming Switch to NORMAL Page 31 of 75 Question:(1 point)32ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: * "A" Train RHR is in service | |||
* Instrument Air pressure lowers to 30 psig Which ONE of the following correctly completes the statement below? RCS temperature will INITIALLY ____(1)____, and RHR System Flow will INITIALLY ____(2)____. A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Lower (2) Lower D. (1) Lower (2) Rise Page 32 of 75 Question:(1 point)33ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% RTP | |||
* The following timeline is observed: TIME "A" SI accumulator pressure"A" SI accumulator level1108 637 psig 68 percent 1111 646 psig 70 percent 1114 660 psig 75 percent Which ONE of the following correctly completes the statement below? The EARLIEST time at which an RTGB annunciator alarm would occur is at time ____(1)____, due to ____(2)____ reaching its alarm setpoint. A. (1) 1111 (2) APP-002-A4, SI ACCUM A HI/LO LVL B. (1) 1114 (2) APP-002-B4, SI ACCUM A HI/LO PRESS C. (1) 1111 (2) APP-002-B4, SI ACCUM A HI/LO PRESS D. (1) 1114 (2) APP-002-A4, SI ACCUM A HI/LO LVL Page 33 of 75 Question:(1 point)34ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% power when a LOCA occurs inside Containment Which ONE of the following correctly completes the statements below? While operating in the EOP Network, the LOWEST pressure in which "Adverse" containment values are applicable is ____(1)____. Based on the increased containment temperature, level detectors with wet reference legs will indicate ____(2)____ than the actual level. A. (1) 4 psig (2) lower B. (1) 4 psig (2) higher C. (1) 10 psig (2) lower D. (1) 10 psig (2) higher Page 34 of 75 Question:(1 point)35ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* Containment pressure is 0.2 psig | |||
* Containment temperature is 94°F Subsequently: | |||
* A load rejection results in a reactor trip | |||
* Following the trip, a Pressurizer Safety valve opens, and will NOT reseat | |||
* The PRT rupture disks function as designed | |||
* Containment pressure is rising at 0.1 psig every 5 minutes | |||
* Containment temperature is rising at 2°F every 5 minutes Assuming these conditions remain constant, which ONE of the following identifies the Containment Technical Specifications LCOs that will be affected one hour from now? A. Both LCO 3.6.4, Containment Pressure, and LCO 3.6.5, Containment Air Temperature, will be exceeded. B. Only LCO 3.6.4, Containment Pressure, will be exceeded. C. Only LCO 3.6.5, Containment Air Temperature, will be exceeded. D. Neither LCO 3.6.4, Containment Pressure, nor LCO 3.6.5, Containment Air Temperature, will be exceeded. Page 35 of 75 Question:(1 point)36ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
T= 1305:10 | |||
* A loss of off-site power has occurred concurrent with a Reactor trip | |||
* The crew enters EOP-E-0, Reactor Trip or Safety Injection T=1307:40 | |||
* Immediate actions of EOP-E-0 are complete | |||
* The following parameters are noted: | |||
* RCS pressure is 2110 psig and stable | |||
* SG pressures are all 910 psig and lowering slowly | |||
* CV pressure is 0.7 psig and rising slowly At time 1307:40, which ONE of the following describes the CCW Pump indication available in the control room? A. "B" and "C" CCW Pump RED indicating lights are LIT. "A" CCW Pump GREEN indicating light is LIT. B. All 3 CCW Pump control switch GREEN indicating lights are LIT. C. "B" and "C" CCW Pump GREEN indicating lights are LIT; "A" CCW Pump RED indicating light is LIT. D. "B" and "C" CCW Pump RED indicating lights are LIT; "A" CCW Pump GREEN and RED indicating lights are EXTINGUISHED. Page 36 of 75 Question:(1 point)37ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant The plant is at 100% power when the following occurs: | |||
* A load rejection results in a PZR PORV actuation | |||
* The PZR PORV will not fully seat | |||
* The depressurization led to a Reactor Trip and Safety Injection | |||
* PZR pressure reduces to 1400 psig and stabilizes | |||
* The PRT rupture discs rupture at their design setpoint | |||
* Containment pressure peaks at 15 psig Which ONE of the following is the MAXIMUM temperature indicated by the Safety Valve tailpiece RTD during the entire event? A. 213°F B. 250°F C. 298°F D. 338°F Page 37 of 75 Question:(1 point)38ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following identifies a condition which will cause an automatic reactor trip? A. RCP bus frequency reads 58.0 Hz when THREE Power Range channels read 5% RTP. B. Flow in ONE Reactor Coolant Loop reads 91% when ALL Power Range channels read 35% RTP. C. ONE Intermediate Range NI channel reads 1 x10E-6 AMPS when TWO Power Range channels read 15% RTP. D. ONE Source Range NI channel reads 5 x10E5 CPS when TWO Intermediate Range NI channels read 9 x10E-11 AMPS. Page 38 of 75 Question:(1 point)39ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant was at 100% when a SI occurredWhich ONE of the following correctly completes the statements below regarding the Feed Reg Valves and the Feed Reg Bypass Valves? Following the SI signal, the Feed Reg Bypass Valves ____(1)____ receive a CLOSE signal. The Feed Reg Valves ____(2)_____ be available when the SI is RESET and the Feedwater Isolation OVRD/RESET key switches are placed in OVRD/RESET. A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 39 of 75 Question:(1 point)40ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below regarding the Containment Spray Actuation logic scheme? | |||
The MINIMUM number of Containment Pressure channels that must sense pressure greater than the Hi-Hi pressure setpoint to generate an automatic Containment Spray Actuation is ____(1)____. The Containment Spray Actuation bistables are ____(2)____ to actuate. A. (1) Two (2) Energize B. (1) Two (2) De-energize C. (1) Four (2) Energize D. (1) Four (2) De-energize Page 40 of 75 Question:(1 point)41ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*A realignment has just occurred and the operator observes the following Service Watervalve alignments for HVH-1 (CV Recirc Fan A) and HVH-2 (CV Recirc Fan B):Assuming no conditions change, which ONE of the following identifies the operational restrictions, if any, placed on HVH-1? A. HVH-1 may run continuously, there are no restrictions. B. HVH-1 may continue to run for up to 15 additional minutes. C. HVH-1 must be immediately secured and cannot be run under these conditions. D. HVH-1 must be immediately secured and can ONLY be started during emergencies. Page 41 of 75 Question:(1 point)42ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant was at 100% | |||
* A LOCA inside containment occurs and the following timeline is observed: TIME OBSERVATION 1200 LOCA occurs 1201 CV Spray system actuates 1211 CV Pressure peaks at 22 PSIG 1235 CV Pressure lowers to less than 10 PSIG 1245 CV Pressure lowers to less than 4 PSIG Which ONE of the following correctly completes the statements below? IAW EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, the EARLIEST TIME that the Containment Spray Pumps may be secured is ____(1)____. | |||
In order to successfully reset the Phase B Containment Isolation signal, the Containment Spray Signal ____(2)____ required to be reset FIRST. A. (1) 1235 (2) is B. (1) 1235 (2) is NOT C. (1) 1245 (2) is D. (1) 1245 (2) is NOT Page 42 of 75 Question:(1 point)43ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*R-15, Air Ejector Radiation Monitor, alarms*The crew entered AOP-035, S/G TUBE LEAK*The crew has initiated Attachment 5, R-15 Monitoring*Chemistry reports the following leakrates:Time "A" S/G Tube leakrate 0800 31 gpd 0900 51 gpd 1000 81 gpd 1100 111 gpd IAW AOP-035, which ONE of the following identifies the EARLIEST time that a plant shutdown is required? A. 0800 B. 0900 C. 1000 D. 1100 Page 43 of 75 Question:(1 point)44ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occursWhich ONE of the following describes how this actuation affects the Reactor and the Main Turbine? A. BOTH the Reactor and the Main Turbine receive trip signals directly from the FWIS. B. The Reactor receives a trip signal directly from the FWIS, and causes a Main Turbine trip. C. The Main Turbine receives a trip signal directly from the FWIS and the Reactor will trip because the Main Turbine tripped with power above P-8. D. NEITHER the Reactor nor the Main Turbine receive trip signals directly from the FWIS. However, the Reactor will trip on plant conditions created by the FWIS actuation and cause a Main Turbine trip. Page 44 of 75 Question:(1 point)45ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power, an ATWS event occurred*The crew entered FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION ATWS*All SG Narrow Range levels are OFF-Scale LOWWhich ONE of the following correctly completes the statement below? IAW FRP-S.1, AFW flow must be greater than a MINIMUM value of ________ to establish a Secondary Heat Sink? A. 300 gpm B. 500 gpm C. 600 gpm D. 1000 gpm Page 45 of 75 Question:(1 point)46ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* A reactor trip has occurred Which ONE of the following identifies the breakers which will automatically CLOSE one minuteafter the reactor trip? Breaker nomenclature: 52/10 4KV BUS 1-2 TIE BKR 52/12 START-UP TRANSFORMER TO 4KV BUS 2 52/17 START-UP TRANSFORMER TO 4KV BUS 3 52/19 4KV BUS 3-4 TIE BKR A. 52/10 and 52/12 B. 52/10 and 52/17 C. 52/12 and 52/19 D. 52/17 and 52/19 Page 46 of 75 Question:(1 point)47ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on faultWhich ONE of the following correctly completes the statement below? Circulating Water pump(s) _________ lost power. A. "A" & "B" have B. "B" & "C" have C. "A" & "C" have D. "B" ONLY has Page 47 of 75 Question:(1 point)48ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is in Mode 3*The "B" Battery Charger is in service*The "B-1" Battery Charger is in standbySubsequently: *MCC-6 is de-energized*APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms*Two minutes later MCC-6 is re-energizedWhich ONE of the following identifies when APP-036-D2 will clear? APP-036-D2 will clear-- A. when the "B" Battery Charger automatically restarts. B. only after the operator manually restarts the "B" Battery Charger. C. only after the operator manually places the "B-1" Battery Charger back in the STANDBY mode. D. only after the operator manually restarts the "B" Battery Charger and places the "B-1" Battery Charger back in the STANDBY mode. Page 48 of 75 Question:(1 point)49ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*OST-401-1, EDG "A" SLOW SPEED START testing is in progress*Current "A" EDG load is 2500 KWSubsequently: *The Normal Supply Breaker to E-1, 52/18B, opens*EDG "A" Output Breaker 52/17B, opensWhich ONE of the following correctly completes the statements below? IAW OP-604 CAUTION statement, the consequence of opening the EDG "A" Output Breaker under load is ____(1)____. IAW OP-604 when attempting to recover, the local Generator Parallel/Isolate Switch must be placed in the ____(2)____ position. OP-604, DIESEL GENERATORS "A" AND "B" A. (1) the diesel engine may trip due to overspeed (2) ISOL B. (1) excessive carbon buildup in the engine could occur (2) PARALLEL C. (1) the diesel engine may trip due to overspeed (2) PARALLEL D. (1) excessive carbon buildup in the engine could occur (2) ISOL Page 49 of 75 Question:(1 point)50ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following supplies power to the "A" and "B" EDG Fuel Oil Transfer Pumps? A. MCC-10 and MCC-9 respectively B. MCC-9 and MCC-10 respectively C. MCC-6 and MCC-5 respectively D. MCC-5 and MCC-6 respectively Page 50 of 75 Question:(1 point)51ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The reactor is at 100%*The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIRHANDLING*R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarmsV12-12, CV VAC RELIEF V12-13, CV VAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE of the following correctly completes the statements below? The crew would expect to see ____(1)____ annunciator flashing. Due to the conditions above, ____(2)____ will automatically close. A. (1) APP-036-D7 (2) V12-12 & V12-13 ONLY B. (1) APP-036-D8 (2) V12-12 & V12-13 ONLY C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Page 51 of 75 Question:(1 point)52ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*R-19A, STM GEN BLOW DN SG-A, enters the alarm conditionWhich ONE of the following correctly completes the statements below? In regards to the Blowdown Isolation Valves and the Blowdown Sample Isolation Valves, an alarm condition on R-19A will automatically close the ____(1)____. IAW AOP-005, RADIATION MONITORING SYSTEM, if the automatic actions fail to occur, the crew ____(2)____ de-energize R-19A in an attempt to cause the automatic actions to occur. A. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will D. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will NOT Page 52 of 75 Question:(1 point)53ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following correctly completes the statements below regarding components normally cooled by Service Water? The Circulating Water Pumps ____(1)____ be cooled by the Fire Water System during an emergency. The Control Room HVAC Cooling Units ____(2)____ be cooled by the Fire Water System during an emergency. A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can NOT D. (1) can NOT (2) can Page 53 of 75 Question:(1 point)54ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power * "D" IA Compressor is running | |||
* Station Air Compressor is running Subsequently: | |||
* IA Header pressure is 79 PSIG and lowering | |||
* The crew is implementing AOP-017, LOSS OF INSTRUMENT AIR SA-5, STATION AIR TO INST AIR CROSS CONNECT SA-220, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION SA-221, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION Which ONE of the following correctly completes the statements below? IAW AOP-017, the PREFERRED method to cross connect IA from Station Air is by opening ____(1)____ . | |||
IA will no longer be used to supply Breathing Air to ____(2)____. A. (1) SA-5 (2) minimize IA loads ONLY B. (1) SA-5 (2) minimize IA loads and prevent harm to users of Breathing Air C. (1) SA-220 and SA-221 (2) minimize IA loads ONLY D. (1) SA-220 and SA-221 (2) minimize IA loads and prevent harm to users of Breathing Air Page 54 of 75 Question:(1 point)55ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A LOCA occurred 45 minutes ago | |||
* The crew is implementing the Emergency Operating Procedures | |||
* The following conditions exist: | |||
* CET temperature is 340°F | |||
* RCS pressure is 60 psig and lowering | |||
* Full Range RVLIS is 40% | |||
* RCS Cold Leg temperature is 320°F and lowering | |||
* S/G NR levels are off-scale LOW | |||
* S/G pressures are 550 psig and trending down | |||
* AFW flow is 450 gpm | |||
* All RCPs are OFF | |||
* CV pressure is 43 psig and rising | |||
* SPDS has been reset Which ONE of the following identifies the MOST challenged Critical Safety Function? A. Integrity B. Heat Sink C. Containment D. Core Cooling Page 55 of 75 Question:(1 point)56ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power Subsequently, all IRPI indication is lost except a green LED is illuminated on each rod indicator Which ONE of the following correctly completes the statements below? The cause of this condition is the ____(1)____ has tripped. | |||
For this condition entry into AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, ____(2)____ required. A. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is B. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is D. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is NOT Page 56 of 75 Question:(1 point)57ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* GP-008, DRAINING THE REACTOR COOLANT SYSTEM, is in progress | |||
* The crew has positioned HIC-142, PURFICATION FLOW, to establish required drain rate Which ONE of the following correctly completes the statements below? LCV-115A, VCT/HLDP TK DIV, will begin to divert at ____(1)____ in the VCT. | |||
IAW GP-008, ____(2)____ level change can be used to determine the volume drained from the RCS. A. (1) 30" (2) WHUT B. (1) 30" (2) CVCS HUT C. (1) 51.6" (2) CVCS HUT D. (1) 51.6" (2) WHUT Page 57 of 75 Question:(1 point)58ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 35% power and stable | |||
* The "A" Charging Pump is running in AUTO | |||
* The "B" Charging Pump is running in MANUAL and adjusted to 50% output on Charging Pump Speed Controller SC-151 | |||
* Letdown flow is 105 gpm Subsequently: | |||
* Letdown flow is lowered 45 gpm | |||
* Reactor power is lowered to 30% and stabilized | |||
* Pressurizer Level lowers to, and has stabilized at 31.5% Which ONE of the following correctly completes the statements below? The Pressurizer Level Control System ____(1)____ operating as expected for these plant conditions. While Letdown was being lowered, APP-003-F3, CHG PMP LO SPEED, alarmed. According to OP-301, CHEMICAL AND VOLUME CONTROL SYSTEM, the operator will be required to ____(2)____ Charging Pump to clear the alarm. A. (1) is (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" B. (1) is (2) adjust the speed of the "B" C. (1) is NOT (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" D. (1) is NOT (2) adjust the speed of the "B" Page 58 of 75 Question:(1 point)59ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The Plant is in Mode 1, following a control rod manipulation | |||
* The RTGB IRPI indication for Control Bank "D" Rod M-8 indicates 120 inches | |||
* The RTGB IRPI indication for Control Bank "D" Rod H-4 indicates 110 inches | |||
* Control Bank "D" step counter position is 192 steps Which ONE of the following correctly completes the statements below? Based on the given conditions, control rod ____(1)____ is stuck. Assuming the average of the individual rod positions in the affected bank indicate 120 inches, entry into ITS LCO 3.1.4, ROD GROUP ALIGNMENT LIMITS, ____(2)____ required. A. (1) M-8 (2) is B. (1) M-8 (2) is NOT C. (1) H-4 (2) is D. (1) H-4 (2) is NOT Page 59 of 75 Question:(1 point)60ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The operator is reviewing the T/C TREND pages on both the Train "A" and Train "B" ICCM displays Which ONE of the following correctly completes the statements below? The TOTAL number of Core Exit Thermocouples (CET) that monitor the core is ____(1)____. The T/C TREND page displays the average of ____(2)____ CET indications over the last 30 minutes. A. (1) 23 (2) the five highest B. (1) 23 (2) all C. (1) 46 (2) all D. (1) 46 (2) the five highest Page 60 of 75 Question:(1 point)61ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE (1) of the following is the power supply for HVE-3, CV Air Iodine Removal Fan? A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-10 Page 61 of 75 Question:(1 point)62ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW GP-010, REFUELING, the Containment Purge System ____(1)____ required be in operation during Core Alterations with the Equipment Hatch removed. | |||
The Containment Purge System ____(2)____ required be in operation if a Containment entry is being made with the plant in Mode 1. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 62 of 75 Question:(1 point)63ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* Spent fuel handling activities are NOT in progress Subsequently: | |||
* SFP level starts to rapidly lower due to a large structural and piping failure | |||
* The crew has entered AOP-036, SFP EVENTS R-14, Plant Vent Effluent Monitor R-21, Fuel Handling Building Upper Level, Noble Gas HVE-15, Fuel Handling Building Exhaust Fan Which ONE of the following correctly completes the statements below? IAW AOP-036, R-14 ____(1)____ monitored for indications of fuel damage. | |||
If R-21 were to subsequently alarm, HVE-15 ____(2)____ automatically trip. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 63 of 75 Question:(1 point)64ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* The SDAFW Pump is OOS Subsequently: | |||
* The crew trips the reactor and initiates safety injection due to a SGTR on the "B" Steam Generator | |||
* V2-16A, AFW Header Discharge Valve, has failed CLOSED | |||
* The "B" MDAFW Pump trips on auto-start * "B" SG NR level is 6% and rising slowly * "A" and "C" SG NR levels are off-scale low Which ONE of the following correctly completes the statements below? Without operator action, a Secondary Heat Sink ____(1)____ established. | |||
Based on the current conditions, the operator ____(2)____ immediately isolate feed to the "B" S/G. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 64 of 75 Question:(1 point)65ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following discharges to the Reactor Coolant Drain Tank? A. RCV-609, CC SURGE TANK VENT B. CVC-203 A/B, LETDOWN RELIEF VALVES C. CVC-389, EXCESS LETDOWN DIVERSION D. CVC-400 A/B/C, CHARGING PUMP "A/B/C" LEAKAGE ISOLATION Page 65 of 75 Question:(1 point)66ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW OPS-NGGC-1303, VERIFICATION PRACTICES, guidance for waiving Independent Verification (IV) requirements states that the IV may be waived if the operators were expected to ____(1)____ to complete the verification. | |||
In these cases, ____(2)____ Verification will be used as an alternative to Independent Verification. A. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Concurrent B. (1) receive a total exposure of greater than 10 mrem (2) Concurrent C. (1) receive a total exposure of greater than 10 mrem (2) Functional D. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Functional Page 66 of 75 Question:(1 point)67ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions: | |||
* The plant is in MODE 6 for refueling operations | |||
* Core alterations are in progress Which ONE of the following correctly completes the statements below? IAW LCO 3.9.2, NUCLEAR INSTRUMENTATION, ____(1)____ shall be OPERABLE. N-51 and N-52, ____(2)____ capable of providing audible indication inside Containment. N-31, N-32, SOURCE RANGE NUCLEAR INSTRUMENTS N-51, N-52, REG. GUIDE 1.97 NEUTRON FLUX (SOURCE RANGE, WIDE RANGE) A. (1) either N-31 OR N-32 (2) are B. (1) both N-31 AND N-32 (2) are C. (1) either N-31 OR N-32 (2) are NOT D. (1) both N-31 AND N-32 (2) are NOT Page 67 of 75 Question:(1 point)68ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant startup is in progress | |||
* NIS Power Indication is 50% | |||
* The STA is recording data IAW GP-005, POWER OPERATION, Attachment 1, REACTOR POWER ASCENSION INDICATOR LOG Which ONE of the following correctly completes the statements below? IAW GP-005, if Core T indicates 33°F, the crew ____(1)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). IAW GP-005, if Calorimetric power indicates 51.5%, the crew ____(2)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Page 68 of 75 Question:(1 point)69ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The FWUFM System has been OOS for five days Subsequently: | |||
* An AO reports a steam leak near the Main Steam Isolation Valves | |||
* The following indications are noted in the Control Room: | |||
* Tavg is LOWERING | |||
* Steam flow and feed flow have RISEN | |||
* A Power Limit Warning alarm on ERFIS has been received | |||
* Reactor power is slowly RISING Which ONE of the following identifies the MAXIMUM thermal power limit allowed by the operating license under these conditions? A. 2300 MWt B. 2307 MWt C. 2339 MWt D. 2346 MWt Page 69 of 75 Question:(1 point)70ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band. Which ONE of the following correctly completes the statement below? IAW Technical Specification LCO 3.2.3 ACTION--. Restore AFD to within target band within ___(1)___. If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___. A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour Page 70 of 75 Question:(1 point)71ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power | |||
* Letdown flow is 45 gpm | |||
* The "A" Charging Pump is operating in AUTO | |||
* The "B" Charging Pump is operating in MANUAL Subsequently: | |||
* R-9, Letdown Line Area Monitor, alarms | |||
* The alarm is determined to be valid | |||
* The crew enters AOP-005, RADIATION MONITORING SYSTEM Which ONE of the following correctly completes the statements below? IAW with Attachment 9 of AOP-005, the operator ____(1)____ required to evacuate the Aux Building of non-essential personnel. | |||
IAW with Attachment 9 of AOP-005, the operator ____(2)____ required to isolate letdown flow. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 71 of 75 Question:(1 point)72ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* An operator has been assigned work in the radiologically controlled area | |||
* The dose rate in the area is 500 mR/hr | |||
* The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension? A. 1 hour B. 3 hours C. 4 hours D. 7 hours Page 72 of 75 Question:(1 point)73ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* A plant cooldown is in progress | |||
* RCS Temperature is 430°F | |||
* RCS pressure is 725 psig | |||
* The SI Accumulators have been isolated Subsequently, an RCS leak occurs and the operating crew enters AOP-016, EXCESSIVE RCS LEAKAGE. | |||
Which ONE of the following correctly completes the statements below? AOP-016 will ensure that a MINIMUM of ____(1)____ Charging Pumps are running with their speed adjusted to maximum. | |||
With the current plant conditions, if Pressurizer level continues to lower uncontrollably with maximum charging flow, the crew would transition to ____(2)____. A. (1) two (2) AOP-033, SHUTDOWN LOCA B. (1) two (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION C. (1) three (2) AOP-033, SHUTDOWN LOCA D. (1) three (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 73 of 75 Question:(1 point)74ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is at 100% power | |||
* The Control Room receives a confirmed report of a fire in the Unit 2 Cable Spread Room (Fire Zone 19) at 0730 Which ONE of the following correctly completes the statements below? IAW AOP-041, RESPONSE TO FIRE EVENT, the operator must ____(1)____. The LATEST time that this action may be complete is ____(2)____. A. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0740 B. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0745 C. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (2) 0745 D. (3) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (4) 0740 Page 74 of 75 Question:(1 point)75ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: | |||
* The plant is operating at 100% power Subsequently, the following time line of events occur: TIME EVENT 1200 APP-009-C5, MAIN TRANSF TROUBLE, alarms 1203 The Outside AO reports that all Main Transformer Fans and Pumps are NOT operating 1204 The crew enters AOP-037, LARGE TRANSFORMER MALFUNCTIONS 1208 TIME NOW IAW AOP-037, which ONE of the following identifies the EARLIEST time that the reactor must be tripped? A. IMMEDIATELY B. 1211 C. 1214 D. 1231 Page 75 of 75 RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-7 Amendment No.218 0 2550751000 1250 1500 1750 2000 2250 2500 2750 0 5100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) MATERIALS PROPERTIES BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Curves applicable for heatup rates up to 60 ºF/Hr for Service period up to 35 EFPY. Heatup Curves include +10ºF and -60 psig allowance For instrumentation error. Acceptable Operation Unacceptable Operation Leak Test Limit Heatup Rate to 60 ° F/Hr Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 35 EFPY Indicated Pressure (psig) Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-8 Amendment No. 218 0 250 500 750 1000 1250 1500 1750 2000 2250 2500 2750 0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) Unacceptable Operation Acceptable Operation 100°F/ Hr Cooldown Rates ( ° F/Hr) 0 ° F/Hr. Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY 60°F/ Hr 40°F/ Hr 20°F/ Hr 100 60 40 0 and 20 Curves applicable for cooldown rates up to 100°F/Hr for the service period up to 35 EFPY. Curves include +10°F and -60 PSIG allowance for instrument error. Indicated Pressure (PSIG) MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 and Girth Weld 10-273 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F 3/4T, 147°F and 172°F REV. REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR5007009001100 1300150017000200040006000800010000120001400016000180002000022000CYCLE EXPOSURE (MWD/MTU)CURVE 1.14BORON CONCENTRATION REQUIRED TO MAINTAINSHUTDOWN MARGIN BORON (PPM)HBR2 CYCLE 30200 F300 F350 FA MINIMUM OF 2.6% SHUTDOWN MARGIN(ARI-MRR)38 FRNP Cycle 30 Curve Book Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve BookRNP-F/NFSA-0237, Rev. 0 Page A46 of A86 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer1B2D3C4C5B6B7B8B9D10C11A12D13D14B15A16A17B18B19C20A21B22D23D24D25CPrinted 2/11/2016 2:53:31 PMPage 1 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer26A27D28C29B30C31B32B33C34B35B36A37D38D39C40C41B42C43C44C45C46C47B48A49A50DPrinted 2/11/2016 2:53:32 PMPage 2 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer51D52C53D54D55C56C57B58B59C60D61A62B63A64B65C66C67D68B69A70A71B72B73A74D75BPrinted 2/11/2016 2:53:32 PMPage 3 of 3}} | |||
Revision as of 20:01, 28 May 2018
| ML16061A453 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/01/2016 |
| From: | NRC/RGN-II |
| To: | Carolina Power & Light Co |
| References | |
| Download: ML16061A453 (82) | |
Text
Question:(1 point)1ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The "A" Reactor Trip Bypass Breaker has been placed in service for testing*The "A" Reactor Trip Breaker has been removed from service*A transient condition exists requiring a reactor trip*The OAC depresses the manual reactor trip pushbutton prior to an RPS setpoint beingreachedWhich ONE of the following describes the plant response? The "A" Reactor Trip Bypass Breaker opens due to actuation of its ____(1)____ and the "B" Reactor Trip Breaker opens due to actuation of its ____(2)____. A. (1) UV trip, ONLY (2) UV trip, ONLYB. (1) UV trip, ONLY (2) UV and shunt trip C. (1) UV and shunt trip (2) UV trip, ONLY D. (1) UV and shunt trip (2) UV and shunt trip Page 1 of 75 Question:(1 point)2ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- A transient results in both Pressurizer PORVs opening and sticking OPEN after pressure lowers below the OPEN setpoint
- When the operator attempts to close the Block Valves for each PORV, the OATC observes that the status lights for Block Valves RC-535 and RC-536 are all EXTINGUISHED Subsequently, the CRS directs that the power to each Block Valve be restored. RC-535, Block Valve to Pressurizer PORV PCV-456 RC-536, Block Valve to Pressurizer PORV PCV-455C Which ONE of the following identifies the location(s) to which the operator must be dispatched to close the breakers for the Block Valves? The operator must proceed to-- A. MCC-5 for BOTH RC-535 and RC-536 B. MCC-5 for RC-535; and MCC-6 for RC-536 C. MCC-5 for RC-536; and MCC-6 for RC-535 D. MCC-6 for BOTH RC-535 and RC-536 Page 2 of 75 Question:(1 point)3ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*"A" CV Spray pump is out of service for maintenanceSubsequently: *A SBLOCA occurred at 0930 coincident with a Loss of Offsite Power*"B" EDG tripped immediately after starting*At 1000, the crew is performing the actions of EOP-E-1, LOSS OF REACTOR ORSECONDARY COOLANT with the following current plant conditions:*CV pressure: 11 psig and rising slowly*CV Sump level: 178 inches and rising*CV radiation level: 0.5 R/hr*"A" Loop Cold Leg temperature: 338 °F*"B" Loop Cold Leg temperature: 425 °F*"C" Loop Cold Leg temperature: 427 °FWhich ONE of the following correctly completes the statements below? CSF-4 Integrity critical safety function status tree color is ____(1)____. CSF-5 Containment critical safety function status tree color is ____(2)____. A. (1) Yellow (2) Yellow B. (1) Orange (2) Yellow C. (1) Yellow (2) Orange D. (1) Orange (2) Orange Page 3 of 75 Question:(1 point)4ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power a Large Break LOCA occursWhich ONE of the following correctly completes the statements below? IAW EOP-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION entry conditions, the HIGHEST allowable RWST level before transfer to Cold Leg Recirculation is required is ____(1)____. The reason that the above switchover criteria is established is to ensure that core flow can be maintained using one ____(2)____ pump taking suction on the RWST during realignment to the CV sump. A. (1) 19% (2) SI B. (1) 19%
(2) RHR C. (1) 27% (2) SI D. (1) 27%
(2) RHR Page 4 of 75 Question:(1 point)5ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The "A" Charging pump is operating in AUTO
- The following annunciators alarm in the control room, all within 30 seconds:
- APP-001-B4, RCP SEAL INJECTION HI/LO FLOW
- APP-001-B6, LP LTDN LN HI TEMP
- APP-001-D6, LP LTDN HI PRESS
- APP-001-E6, LP LTDN RELIEF HI TEMP Which ONE of the following identifies the cause of these alarms? A. Seal Injection Filter clogged B. HCV-121, Charging Flow Valve failed closed C. TCV-144, NRHX Temperature Control Valve failed closed D. CVC-204A, Letdown Line Isolation Stop Valve failed closed Page 5 of 75 Question:(1 point)6ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant cooldown is in progress
- The "A" RHR Train is in service
- At 0700 RCS temperature was 130°F Subsequently, cooling water flow is interrupted to the "A" RHR Heat Exchanger and the following is observed: Time RCS Temp 0715 146 0730 162 0745 178 Which ONE of the following correctly completes the statements below? If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 Mode 4 ____(1)____ be entered.
If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 the Technical Specification Heat up limit ____(2)____ be exceeded. (REFERENCES PROVIDED)A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 6 of 75 Question:(1 point)7ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- A Pressurizer pressure instrument has failed resulting in the following:
- All Pressurizer heaters are energized
- RCS pressure is 2270 psig and rising Which ONE of the following correctly completes the statement below? Pressurizer Pressure channel ____(1)____ has failed LOW.
Pressurizer PORV ____(2)____ will cycle open and closed to limit the RCS pressure rise. A. (1) PT-444 (2) PCV-455C B. (1) PT-444 (2) PCV-456 C. (1) PT-445 (2) PCV-456 D. (1) PT-445 (2) PCV-455C Page 7 of 75 Question:(1 point)8ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An ATWS has occurred
- Immediate Actions of FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, are in progress Which ONE of the following correctly completes the statements below? Opening a MINIMUM of ____(1)____ breaker(s) in the Rod Drive MG Set Room will result in a reactor trip. OR Opening a MINIMUM of ____(2)____ breaker(s) in the 4 KV Room will result in a reactor trip. A. (1) one (2) one B. (1) one (2) two C. (1) two (2) one D. (1) two (2) two Page 8 of 75 Question:(1 point)9ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A SGTR has occurred
- The crew has entered EOP-E-3, STEAM GENERATOR TUBE RUPTURE
- The Subcooled Margin Monitor is OOS
- The crew has initiated an RCS cooldown using the Steam Dumps to a target CET temperature Which ONE of the following correctly completes the statements below? The operator will open the steam dumps to cooldown at ____(1)____.
Subsequently:
- The RCS cooldown is completed
- CET Temperature is being maintained at 510°F
- Ruptured S/G pressure is 1000 psig
- RCS pressure has stabilized at 1400 psig
- The CRS directs you to report RCS Subcooling Based on current plant conditions RCS Subcooling is approximately ____(2)____°F. A. (1) a maximum of 100°F/hour (2) 30-40 B. (1) the maximum achievable rate (2) 30-40 C. (1) a maximum of 100°F/hour (2) 70-80 D. (1) the maximum achievable rate (2) 70-80 Page 9 of 75 Question:(1 point)10ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant tripped from 100% power
- The crew is implementing EOP-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS
- RCS Boration has been initiated
- RCS temperature is 348°F and lowering
- The current time in Core Life is 20,000 MWD/MTU
- The current boron concentration is 100 ppm Which ONE of the following correctly completes the statements below? IAW EOP-ECA-2.1, the operator must raise the RCS boron concentration to a MINIMUM of approximately ____(1)____ to establish the Cold Shutdown boron concentration. The reactivity effects due to this event are more severe while operating at the ____(2)____-Of-Life. (REFERENCES PROVIDED) A. (1) 680-690 ppm (2) Beginning B. (1) 680-690 ppm (2) End C. (1) 760-770 ppm (2) End D. (1) 760-770 ppm (2) Beginning Page 10 of 75 Question:(1 point)11ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a loss of both MFW pumps occurred
- All Service Water pumps have lost power and cannot be restored
- CST level is 12% and rapidly lowering
- The SDAFW pump is out of service IAW OP-402, AUXILIARY FEEDWATER SYSTEM, which ONE of the following is required to supply the OIL COOLER for operation of the "B" MDAFW pump under these conditions? A. Fire Water B. Potable Water C. Deepwell Water D. Fukushima AFW Suction Tank water Page 11 of 75 Question:(1 point)12ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating anExtended Loss of AC Power (ELAP)*A depressurization of all S/G's was initiated at 10:00*The following timeline of events is observed:Time S/G Pressures Pzr Level 10:15 500 psig 13% 10:45 190 psig 0% Which ONE of the following correctly completes the statements below? The EARLIEST time at which the depressurization is required to be stopped IAW EOP-ECA-0.0, is ____(1)____. The reason the depressurization is stopped is to ____(2)____. A. (1) 1015 (2) prevent injection of accumulator nitrogen into the RCS B. (1) 1045 (2) ensure that no reactor head voiding will occur C. (1) 1015 (2) ensure that no reactor head voiding will occur D. (1) 1045 (2) prevent injection of accumulator nitrogen into the RCS Page 12 of 75 Question:(1 point)13ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power when a loss of off-site power occurs*Fifteen seconds later an SI actuation occurred due to a Large Break LOCAWhich ONE of the following correctly completes the statements below? The BOP will expect to see the SW Booster Pumps started on the ____(1)____. SW Booster Pump suction pressure ____(2)____ have to be at least 30 psig for the SW Booster Pump to start. A. (1) Blackout Sequencer (2) does B. (1) Blackout Sequencer (2) does NOT C. (1) SI Sequencer (2) does D. (1) SI Sequencer (2) does NOT Page 13 of 75 Question:(1 point)14ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- A Startup Transformer lockout occurs Which ONE of the following describes how Instrument Buses 1 and 4 will respond to this event? A. Both Instrument Buses 1 and 4 will de-energize B. Instrument Bus 1 will remain energized; Instrument Bus 4 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus C. Instrument Bus 4 will remain energized; Instrument Bus 1 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus D. Both Instrument Buses 1 and 4 will remain energized Page 14 of 75 Question:(1 point)15ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- APP-036-D1, BATT CHARGER A/A-1 TROUBLE, annunciated.
- The OAO reports the following indications from Battery Charger "A-1": * +40 Volts on the Ground Detection Voltmeter.
- 135 Volts DC on Charger Voltage. Which ONE of the following correctly completes the statements below? IAW OMM-035, GROUND ISOLATION, the FIRST action the operator will take to attempt to identify the cause of the ground is ____(1)____. Subsequently, MCC-A spuriously de-energizes. Instrument Bus 2 and 7 will ____(2)____. A. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) de-energize B. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) remain energized C. (1) cycle selected breakers on Distribution Panel A (2) de-energize D. (1) cycle selected breakers on Distribution Panel A (2) remain energized Page 15 of 75 Question:(1 point)16ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a reactor trip and SI occurred
- APP-036-D7, AREA MONITOR HI RAD, has just alarmed
- APP-036-H1, WDBRP TROUBLE, has just alarmed Which ONE of the following correctly completes the statements below? IAW EOP-E-1, radiation monitor ____(1)____ would be used to diagnose a LOCA outside containment. The WDBRP TROUBLE alarm ____(2)____ consistent with a LOCA outside Containment in the Auxiliary Building. A. (1) R-3, PASS Panel Area (2) is B. (1) R-3, PASS Panel Area (2) is NOT C. (1) R-8, Drumming Room (2) is D. (1) R-8, Drumming Room (2) is NOT Page 16 of 75 Question:(1 point)17ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The reactor was tripped from 100% power due to a loss of MFW
- A spurious SI has actuated
- RCS Pressure - 2300 psig
- All S/G pressures - 1050 psig
- S/G WIDE RANGE levels are as follows:
- WIDE RANGE: A - 10%,
- WIDE RANGE: B - 15%,
- WIDE RANGE: C - 9%
- AFW flow is indicating 0 gpm
- EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Immediate Actions are complete and have just been verified Which ONE (1) of the following correctly completes the statement below? The crew should ____(1)____ because ____(2)____. A. (1) remain in EOP-E-0 until directed to transition out (2) the "B" S/G is still a viable Heat Sink B. (1) remain in EOP-E-0 until directed to transition out (2) rules of usage require continuing in EOP-E-0 C. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed is required D. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed can still be avoided Page 17 of 75 Question:(1 point)18ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant has tripped from 100% power due to a LOCA
- The crew is operating in EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION
- RWST level is at 16%
- The only ECCS Pump drawing on the RWST is the "A" SI Pump and pump flow has been adjusted to 150 gpm. Which ONE of the following correctly completes the statements below? IAW EOP-ECA-1.1, the EARLIEST that the "A" SI Pump must be stopped is when the RWST Level lowers to ____(1)____. Assuming these conditions remain the same, four hours from now the RWST level will be ____(2)____. A. (1) 9% (2) higher B. (1) 9% (2) lower C. (1) 13% (2) higher D. (1) 13%
(2) lower Page 18 of 75 Question:(1 point)19ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 50% power
- During the performance of OST-011, ROD CLUSTER CONTROL EXERCISE & ROD POSITION INDICATION, ONE Control Bank "B" rod is 17 steps below the rest of the bank
- The crew is performing the steps to realign the rod IAW AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM Which ONE of the following correctly completes the statements below? 1) IAW AOP-001, OPEN the Control Bank "B" lift coil switch(es) for ____(1)____. 2) Realign the rod using the ____(2)____ position of the rod bank selector switch. A. (1) the misaligned rod ONLY (2) CB B B. (1) the misaligned rod ONLY (2) M (MANUAL) C. (1) all but the misaligned rod (2) CB B D. (1) all but the misaligned rod (2) M (MANUAL) Page 19 of 75 Question:(1 point)20ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The Pressurizer Level Channel Selector Switch is selected to NORMAL*The reference leg for Pressurizer level Transmitter LT-459 develops a slow leak*The "A" Charging Pump is running in AUTOWhich ONE of the following describes the instrument response? LT-459 __LT-460__ A. rises lowers B. lowers remains the same C. rises remains the same D. lowers rises Page 20 of 75 Question:(1 point)21ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A reactor startup is being commenced
- Source Range count rate (CR0) prior to control bank rod withdrawal is as follows:
- N31: 3.0E+001 cps
- N32: 3.0E+001 cps Subsequently:
- The crew has completed the MINIMUM number of doublings required to allow the crew to withdraw control rods as necessary to achieve criticality IAW GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL
- The following indications are observed:
- N31: 2.4E+002 cps
- N32: 1.2E+002 cps Which ONE of the following correctly completes the statement below? IAW GP-003, Source Range Channel ____(1)____ is indicating AS EXPECTED. When the Source Range Channel with the unexpected reading is removed from service per the appropriate OWP, the reactor startup ____(2)____ continue. A. (1) N31 (2) may B. (1) N31 (2) may not C. (1) N32 (2) may D. (1) N32 (2) may not Page 21 of 75 Question:(1 point)22ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A Reactor startup is in progress
- The following indications are observed:
- N31/32 = 900 cps
- N35/36 = 5 x 10-11 amps Subsequently:
- Intermediate Range (IR) channel N36 fails LOW
- The crew places the Reactor startup on HOLD Which ONE of the following correctly completes the following statement? The reason that the reactor startup is placed on HOLD is because a Reactor Protection Trip Function for the ________ accident is degraded. A. rod ejection B. boron dilution C. steam line break D. uncontrolled RCCA bank rod withdrawal Page 22 of 75 Question:(1 point)23ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An accidental gaseous radwaste release is in progress
- R-1, Control Room Area Radiation Monitor, alarms
- R-1 is indicating 8.62E-2 mR/hr and stable Which ONE of the following correctly completes the statements below? R-1 ____(1)____ operating properly.
When R-1 alarms, the CR HVAC will automatically shift to the Emergency ____(2)____ Mode. A. (1) is (2) Recirculation B. (1) is (2) Pressurization C. (1) is NOT (2) Recirculation D. (1) is NOT (2) Pressurization Page 23 of 75 Question:(1 point)24ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- The following is observed on the Fire Alarm Console: (SEE REFERENCE CONDITIONS ON NEXT PAGE) Which ONE of the following correctly completes the statements below? It is expected that the automatic water suppression system ____(1)____ actuate for these conditions. Based on this information, the entry conditions ____(2)____ met for AOP-041, RESPONSE TO FIRE EVENTS. A. (1) will (2) are B. (1) will (2) are NOT C. (1) will NOT (2) are D. (1) will NOT (2) are NOT Page 24 of 75 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- With the plant at 100%, a confirmed bomb threat has been received
- The caller specified that the bomb was located in the Control Room
- The following timeline of events is recorded: 2110 The Control Room was evacuated after all appropriate actions were taken 2145 A Control operator in the Charging Pump Room informs the SM that:
- N51 reads 3.0E5 cps and is slowly lowering
- Pressurizer pressure is 2225 psig
- Pressurizer level is 35%
- The "A" Charging Pump is operating Which ONE of the following correctly completes the statements below? IAW Attachment 1 of AOP-004, CONTROL ROOM INACCESSIBILITY, the operator will raise Pressurizer level to at LEAST greater than ____(1)____, and then stop the running Charging Pump.
The basis for this action is to ____(2)____. A. (1) 60% (2) prevent exceeding the Charging Pump starting duty limitations B. (1) 60% (2) ensure that the reactor is subcritical C. (1) 86%
(2) ensure that the reactor is subcritical D. (1) 86%
(2) prevent exceeding the Charging Pump starting duty limitations Page 25 of 75 Question:(1 point)26ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The R-9, Letdown Line Area, indication on Radiation Monitoring System Recorder RR-1 is rising Which ONE of the following correctly completes the statements below? If the trend continues, it is expected that ____(1)____. The basis for the R-9 setpoint is to detect ____(2)____. A. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) small leaks in fuel rods B. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) release of resin from the in-service demineralizers C. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) small leaks in fuel rods D. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) release of resin from the in-service demineralizers Page 26 of 75 Question:(1 point)27ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- EOP-ECA-0.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED has been implemented
- The crew is checking for Natural Circulation with the following conditions:
- Containment pressure is 0.5 psig
- Steam dump using the S/G PORVs is in progress
- CETC are 555°F and stable
- S/G pressures are stable at 900 psig
- RCS Hot Leg temperatures are 555°F and stable
- RCS Cold Leg temperatures are 545°F and slowly rising
- S/G NR levels are 21% and stable Which ONE of the following correctly completes the statements below? Based on the indications above, Natural Circulation (NC) flow ____(1)____ been established. IAW EOP-ECA-0.1, the crew will ____(2)____. A. (1) has NOT (2) raise S/G levels to promote the establishment of NC flow B. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 9% C. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 18% D. (1) has NOT (2) raise the rate of dumping steam to promote the establishment of NC flow Page 27 of 75 Question:(1 point)28ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power when a transient occurs
- Over 15-20 seconds a load rejection lowers and then stabilizes power at 80% Which ONE of the following correctly completes the statements below? Seal water injection flow will INITIALLY ____(1)____. Subsequently,
- APP-001-B4, RCP SEAL INJ HI/LO FLOW, has alarmed
- The CRS has directed use of the expanded seal water injection flow control band The expanded seal water injection flow control band is ____(2)____. A. (1) rise (2) 6-20 gpm B. (1) rise (2) 7-18 gpm C. (1) lower (2) 6-20 gpm D. (1) lower (2) 7-18 gpm Page 28 of 75 Question:(1 point)29ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is in Mode 3
- APP-003-E2, VCT HI/LO PRESS, has alarmed
- Actual VCT pressure is 15 psig Which ONE of the following correctly completes the statement below? If VCT pressure continues to lower, RCP #1 Seal Leakoff flow will ____(1)____ and RCP #2 Seal leakoff flow will ____(2)____. A. (1) lower (2) rise B. (1) rise (2) lower C. (1) rise (2) rise D. (1) lower (2) lower Page 29 of 75 Question:(1 point)30ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*Due to RTGB indications the crew has entered AOP-024, LOSS OF INSTRUMENT BUS*An Auto Makeup to the VCT has initiated on the loss of instrument busWhich ONE of the following correctly completes the statement below? The Auto makeup has occurred because VCT Level transmitter ____(1)____ has de-energized on a loss of Instrument Bus ____(2)____. A. (1) LT-112 (2) 7 B. (1) LT-112 (2) 9 C. (1) LT-115 (2) 7 D. (1) LT-115 (2) 9 Page 30 of 75 Question:(1 point)31ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *A plant cooldown is in progress*The "A" RHR Train is in service*RCS temperature is 190°F*RCS Pressure is 350 psig*The RCS is in Solid Plant Operation with LTOPP in serviceSubsequently, a transient occurs resulting in the following: *RCS temperature is 195°F*RCS Pressure is 420 psig*PZR PORV PCV-456 indicates OPEN*PZR PORV PCV-455C indicates CLOSEDThe crew has entered AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Which ONE of the following correctly completes the statements below? Based on plant conditions, both PORVs should have ____(1)____. IAW AOP-019 immediate actions, the operator will FIRST ____(2)____ to control or mitigate the consequences of this event. A. (1) remained closed (2) close PCV-456 B. (1) opened (2) stop all Charging Pumps and RCPs C. (1) opened (2) ensure the block valve for PCV-456 is OPEN D. (1) remained closed (2) place the PCV-456 LTOPP Arming Switch to NORMAL Page 31 of 75 Question:(1 point)32ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: * "A" Train RHR is in service
- Instrument Air pressure lowers to 30 psig Which ONE of the following correctly completes the statement below? RCS temperature will INITIALLY ____(1)____, and RHR System Flow will INITIALLY ____(2)____. A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Lower (2) Lower D. (1) Lower (2) Rise Page 32 of 75 Question:(1 point)33ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% RTP
- The following timeline is observed: TIME "A" SI accumulator pressure"A" SI accumulator level1108 637 psig 68 percent 1111 646 psig 70 percent 1114 660 psig 75 percent Which ONE of the following correctly completes the statement below? The EARLIEST time at which an RTGB annunciator alarm would occur is at time ____(1)____, due to ____(2)____ reaching its alarm setpoint. A. (1) 1111 (2) APP-002-A4, SI ACCUM A HI/LO LVL B. (1) 1114 (2) APP-002-B4, SI ACCUM A HI/LO PRESS C. (1) 1111 (2) APP-002-B4, SI ACCUM A HI/LO PRESS D. (1) 1114 (2) APP-002-A4, SI ACCUM A HI/LO LVL Page 33 of 75 Question:(1 point)34ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a LOCA occurs inside Containment Which ONE of the following correctly completes the statements below? While operating in the EOP Network, the LOWEST pressure in which "Adverse" containment values are applicable is ____(1)____. Based on the increased containment temperature, level detectors with wet reference legs will indicate ____(2)____ than the actual level. A. (1) 4 psig (2) lower B. (1) 4 psig (2) higher C. (1) 10 psig (2) lower D. (1) 10 psig (2) higher Page 34 of 75 Question:(1 point)35ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- Containment pressure is 0.2 psig
- Containment temperature is 94°F Subsequently:
- A load rejection results in a reactor trip
- Following the trip, a Pressurizer Safety valve opens, and will NOT reseat
- The PRT rupture disks function as designed
- Containment pressure is rising at 0.1 psig every 5 minutes
- Containment temperature is rising at 2°F every 5 minutes Assuming these conditions remain constant, which ONE of the following identifies the Containment Technical Specifications LCOs that will be affected one hour from now? A. Both LCO 3.6.4, Containment Pressure, and LCO 3.6.5, Containment Air Temperature, will be exceeded. B. Only LCO 3.6.4, Containment Pressure, will be exceeded. C. Only LCO 3.6.5, Containment Air Temperature, will be exceeded. D. Neither LCO 3.6.4, Containment Pressure, nor LCO 3.6.5, Containment Air Temperature, will be exceeded. Page 35 of 75 Question:(1 point)36ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
T= 1305:10
- A loss of off-site power has occurred concurrent with a Reactor trip
- The crew enters EOP-E-0, Reactor Trip or Safety Injection T=1307:40
- Immediate actions of EOP-E-0 are complete
- The following parameters are noted:
- RCS pressure is 2110 psig and stable
- SG pressures are all 910 psig and lowering slowly
- CV pressure is 0.7 psig and rising slowly At time 1307:40, which ONE of the following describes the CCW Pump indication available in the control room? A. "B" and "C" CCW Pump RED indicating lights are LIT. "A" CCW Pump GREEN indicating light is LIT. B. All 3 CCW Pump control switch GREEN indicating lights are LIT. C. "B" and "C" CCW Pump GREEN indicating lights are LIT; "A" CCW Pump RED indicating light is LIT. D. "B" and "C" CCW Pump RED indicating lights are LIT; "A" CCW Pump GREEN and RED indicating lights are EXTINGUISHED. Page 36 of 75 Question:(1 point)37ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant The plant is at 100% power when the following occurs:
- A load rejection results in a PZR PORV actuation
- The PZR PORV will not fully seat
- The depressurization led to a Reactor Trip and Safety Injection
- PZR pressure reduces to 1400 psig and stabilizes
- The PRT rupture discs rupture at their design setpoint
- Containment pressure peaks at 15 psig Which ONE of the following is the MAXIMUM temperature indicated by the Safety Valve tailpiece RTD during the entire event? A. 213°F B. 250°F C. 298°F D. 338°F Page 37 of 75 Question:(1 point)38ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following identifies a condition which will cause an automatic reactor trip? A. RCP bus frequency reads 58.0 Hz when THREE Power Range channels read 5% RTP. B. Flow in ONE Reactor Coolant Loop reads 91% when ALL Power Range channels read 35% RTP. C. ONE Intermediate Range NI channel reads 1 x10E-6 AMPS when TWO Power Range channels read 15% RTP. D. ONE Source Range NI channel reads 5 x10E5 CPS when TWO Intermediate Range NI channels read 9 x10E-11 AMPS. Page 38 of 75 Question:(1 point)39ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant was at 100% when a SI occurredWhich ONE of the following correctly completes the statements below regarding the Feed Reg Valves and the Feed Reg Bypass Valves? Following the SI signal, the Feed Reg Bypass Valves ____(1)____ receive a CLOSE signal. The Feed Reg Valves ____(2)_____ be available when the SI is RESET and the Feedwater Isolation OVRD/RESET key switches are placed in OVRD/RESET. A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 39 of 75 Question:(1 point)40ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below regarding the Containment Spray Actuation logic scheme?
The MINIMUM number of Containment Pressure channels that must sense pressure greater than the Hi-Hi pressure setpoint to generate an automatic Containment Spray Actuation is ____(1)____. The Containment Spray Actuation bistables are ____(2)____ to actuate. A. (1) Two (2) Energize B. (1) Two (2) De-energize C. (1) Four (2) Energize D. (1) Four (2) De-energize Page 40 of 75 Question:(1 point)41ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*A realignment has just occurred and the operator observes the following Service Watervalve alignments for HVH-1 (CV Recirc Fan A) and HVH-2 (CV Recirc Fan B):Assuming no conditions change, which ONE of the following identifies the operational restrictions, if any, placed on HVH-1? A. HVH-1 may run continuously, there are no restrictions. B. HVH-1 may continue to run for up to 15 additional minutes. C. HVH-1 must be immediately secured and cannot be run under these conditions. D. HVH-1 must be immediately secured and can ONLY be started during emergencies. Page 41 of 75 Question:(1 point)42ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100%
- A LOCA inside containment occurs and the following timeline is observed: TIME OBSERVATION 1200 LOCA occurs 1201 CV Spray system actuates 1211 CV Pressure peaks at 22 PSIG 1235 CV Pressure lowers to less than 10 PSIG 1245 CV Pressure lowers to less than 4 PSIG Which ONE of the following correctly completes the statements below? IAW EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, the EARLIEST TIME that the Containment Spray Pumps may be secured is ____(1)____.
In order to successfully reset the Phase B Containment Isolation signal, the Containment Spray Signal ____(2)____ required to be reset FIRST. A. (1) 1235 (2) is B. (1) 1235 (2) is NOT C. (1) 1245 (2) is D. (1) 1245 (2) is NOT Page 42 of 75 Question:(1 point)43ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*R-15, Air Ejector Radiation Monitor, alarms*The crew entered AOP-035, S/G TUBE LEAK*The crew has initiated Attachment 5, R-15 Monitoring*Chemistry reports the following leakrates:Time "A" S/G Tube leakrate 0800 31 gpd 0900 51 gpd 1000 81 gpd 1100 111 gpd IAW AOP-035, which ONE of the following identifies the EARLIEST time that a plant shutdown is required? A. 0800 B. 0900 C. 1000 D. 1100 Page 43 of 75 Question:(1 point)44ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occursWhich ONE of the following describes how this actuation affects the Reactor and the Main Turbine? A. BOTH the Reactor and the Main Turbine receive trip signals directly from the FWIS. B. The Reactor receives a trip signal directly from the FWIS, and causes a Main Turbine trip. C. The Main Turbine receives a trip signal directly from the FWIS and the Reactor will trip because the Main Turbine tripped with power above P-8. D. NEITHER the Reactor nor the Main Turbine receive trip signals directly from the FWIS. However, the Reactor will trip on plant conditions created by the FWIS actuation and cause a Main Turbine trip. Page 44 of 75 Question:(1 point)45ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power, an ATWS event occurred*The crew entered FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION ATWS*All SG Narrow Range levels are OFF-Scale LOWWhich ONE of the following correctly completes the statement below? IAW FRP-S.1, AFW flow must be greater than a MINIMUM value of ________ to establish a Secondary Heat Sink? A. 300 gpm B. 500 gpm C. 600 gpm D. 1000 gpm Page 45 of 75 Question:(1 point)46ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- A reactor trip has occurred Which ONE of the following identifies the breakers which will automatically CLOSE one minuteafter the reactor trip? Breaker nomenclature: 52/10 4KV BUS 1-2 TIE BKR 52/12 START-UP TRANSFORMER TO 4KV BUS 2 52/17 START-UP TRANSFORMER TO 4KV BUS 3 52/19 4KV BUS 3-4 TIE BKR A. 52/10 and 52/12 B. 52/10 and 52/17 C. 52/12 and 52/19 D. 52/17 and 52/19 Page 46 of 75 Question:(1 point)47ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on faultWhich ONE of the following correctly completes the statement below? Circulating Water pump(s) _________ lost power. A. "A" & "B" have B. "B" & "C" have C. "A" & "C" have D. "B" ONLY has Page 47 of 75 Question:(1 point)48ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is in Mode 3*The "B" Battery Charger is in service*The "B-1" Battery Charger is in standbySubsequently: *MCC-6 is de-energized*APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms*Two minutes later MCC-6 is re-energizedWhich ONE of the following identifies when APP-036-D2 will clear? APP-036-D2 will clear-- A. when the "B" Battery Charger automatically restarts. B. only after the operator manually restarts the "B" Battery Charger. C. only after the operator manually places the "B-1" Battery Charger back in the STANDBY mode. D. only after the operator manually restarts the "B" Battery Charger and places the "B-1" Battery Charger back in the STANDBY mode. Page 48 of 75 Question:(1 point)49ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*OST-401-1, EDG "A" SLOW SPEED START testing is in progress*Current "A" EDG load is 2500 KWSubsequently: *The Normal Supply Breaker to E-1, 52/18B, opens*EDG "A" Output Breaker 52/17B, opensWhich ONE of the following correctly completes the statements below? IAW OP-604 CAUTION statement, the consequence of opening the EDG "A" Output Breaker under load is ____(1)____. IAW OP-604 when attempting to recover, the local Generator Parallel/Isolate Switch must be placed in the ____(2)____ position. OP-604, DIESEL GENERATORS "A" AND "B" A. (1) the diesel engine may trip due to overspeed (2) ISOL B. (1) excessive carbon buildup in the engine could occur (2) PARALLEL C. (1) the diesel engine may trip due to overspeed (2) PARALLEL D. (1) excessive carbon buildup in the engine could occur (2) ISOL Page 49 of 75 Question:(1 point)50ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following supplies power to the "A" and "B" EDG Fuel Oil Transfer Pumps? A. MCC-10 and MCC-9 respectively B. MCC-9 and MCC-10 respectively C. MCC-6 and MCC-5 respectively D. MCC-5 and MCC-6 respectively Page 50 of 75 Question:(1 point)51ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The reactor is at 100%*The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIRHANDLING*R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarmsV12-12, CV VAC RELIEF V12-13, CV VAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE of the following correctly completes the statements below? The crew would expect to see ____(1)____ annunciator flashing. Due to the conditions above, ____(2)____ will automatically close. A. (1) APP-036-D7 (2) V12-12 & V12-13 ONLY B. (1) APP-036-D8 (2) V12-12 & V12-13 ONLY C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Page 51 of 75 Question:(1 point)52ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*R-19A, STM GEN BLOW DN SG-A, enters the alarm conditionWhich ONE of the following correctly completes the statements below? In regards to the Blowdown Isolation Valves and the Blowdown Sample Isolation Valves, an alarm condition on R-19A will automatically close the ____(1)____. IAW AOP-005, RADIATION MONITORING SYSTEM, if the automatic actions fail to occur, the crew ____(2)____ de-energize R-19A in an attempt to cause the automatic actions to occur. A. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will D. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will NOT Page 52 of 75 Question:(1 point)53ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following correctly completes the statements below regarding components normally cooled by Service Water? The Circulating Water Pumps ____(1)____ be cooled by the Fire Water System during an emergency. The Control Room HVAC Cooling Units ____(2)____ be cooled by the Fire Water System during an emergency. A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can NOT D. (1) can NOT (2) can Page 53 of 75 Question:(1 point)54ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power * "D" IA Compressor is running
- Station Air Compressor is running Subsequently:
- The crew is implementing AOP-017, LOSS OF INSTRUMENT AIR SA-5, STATION AIR TO INST AIR CROSS CONNECT SA-220, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION SA-221, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION Which ONE of the following correctly completes the statements below? IAW AOP-017, the PREFERRED method to cross connect IA from Station Air is by opening ____(1)____ .
IA will no longer be used to supply Breathing Air to ____(2)____. A. (1) SA-5 (2) minimize IA loads ONLY B. (1) SA-5 (2) minimize IA loads and prevent harm to users of Breathing Air C. (1) SA-220 and SA-221 (2) minimize IA loads ONLY D. (1) SA-220 and SA-221 (2) minimize IA loads and prevent harm to users of Breathing Air Page 54 of 75 Question:(1 point)55ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A LOCA occurred 45 minutes ago
- The crew is implementing the Emergency Operating Procedures
- The following conditions exist:
- CET temperature is 340°F
- RCS pressure is 60 psig and lowering
- Full Range RVLIS is 40%
- RCS Cold Leg temperature is 320°F and lowering
- S/G NR levels are off-scale LOW
- S/G pressures are 550 psig and trending down
- AFW flow is 450 gpm
- All RCPs are OFF
- CV pressure is 43 psig and rising
- SPDS has been reset Which ONE of the following identifies the MOST challenged Critical Safety Function? A. Integrity B. Heat Sink C. Containment D. Core Cooling Page 55 of 75 Question:(1 point)56ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power Subsequently, all IRPI indication is lost except a green LED is illuminated on each rod indicator Which ONE of the following correctly completes the statements below? The cause of this condition is the ____(1)____ has tripped.
For this condition entry into AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, ____(2)____ required. A. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is B. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is D. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is NOT Page 56 of 75 Question:(1 point)57ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- GP-008, DRAINING THE REACTOR COOLANT SYSTEM, is in progress
- The crew has positioned HIC-142, PURFICATION FLOW, to establish required drain rate Which ONE of the following correctly completes the statements below? LCV-115A, VCT/HLDP TK DIV, will begin to divert at ____(1)____ in the VCT.
IAW GP-008, ____(2)____ level change can be used to determine the volume drained from the RCS. A. (1) 30" (2) WHUT B. (1) 30" (2) CVCS HUT C. (1) 51.6" (2) CVCS HUT D. (1) 51.6" (2) WHUT Page 57 of 75 Question:(1 point)58ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 35% power and stable
- The "A" Charging Pump is running in AUTO
- The "B" Charging Pump is running in MANUAL and adjusted to 50% output on Charging Pump Speed Controller SC-151
- Letdown flow is 105 gpm Subsequently:
- Letdown flow is lowered 45 gpm
- Reactor power is lowered to 30% and stabilized
- Pressurizer Level lowers to, and has stabilized at 31.5% Which ONE of the following correctly completes the statements below? The Pressurizer Level Control System ____(1)____ operating as expected for these plant conditions. While Letdown was being lowered, APP-003-F3, CHG PMP LO SPEED, alarmed. According to OP-301, CHEMICAL AND VOLUME CONTROL SYSTEM, the operator will be required to ____(2)____ Charging Pump to clear the alarm. A. (1) is (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" B. (1) is (2) adjust the speed of the "B" C. (1) is NOT (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" D. (1) is NOT (2) adjust the speed of the "B" Page 58 of 75 Question:(1 point)59ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The Plant is in Mode 1, following a control rod manipulation
- The RTGB IRPI indication for Control Bank "D" Rod M-8 indicates 120 inches
- The RTGB IRPI indication for Control Bank "D" Rod H-4 indicates 110 inches
- Control Bank "D" step counter position is 192 steps Which ONE of the following correctly completes the statements below? Based on the given conditions, control rod ____(1)____ is stuck. Assuming the average of the individual rod positions in the affected bank indicate 120 inches, entry into ITS LCO 3.1.4, ROD GROUP ALIGNMENT LIMITS, ____(2)____ required. A. (1) M-8 (2) is B. (1) M-8 (2) is NOT C. (1) H-4 (2) is D. (1) H-4 (2) is NOT Page 59 of 75 Question:(1 point)60ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The operator is reviewing the T/C TREND pages on both the Train "A" and Train "B" ICCM displays Which ONE of the following correctly completes the statements below? The TOTAL number of Core Exit Thermocouples (CET) that monitor the core is ____(1)____. The T/C TREND page displays the average of ____(2)____ CET indications over the last 30 minutes. A. (1) 23 (2) the five highest B. (1) 23 (2) all C. (1) 46 (2) all D. (1) 46 (2) the five highest Page 60 of 75 Question:(1 point)61ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE (1) of the following is the power supply for HVE-3, CV Air Iodine Removal Fan? A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-10 Page 61 of 75 Question:(1 point)62ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW GP-010, REFUELING, the Containment Purge System ____(1)____ required be in operation during Core Alterations with the Equipment Hatch removed.
The Containment Purge System ____(2)____ required be in operation if a Containment entry is being made with the plant in Mode 1. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 62 of 75 Question:(1 point)63ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- Spent fuel handling activities are NOT in progress Subsequently:
- SFP level starts to rapidly lower due to a large structural and piping failure
- The crew has entered AOP-036, SFP EVENTS R-14, Plant Vent Effluent Monitor R-21, Fuel Handling Building Upper Level, Noble Gas HVE-15, Fuel Handling Building Exhaust Fan Which ONE of the following correctly completes the statements below? IAW AOP-036, R-14 ____(1)____ monitored for indications of fuel damage.
If R-21 were to subsequently alarm, HVE-15 ____(2)____ automatically trip. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 63 of 75 Question:(1 point)64ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- The crew trips the reactor and initiates safety injection due to a SGTR on the "B" Steam Generator
- The "B" MDAFW Pump trips on auto-start * "B" SG NR level is 6% and rising slowly * "A" and "C" SG NR levels are off-scale low Which ONE of the following correctly completes the statements below? Without operator action, a Secondary Heat Sink ____(1)____ established.
Based on the current conditions, the operator ____(2)____ immediately isolate feed to the "B" S/G. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 64 of 75 Question:(1 point)65ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following discharges to the Reactor Coolant Drain Tank? A. RCV-609, CC SURGE TANK VENT B. CVC-203 A/B, LETDOWN RELIEF VALVES C. CVC-389, EXCESS LETDOWN DIVERSION D. CVC-400 A/B/C, CHARGING PUMP "A/B/C" LEAKAGE ISOLATION Page 65 of 75 Question:(1 point)66ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW OPS-NGGC-1303, VERIFICATION PRACTICES, guidance for waiving Independent Verification (IV) requirements states that the IV may be waived if the operators were expected to ____(1)____ to complete the verification.
In these cases, ____(2)____ Verification will be used as an alternative to Independent Verification. A. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Concurrent B. (1) receive a total exposure of greater than 10 mrem (2) Concurrent C. (1) receive a total exposure of greater than 10 mrem (2) Functional D. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Functional Page 66 of 75 Question:(1 point)67ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions:
- The plant is in MODE 6 for refueling operations
- Core alterations are in progress Which ONE of the following correctly completes the statements below? IAW LCO 3.9.2, NUCLEAR INSTRUMENTATION, ____(1)____ shall be OPERABLE. N-51 and N-52, ____(2)____ capable of providing audible indication inside Containment. N-31, N-32, SOURCE RANGE NUCLEAR INSTRUMENTS N-51, N-52, REG. GUIDE 1.97 NEUTRON FLUX (SOURCE RANGE, WIDE RANGE) A. (1) either N-31 OR N-32 (2) are B. (1) both N-31 AND N-32 (2) are C. (1) either N-31 OR N-32 (2) are NOT D. (1) both N-31 AND N-32 (2) are NOT Page 67 of 75 Question:(1 point)68ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant startup is in progress
- NIS Power Indication is 50%
- The STA is recording data IAW GP-005, POWER OPERATION, Attachment 1, REACTOR POWER ASCENSION INDICATOR LOG Which ONE of the following correctly completes the statements below? IAW GP-005, if Core T indicates 33°F, the crew ____(1)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). IAW GP-005, if Calorimetric power indicates 51.5%, the crew ____(2)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Page 68 of 75 Question:(1 point)69ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The FWUFM System has been OOS for five days Subsequently:
- An AO reports a steam leak near the Main Steam Isolation Valves
- The following indications are noted in the Control Room:
- Tavg is LOWERING
- Steam flow and feed flow have RISEN
- A Power Limit Warning alarm on ERFIS has been received
- Reactor power is slowly RISING Which ONE of the following identifies the MAXIMUM thermal power limit allowed by the operating license under these conditions? A. 2300 MWt B. 2307 MWt C. 2339 MWt D. 2346 MWt Page 69 of 75 Question:(1 point)70ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band. Which ONE of the following correctly completes the statement below? IAW Technical Specification LCO 3.2.3 ACTION--. Restore AFD to within target band within ___(1)___. If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___. A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Page 70 of 75 Question:(1 point)71ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- Letdown flow is 45 gpm
- The "A" Charging Pump is operating in AUTO
- The "B" Charging Pump is operating in MANUAL Subsequently:
- R-9, Letdown Line Area Monitor, alarms
- The alarm is determined to be valid
- The crew enters AOP-005, RADIATION MONITORING SYSTEM Which ONE of the following correctly completes the statements below? IAW with Attachment 9 of AOP-005, the operator ____(1)____ required to evacuate the Aux Building of non-essential personnel.
IAW with Attachment 9 of AOP-005, the operator ____(2)____ required to isolate letdown flow. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 71 of 75 Question:(1 point)72ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An operator has been assigned work in the radiologically controlled area
- The dose rate in the area is 500 mR/hr
- The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension? A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Page 72 of 75 Question:(1 point)73ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant cooldown is in progress
- RCS Temperature is 430°F
- RCS pressure is 725 psig
- The SI Accumulators have been isolated Subsequently, an RCS leak occurs and the operating crew enters AOP-016, EXCESSIVE RCS LEAKAGE.
Which ONE of the following correctly completes the statements below? AOP-016 will ensure that a MINIMUM of ____(1)____ Charging Pumps are running with their speed adjusted to maximum.
With the current plant conditions, if Pressurizer level continues to lower uncontrollably with maximum charging flow, the crew would transition to ____(2)____. A. (1) two (2) AOP-033, SHUTDOWN LOCA B. (1) two (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION C. (1) three (2) AOP-033, SHUTDOWN LOCA D. (1) three (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 73 of 75 Question:(1 point)74ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The Control Room receives a confirmed report of a fire in the Unit 2 Cable Spread Room (Fire Zone 19) at 0730 Which ONE of the following correctly completes the statements below? IAW AOP-041, RESPONSE TO FIRE EVENT, the operator must ____(1)____. The LATEST time that this action may be complete is ____(2)____. A. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0740 B. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0745 C. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (2) 0745 D. (3) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (4) 0740 Page 74 of 75 Question:(1 point)75ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power Subsequently, the following time line of events occur: TIME EVENT 1200 APP-009-C5, MAIN TRANSF TROUBLE, alarms 1203 The Outside AO reports that all Main Transformer Fans and Pumps are NOT operating 1204 The crew enters AOP-037, LARGE TRANSFORMER MALFUNCTIONS 1208 TIME NOW IAW AOP-037, which ONE of the following identifies the EARLIEST time that the reactor must be tripped? A. IMMEDIATELY B. 1211 C. 1214 D. 1231 Page 75 of 75 RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-7 Amendment No.218 0 2550751000 1250 1500 1750 2000 2250 2500 2750 0 5100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) MATERIALS PROPERTIES BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Curves applicable for heatup rates up to 60 ºF/Hr for Service period up to 35 EFPY. Heatup Curves include +10ºF and -60 psig allowance For instrumentation error. Acceptable Operation Unacceptable Operation Leak Test Limit Heatup Rate to 60 ° F/Hr Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 35 EFPY Indicated Pressure (psig) Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-8 Amendment No. 218 0 250 500 750 1000 1250 1500 1750 2000 2250 2500 2750 0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) Unacceptable Operation Acceptable Operation 100°F/ Hr Cooldown Rates ( ° F/Hr) 0 ° F/Hr. Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY 60°F/ Hr 40°F/ Hr 20°F/ Hr 100 60 40 0 and 20 Curves applicable for cooldown rates up to 100°F/Hr for the service period up to 35 EFPY. Curves include +10°F and -60 PSIG allowance for instrument error. Indicated Pressure (PSIG) MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 and Girth Weld 10-273 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F 3/4T, 147°F and 172°F REV. REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR5007009001100 1300150017000200040006000800010000120001400016000180002000022000CYCLE EXPOSURE (MWD/MTU)CURVE 1.14BORON CONCENTRATION REQUIRED TO MAINTAINSHUTDOWN MARGIN BORON (PPM)HBR2 CYCLE 30200 F300 F350 FA MINIMUM OF 2.6% SHUTDOWN MARGIN(ARI-MRR)38 FRNP Cycle 30 Curve Book Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve BookRNP-F/NFSA-0237, Rev. 0 Page A46 of A86 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer1B2D3C4C5B6B7B8B9D10C11A12D13D14B15A16A17B18B19C20A21B22D23D24D25CPrinted 2/11/2016 2:53:31 PMPage 1 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer26A27D28C29B30C31B32B33C34B35B36A37D38D39C40C41B42C43C44C45C46C47B48A49A50DPrinted 2/11/2016 2:53:32 PMPage 2 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer51D52C53D54D55C56C57B58B59C60D61A62B63A64B65C66C67D68B69A70A71B72B73A74D75BPrinted 2/11/2016 2:53:32 PMPage 3 of 3 Question:(1 point)1ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The "A" Reactor Trip Bypass Breaker has been placed in service for testing*The "A" Reactor Trip Breaker has been removed from service*A transient condition exists requiring a reactor trip*The OAC depresses the manual reactor trip pushbutton prior to an RPS setpoint beingreachedWhich ONE of the following describes the plant response? The "A" Reactor Trip Bypass Breaker opens due to actuation of its ____(1)____ and the "B" Reactor Trip Breaker opens due to actuation of its ____(2)____. A. (1) UV trip, ONLY (2) UV trip, ONLYB. (1) UV trip, ONLY (2) UV and shunt trip C. (1) UV and shunt trip (2) UV trip, ONLY D. (1) UV and shunt trip (2) UV and shunt trip Page 1 of 75 Question:(1 point)2ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- A transient results in both Pressurizer PORVs opening and sticking OPEN after pressure lowers below the OPEN setpoint
- When the operator attempts to close the Block Valves for each PORV, the OATC observes that the status lights for Block Valves RC-535 and RC-536 are all EXTINGUISHED Subsequently, the CRS directs that the power to each Block Valve be restored. RC-535, Block Valve to Pressurizer PORV PCV-456 RC-536, Block Valve to Pressurizer PORV PCV-455C Which ONE of the following identifies the location(s) to which the operator must be dispatched to close the breakers for the Block Valves? The operator must proceed to-- A. MCC-5 for BOTH RC-535 and RC-536 B. MCC-5 for RC-535; and MCC-6 for RC-536 C. MCC-5 for RC-536; and MCC-6 for RC-535 D. MCC-6 for BOTH RC-535 and RC-536 Page 2 of 75 Question:(1 point)3ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*"A" CV Spray pump is out of service for maintenanceSubsequently: *A SBLOCA occurred at 0930 coincident with a Loss of Offsite Power*"B" EDG tripped immediately after starting*At 1000, the crew is performing the actions of EOP-E-1, LOSS OF REACTOR ORSECONDARY COOLANT with the following current plant conditions:*CV pressure: 11 psig and rising slowly*CV Sump level: 178 inches and rising*CV radiation level: 0.5 R/hr*"A" Loop Cold Leg temperature: 338 °F*"B" Loop Cold Leg temperature: 425 °F*"C" Loop Cold Leg temperature: 427 °FWhich ONE of the following correctly completes the statements below? CSF-4 Integrity critical safety function status tree color is ____(1)____. CSF-5 Containment critical safety function status tree color is ____(2)____. A. (1) Yellow (2) Yellow B. (1) Orange (2) Yellow C. (1) Yellow (2) Orange D. (1) Orange (2) Orange Page 3 of 75 Question:(1 point)4ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power a Large Break LOCA occursWhich ONE of the following correctly completes the statements below? IAW EOP-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION entry conditions, the HIGHEST allowable RWST level before transfer to Cold Leg Recirculation is required is ____(1)____. The reason that the above switchover criteria is established is to ensure that core flow can be maintained using one ____(2)____ pump taking suction on the RWST during realignment to the CV sump. A. (1) 19% (2) SI B. (1) 19%
(2) RHR C. (1) 27% (2) SI D. (1) 27%
(2) RHR Page 4 of 75 Question:(1 point)5ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The "A" Charging pump is operating in AUTO
- The following annunciators alarm in the control room, all within 30 seconds:
- APP-001-B4, RCP SEAL INJECTION HI/LO FLOW
- APP-001-B6, LP LTDN LN HI TEMP
- APP-001-D6, LP LTDN HI PRESS
- APP-001-E6, LP LTDN RELIEF HI TEMP Which ONE of the following identifies the cause of these alarms? A. Seal Injection Filter clogged B. HCV-121, Charging Flow Valve failed closed C. TCV-144, NRHX Temperature Control Valve failed closed D. CVC-204A, Letdown Line Isolation Stop Valve failed closed Page 5 of 75 Question:(1 point)6ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant cooldown is in progress
- The "A" RHR Train is in service
- At 0700 RCS temperature was 130°F Subsequently, cooling water flow is interrupted to the "A" RHR Heat Exchanger and the following is observed: Time RCS Temp 0715 146 0730 162 0745 178 Which ONE of the following correctly completes the statements below? If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 Mode 4 ____(1)____ be entered.
If the current heat up rate trend continues as it has for the last 45 minutes, by 0800 the Technical Specification Heat up limit ____(2)____ be exceeded. (REFERENCES PROVIDED)A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 6 of 75 Question:(1 point)7ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- A Pressurizer pressure instrument has failed resulting in the following:
- All Pressurizer heaters are energized
- RCS pressure is 2270 psig and rising Which ONE of the following correctly completes the statement below? Pressurizer Pressure channel ____(1)____ has failed LOW.
Pressurizer PORV ____(2)____ will cycle open and closed to limit the RCS pressure rise. A. (1) PT-444 (2) PCV-455C B. (1) PT-444 (2) PCV-456 C. (1) PT-445 (2) PCV-456 D. (1) PT-445 (2) PCV-455C Page 7 of 75 Question:(1 point)8ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An ATWS has occurred
- Immediate Actions of FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, are in progress Which ONE of the following correctly completes the statements below? Opening a MINIMUM of ____(1)____ breaker(s) in the Rod Drive MG Set Room will result in a reactor trip. OR Opening a MINIMUM of ____(2)____ breaker(s) in the 4 KV Room will result in a reactor trip. A. (1) one (2) one B. (1) one (2) two C. (1) two (2) one D. (1) two (2) two Page 8 of 75 Question:(1 point)9ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A SGTR has occurred
- The crew has entered EOP-E-3, STEAM GENERATOR TUBE RUPTURE
- The Subcooled Margin Monitor is OOS
- The crew has initiated an RCS cooldown using the Steam Dumps to a target CET temperature Which ONE of the following correctly completes the statements below? The operator will open the steam dumps to cooldown at ____(1)____.
Subsequently:
- The RCS cooldown is completed
- CET Temperature is being maintained at 510°F
- Ruptured S/G pressure is 1000 psig
- RCS pressure has stabilized at 1400 psig
- The CRS directs you to report RCS Subcooling Based on current plant conditions RCS Subcooling is approximately ____(2)____°F. A. (1) a maximum of 100°F/hour (2) 30-40 B. (1) the maximum achievable rate (2) 30-40 C. (1) a maximum of 100°F/hour (2) 70-80 D. (1) the maximum achievable rate (2) 70-80 Page 9 of 75 Question:(1 point)10ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant tripped from 100% power
- The crew is implementing EOP-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS
- RCS Boration has been initiated
- RCS temperature is 348°F and lowering
- The current time in Core Life is 20,000 MWD/MTU
- The current boron concentration is 100 ppm Which ONE of the following correctly completes the statements below? IAW EOP-ECA-2.1, the operator must raise the RCS boron concentration to a MINIMUM of approximately ____(1)____ to establish the Cold Shutdown boron concentration. The reactivity effects due to this event are more severe while operating at the ____(2)____-Of-Life. (REFERENCES PROVIDED) A. (1) 680-690 ppm (2) Beginning B. (1) 680-690 ppm (2) End C. (1) 760-770 ppm (2) End D. (1) 760-770 ppm (2) Beginning Page 10 of 75 Question:(1 point)11ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a loss of both MFW pumps occurred
- All Service Water pumps have lost power and cannot be restored
- CST level is 12% and rapidly lowering
- The SDAFW pump is out of service IAW OP-402, AUXILIARY FEEDWATER SYSTEM, which ONE of the following is required to supply the OIL COOLER for operation of the "B" MDAFW pump under these conditions? A. Fire Water B. Potable Water C. Deepwell Water D. Fukushima AFW Suction Tank water Page 11 of 75 Question:(1 point)12ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating anExtended Loss of AC Power (ELAP)*A depressurization of all S/G's was initiated at 10:00*The following timeline of events is observed:Time S/G Pressures Pzr Level 10:15 500 psig 13% 10:45 190 psig 0% Which ONE of the following correctly completes the statements below? The EARLIEST time at which the depressurization is required to be stopped IAW EOP-ECA-0.0, is ____(1)____. The reason the depressurization is stopped is to ____(2)____. A. (1) 1015 (2) prevent injection of accumulator nitrogen into the RCS B. (1) 1045 (2) ensure that no reactor head voiding will occur C. (1) 1015 (2) ensure that no reactor head voiding will occur D. (1) 1045 (2) prevent injection of accumulator nitrogen into the RCS Page 12 of 75 Question:(1 point)13ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power when a loss of off-site power occurs*Fifteen seconds later an SI actuation occurred due to a Large Break LOCAWhich ONE of the following correctly completes the statements below? The BOP will expect to see the SW Booster Pumps started on the ____(1)____. SW Booster Pump suction pressure ____(2)____ have to be at least 30 psig for the SW Booster Pump to start. A. (1) Blackout Sequencer (2) does B. (1) Blackout Sequencer (2) does NOT C. (1) SI Sequencer (2) does D. (1) SI Sequencer (2) does NOT Page 13 of 75 Question:(1 point)14ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- A Startup Transformer lockout occurs Which ONE of the following describes how Instrument Buses 1 and 4 will respond to this event? A. Both Instrument Buses 1 and 4 will de-energize B. Instrument Bus 1 will remain energized; Instrument Bus 4 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus C. Instrument Bus 4 will remain energized; Instrument Bus 1 will momentarily de-energize until the Emergency Diesel Generator re-powers the associated Emergency Bus D. Both Instrument Buses 1 and 4 will remain energized Page 14 of 75 Question:(1 point)15ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- APP-036-D1, BATT CHARGER A/A-1 TROUBLE, annunciated.
- The OAO reports the following indications from Battery Charger "A-1": * +40 Volts on the Ground Detection Voltmeter.
- 135 Volts DC on Charger Voltage. Which ONE of the following correctly completes the statements below? IAW OMM-035, GROUND ISOLATION, the FIRST action the operator will take to attempt to identify the cause of the ground is ____(1)____. Subsequently, MCC-A spuriously de-energizes. Instrument Bus 2 and 7 will ____(2)____. A. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) de-energize B. (1) swap Battery Chargers to place Battery Charger "A" in-service (2) remain energized C. (1) cycle selected breakers on Distribution Panel A (2) de-energize D. (1) cycle selected breakers on Distribution Panel A (2) remain energized Page 15 of 75 Question:(1 point)16ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a reactor trip and SI occurred
- APP-036-D7, AREA MONITOR HI RAD, has just alarmed
- APP-036-H1, WDBRP TROUBLE, has just alarmed Which ONE of the following correctly completes the statements below? IAW EOP-E-1, radiation monitor ____(1)____ would be used to diagnose a LOCA outside containment. The WDBRP TROUBLE alarm ____(2)____ consistent with a LOCA outside Containment in the Auxiliary Building. A. (1) R-3, PASS Panel Area (2) is B. (1) R-3, PASS Panel Area (2) is NOT C. (1) R-8, Drumming Room (2) is D. (1) R-8, Drumming Room (2) is NOT Page 16 of 75 Question:(1 point)17ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The reactor was tripped from 100% power due to a loss of MFW
- A spurious SI has actuated
- RCS Pressure - 2300 psig
- All S/G pressures - 1050 psig
- S/G WIDE RANGE levels are as follows:
- WIDE RANGE: A - 10%,
- WIDE RANGE: B - 15%,
- WIDE RANGE: C - 9%
- AFW flow is indicating 0 gpm
- EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Immediate Actions are complete and have just been verified Which ONE (1) of the following correctly completes the statement below? The crew should ____(1)____ because ____(2)____. A. (1) remain in EOP-E-0 until directed to transition out (2) the "B" S/G is still a viable Heat Sink B. (1) remain in EOP-E-0 until directed to transition out (2) rules of usage require continuing in EOP-E-0 C. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed is required D. (1) immediately go to FRP-H.1, RESPONSE TO A LOSS OF SECONDARY HEAT SINK (2) RCS Bleed and Feed can still be avoided Page 17 of 75 Question:(1 point)18ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant has tripped from 100% power due to a LOCA
- The crew is operating in EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION
- RWST level is at 16%
- The only ECCS Pump drawing on the RWST is the "A" SI Pump and pump flow has been adjusted to 150 gpm. Which ONE of the following correctly completes the statements below? IAW EOP-ECA-1.1, the EARLIEST that the "A" SI Pump must be stopped is when the RWST Level lowers to ____(1)____. Assuming these conditions remain the same, four hours from now the RWST level will be ____(2)____. A. (1) 9% (2) higher B. (1) 9% (2) lower C. (1) 13% (2) higher D. (1) 13%
(2) lower Page 18 of 75 Question:(1 point)19ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 50% power
- During the performance of OST-011, ROD CLUSTER CONTROL EXERCISE & ROD POSITION INDICATION, ONE Control Bank "B" rod is 17 steps below the rest of the bank
- The crew is performing the steps to realign the rod IAW AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM Which ONE of the following correctly completes the statements below? 1) IAW AOP-001, OPEN the Control Bank "B" lift coil switch(es) for ____(1)____. 2) Realign the rod using the ____(2)____ position of the rod bank selector switch. A. (1) the misaligned rod ONLY (2) CB B B. (1) the misaligned rod ONLY (2) M (MANUAL) C. (1) all but the misaligned rod (2) CB B D. (1) all but the misaligned rod (2) M (MANUAL) Page 19 of 75 Question:(1 point)20ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*The Pressurizer Level Channel Selector Switch is selected to NORMAL*The reference leg for Pressurizer level Transmitter LT-459 develops a slow leak*The "A" Charging Pump is running in AUTOWhich ONE of the following describes the instrument response? LT-459 __LT-460__ A. rises lowers B. lowers remains the same C. rises remains the same D. lowers rises Page 20 of 75 Question:(1 point)21ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A reactor startup is being commenced
- Source Range count rate (CR0) prior to control bank rod withdrawal is as follows:
- N31: 3.0E+001 cps
- N32: 3.0E+001 cps Subsequently:
- The crew has completed the MINIMUM number of doublings required to allow the crew to withdraw control rods as necessary to achieve criticality IAW GP-003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL
- The following indications are observed:
- N31: 2.4E+002 cps
- N32: 1.2E+002 cps Which ONE of the following correctly completes the statement below? IAW GP-003, Source Range Channel ____(1)____ is indicating AS EXPECTED. When the Source Range Channel with the unexpected reading is removed from service per the appropriate OWP, the reactor startup ____(2)____ continue. A. (1) N31 (2) may B. (1) N31 (2) may not C. (1) N32 (2) may D. (1) N32 (2) may not Page 21 of 75 Question:(1 point)22ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A Reactor startup is in progress
- The following indications are observed:
- N31/32 = 900 cps
- N35/36 = 5 x 10-11 amps Subsequently:
- Intermediate Range (IR) channel N36 fails LOW
- The crew places the Reactor startup on HOLD Which ONE of the following correctly completes the following statement? The reason that the reactor startup is placed on HOLD is because a Reactor Protection Trip Function for the ________ accident is degraded. A. rod ejection B. boron dilution C. steam line break D. uncontrolled RCCA bank rod withdrawal Page 22 of 75 Question:(1 point)23ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An accidental gaseous radwaste release is in progress
- R-1, Control Room Area Radiation Monitor, alarms
- R-1 is indicating 8.62E-2 mR/hr and stable Which ONE of the following correctly completes the statements below? R-1 ____(1)____ operating properly.
When R-1 alarms, the CR HVAC will automatically shift to the Emergency ____(2)____ Mode. A. (1) is (2) Recirculation B. (1) is (2) Pressurization C. (1) is NOT (2) Recirculation D. (1) is NOT (2) Pressurization Page 23 of 75 Question:(1 point)24ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- The following is observed on the Fire Alarm Console: (SEE REFERENCE CONDITIONS ON NEXT PAGE) Which ONE of the following correctly completes the statements below? It is expected that the automatic water suppression system ____(1)____ actuate for these conditions. Based on this information, the entry conditions ____(2)____ met for AOP-041, RESPONSE TO FIRE EVENTS. A. (1) will (2) are B. (1) will (2) are NOT C. (1) will NOT (2) are D. (1) will NOT (2) are NOT Page 24 of 75 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- With the plant at 100%, a confirmed bomb threat has been received
- The caller specified that the bomb was located in the Control Room
- The following timeline of events is recorded: 2110 The Control Room was evacuated after all appropriate actions were taken 2145 A Control operator in the Charging Pump Room informs the SM that:
- N51 reads 3.0E5 cps and is slowly lowering
- Pressurizer pressure is 2225 psig
- Pressurizer level is 35%
- The "A" Charging Pump is operating Which ONE of the following correctly completes the statements below? IAW Attachment 1 of AOP-004, CONTROL ROOM INACCESSIBILITY, the operator will raise Pressurizer level to at LEAST greater than ____(1)____, and then stop the running Charging Pump.
The basis for this action is to ____(2)____. A. (1) 60% (2) prevent exceeding the Charging Pump starting duty limitations B. (1) 60% (2) ensure that the reactor is subcritical C. (1) 86%
(2) ensure that the reactor is subcritical D. (1) 86%
(2) prevent exceeding the Charging Pump starting duty limitations Page 25 of 75 Question:(1 point)26ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The R-9, Letdown Line Area, indication on Radiation Monitoring System Recorder RR-1 is rising Which ONE of the following correctly completes the statements below? If the trend continues, it is expected that ____(1)____. The basis for the R-9 setpoint is to detect ____(2)____. A. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) small leaks in fuel rods B. (1) the RR-1 will alarm BEFORE the R-9 ratemeter (2) release of resin from the in-service demineralizers C. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) small leaks in fuel rods D. (1) the R-9 ratemeter will alarm BEFORE RR-1 (2) release of resin from the in-service demineralizers Page 26 of 75 Question:(1 point)27ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- EOP-ECA-0.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED has been implemented
- The crew is checking for Natural Circulation with the following conditions:
- Containment pressure is 0.5 psig
- Steam dump using the S/G PORVs is in progress
- CETC are 555°F and stable
- S/G pressures are stable at 900 psig
- RCS Hot Leg temperatures are 555°F and stable
- RCS Cold Leg temperatures are 545°F and slowly rising
- S/G NR levels are 21% and stable Which ONE of the following correctly completes the statements below? Based on the indications above, Natural Circulation (NC) flow ____(1)____ been established. IAW EOP-ECA-0.1, the crew will ____(2)____. A. (1) has NOT (2) raise S/G levels to promote the establishment of NC flow B. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 9% C. (1) has (2) maintain steam dump rate and a minimum S/G NR level of 18% D. (1) has NOT (2) raise the rate of dumping steam to promote the establishment of NC flow Page 27 of 75 Question:(1 point)28ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power when a transient occurs
- Over 15-20 seconds a load rejection lowers and then stabilizes power at 80% Which ONE of the following correctly completes the statements below? Seal water injection flow will INITIALLY ____(1)____. Subsequently,
- APP-001-B4, RCP SEAL INJ HI/LO FLOW, has alarmed
- The CRS has directed use of the expanded seal water injection flow control band The expanded seal water injection flow control band is ____(2)____. A. (1) rise (2) 6-20 gpm B. (1) rise (2) 7-18 gpm C. (1) lower (2) 6-20 gpm D. (1) lower (2) 7-18 gpm Page 28 of 75 Question:(1 point)29ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is in Mode 3
- APP-003-E2, VCT HI/LO PRESS, has alarmed
- Actual VCT pressure is 15 psig Which ONE of the following correctly completes the statement below? If VCT pressure continues to lower, RCP #1 Seal Leakoff flow will ____(1)____ and RCP #2 Seal leakoff flow will ____(2)____. A. (1) lower (2) rise B. (1) rise (2) lower C. (1) rise (2) rise D. (1) lower (2) lower Page 29 of 75 Question:(1 point)30ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*Due to RTGB indications the crew has entered AOP-024, LOSS OF INSTRUMENT BUS*An Auto Makeup to the VCT has initiated on the loss of instrument busWhich ONE of the following correctly completes the statement below? The Auto makeup has occurred because VCT Level transmitter ____(1)____ has de-energized on a loss of Instrument Bus ____(2)____. A. (1) LT-112 (2) 7 B. (1) LT-112 (2) 9 C. (1) LT-115 (2) 7 D. (1) LT-115 (2) 9 Page 30 of 75 Question:(1 point)31ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *A plant cooldown is in progress*The "A" RHR Train is in service*RCS temperature is 190°F*RCS Pressure is 350 psig*The RCS is in Solid Plant Operation with LTOPP in serviceSubsequently, a transient occurs resulting in the following: *RCS temperature is 195°F*RCS Pressure is 420 psig*PZR PORV PCV-456 indicates OPEN*PZR PORV PCV-455C indicates CLOSEDThe crew has entered AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Which ONE of the following correctly completes the statements below? Based on plant conditions, both PORVs should have ____(1)____. IAW AOP-019 immediate actions, the operator will FIRST ____(2)____ to control or mitigate the consequences of this event. A. (1) remained closed (2) close PCV-456 B. (1) opened (2) stop all Charging Pumps and RCPs C. (1) opened (2) ensure the block valve for PCV-456 is OPEN D. (1) remained closed (2) place the PCV-456 LTOPP Arming Switch to NORMAL Page 31 of 75 Question:(1 point)32ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following: * "A" Train RHR is in service
- Instrument Air pressure lowers to 30 psig Which ONE of the following correctly completes the statement below? RCS temperature will INITIALLY ____(1)____, and RHR System Flow will INITIALLY ____(2)____. A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Lower (2) Lower D. (1) Lower (2) Rise Page 32 of 75 Question:(1 point)33ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% RTP
- The following timeline is observed: TIME "A" SI accumulator pressure"A" SI accumulator level1108 637 psig 68 percent 1111 646 psig 70 percent 1114 660 psig 75 percent Which ONE of the following correctly completes the statement below? The EARLIEST time at which an RTGB annunciator alarm would occur is at time ____(1)____, due to ____(2)____ reaching its alarm setpoint. A. (1) 1111 (2) APP-002-A4, SI ACCUM A HI/LO LVL B. (1) 1114 (2) APP-002-B4, SI ACCUM A HI/LO PRESS C. (1) 1111 (2) APP-002-B4, SI ACCUM A HI/LO PRESS D. (1) 1114 (2) APP-002-A4, SI ACCUM A HI/LO LVL Page 33 of 75 Question:(1 point)34ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100% power when a LOCA occurs inside Containment Which ONE of the following correctly completes the statements below? While operating in the EOP Network, the LOWEST pressure in which "Adverse" containment values are applicable is ____(1)____. Based on the increased containment temperature, level detectors with wet reference legs will indicate ____(2)____ than the actual level. A. (1) 4 psig (2) lower B. (1) 4 psig (2) higher C. (1) 10 psig (2) lower D. (1) 10 psig (2) higher Page 34 of 75 Question:(1 point)35ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- Containment pressure is 0.2 psig
- Containment temperature is 94°F Subsequently:
- A load rejection results in a reactor trip
- Following the trip, a Pressurizer Safety valve opens, and will NOT reseat
- The PRT rupture disks function as designed
- Containment pressure is rising at 0.1 psig every 5 minutes
- Containment temperature is rising at 2°F every 5 minutes Assuming these conditions remain constant, which ONE of the following identifies the Containment Technical Specifications LCOs that will be affected one hour from now? A. Both LCO 3.6.4, Containment Pressure, and LCO 3.6.5, Containment Air Temperature, will be exceeded. B. Only LCO 3.6.4, Containment Pressure, will be exceeded. C. Only LCO 3.6.5, Containment Air Temperature, will be exceeded. D. Neither LCO 3.6.4, Containment Pressure, nor LCO 3.6.5, Containment Air Temperature, will be exceeded. Page 35 of 75 Question:(1 point)36ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
T= 1305:10
- A loss of off-site power has occurred concurrent with a Reactor trip
- The crew enters EOP-E-0, Reactor Trip or Safety Injection T=1307:40
- Immediate actions of EOP-E-0 are complete
- The following parameters are noted:
- RCS pressure is 2110 psig and stable
- SG pressures are all 910 psig and lowering slowly
- CV pressure is 0.7 psig and rising slowly At time 1307:40, which ONE of the following describes the CCW Pump indication available in the control room? A. "B" and "C" CCW Pump RED indicating lights are LIT. "A" CCW Pump GREEN indicating light is LIT. B. All 3 CCW Pump control switch GREEN indicating lights are LIT. C. "B" and "C" CCW Pump GREEN indicating lights are LIT; "A" CCW Pump RED indicating light is LIT. D. "B" and "C" CCW Pump RED indicating lights are LIT; "A" CCW Pump GREEN and RED indicating lights are EXTINGUISHED. Page 36 of 75 Question:(1 point)37ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant The plant is at 100% power when the following occurs:
- A load rejection results in a PZR PORV actuation
- The PZR PORV will not fully seat
- The depressurization led to a Reactor Trip and Safety Injection
- PZR pressure reduces to 1400 psig and stabilizes
- The PRT rupture discs rupture at their design setpoint
- Containment pressure peaks at 15 psig Which ONE of the following is the MAXIMUM temperature indicated by the Safety Valve tailpiece RTD during the entire event? A. 213°F B. 250°F C. 298°F D. 338°F Page 37 of 75 Question:(1 point)38ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following identifies a condition which will cause an automatic reactor trip? A. RCP bus frequency reads 58.0 Hz when THREE Power Range channels read 5% RTP. B. Flow in ONE Reactor Coolant Loop reads 91% when ALL Power Range channels read 35% RTP. C. ONE Intermediate Range NI channel reads 1 x10E-6 AMPS when TWO Power Range channels read 15% RTP. D. ONE Source Range NI channel reads 5 x10E5 CPS when TWO Intermediate Range NI channels read 9 x10E-11 AMPS. Page 38 of 75 Question:(1 point)39ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant was at 100% when a SI occurredWhich ONE of the following correctly completes the statements below regarding the Feed Reg Valves and the Feed Reg Bypass Valves? Following the SI signal, the Feed Reg Bypass Valves ____(1)____ receive a CLOSE signal. The Feed Reg Valves ____(2)_____ be available when the SI is RESET and the Feedwater Isolation OVRD/RESET key switches are placed in OVRD/RESET. A. (1) will (2) will B. (1) will NOT (2) will C. (1) will (2) will NOT D. (1) will NOT (2) will NOT Page 39 of 75 Question:(1 point)40ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below regarding the Containment Spray Actuation logic scheme?
The MINIMUM number of Containment Pressure channels that must sense pressure greater than the Hi-Hi pressure setpoint to generate an automatic Containment Spray Actuation is ____(1)____. The Containment Spray Actuation bistables are ____(2)____ to actuate. A. (1) Two (2) Energize B. (1) Two (2) De-energize C. (1) Four (2) Energize D. (1) Four (2) De-energize Page 40 of 75 Question:(1 point)41ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*A realignment has just occurred and the operator observes the following Service Watervalve alignments for HVH-1 (CV Recirc Fan A) and HVH-2 (CV Recirc Fan B):Assuming no conditions change, which ONE of the following identifies the operational restrictions, if any, placed on HVH-1? A. HVH-1 may run continuously, there are no restrictions. B. HVH-1 may continue to run for up to 15 additional minutes. C. HVH-1 must be immediately secured and cannot be run under these conditions. D. HVH-1 must be immediately secured and can ONLY be started during emergencies. Page 41 of 75 Question:(1 point)42ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant was at 100%
- A LOCA inside containment occurs and the following timeline is observed: TIME OBSERVATION 1200 LOCA occurs 1201 CV Spray system actuates 1211 CV Pressure peaks at 22 PSIG 1235 CV Pressure lowers to less than 10 PSIG 1245 CV Pressure lowers to less than 4 PSIG Which ONE of the following correctly completes the statements below? IAW EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, the EARLIEST TIME that the Containment Spray Pumps may be secured is ____(1)____.
In order to successfully reset the Phase B Containment Isolation signal, the Containment Spray Signal ____(2)____ required to be reset FIRST. A. (1) 1235 (2) is B. (1) 1235 (2) is NOT C. (1) 1245 (2) is D. (1) 1245 (2) is NOT Page 42 of 75 Question:(1 point)43ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*R-15, Air Ejector Radiation Monitor, alarms*The crew entered AOP-035, S/G TUBE LEAK*The crew has initiated Attachment 5, R-15 Monitoring*Chemistry reports the following leakrates:Time "A" S/G Tube leakrate 0800 31 gpd 0900 51 gpd 1000 81 gpd 1100 111 gpd IAW AOP-035, which ONE of the following identifies the EARLIEST time that a plant shutdown is required? A. 0800 B. 0900 C. 1000 D. 1100 Page 43 of 75 Question:(1 point)44ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occursWhich ONE of the following describes how this actuation affects the Reactor and the Main Turbine? A. BOTH the Reactor and the Main Turbine receive trip signals directly from the FWIS. B. The Reactor receives a trip signal directly from the FWIS, and causes a Main Turbine trip. C. The Main Turbine receives a trip signal directly from the FWIS and the Reactor will trip because the Main Turbine tripped with power above P-8. D. NEITHER the Reactor nor the Main Turbine receive trip signals directly from the FWIS. However, the Reactor will trip on plant conditions created by the FWIS actuation and cause a Main Turbine trip. Page 44 of 75 Question:(1 point)45ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *With the plant at 100% power, an ATWS event occurred*The crew entered FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION ATWS*All SG Narrow Range levels are OFF-Scale LOWWhich ONE of the following correctly completes the statement below? IAW FRP-S.1, AFW flow must be greater than a MINIMUM value of ________ to establish a Secondary Heat Sink? A. 300 gpm B. 500 gpm C. 600 gpm D. 1000 gpm Page 45 of 75 Question:(1 point)46ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- A reactor trip has occurred Which ONE of the following identifies the breakers which will automatically CLOSE one minuteafter the reactor trip? Breaker nomenclature: 52/10 4KV BUS 1-2 TIE BKR 52/12 START-UP TRANSFORMER TO 4KV BUS 2 52/17 START-UP TRANSFORMER TO 4KV BUS 3 52/19 4KV BUS 3-4 TIE BKR A. 52/10 and 52/12 B. 52/10 and 52/17 C. 52/12 and 52/19 D. 52/17 and 52/19 Page 46 of 75 Question:(1 point)47ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on faultWhich ONE of the following correctly completes the statement below? Circulating Water pump(s) _________ lost power. A. "A" & "B" have B. "B" & "C" have C. "A" & "C" have D. "B" ONLY has Page 47 of 75 Question:(1 point)48ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is in Mode 3*The "B" Battery Charger is in service*The "B-1" Battery Charger is in standbySubsequently: *MCC-6 is de-energized*APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms*Two minutes later MCC-6 is re-energizedWhich ONE of the following identifies when APP-036-D2 will clear? APP-036-D2 will clear-- A. when the "B" Battery Charger automatically restarts. B. only after the operator manually restarts the "B" Battery Charger. C. only after the operator manually places the "B-1" Battery Charger back in the STANDBY mode. D. only after the operator manually restarts the "B" Battery Charger and places the "B-1" Battery Charger back in the STANDBY mode. Page 48 of 75 Question:(1 point)49ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is at 100% power*OST-401-1, EDG "A" SLOW SPEED START testing is in progress*Current "A" EDG load is 2500 KWSubsequently: *The Normal Supply Breaker to E-1, 52/18B, opens*EDG "A" Output Breaker 52/17B, opensWhich ONE of the following correctly completes the statements below? IAW OP-604 CAUTION statement, the consequence of opening the EDG "A" Output Breaker under load is ____(1)____. IAW OP-604 when attempting to recover, the local Generator Parallel/Isolate Switch must be placed in the ____(2)____ position. OP-604, DIESEL GENERATORS "A" AND "B" A. (1) the diesel engine may trip due to overspeed (2) ISOL B. (1) excessive carbon buildup in the engine could occur (2) PARALLEL C. (1) the diesel engine may trip due to overspeed (2) PARALLEL D. (1) excessive carbon buildup in the engine could occur (2) ISOL Page 49 of 75 Question:(1 point)50ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following supplies power to the "A" and "B" EDG Fuel Oil Transfer Pumps? A. MCC-10 and MCC-9 respectively B. MCC-9 and MCC-10 respectively C. MCC-6 and MCC-5 respectively D. MCC-5 and MCC-6 respectively Page 50 of 75 Question:(1 point)51ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The reactor is at 100%*The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIRHANDLING*R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarmsV12-12, CV VAC RELIEF V12-13, CV VAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE of the following correctly completes the statements below? The crew would expect to see ____(1)____ annunciator flashing. Due to the conditions above, ____(2)____ will automatically close. A. (1) APP-036-D7 (2) V12-12 & V12-13 ONLY B. (1) APP-036-D8 (2) V12-12 & V12-13 ONLY C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Page 51 of 75 Question:(1 point)52ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantGiven the following: *The plant is operating at 100% power*R-19A, STM GEN BLOW DN SG-A, enters the alarm conditionWhich ONE of the following correctly completes the statements below? In regards to the Blowdown Isolation Valves and the Blowdown Sample Isolation Valves, an alarm condition on R-19A will automatically close the ____(1)____. IAW AOP-005, RADIATION MONITORING SYSTEM, if the automatic actions fail to occur, the crew ____(2)____ de-energize R-19A in an attempt to cause the automatic actions to occur. A. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-193A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will D. (1) Blowdown Isolation Valves (FCV-193A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B) (2) will NOT Page 52 of 75 Question:(1 point)53ILC15 RNP RO NRC ExaminationRobinson Nuclear PlantWhich ONE of the following correctly completes the statements below regarding components normally cooled by Service Water? The Circulating Water Pumps ____(1)____ be cooled by the Fire Water System during an emergency. The Control Room HVAC Cooling Units ____(2)____ be cooled by the Fire Water System during an emergency. A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can NOT D. (1) can NOT (2) can Page 53 of 75 Question:(1 point)54ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power * "D" IA Compressor is running
- Station Air Compressor is running Subsequently:
- The crew is implementing AOP-017, LOSS OF INSTRUMENT AIR SA-5, STATION AIR TO INST AIR CROSS CONNECT SA-220, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION SA-221, SA TO IA CROSS CONNECT BYPASS FILTER ISOLATION Which ONE of the following correctly completes the statements below? IAW AOP-017, the PREFERRED method to cross connect IA from Station Air is by opening ____(1)____ .
IA will no longer be used to supply Breathing Air to ____(2)____. A. (1) SA-5 (2) minimize IA loads ONLY B. (1) SA-5 (2) minimize IA loads and prevent harm to users of Breathing Air C. (1) SA-220 and SA-221 (2) minimize IA loads ONLY D. (1) SA-220 and SA-221 (2) minimize IA loads and prevent harm to users of Breathing Air Page 54 of 75 Question:(1 point)55ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A LOCA occurred 45 minutes ago
- The crew is implementing the Emergency Operating Procedures
- The following conditions exist:
- CET temperature is 340°F
- RCS pressure is 60 psig and lowering
- Full Range RVLIS is 40%
- RCS Cold Leg temperature is 320°F and lowering
- S/G NR levels are off-scale LOW
- S/G pressures are 550 psig and trending down
- AFW flow is 450 gpm
- All RCPs are OFF
- CV pressure is 43 psig and rising
- SPDS has been reset Which ONE of the following identifies the MOST challenged Critical Safety Function? A. Integrity B. Heat Sink C. Containment D. Core Cooling Page 55 of 75 Question:(1 point)56ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power Subsequently, all IRPI indication is lost except a green LED is illuminated on each rod indicator Which ONE of the following correctly completes the statements below? The cause of this condition is the ____(1)____ has tripped.
For this condition entry into AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, ____(2)____ required. A. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is B. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is D. (1) Instrument Bus 7A, Circuit 10 breaker, (RTGB receptacles), (2) is NOT Page 56 of 75 Question:(1 point)57ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- GP-008, DRAINING THE REACTOR COOLANT SYSTEM, is in progress
- The crew has positioned HIC-142, PURFICATION FLOW, to establish required drain rate Which ONE of the following correctly completes the statements below? LCV-115A, VCT/HLDP TK DIV, will begin to divert at ____(1)____ in the VCT.
IAW GP-008, ____(2)____ level change can be used to determine the volume drained from the RCS. A. (1) 30" (2) WHUT B. (1) 30" (2) CVCS HUT C. (1) 51.6" (2) CVCS HUT D. (1) 51.6" (2) WHUT Page 57 of 75 Question:(1 point)58ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 35% power and stable
- The "A" Charging Pump is running in AUTO
- The "B" Charging Pump is running in MANUAL and adjusted to 50% output on Charging Pump Speed Controller SC-151
- Letdown flow is 105 gpm Subsequently:
- Letdown flow is lowered 45 gpm
- Reactor power is lowered to 30% and stabilized
- Pressurizer Level lowers to, and has stabilized at 31.5% Which ONE of the following correctly completes the statements below? The Pressurizer Level Control System ____(1)____ operating as expected for these plant conditions. While Letdown was being lowered, APP-003-F3, CHG PMP LO SPEED, alarmed. According to OP-301, CHEMICAL AND VOLUME CONTROL SYSTEM, the operator will be required to ____(2)____ Charging Pump to clear the alarm. A. (1) is (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" B. (1) is (2) adjust the speed of the "B" C. (1) is NOT (2) place the "A" Charging Pump in Manual and adjust the speed of the "A" D. (1) is NOT (2) adjust the speed of the "B" Page 58 of 75 Question:(1 point)59ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The Plant is in Mode 1, following a control rod manipulation
- The RTGB IRPI indication for Control Bank "D" Rod M-8 indicates 120 inches
- The RTGB IRPI indication for Control Bank "D" Rod H-4 indicates 110 inches
- Control Bank "D" step counter position is 192 steps Which ONE of the following correctly completes the statements below? Based on the given conditions, control rod ____(1)____ is stuck. Assuming the average of the individual rod positions in the affected bank indicate 120 inches, entry into ITS LCO 3.1.4, ROD GROUP ALIGNMENT LIMITS, ____(2)____ required. A. (1) M-8 (2) is B. (1) M-8 (2) is NOT C. (1) H-4 (2) is D. (1) H-4 (2) is NOT Page 59 of 75 Question:(1 point)60ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The operator is reviewing the T/C TREND pages on both the Train "A" and Train "B" ICCM displays Which ONE of the following correctly completes the statements below? The TOTAL number of Core Exit Thermocouples (CET) that monitor the core is ____(1)____. The T/C TREND page displays the average of ____(2)____ CET indications over the last 30 minutes. A. (1) 23 (2) the five highest B. (1) 23 (2) all C. (1) 46 (2) all D. (1) 46 (2) the five highest Page 60 of 75 Question:(1 point)61ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE (1) of the following is the power supply for HVE-3, CV Air Iodine Removal Fan? A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-10 Page 61 of 75 Question:(1 point)62ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW GP-010, REFUELING, the Containment Purge System ____(1)____ required be in operation during Core Alterations with the Equipment Hatch removed.
The Containment Purge System ____(2)____ required be in operation if a Containment entry is being made with the plant in Mode 1. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 62 of 75 Question:(1 point)63ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- Spent fuel handling activities are NOT in progress Subsequently:
- SFP level starts to rapidly lower due to a large structural and piping failure
- The crew has entered AOP-036, SFP EVENTS R-14, Plant Vent Effluent Monitor R-21, Fuel Handling Building Upper Level, Noble Gas HVE-15, Fuel Handling Building Exhaust Fan Which ONE of the following correctly completes the statements below? IAW AOP-036, R-14 ____(1)____ monitored for indications of fuel damage.
If R-21 were to subsequently alarm, HVE-15 ____(2)____ automatically trip. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 63 of 75 Question:(1 point)64ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- The crew trips the reactor and initiates safety injection due to a SGTR on the "B" Steam Generator
- The "B" MDAFW Pump trips on auto-start * "B" SG NR level is 6% and rising slowly * "A" and "C" SG NR levels are off-scale low Which ONE of the following correctly completes the statements below? Without operator action, a Secondary Heat Sink ____(1)____ established.
Based on the current conditions, the operator ____(2)____ immediately isolate feed to the "B" S/G. A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page 64 of 75 Question:(1 point)65ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following discharges to the Reactor Coolant Drain Tank? A. RCV-609, CC SURGE TANK VENT B. CVC-203 A/B, LETDOWN RELIEF VALVES C. CVC-389, EXCESS LETDOWN DIVERSION D. CVC-400 A/B/C, CHARGING PUMP "A/B/C" LEAKAGE ISOLATION Page 65 of 75 Question:(1 point)66ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below? IAW OPS-NGGC-1303, VERIFICATION PRACTICES, guidance for waiving Independent Verification (IV) requirements states that the IV may be waived if the operators were expected to ____(1)____ to complete the verification.
In these cases, ____(2)____ Verification will be used as an alternative to Independent Verification. A. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Concurrent B. (1) receive a total exposure of greater than 10 mrem (2) Concurrent C. (1) receive a total exposure of greater than 10 mrem (2) Functional D. (1) be in an area where the dose rate is greater than 100 mrem/hour (2) Functional Page 66 of 75 Question:(1 point)67ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions:
- The plant is in MODE 6 for refueling operations
- Core alterations are in progress Which ONE of the following correctly completes the statements below? IAW LCO 3.9.2, NUCLEAR INSTRUMENTATION, ____(1)____ shall be OPERABLE. N-51 and N-52, ____(2)____ capable of providing audible indication inside Containment. N-31, N-32, SOURCE RANGE NUCLEAR INSTRUMENTS N-51, N-52, REG. GUIDE 1.97 NEUTRON FLUX (SOURCE RANGE, WIDE RANGE) A. (1) either N-31 OR N-32 (2) are B. (1) both N-31 AND N-32 (2) are C. (1) either N-31 OR N-32 (2) are NOT D. (1) both N-31 AND N-32 (2) are NOT Page 67 of 75 Question:(1 point)68ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant startup is in progress
- NIS Power Indication is 50%
- The STA is recording data IAW GP-005, POWER OPERATION, Attachment 1, REACTOR POWER ASCENSION INDICATOR LOG Which ONE of the following correctly completes the statements below? IAW GP-005, if Core T indicates 33°F, the crew ____(1)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). IAW GP-005, if Calorimetric power indicates 51.5%, the crew ____(2)____ be required to stabilize reactor power and perform OST-010, Power Range Calorimetric During Power Operation (ERFIS). A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Page 68 of 75 Question:(1 point)69ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The FWUFM System has been OOS for five days Subsequently:
- An AO reports a steam leak near the Main Steam Isolation Valves
- The following indications are noted in the Control Room:
- Tavg is LOWERING
- Steam flow and feed flow have RISEN
- A Power Limit Warning alarm on ERFIS has been received
- Reactor power is slowly RISING Which ONE of the following identifies the MAXIMUM thermal power limit allowed by the operating license under these conditions? A. 2300 MWt B. 2307 MWt C. 2339 MWt D. 2346 MWt Page 69 of 75 Question:(1 point)70ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band. Which ONE of the following correctly completes the statement below? IAW Technical Specification LCO 3.2.3 ACTION--. Restore AFD to within target band within ___(1)___. If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___. A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Page 70 of 75 Question:(1 point)71ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power
- Letdown flow is 45 gpm
- The "A" Charging Pump is operating in AUTO
- The "B" Charging Pump is operating in MANUAL Subsequently:
- R-9, Letdown Line Area Monitor, alarms
- The alarm is determined to be valid
- The crew enters AOP-005, RADIATION MONITORING SYSTEM Which ONE of the following correctly completes the statements below? IAW with Attachment 9 of AOP-005, the operator ____(1)____ required to evacuate the Aux Building of non-essential personnel.
IAW with Attachment 9 of AOP-005, the operator ____(2)____ required to isolate letdown flow. A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 71 of 75 Question:(1 point)72ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- An operator has been assigned work in the radiologically controlled area
- The dose rate in the area is 500 mR/hr
- The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension? A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Page 72 of 75 Question:(1 point)73ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- A plant cooldown is in progress
- RCS Temperature is 430°F
- RCS pressure is 725 psig
- The SI Accumulators have been isolated Subsequently, an RCS leak occurs and the operating crew enters AOP-016, EXCESSIVE RCS LEAKAGE.
Which ONE of the following correctly completes the statements below? AOP-016 will ensure that a MINIMUM of ____(1)____ Charging Pumps are running with their speed adjusted to maximum.
With the current plant conditions, if Pressurizer level continues to lower uncontrollably with maximum charging flow, the crew would transition to ____(2)____. A. (1) two (2) AOP-033, SHUTDOWN LOCA B. (1) two (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION C. (1) three (2) AOP-033, SHUTDOWN LOCA D. (1) three (2) EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 73 of 75 Question:(1 point)74ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is at 100% power
- The Control Room receives a confirmed report of a fire in the Unit 2 Cable Spread Room (Fire Zone 19) at 0730 Which ONE of the following correctly completes the statements below? IAW AOP-041, RESPONSE TO FIRE EVENT, the operator must ____(1)____. The LATEST time that this action may be complete is ____(2)____. A. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0740 B. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536), ONLY (2) 0745 C. (1) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (2) 0745 D. (3) close both Pressurizer PORV Block Valves (RC-535 and RC-536) AND place the PCV-455C and 456 Isolate Switches to the ISOLATE position (4) 0740 Page 74 of 75 Question:(1 point)75ILC15 RNP RO NRC ExaminationRobinson Nuclear Plant Given the following:
- The plant is operating at 100% power Subsequently, the following time line of events occur: TIME EVENT 1200 APP-009-C5, MAIN TRANSF TROUBLE, alarms 1203 The Outside AO reports that all Main Transformer Fans and Pumps are NOT operating 1204 The crew enters AOP-037, LARGE TRANSFORMER MALFUNCTIONS 1208 TIME NOW IAW AOP-037, which ONE of the following identifies the EARLIEST time that the reactor must be tripped? A. IMMEDIATELY B. 1211 C. 1214 D. 1231 Page 75 of 75 RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-7 Amendment No.218 0 2550751000 1250 1500 1750 2000 2250 2500 2750 0 5100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) MATERIALS PROPERTIES BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Curves applicable for heatup rates up to 60 ºF/Hr for Service period up to 35 EFPY. Heatup Curves include +10ºF and -60 psig allowance For instrumentation error. Acceptable Operation Unacceptable Operation Leak Test Limit Heatup Rate to 60 ° F/Hr Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 35 EFPY Indicated Pressure (psig) Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY RCS P/T Limits 3.4.3 HBRSEP Unit No. 2 3.4-8 Amendment No. 218 0 250 500 750 1000 1250 1500 1750 2000 2250 2500 2750 0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F) Unacceptable Operation Acceptable Operation 100°F/ Hr Cooldown Rates ( ° F/Hr) 0 ° F/Hr. Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY 60°F/ Hr 40°F/ Hr 20°F/ Hr 100 60 40 0 and 20 Curves applicable for cooldown rates up to 100°F/Hr for the service period up to 35 EFPY. Curves include +10°F and -60 PSIG allowance for instrument error. Indicated Pressure (PSIG) MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 and Girth Weld 10-273 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F 3/4T, 147°F and 172°F REV. REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR5007009001100 1300150017000200040006000800010000120001400016000180002000022000CYCLE EXPOSURE (MWD/MTU)CURVE 1.14BORON CONCENTRATION REQUIRED TO MAINTAINSHUTDOWN MARGIN BORON (PPM)HBR2 CYCLE 30200 F300 F350 FA MINIMUM OF 2.6% SHUTDOWN MARGIN(ARI-MRR)38 FRNP Cycle 30 Curve Book Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve BookRNP-F/NFSA-0237, Rev. 0 Page A46 of A86 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer1B2D3C4C5B6B7B8B9D10C11A12D13D14B15A16A17B18B19C20A21B22D23D24D25CPrinted 2/11/2016 2:53:31 PMPage 1 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer26A27D28C29B30C31B32B33C34B35B36A37D38D39C40C41B42C43C44C45C46C47B48A49A50DPrinted 2/11/2016 2:53:32 PMPage 2 of 3 Examination KEY for:ILC15 RNP RO NRC ExaminaQuestionNumberAnswer51D52C53D54D55C56C57B58B59C60D61A62B63A64B65C66C67D68B69A70A71B72B73A74D75BPrinted 2/11/2016 2:53:32 PMPage 3 of 3