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Robinson 2016-301 SRO As-Given Written Exam
	ML16061A457
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Site:	Robinson
Issue date:	03/01/2016
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To:	; Carolina Power & Light Co
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Question:(1 point)1ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 being reached Which 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, ONLY B. (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 100 Question:(1 point)2ILC15 RNP SRO 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 100 Question:(1 point)3ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power * "A" CV Spray pump is out of service for maintenance Subsequently:

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 OR SECONDARY 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 °F Which 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 100 Question:(1 point)4ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

With the plant at 100% power a Large Break LOCA occurs Which 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 100 Question:(1 point)5ILC15 RNP SRO 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 100 Question:(1 point)6ILC15 RNP SRO 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 100 Question:(1 point)7ILC15 RNP SRO 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 100 Question:(1 point)8ILC15 RNP SRO 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 100 Question:(1 point)9ILC15 RNP SRO 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 100 Question:(1 point)10ILC15 RNP SRO 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 100 Question:(1 point)11ILC15 RNP SRO 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 100 Question:(1 point)12ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating an Extended 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 100 Question:(1 point)13ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 LOCA Which 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 100 Question:(1 point)14ILC15 RNP SRO 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 100 Question:(1 point)15ILC15 RNP SRO 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 100 Question:(1 point)16ILC15 RNP SRO 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 100 Question:(1 point)17ILC15 RNP SRO 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 100 Question:(1 point)18ILC15 RNP SRO 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 100 Question:(1 point)19ILC15 RNP SRO 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 100 Question:(1 point)20ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 AUTO Which 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 100 Question:(1 point)21ILC15 RNP SRO 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 100 Question:(1 point)22ILC15 RNP SRO 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 100 Question:(1 point)23ILC15 RNP SRO 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 100 Question:(1 point)24ILC15 RNP SRO 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 100 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP SRO 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 100 Question:(1 point)26ILC15 RNP SRO 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 100 Question:(1 point)27ILC15 RNP SRO 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 100 Question:(1 point)28ILC15 RNP SRO 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 100 Question:(1 point)29ILC15 RNP SRO 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 100 Question:(1 point)30ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 bus Which 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 100 Question:(1 point)31ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 service Subsequently, 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 CLOSED The 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 100 Question:(1 point)32ILC15 RNP SRO 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 100 Question:(1 point)33ILC15 RNP SRO 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 100 Question:(1 point)34ILC15 RNP SRO 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 100 Question:(1 point)35ILC15 RNP SRO 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 100 Question:(1 point)36ILC15 RNP SRO 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 100 Question:(1 point)37ILC15 RNP SRO 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 100 Question:(1 point)38ILC15 RNP SRO 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 100 Question:(1 point)39ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 100% when a SI occurred Which 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 100 Question:(1 point)40ILC15 RNP SRO 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 100 Question:(1 point)41ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

A realignment has just occurred and the operator observes the following Service Water valve 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 100 Question:(1 point)42ILC15 RNP SRO 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 100 Question:(1 point)43ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 100 Question:(1 point)44ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occurs Which 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 100 Question:(1 point)45ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 LOW Which 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 100 Question:(1 point)46ILC15 RNP SRO 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 100 Question:(1 point)47ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power

Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on fault Which 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 100 Question:(1 point)48ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is in Mode 3

The "B" Battery Charger is in service

The "B-1" Battery Charger is in standby Subsequently:

MCC-6 is de-energized

APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms

Two minutes later MCC-6 is re-energized Which 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 100 Question:(1 point)49ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 KW Subsequently:

The Normal Supply Breaker to E-1, 52/18B, opens

EDG "A" Output Breaker 52/17B, opens Which 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 100 Question:(1 point)50ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which 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 100 Question:(1 point)51ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The reactor is at 100%

The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIR HANDLING

R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarms V12-12, 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 100 Question:(1 point)52ILC15 RNP SRO 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 100 Question:(1 point)53ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which 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 100 Question:(1 point)54ILC15 RNP SRO 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 100 Question:(1 point)55ILC15 RNP SRO 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 100 Question:(1 point)56ILC15 RNP SRO 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 100 Question:(1 point)57ILC15 RNP SRO 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 100 Question:(1 point)58ILC15 RNP SRO 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 100 Question:(1 point)59ILC15 RNP SRO 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 100 Question:(1 point)60ILC15 RNP SRO 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 100 Question:(1 point)61ILC15 RNP SRO 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 100 Question:(1 point)62ILC15 RNP SRO 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 100 Question:(1 point)63ILC15 RNP SRO 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 100 Question:(1 point)64ILC15 RNP SRO 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 100 Question:(1 point)65ILC15 RNP SRO 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 100 Question:(1 point)66ILC15 RNP SRO 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 100 Question:(1 point)67ILC15 RNP SRO 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 100 Question:(1 point)68ILC15 RNP SRO 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 100 Question:(1 point)69ILC15 RNP SRO 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 100 Question:(1 point)70ILC15 RNP SRO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 70 of 100 Question:(1 point)71ILC15 RNP SRO 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 100 Question:(1 point)72ILC15 RNP SRO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Page 72 of 100 Question:(1 point)73ILC15 RNP SRO 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 100 Question:(1 point)74ILC15 RNP SRO 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 100 Question:(1 point)75ILC15 RNP SRO 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 100 Question:(1 point)76ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

With the plant at 100% power a Feedwater Isolation Signal occurs

Safety Injection actuates

The crew is implementing FRP-S.1, RESPONSE TO NUCLEAR GENERATION-ATWS. Which ONE of the following correctly completes the statement below? IAW the FRP-S.1 basis document, the Turbine Stop Valves must be CLOSED within a MAXIMUM of ____(1)____ from event initiation.

This action ____(2)____ taken in order to maintain S/G inventory. A. (1) 30 seconds (2) is B. (1) 30 seconds (2) is NOT C. (1) 60 seconds (2) is D. (1) 60 seconds (2) is NOT Page 76 of 100 Question:(1 point)77ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The crew is in EOP-E-3, STEAM GENERATOR TUBE RUPTURE, has completed tube rupture mitigation in the "C" S/G and is now selecting a recovery procedure

Containment pressure is 4.5 psig due to a previously faulted "B" S/G

A Loss of Off Site Power has occurred

The Shift Manager has indicated that the recovery procedure should minimize radiation release The following indications are observed:

S/G "C" level is 86% and rising

PZR level is 67% and stable Which ONE of the following correctly completes the statement below? Based on the current plant conditions RCS depressurization ____(1)____ required. The CRS will select ____(2)____ as the recovery procedure. (REFERENCES PROVIDED) A. (1) is (2) EOP-ES-3.2, POSTSGTR COOLDOWN USING BLOWDOWN B. (1) is (2) EOP-ES-3.3, POSTSGTR COOLDOWN USING STEAM DUMP C. (1) is NOT (2) EOP-ES-3.2, POSTSGTR COOLDOWN USING BLOWDOWN D. (1) is NOT (2) EOP-ES-3.3, POSTSGTR COOLDOWN USING STEAM DUMP Page 77 of 100 Question:(1 point)78ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 5% power

One PZR PORV is CLOSED, has been isolated and cannot be manually cycled Subsequently:

A transient occurs causing a reactor trip and SI actuation

The crew enters FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

Bleed and Feed criteria has been met

Safety Injection has been manually actuated

The OPERABLE PZR PORV has been OPENED RC567, HEAD VENT RC568, HEAD VENT RC569, PZR VENT RC570, PZR VENT RC571, PRT ISO RC572, CV ATMOS IAW FRP-H.1, which ONE of the following actions, if any, is required to establish an adequate bleed path? A. No action is required, an adequate bleed path exists. B. Open the Reactor Head Vent Valves, RC-571 and RC-572, ONLY. C. Open the Pressurizer Vent Valves, RC-571 and RC-572, ONLY. D. Open the Reactor Head Vent Valves, Pressurizer Vent Valves, RC-571 and RC-572. Page 78 of 100 Question:(1 point)79ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A Station Blackout has occurred from 100% power

The crew is performing actions of ECA-0.0, LOSS OF ALL AC POWER

Immediate actions are complete

Offsite power is available to re-energize the Start-up Transformer (SUT)

APP-009-B5, MAIN TRANSF FAULT TRIP, alarm is ILLUMINATED. Subsequently:

E-1 is restored with EDG "A"

Transmission Maintenance has taken action such that APP-009-B5 is now extinguished. 86P, Generator Lockout Relay, Primary 86BU, Generator Lockout Relay, Backup OP-603, ELECTRICAL DISTRIBUTION OP-603-3, RESETTING HIGH IMPEDANCE FAULTS Which ONE of the following correctly completes the statements below regarding the actions performed IAW EOP-ECA-0.0 to restore normal power? The CRS will direct the use of ____(1)____ to restore power via the SUT. Prior to restoration of power via the SUT, the selected procedure ____(2)____ direct the crew to ensure the Main Generator Lockout Relays 86P and 86BU are reset. A. (1) OP-603 (2) will NOT B. (1) OP-603 (2) will C. (1) OP-603-3 (2) will NOT D. (1) OP-603-3 (2) will Page 79 of 100 Question:(1 point)80ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant tripped from 100% power when the "B" DC Bus de-energized.

EPP-27, LOSS OF DC BUS "B", has been entered.

The "B" battery and the in-service battery charger are determined to be damaged. Which ONE of the following completes the statements below? Generator Output Breakers OCBs 52/8 AND 52/9 ____(1)____.

Within four hours of the failure:

The plant is at normal operating temperature and pressure

The standby battery charger is aligned to energize DC Bus "B" to nominal voltage, while repair efforts continue IAW Technical Specification 3.8, Electrical Power Systems, OPERABILITY of DC Bus "B" ____(2)____ restored. A. (1) must be tripped locally (2) is B. (1) must be tripped locally (2) is NOT C. (1) will trip on Generator Lockout (2) is D. (1) will trip on Generator Lockout (2) is NOT Page 80 of 100 Question:(1 point)81ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

The "A" Emergency Diesel Generator is paralleled to Bus E-1 for periodic surveillance Subsequently:

The Load Dispatcher notifies the Shift Manager of a low frequency condition on the Grid

The crew entered AOP-026, GRID INSTABILITY, and stabilized power at 98.5%

The following conditions exist 1 minute after the load reduction:

Main Generator Frequency: 59.6 Hz and Stable

GEN Phase "A" and "B" Volts: 22 KV and Stable

GEN Phase "C" amps: 21.9 KA and Stable Which ONE of the following correctly completes the statement below? IAW AOP-026, the Generator output is ____(1)____. Based on plant conditions, the CRS will ____(2)____. (REFERENCES PROVIDED) A. (1) acceptable (2) shutdown the "A" Emergency Diesel Generator B. (1) unacceptable (2) shutdown the "A" Emergency Diesel Generator C. (1) acceptable (2) isolate the Emergency Busses so that the busses are being solely supplied from the Emergency Diesel Generators D. (1) unacceptable (2) isolate the Emergency Busses so that the busses are being solely supplied from the Emergency Diesel Generators Page 81 of 100 Question:(1 point)82ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 17% power with power being raised IAW GP-005, POWER OPERATION

The Control Bank "D" rods continued to withdraw after the RO released the rod drive switch

At 14:40 the crew has completed immediate actions and is implementing FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION - ATWS Which ONE of the following correctly completes the statements below? FRP-S.1 directs alignment of the emergency boration flow path by ____(1)____, then starting the Boric Acid pump aligned for BLEND. After emergency boration is commenced the following conditions exist:

Power is in the Intermediate Range with a negative Startup Rate

Control rods H-8, D-6 and K-14 are stuck out, all other rods indicate on the bottom

The STA is performing a Manual Determination of Shutdown Margin Boron concentration, and is not yet complete Subsequently: 15:00 Control Rod D-6 drops fully into the core 15:15 Chemistry reports the RCS boron concentration is 1975 ppm The EARLIEST time that the crew can stop the emergency boration is ____(2)____ .

MOV-350, BA TO CHARGING PMP SUCT FCV-113A, BA TO BLENDER FCV-113B, BLENDED MU TO CHG SUCT A. (1) opening MOV-350 (2) 15:00 B. (1) opening FCV-113A and FCV-113B (2) 15:00 C. (1) opening MOV-350 (2) 15:15 D. (1) opening FCV-113A and FCV-113B (2) 15:15 Page 82 of 100 Question:(1 point)83ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant at 25% power

The crew enters AOP-012, PARTIAL LOSS OF CONDENSER VACUUM OR CIRCULATING WATER PUMP TRIP, due to a trip of the "A" Circulating Water Pump

Condenser backpressure is approaching the Restricted Region of the Condenser Backpressure Limit Curve Which ONE of the following correctly completes the statements below? IAW AOP-012, it ____(1)____ expected that an AO will be dispatched to complete Attachment 1, Local Actions, during the mitigation of this event. IAW AOP-012, the CRS ____(2)____. A. (1) is (2) will direct a reactor trip and go to EOP-E-0, REACTOR TRIP OR SAFETY INJECTION B. (1) is (2) will direct a turbine trip and goto AOP-007, TURBINE TRIP BELOW P-8 C. (1) is not (2) will direct a turbine trip and go to AOP-007, TURBINE TRIP BELOW P-8 D. (1) is not (2) will direct a reactor trip and go to EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 83 of 100 Question:(1 point)84ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

Core Alterations are on-going in accordance with GP-010, REFUELING

R-2, CV Low Range, alarms (HIGH LED is LIT) Which ONE of the following correctly completes the statement below? To determine the correct R-2 setpoint the operator will use ____(1)____. If R-2 was subsequently determined to be inoperable, Core Alterations ____(2)____. A. (1) Section 3.1, Monitor Alarm Setpoint Determination, of the Offsite Dose Calculation Manual (ODCM) (2) must be suspended immediately B. (1) the Setpoint Change and Log Record of OMM-014, Radiation Monitor Setpoints (2) must be suspended immediately C. (1) the Setpoint Change and Log Record of OMM-014, Radiation Monitor Setpoints (2) may continue, provided that continuous HP Technician coverage and a Portable Area Radiation Monitor are provided D. (1) Section 3.1, Monitor Alarm Setpoint Determination, of the Offsite Dose Calculation Manual (ODCM) (2) may continue, provided that continuous HP Technician coverage and a Portable Area Radiation Monitor are provided Page 84 of 100 Question:(1 point)85ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A LOCA has occurred and NO ECCS Pumps are operating

The crew is implementing FRP-C.2, RESPONSE TO DEGRADED CORE COOLING

While depressurizing all intact S/G's they receive a RED condition on CSF-4, Integrity

RCS pressure is 200 psig Which ONE of the following identifies the required implementation of procedures for this event?

FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK A. Remain in FRP-C.2 until completed, THEN transition to FRP-P.1 B. Transition to FRP-P.1 and perform until completed, THEN transition to FRP-C.2 C. Transition to FRP-P.1 and when it is determined that RCS Integrity does not exist at Step 2, return to FRP-C.2 D. Transition to FRP-P.1 and initiate a soak, THEN perform FRP-C.2 actions that do not cooldown or raise RCS pressure until the soak is complete Page 85 of 100 Question:(1 point)86ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 25% power

A plant shutdown is in progress

The following timeline of events occur: 0800 Pressurizer Level Transmitter LT-460 starts to fluctuate rapidly characterized by abrupt spiking in the high and low direction 0800 A channel check indicates that all other Pressurizer level indications indicate on program and stable 0800 ITS LCO 3.3.1, REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION, action statement for LT-460, PZR level, was entered 0802 The lowest spike on the LT-460 indication reaches 13% 0804 The highest spike on the LT-460 indication reaches 92% 0810 The crew completes removing the instrument from service IAW OWP-030, PRESSURIZER LEVEL TRANSMITTERS (PLT) 0830 Plant down-power is initiated 1000 Reactor Power is stabilized at 8% and REACTOR TRIP BLOCK P-7 status light is ILLUMINATED Which ONE of the following correctly completes the statements below? The EARLIEST time that a single Reactor Protection Bistable will illuminate due to the erratic behavior of LT-460 is ____(1)____.

At 1000, IAW ITS LCO 3.3.1, the action statement for LT-460, PZR level ____(2)____ applicable. A. (1) 0802 (2) is NOT B. (1) 0802 (2) is C. (1) 0804 (2) is D. (1) 0804 (2) is NOT Page 86 of 100 Question:(1 point)87ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following initial plant conditions:

The plant was at 100% power when a reactor trip and safety injection occurred

R-31C, STEAM LINE RADIATION MONITOR, is in alarm and rising

The crew is implementing EOP-E-3,STEAM GENERATOR TUBE RUPTURE with the following conditions:

ALL MSIVs are closed

Containment pressure 0.8 psig

RWST level is 50% and lowering due to a leak in the RWST

S/G Parameters: Pressure NR Level A 960 psig and lowering slowly 22% and rising B 960 psig and lowering slowly 7% and rising C 450 psig and lowering rapidly 7% and lowering Which ONE (1) of the following correctly completes the statements below? IAW EOP-E-3 the crew will continue to feed ____(1)____ . When the CRS is transitioning from EOP-E-3, a transition to EOP-ECA-3.1 ____(2)____ required PRIOR to entering EOP-ECA-3.2. EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EOP-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT: SUBCOOLED RECOVERY DESIRED EOP-ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT: SATURATED RECOVERY DESIRED A. (1) "A" AND "B" Steam Generators ONLY (2) is B. (1) ALL Steam Generators (2) is C. (1) "A" AND "B" Steam Generators ONLY (2) is NOT D. (1) ALL Steam Generators (2) is NOT Page 87 of 100 Question:(1 point)88ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power

The crew has just completed swapping Service Water Booster Pumps from "A" to "B" IAW OP-903, SERVICE WATER SYSTEM

The following data was obtained after the pump swap:

HVH FI-1698A: 830 gpm

HVH FI-1698B: 810 gpm

HVH FI-1698C: 745 gpm

HVH FI-1689D: 805 gpm Which ONE of the following correctly completes the statements below? Entry into Technical Specification LCO 3.6.6, Containment Spray and Cooling Systems ____(1)____ required. OP-903 states that the electrical analysis for the Service Water Booster Pump motors may be exceeded if total HVH Unit Service Water Flow exceeds ____(2)____. A. (1) is NOT (2) 4000 gpm B. (1) is NOT (2) 4220 gpm C. (1) is (2) 4220 gpm D. (1) is (2) 4000 gpm Page 88 of 100 Question:(1 point)89ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A plant cooldown is in progress

RCS temperature is 380°F * "B" Instrument Air Compressor is in AUTO with the "B" Instrument Air Dryer in service * "D" Instrument Air Compressor is operating * "A" Instrument Air Compressor and "A" Instrument Air Dryer are out of service Subsequently:

The "D" Instrument Air Compressor trips, followed by the "B" Instrument Air Dryer clogging

The crew has entered AOP-017, LOSS OF INSTRUMENT AIR

RCS temperature is slowly rising

IA header pressure is 40 psig and rising slowly Which ONE of the following correctly completes the statements below? Based upon current conditions, FCV-1740, Air Dryer Hi DP Flow Control valve ____(1)____ be open. IAW AOP-017, the CRS will direct use of ____(2)____ as the preferred method to control RCS temperature. Attachment 2, Nitrogen Alignment to Steam Line PORVs Attachment 3, Manual Steam Dump of S/Gs A. (1) will (2) Attachment 2 B. (1) will NOT (2) Attachment 2 C. (1) will (2) Attachment 3 D. (1) will NOT (2) Attachment 3 Page 89 of 100 Question:(1 point)90ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions:

The plant is operating at 100% power Subsequently:

A Large Break LOCA and loss of offsite power has occurred

The "A" EDG has failed to start

HVH-3, CV RECIRC FAN C, failed to AUTO start on the SI actuation

SI-880D, CV SPRAY PUMP "B" DISCHARGE, failed to automatically OPEN

Containment pressure is 13 psig and rising The Shift Manager is evaluating whether or not the EAL Threshold "Containment pressure > 10 psig with < one full train of depressurizing equipment," is met.

Which ONE of the following assesses whether or not one full train of depressurizing equipment is operating, and if not, identifies the MINIMUM action that must be taken from the Control Room to ensure that one full train is running? A. One full train of depressurization equipment is operating. B. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started. C. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started OR SI-880D must be OPENED. D. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started AND SI-880D must be OPENED. Page 90 of 100 Question:(1 point)91ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 100% when Control Rod H-12 dropped

The crew lowered reactor power to 68% IAW AOP-001

During this load reduction AFD stabilized at -19 Which ONE of the following correctly completes the statements below? NI-41 and NI-43 will indicate ____(1)____ than NI-42 and NI-44 due to the Rod H-12 drop.

IAW AOP-001, the CRS ____(2)____ required to use Attachment 1 to reduce power to less than or equal to 50% within 30 minutes. AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM AOP-001, ATTACHMENT 1, TURBINE LOAD ADJUSTMENT (REFERENCE PROVIDED)A. (1) higher (2) is B. (1) lower (2) is NOT C. (1) lower (2) is D. (1) higher (2) is NOT Page 91 of 100 Question:(1 point)92ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

Monitor Tank "A" is being prepared for release

Tank pH was sampled and found to be too low Which ONE of the following correctly completes the statements below? IAW OP-705, WASTE LIQUID RELEASE AND RECIRCULATION Monitor Tank "A" is recirculated for a MINIMUM period of time to ensure ____(1)____. IAW EMP-023, LIQUID WASTE RELEASE AND SAMPLING, pH must be adjusted to a MINIMUM of ____(2)____ before the tank is released. A. (1) representative samples are obtained (2) > 5.0 B. (1) representative samples are obtained (2) > 6.0 C. (1) radioactive hot spots do not occur during the release (2) > 5.0 D. (1) radioactive hot spots do not occur during the release (2) > 6.0 Page 92 of 100 Question:(1 point)93ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below?

The TRM limitation on the quantity of radioactivity permitted in ____(1)____ Waste Gas Decay Tank(s) is < 1.9 X 104 Curies noble gas. The bases for TRM 3.21 is concerned with exposure to ____(2)____. A. (1) each (2) personnel in the Control Room B. (1) ALL (2) personnel in the Control Room C. (1) each (2) members of the public at the site boundary D. (1) ALL (2) members of the public at the site boundary Page 93 of 100 Question:(1 point)94ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 35% power when a valid alarm on R-19 occurred

The crew has just entered AOP-035, S/G TUBE LEAK

Chemistry is sampling S/G's to determine primary to secondary leakage rate Which ONE of the following correctly completes the statements below? IAW AOP-035 the crew will use ____(1)____ as a reliable diverse indication to confirm the S/G tube leak.

Subsequently, Chemistry reports that the "B" S/G tube leakage rate is 0.071 gpm IAW AOP-035, the CRS is required to initiate a plant shutdown and place the unit in MODE 3 within ____(2)____. R-15, CONDENSER AIR EJECTOR GAS R-19, A, B, C STEAM GENERATOR BLOWDOWN R-24, A, B, C, MAIN STEAM LINE N-16 A. (1) R-15 (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months B. (1) R-15 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. (1) R-24 (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. (1) R-24 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Page 94 of 100 Question:(1 point)95ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power.

The crew has tested SW-PMP-A, "SERVICE WATER PUMP A" on the previous shift per OST-302-1, SERVICE WATER PUMPS A & B INSERVICE TEST" and recorded elevated vibration level readings that are in the REQUIRED ACTION range.

Maintenance now has a plan to repair the pump. Subsequently, the following sequence of events occur:

SW-PMP-A is shutdown, placed under clearance, and repairs completed.

SW-PMP-A is re-energized and realigned in preparation for retesting.

SW-PMP-A is retested IAW OST-302-1 and vibrations are now found in the ALERT range. Based on the above information, Which ONE of the following correctly completes the statements below? IAW OST-302-1, SW-PMP-A is required to be declared INOPERABLE when ____(1)____. Based on the retest of SW-PMP-A, the pump is ____(2)____. A. (1) the pump is placed under clearance (2) INOPERABLE B. (1) the pump is placed under clearance (2) OPERABLE C. (1) when OST 302-1 was completed on the previous shift (2) INOPERABLE D. (1) when OST 302-1 was completed on the previous shift (2) OPERABLE Page 95 of 100 Question:(1 point)96ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power Subsequently, the following timeline of events occurs: 0200 EDG "A" is declared inoperable due to wrong oil being added during maintenance 0400 EDG "B" is declared inoperable due to mechanical issues 0400 The crew enters Technical Specification LCO 3.0.3 0500 A downpower is initiated 0900 Mode 3 is entered Which ONE of the following correctly completes the statements below? IAW Technical Specifications LCO 3.8.1, the operator must verify the correct breaker alignment and indicated power availability for the offsite circuit (offsite power checks) no later than ____(1)____. Based on this, the LATEST time that the plant must be placed in Mode 4 is ____(2)____. A. (1) 0300 (2) 1500 B. (1) 0300 (2) 1700 C. (1) 0500 (2) 1500 D. (1) 0500 (2) 1700 Page 96 of 100 Question:(1 point)97ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The Inside AO needs to enter a room during EOP implementation

The TSC and OSC are NOT activated

General dose rate levels in the room range from 25-45 mr/hr

The survey map shows the following on contact readings:

Point 1 is 100 mr/hr at 30 cm

Point 2 is 500 mr/hr at 30 cm

Point 3 is 1100 mr/hr at 30 cm Which ONE of the following correctly completes the statements below? Based on the plant indications, the radiological posting required is ____(1)____. Under the stated plant conditions, the Shift Manager ____(2)____ grant access to this area. A. (1) Very High Radiation Area (2) may B. (1) Very High Radiation Area (2) may NOT C. (1) Locked High Radiation Area (2) may NOT D. (1) Locked High Radiation Area (2) may Page 97 of 100 Question:(1 point)98ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A General Emergency has been declared

The Dose Rate in Pipe Alley is 105 R/hr

A 10-minute evolution in Pipe Alley is necessary to conduct repair and re-entry activities

Two two-person teams have been briefed and are prepared to enter Pipe Alley to complete the task Which ONE of the following correctly completes the statement below?

IAW EPOSC-04, EMERGENCY WORK CONTROL, the ____(1)____ can authorize performance of the evolution in Pipe Alley.

The MINIMUM number of two-person teams needed to be dispatched to complete the 10-minute evolution in Pipe Alley without exceeding any emergency exposure limits is ____(2)____. A. (1) Site Emergency Coordinator (2) one B. (1) Site Emergency Coordinator (2) two C. (1) Radiological Control Director (2) one D. (1) Radiological Control Director (2) two Page 98 of 100 Question:(1 point)99ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power.

At 0100, LCO 3.4.13, RCS OPERATIONAL LEAKAGE, was entered due to an 15 gpm leak from a crack on the spray line penetration weld at the PZR

The crew commenced a shutdown at 0200

The plant reached MODE 3 at 0545 when the OATC manually tripped the Rx as part of the plant shutdown per GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN. Which ONE of the following identifies the LATEST time at which the NRC must be notified? (REFERENCES PROVIDED) A. 0130 B. 0215 C. 0315 D. 0600 Page 99 of 100 Question:(1 point)100ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power when the following annunciators alarm:

APP-001-C5, RCP Standpipe HI/LO LVL

APP-001-E2, RCP #1 SEAL LEAKOFF LO FLOW

The crew has entered AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS Which ONE of the following correctly completes the statements below? APP-001-C5, RCP Standpipe HI/LO LVL is due to ____(1)____. Subsequently:

Indicated "B" RCP #1 seal leakoff flow: 0.6 gpm

The BOP performed Attachment 2 of AOP-018, RCP #2 SEAL LEAK RATE CALCULATION,and calculates Total "B" RCP #1 seal leakoff flow at 6.5 gpm * "B" RCP Bearing Temperatures are 130°F and stable * "B" RCP #1 Seal Leakoff Temperature is 125°F and stable IAW AOP-018 the CRS will direct the crew to continue to monitor RCP parameters and place the plant in MODE 3 within ____(2)____ using GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN. A. (1) high level (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months B. (1) high level (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. (1) low level (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. (1) low level (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Page 100 of 100 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

ATTACHMENT 10.1 Page 12 of 13 FMP-001 Rev. 31 Page 23 of 25 HBRSEP UNIT NO. 2, CYCLE 30 CORE OPERATING LIMITS REPORT REVISION 0 NOTE: For power levels above 90%, power operation is allowed within the target bands (+3% and +5%).

ATTACHMENT 11.1 Page 1 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 16 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 10 CFR 50.72 states that immediate reports shall be made to the NRC Operations Center of these Emergency Events via the NRC Emergency Telecommunications System (ETS) as specified in the Emergency Plan. 10 CFR 50.72 additionally identifies Non-Emergency Events which are to be reported within one-hour, four-hours, or eight hours to the NRC. ETS Telephones, which are identified, are located in the Control Room, the TSC, and the EOF. In the event that the ETS is not available, 10 CFR 50.72(a)(2) permits the use of commercial telephone. EVENT KEY WORDS REQUIREMENT EXAMPLES NOTE: 10 CFR 50.72 recognizes the Emergency Plan and its four Emergency Classes of Unusual Event, Alert, Site Area Emergency and General Emergency. EMERGENCIES 10 CFR 50.72(a)(i) 10 CFR 30.32(i)(3)(viii) 10 CFR 40.31(i)(3)(viii) 10 CFR 72.75(a) Emergency Unusual Event Alert Site Area Emergency General Emergency ISFSI HBRSEP shall notify the NRC of the declaration of any of the Emergency Classes specified in the Emergency Plan. (See EPNOT-01) Declaration of an Unusual Event, Alert, Site Area Emergency, or General Emergency. Discovery of an event that should have resulted in an Emergency Classification, but no emergency was declared. Discovery that a declared emergency exceeded the Emergency Action Levels for a higher emergency declaration, but the higher classification was not declared. ERDS ACTIVATION 10 CFR 50.72(a)(4) ERDS Emergency HBRSEP shall activate the ERDS as soon as possible but not later than one hour after declaring an Alert, Site Area Emergency, or General Emergency. An Alert, Site Area Emergency, or General Emergency is declared. DEVIATION FROM TS (10 CFR 50.54(X)) 10 CFR 50.72(b)(1) Deviation Departure License Condition Any deviation from the TS authorized pursuant to 10 CFR 50.54(x). Intentional deviation from an approved plant procedure in order to preserve plant safety 10 CFR 50.54(x).

ATTACHMENT 11.1 Page 2 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 17 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC HBRSEP shall immediately notify the NRC Operations Center via ETS as soon as practical and in all cases within one hour of the occurrence of any of the following: EVENT KEY WORDS REQUIREMENT EXAMPLES SAFETY LIMIT, LIMITING SAFETY SYSTEM SETTING EXCEEDED 10 CFR 50.36(c)(1)(i)(A) UFSAR Section 17.3A, Paragraph 3.1.a Safety Limit Limiting Safety System Setting If any safety limit is exceeded, shut down the reactor. HBRSEP shall notify the NRC [within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months via ETS per 10 CFR 50.72(a)(1), See Emergency Plan Procedures]. Operation must not be resumed until authorized by the NRC. NRC Region II must also be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and the Vice President - Robinson Nuclear Plant within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months The limits of TS Figure 2.1.1-1 are exceeded. SAFETY SYSTEM DOES NOT FUNCTION AS REQUIRED 10 CFR 50.36(c)(1)(ii)(A) ESF RPS Limiting Safety System Setting HBRSEP shall notify the NRC if the automatic safety system [to correct an abnormal situation before a safety limit is exceeded] has been determined not to function as required. A failure mechanism is discovered that indicates that the RPS will not function to trip the reactor under certain required conditions.

ATTACHMENT 11.1 Page 3 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 18 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SECURITY SAFEGUARDS EVENTS HBRSEP shall notify the NRC Operations Center via the ETS within one hour* after discovery of the safeguards events described as follows (10 CFR 73.71(b)(1)): EVENT KEY WORDS REQUIREMENT EXAMPLES THEFT/UNLAWFUL DIVERSION OF SNM OR SPENT FUEL SHIPMENT 10 CFR 73.71(a)(1) SNM Spent Fuel Security Safeguards Any discovery of the loss of any shipment of SNM or spent fuel, and within one hour after recovery of or accounting for such lost shipment Shipment Emergency Event THEFT/UNLAWFUL DIVERSION OF SNM 10 CFR 73.71(b)(1) 10 CFR 73, Appendix G, I(a)(1) Theft of SNM Diversion Security Safeguards Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause: (1) A theft or unlawful diversion of SNM Shipment Emergency Event SABOTAGE OF PLANT EQUIPMENT 10 CFR 73.71(b)(1) 10 CFR 73, Appendix G, I(a)(2) Sabotage Damage to Plant SNM Spent Fuel Security Safeguards [Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause:] (2) Significant physical damage to a power reactor...or its equipment or carrier equipment transporting nuclear fuel or spent nuclear fuel, or to the nuclear fuel or spent fuel a facility or carrier possesses. Shipment Emergency Event Security Event (AD-SY-ALL-0150)

In response to NRC Bulletin 2005-02, RNP committed to make an accelerated call to the NRC within approximately 15 minutes following discovery of an imminent threat or attack against the station. The primary purpose is to allow for the NRC to timely notify other licensees of a potential common threat. The accelerated call should not be allowed to interfere with plant or personnel safety, physical security response, or notification of local law enforcement agencies. The information provided in the accelerated call can be limited to: Site name Emergency Classification - if already determined - do not delay call for the purpose of classifying Nature of the threat - briefly described, if known, including the type of attack (e.g., armed assault by land, water or aircraft) and the attack status (e.g., imminent, in progress, or repelled)

ATTACHMENT 11.1 Page 4 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 19 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SECURITY SAFEGUARDS EVENTS HBRSEP shall notify the NRC Operations Center via the ETS within one hour* after discovery of the safeguards events described as follows (10 CFR 73.71(b)(1)): EVENT KEY WORDS REQUIREMENT EXAMPLES UNAUTHORIZED TAMPERING WITH PLANT EQUIPMENT 10 CFR 73, Appendix G, I(a)(3) Unauthorized Use Tampering Security System Safeguards [Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause:] (3) Interruption of normal operation of HBRSEP through the unauthorized use of or tampering with its machinery, components, or controls including the security system. Security Event (AD-SY-ALL-0150) ENTRY OF UNAUTHORIZED PERSON INTO PROTECTED OR VITAL AREA 10 CFR 73, Appendix G, I(b) Unauthorized Entry Security Safeguards An actual entry of an unauthorized person into a protected area, material access area, controlled access area, vital area, or transport. Security Event (AD-SY-ALL-0150) FAILURE, DEGRADATION, OR DISCOVERED VULNERABILITY OF SAFEGUARD SYSTEM 10 CFR 73, Appendix G, I(c) Degradation Vulnerability Safeguards Unauthorized Undetected Access Security Any failure, degradation, or the discovered vulnerability in a safeguard system that could allow unauthorized or undetected access to a protected area, material access area, controlled access area, vital area or transport for which compensatory measures have not been employed. Procedure AD-SY-ALL-0150 INTRODUCTION OF CONTRABAND INTO VITAL OR PROTECTED AREA 10 CFR 73, Appendix G, I(d) Contraband Unauthorized Security Safeguards The actual or attempted introduction of contraband into a protected area, material process area, vital area, or transport. Contraband applies to items that could be used to commit radiological sabotage as defined in 10 CFR 73.2.

See footnote on the previous page regarding a goal for a 15 minute call to the NRC in regard to an imminent security threat or attack.

ATTACHMENT 11.1 Page 5 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 20 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SOURCE, BYPRODUCT AND SNM HBRSEP shall immediately notify the NRC Operations Center via ETS, when: EVENT KEY WORDS REQUIREMENT EXAMPLES EXTERNAL EXPOSURE FROM BYPRODUCT, SOURCE, OR SNM (5X ANNUAL LIMIT)

10 CFR 20.2202(a)(1) Byproduct Source SNM Exposure Dose Release Occupational Notwithstanding any other requirements for notification, immediately notify the NRC of any event involving byproduct, source, or SNM possessed by HBRSEP that may have caused or threatens to cause any of the following conditions: 1. An individual to receive: (i) A total effective dose equivalent of 25 rems or more; or (ii) An eye dose equivalent of 75 rems or more; or (iii) A shallow dose equivalent to the skin or extremities of 250 rads or more; or 2. The release of radioactive material, inside or outside the restricted area, so that, had an individual been present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the individual could have received an intake five times the occupational annual limit on intake.

ATTACHMENT 11.1 Page 6 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 21 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SOURCE, BYPRODUCT AND SNM HBRSEP shall immediately notify the NRC Operations Center via ETS, when: EVENT KEY WORDS REQUIREMENT EXAMPLES INTERNAL EXPOSURE FROM BYPRODUCT, SOURCE, SNM (>5X OCCUPATIONAL LIMIT) 10 CFR 20.2202(a)(2) Intake Ingestion Release Source Byproduct SNM The release of radioactive material, inside or outside the restricted area, so that, had an individual been present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the individual could have received an intake five times the occupational annual limit on intake. IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - ISFSI HBRSEP shall immediately notify the NRC Operations Center via ETS, when: EVENT KEY WORDS REQUIREMENT EXAMPLES ISFSI - ACCIDENTAL CRITICALITY OR LOSS OF SNM 10 CFR 72.74 ISFSI Criticality SNM Loss The licensee shall notify the NRC Operations Center via ETS within one hour of discovery of accidental criticality or any loss of SNM. Unusually high radiation readings discovered in the vicinity of the ISFSI that could indicate possibility of a criticality event IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SNM SHIPMENTS HBRSEP shall immediately notify the NRC Operations Center via ETS, when: EVENT KEY WORDS REQUIREMENT EXAMPLES LOST OR UNACCOUNTED SHIPMENT OF SNM 10 CFR 70.52(b) 10 CFR 73.71(a)(1) Shipment Loss SNM Spent Fuel Diversion Safeguards Security HBRSEP shall notify the NRC Operations Center via the ETS within one hour after discovery of any loss of any shipment of SNM or spent fuel or any incident in which an attempt has been made, or is believed to have been made, to commit a theft or unlawful diversion of SNM. Shipment Emergency Event Security Event (AD-SY-ALL-0150) LOST OR UNACCOUNTED SHIPMENT OF SNM - RECOVERY 10 CFR 73.71(a)(1) Recovery Accounting Shipment SNM Security Safeguards HBRSEP shall notify the NRC Operations Center via the ETS within one hour after recovery of, or accounting for, any lost shipment of SNM.

ATTACHMENT 11.1 Page 7 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 22 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - FOLLOW-UP With respect to the telephone notifications made under paragraphs (a) and (b) of 10 CFR 50.72 or paragraphs (a), (b), (c), or (d) of 10 CFR 72.75, in addition to making the required initial notification, HBRSEP shall during the course of the event immediately report: EVENT KEY WORDS REQUIREMENT EXAMPLES FOLLOW-UP NOTIFICATION 10 CFR 50.72(c)(1) 10 CFR 72.75(f)(1) Degradation Emergency Class Change Update Termination ISFSI (i) any further degradation in the level of safety of the plant or ISFSI or other worsening conditions, including those that require the declaration of any of the Emergency Classes, if such a declaration has not been previously made, or (ii) any change from one Emergency Class to another, or (iii) a termination of the Emergency Class. Refer to EPNOT-01 FOLLOW-UP NOTIFICATION 10 CFR 50.72(c)(2) 10 CFR 72.75(f)(2) Result Evaluation Effectiveness Unknown ISFSI (i) the results of ensuing evaluations or assessments of plant or ISFSI conditions, (ii) the effectiveness of response or protective measures taken, and (iii) information related to plant or ISFSI behavior that is not understood. FOLLOW-UP NOTIFICATION 10 CFR 50.72(c)(3) 10 CFR 50.72.75(f)(3) Open Continuous Communication ISFSI Maintain an open, continuous communication channel with the NRC Operations Center upon request by the NRC. Refer to EPNOT-01 ATTACHMENT 11.1 Page 8 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 23 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS - NRC REGION II OFFICE HBRSEP shall immediately notify the final delivery carrier and, by telephone and telegram, mailgram, or facsimile, the NRC Region II Office when: EVENT KEY WORDS REQUIREMENT EXAMPLES THEFT/UNLAWFUL DIVERSION OF TRITIUM 10 CFR 30.55(c) Incident Theft Tritium Attempt Security Safeguards Any incident in which an attempt has been made or is believed to have been made to commit a theft of more than 10 curies of tritium (outside of spent fuel) at any one time or more than 100 curies of tritium in one calendar year 10 Curies of tritium discovered missing from the Chemistry Laboratory, and reason exists to suspect that the tritium was stolen THEFT/UNLAWFUL DIVERSION OF SOURCE MATERIAL 10 CFR 40.64(c) Incident Attempt Theft Diversion Source Security Safeguards Any incident in which an attempt has been made or is believed to have been made to commit a theft or unlawful diversion of more than 15 pounds of Source Material at any one time or 150 pounds of Source Material in any one calendar year A source assembly is discovered missing from a new fuel shipment. SHIPPING PACKAGE RADIOACTIVELY CONTAMINATED 10 CFR 20.1906(d)(1) Contamination Shipment Removable radioactive surface contamination exceeds the limits of 10 CFR 71.87 New or Spent Fuel Shipment Cask arrives with surface contamination in excess of limits. SHIPPING PACKAGE EXCEEDING EXTERNAL DOSE RATE LIMITS 10 CFR 20.1906(d)(2) Radiation Dose Rate Shipment External radiation levels exceeds of the limits of 10 CFR 71.47 New or Spent Fuel Shipment Cask arrives with external radiation levels in excess of limits.

ATTACHMENT 11.1 Page 9 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 24 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - FFD The NRC Region II Administrator must be notified immediately by telephone of the following: EVENT KEY WORDS REQUIREMENT EXAMPLES NRC EMPLOYEE NOT FIT FOR DUTY 10 CFR 26.77(c) Alcohol Influence Substance NRC employee FFD Fitness for Duty If HBRSEP has a reasonable belief that an NRC employee or NRC contractor may be under the influence of any substance, or is otherwise unfit for duty, the licensee or other entity may not deny access but shall escort the individual. In any such instance, the licensee or other entity shall immediately notify the Region II Administrator by telephone, followed by written notification (e.g., e-mail or fax) to document the oral notification. If the Region II Administrator cannot be reached, the licensee or other entity shall notify the NRC Operations Center. IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - IAEA The NRC Director, NRR or Director, NMSS must be notified immediately by telephone of the following: SURPRISE VISIT OF IAEA OFFICIAL 10 CFR 75.8(c) IAEA International Atomic Energy Agency Credential HBRSEP shall immediately communicate by telephone, within one hour with respect to the credentials of any person who claims to be an IAEA representative and shall accept written or electronic confirmation of the credentials from the NRC. If the IAEA representative's credentials have not been confirmed by the NRC, the licensee shall not admit the person until the NRC has confirmed the person's credentials. The licensee, shall notify the Commission promptly, by telephone, whenever an IAEA representative arrives at a facility or location without advance notification.

ATTACHMENT 11.2 Page 1 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 25 of 66 FOUR HOUR NOTIFICATIONS TO THE NRC If not reported under paragraphs (a) or (b)(1) of 10 CFR 50.72, HBRSEP shall notify the NRC Operations Center via ETS as soon as practical and in all cases, within four hours of the occurrence of any of the following: EVENT KEY WORDS REQUIREMENT EXAMPLES SHUTDOWN REQUIRED BY TS 10 CFR 50.72(b)(2)(i) Shutdown TS Shutdown Power Reduction The initiation of any shutdown required by the TS. Reactor is in MODEs 1 or 2 and the Control Room takes action to reduce power (i.e., negative reactivity insertion) in order to comply with a Required Action to be in MODE 3 within a Completion Time. Reduction in power for some other purpose than compliance with the shutdown requirement is not reportable. MODE changes required by TS when reactor is in MODEs 3, 4, or other non-power conditions, are not reportable. If allowed outage time plus required shutdown time to MODE 3 is less than the expected restoration time of the LCO and power is reduced in anticipation of the required shutdown, the shutdown is reportable. ECCS DISCHARGE INTO RCS 10 CFR 50.72(b)(2)(iv)(A) ECCS Actuation Safety Injection Any event that results or should have resulted in emergency core cooling system (ECCS) discharge into the reactor coolant system as a result of a valid signal except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. Manual or automatic Safety Injection System actuation in response to a valid signal that resulted in or should have resulted in discharge into the reactor coolant system. RPS INITIATION (MANUAL/AUTOMATIC) DURING OPERATION 10 CFR 50.72(b)(2)(iv)(B) RPS Actuation Reactor Protection System RPS Reactor Trip Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. Manual or automatic reactor trip from critical through RTP of 100%. Trips which occur as part of planned evolutions in accordance with procedures are not reportable.

ATTACHMENT 11.2 Page 2 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 26 of 66 FOUR HOUR NOTIFICATIONS TO THE NRC If not reported under paragraphs (a) or (b)(1) of 10 CFR 50.72, HBRSEP shall notify the NRC Operations Center via ETS as soon as practical and in all cases, within four hours of the occurrence of any of the following: EVENT KEY WORDS REQUIREMENT EXAMPLES PRESS RELEASES AND GOVERNMENT NOTIFICATIONS

10 CFR 50.72(b)(2)(xi) 10 CFR 72.75(b)(2) News Release Press Radio Television Fatality Environment Public Health and Safety Release ISFSI Any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials. Licensees are required to notify the NRC within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of whichever of the following occurs first: - A plan to report to either the press or another government agency is approved by an individual authorized to make the final decision, or - A report has actually been made to the press or another government agency. Any News release concerning - A fatality, - Inadvertent release of radioactively contaminated materials to public areas - unusual or abnormal releases of radioactive effluents (See Attachment 11.14), or - Information associated with an Emergency Event except when the ERO is activated (EPNOT-01). Notification to other government agencies concerning: - A fatality on site, - Health and safety of the public or site personnel, - Inadvertent release of radioactively contaminated materials to public areas, - Discovered endangered species kill. - Notifications to the National Response Center (EPA) related to Lake Robinson ATTACHMENT 11.2 Page 3 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 27 of 66 FOUR HOUR NOTIFICATIONS TO THE NRC HBRSEP shall notify the NRC Operations Center via ETS as soon as possible but not later than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the discovery of any of the following events or conditions involving sources or spent fuel. EVENT KEY WORDS REQUIREMENT EXAMPLES LOSS OR THEFT OF LICENSED MATERIAL (>1000X 10 CFR 20 LIMITS)

10 CFR 20.2201 Loss Theft Missing Licensed Radioactive Material Recovery Immediately notify the NRC, after its occurrence becomes known, any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in [10 CFR 20] Appendix C under such circumstances that it appears to HBRSEP that an exposure could result to persons in unrestricted areas. Follow-up written report required within subsequent 30 days. Note - If the lost, stolen, or missing source exceeds a "Quantity of Concern" as specified in HPP-018, then the NRC desires to be notified within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of any subsequent recovery of the source. A radiography source is discovered missing. The source is licensed to the radiography contractor. If the contractor does not make the required notification, HBRSEP should notify the NRC Operations Center via ETS. ISFSI - DEPARTURE FROM LICENSE CONDITION 10 CFR 72.75(b)(1) ISFSI Emergency Departure Deviation Health and Safety License Condition An action taken in an emergency that departs from a condition or a technical specification contained in a license or certificate of compliance issued under 10 CFR 72 when the action is immediately needed to protect the public health and safety and no action consistent with license conditions or technical specifications that can provide adequate or equivalent protection is immediately apparent. Action taken in an emergency that departs from procedure that is deemed necessary to prevent releases or radiation doses to the public in excess of 10 CFR 20 limits (See AD-HU-ALL-0004).

Examination KEY for:ILC15 RNP SRO NRC ExaminQuestionNumberAnswer1B2D3C4C5B6B7B8B9D10C11A12D13D14B15A16A17B18B19C20A21B22D23D24D25CPrinted 2/11/2016 2:50:36 PMPage 1 of 4 Examination KEY for:ILC15 RNP SRO NRC ExaminQuestionNumberAnswer26A27D28C29B30C31B32B33C34B35B36A37D38D39C40C41B42C43C44C45C46C47B48A49A50DPrinted 2/11/2016 2:50:37 PMPage 2 of 4 Examination KEY for:ILC15 RNP SRO NRC ExaminQuestionNumberAnswer51D52C53D54D55C56C57B58B59C60D61A62B63A64B65C66C67D68B69A70A71B72B73A74D75BPrinted 2/11/2016 2:50:37 PMPage 3 of 4 Examination KEY for:ILC15 RNP SRO NRC ExaminQuestionNumberAnswer76A77C78D79B80B81A82C83D84C85A86D87A88C89A90D91C92B93C94A95D96B97D98B99B100BPrinted 2/11/2016 2:50:37 PMPage 4 of 4 Question:(1 point)1ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 being reached Which 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, ONLY B. (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 100 Question:(1 point)2ILC15 RNP SRO 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 100 Question:(1 point)3ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power * "A" CV Spray pump is out of service for maintenance Subsequently:

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 OR SECONDARY 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 °F Which 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 100 Question:(1 point)4ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

With the plant at 100% power a Large Break LOCA occurs Which 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 100 Question:(1 point)5ILC15 RNP SRO 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 100 Question:(1 point)6ILC15 RNP SRO 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 100 Question:(1 point)7ILC15 RNP SRO 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 100 Question:(1 point)8ILC15 RNP SRO 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 100 Question:(1 point)9ILC15 RNP SRO 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 100 Question:(1 point)10ILC15 RNP SRO 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 100 Question:(1 point)11ILC15 RNP SRO 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 100 Question:(1 point)12ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The crew is implementing EOP-ECA-0.0, LOSS OF ALL AC POWER, mitigating an Extended 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 100 Question:(1 point)13ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 LOCA Which 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 100 Question:(1 point)14ILC15 RNP SRO 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 100 Question:(1 point)15ILC15 RNP SRO 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 100 Question:(1 point)16ILC15 RNP SRO 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 100 Question:(1 point)17ILC15 RNP SRO 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 100 Question:(1 point)18ILC15 RNP SRO 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 100 Question:(1 point)19ILC15 RNP SRO 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 100 Question:(1 point)20ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 AUTO Which 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 100 Question:(1 point)21ILC15 RNP SRO 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 100 Question:(1 point)22ILC15 RNP SRO 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 100 Question:(1 point)23ILC15 RNP SRO 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 100 Question:(1 point)24ILC15 RNP SRO 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 100 Question 24 Given Conditions Page 24a Question:(1 point)25ILC15 RNP SRO 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 100 Question:(1 point)26ILC15 RNP SRO 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 100 Question:(1 point)27ILC15 RNP SRO 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 100 Question:(1 point)28ILC15 RNP SRO 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 100 Question:(1 point)29ILC15 RNP SRO 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 100 Question:(1 point)30ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 bus Which 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 100 Question:(1 point)31ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 service Subsequently, 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 CLOSED The 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 100 Question:(1 point)32ILC15 RNP SRO 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 100 Question:(1 point)33ILC15 RNP SRO 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 100 Question:(1 point)34ILC15 RNP SRO 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 100 Question:(1 point)35ILC15 RNP SRO 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 100 Question:(1 point)36ILC15 RNP SRO 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 100 Question:(1 point)37ILC15 RNP SRO 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 100 Question:(1 point)38ILC15 RNP SRO 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 100 Question:(1 point)39ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 100% when a SI occurred Which 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 100 Question:(1 point)40ILC15 RNP SRO 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 100 Question:(1 point)41ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

A realignment has just occurred and the operator observes the following Service Water valve 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 100 Question:(1 point)42ILC15 RNP SRO 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 100 Question:(1 point)43ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 100 Question:(1 point)44ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occurs Which 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 100 Question:(1 point)45ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 LOW Which 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 100 Question:(1 point)46ILC15 RNP SRO 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 100 Question:(1 point)47ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power

Breaker 52/20, UNIT AUX TO 4KV BUS 4 BKR, trips on fault Which 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 100 Question:(1 point)48ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is in Mode 3

The "B" Battery Charger is in service

The "B-1" Battery Charger is in standby Subsequently:

MCC-6 is de-energized

APP-036-D2, BATT CHARGER B/B-1 TROUBLE, alarms

Two minutes later MCC-6 is re-energized Which 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 100 Question:(1 point)49ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given 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 KW Subsequently:

The Normal Supply Breaker to E-1, 52/18B, opens

EDG "A" Output Breaker 52/17B, opens Which 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 100 Question:(1 point)50ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which 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 100 Question:(1 point)51ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The reactor is at 100%

The crew is performing a containment vacuum relief IAW OP-921, CONTAINMENT AIR HANDLING

R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarms V12-12, 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 100 Question:(1 point)52ILC15 RNP SRO 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 100 Question:(1 point)53ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which 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 100 Question:(1 point)54ILC15 RNP SRO 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 100 Question:(1 point)55ILC15 RNP SRO 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 100 Question:(1 point)56ILC15 RNP SRO 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 100 Question:(1 point)57ILC15 RNP SRO 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 100 Question:(1 point)58ILC15 RNP SRO 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 100 Question:(1 point)59ILC15 RNP SRO 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 100 Question:(1 point)60ILC15 RNP SRO 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 100 Question:(1 point)61ILC15 RNP SRO 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 100 Question:(1 point)62ILC15 RNP SRO 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 100 Question:(1 point)63ILC15 RNP SRO 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 100 Question:(1 point)64ILC15 RNP SRO 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 100 Question:(1 point)65ILC15 RNP SRO 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 100 Question:(1 point)66ILC15 RNP SRO 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 100 Question:(1 point)67ILC15 RNP SRO 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 100 Question:(1 point)68ILC15 RNP SRO 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 100 Question:(1 point)69ILC15 RNP SRO 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 100 Question:(1 point)70ILC15 RNP SRO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 70 of 100 Question:(1 point)71ILC15 RNP SRO 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 100 Question:(1 point)72ILC15 RNP SRO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Page 72 of 100 Question:(1 point)73ILC15 RNP SRO 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 100 Question:(1 point)74ILC15 RNP SRO 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 100 Question:(1 point)75ILC15 RNP SRO 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 100 Question:(1 point)76ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

With the plant at 100% power a Feedwater Isolation Signal occurs

Safety Injection actuates

The crew is implementing FRP-S.1, RESPONSE TO NUCLEAR GENERATION-ATWS. Which ONE of the following correctly completes the statement below? IAW the FRP-S.1 basis document, the Turbine Stop Valves must be CLOSED within a MAXIMUM of ____(1)____ from event initiation.

This action ____(2)____ taken in order to maintain S/G inventory. A. (1) 30 seconds (2) is B. (1) 30 seconds (2) is NOT C. (1) 60 seconds (2) is D. (1) 60 seconds (2) is NOT Page 76 of 100 Question:(1 point)77ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The crew is in EOP-E-3, STEAM GENERATOR TUBE RUPTURE, has completed tube rupture mitigation in the "C" S/G and is now selecting a recovery procedure

Containment pressure is 4.5 psig due to a previously faulted "B" S/G

A Loss of Off Site Power has occurred

The Shift Manager has indicated that the recovery procedure should minimize radiation release The following indications are observed:

S/G "C" level is 86% and rising

PZR level is 67% and stable Which ONE of the following correctly completes the statement below? Based on the current plant conditions RCS depressurization ____(1)____ required. The CRS will select ____(2)____ as the recovery procedure. (REFERENCES PROVIDED) A. (1) is (2) EOP-ES-3.2, POSTSGTR COOLDOWN USING BLOWDOWN B. (1) is (2) EOP-ES-3.3, POSTSGTR COOLDOWN USING STEAM DUMP C. (1) is NOT (2) EOP-ES-3.2, POSTSGTR COOLDOWN USING BLOWDOWN D. (1) is NOT (2) EOP-ES-3.3, POSTSGTR COOLDOWN USING STEAM DUMP Page 77 of 100 Question:(1 point)78ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 5% power

One PZR PORV is CLOSED, has been isolated and cannot be manually cycled Subsequently:

A transient occurs causing a reactor trip and SI actuation

The crew enters FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

Bleed and Feed criteria has been met

Safety Injection has been manually actuated

The OPERABLE PZR PORV has been OPENED RC567, HEAD VENT RC568, HEAD VENT RC569, PZR VENT RC570, PZR VENT RC571, PRT ISO RC572, CV ATMOS IAW FRP-H.1, which ONE of the following actions, if any, is required to establish an adequate bleed path? A. No action is required, an adequate bleed path exists. B. Open the Reactor Head Vent Valves, RC-571 and RC-572, ONLY. C. Open the Pressurizer Vent Valves, RC-571 and RC-572, ONLY. D. Open the Reactor Head Vent Valves, Pressurizer Vent Valves, RC-571 and RC-572. Page 78 of 100 Question:(1 point)79ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A Station Blackout has occurred from 100% power

The crew is performing actions of ECA-0.0, LOSS OF ALL AC POWER

Immediate actions are complete

Offsite power is available to re-energize the Start-up Transformer (SUT)

APP-009-B5, MAIN TRANSF FAULT TRIP, alarm is ILLUMINATED. Subsequently:

E-1 is restored with EDG "A"

Transmission Maintenance has taken action such that APP-009-B5 is now extinguished. 86P, Generator Lockout Relay, Primary 86BU, Generator Lockout Relay, Backup OP-603, ELECTRICAL DISTRIBUTION OP-603-3, RESETTING HIGH IMPEDANCE FAULTS Which ONE of the following correctly completes the statements below regarding the actions performed IAW EOP-ECA-0.0 to restore normal power? The CRS will direct the use of ____(1)____ to restore power via the SUT. Prior to restoration of power via the SUT, the selected procedure ____(2)____ direct the crew to ensure the Main Generator Lockout Relays 86P and 86BU are reset. A. (1) OP-603 (2) will NOT B. (1) OP-603 (2) will C. (1) OP-603-3 (2) will NOT D. (1) OP-603-3 (2) will Page 79 of 100 Question:(1 point)80ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant tripped from 100% power when the "B" DC Bus de-energized.

EPP-27, LOSS OF DC BUS "B", has been entered.

The "B" battery and the in-service battery charger are determined to be damaged. Which ONE of the following completes the statements below? Generator Output Breakers OCBs 52/8 AND 52/9 ____(1)____.

Within four hours of the failure:

The plant is at normal operating temperature and pressure

The standby battery charger is aligned to energize DC Bus "B" to nominal voltage, while repair efforts continue IAW Technical Specification 3.8, Electrical Power Systems, OPERABILITY of DC Bus "B" ____(2)____ restored. A. (1) must be tripped locally (2) is B. (1) must be tripped locally (2) is NOT C. (1) will trip on Generator Lockout (2) is D. (1) will trip on Generator Lockout (2) is NOT Page 80 of 100 Question:(1 point)81ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power

The "A" Emergency Diesel Generator is paralleled to Bus E-1 for periodic surveillance Subsequently:

The Load Dispatcher notifies the Shift Manager of a low frequency condition on the Grid

The crew entered AOP-026, GRID INSTABILITY, and stabilized power at 98.5%

The following conditions exist 1 minute after the load reduction:

Main Generator Frequency: 59.6 Hz and Stable

GEN Phase "A" and "B" Volts: 22 KV and Stable

GEN Phase "C" amps: 21.9 KA and Stable Which ONE of the following correctly completes the statement below? IAW AOP-026, the Generator output is ____(1)____. Based on plant conditions, the CRS will ____(2)____. (REFERENCES PROVIDED) A. (1) acceptable (2) shutdown the "A" Emergency Diesel Generator B. (1) unacceptable (2) shutdown the "A" Emergency Diesel Generator C. (1) acceptable (2) isolate the Emergency Busses so that the busses are being solely supplied from the Emergency Diesel Generators D. (1) unacceptable (2) isolate the Emergency Busses so that the busses are being solely supplied from the Emergency Diesel Generators Page 81 of 100 Question:(1 point)82ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 17% power with power being raised IAW GP-005, POWER OPERATION

The Control Bank "D" rods continued to withdraw after the RO released the rod drive switch

At 14:40 the crew has completed immediate actions and is implementing FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION - ATWS Which ONE of the following correctly completes the statements below? FRP-S.1 directs alignment of the emergency boration flow path by ____(1)____, then starting the Boric Acid pump aligned for BLEND. After emergency boration is commenced the following conditions exist:

Power is in the Intermediate Range with a negative Startup Rate

Control rods H-8, D-6 and K-14 are stuck out, all other rods indicate on the bottom

The STA is performing a Manual Determination of Shutdown Margin Boron concentration, and is not yet complete Subsequently: 15:00 Control Rod D-6 drops fully into the core 15:15 Chemistry reports the RCS boron concentration is 1975 ppm The EARLIEST time that the crew can stop the emergency boration is ____(2)____ .

MOV-350, BA TO CHARGING PMP SUCT FCV-113A, BA TO BLENDER FCV-113B, BLENDED MU TO CHG SUCT A. (1) opening MOV-350 (2) 15:00 B. (1) opening FCV-113A and FCV-113B (2) 15:00 C. (1) opening MOV-350 (2) 15:15 D. (1) opening FCV-113A and FCV-113B (2) 15:15 Page 82 of 100 Question:(1 point)83ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant at 25% power

The crew enters AOP-012, PARTIAL LOSS OF CONDENSER VACUUM OR CIRCULATING WATER PUMP TRIP, due to a trip of the "A" Circulating Water Pump

Condenser backpressure is approaching the Restricted Region of the Condenser Backpressure Limit Curve Which ONE of the following correctly completes the statements below? IAW AOP-012, it ____(1)____ expected that an AO will be dispatched to complete Attachment 1, Local Actions, during the mitigation of this event. IAW AOP-012, the CRS ____(2)____. A. (1) is (2) will direct a reactor trip and go to EOP-E-0, REACTOR TRIP OR SAFETY INJECTION B. (1) is (2) will direct a turbine trip and goto AOP-007, TURBINE TRIP BELOW P-8 C. (1) is not (2) will direct a turbine trip and go to AOP-007, TURBINE TRIP BELOW P-8 D. (1) is not (2) will direct a reactor trip and go to EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Page 83 of 100 Question:(1 point)84ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

Core Alterations are on-going in accordance with GP-010, REFUELING

R-2, CV Low Range, alarms (HIGH LED is LIT) Which ONE of the following correctly completes the statement below? To determine the correct R-2 setpoint the operator will use ____(1)____. If R-2 was subsequently determined to be inoperable, Core Alterations ____(2)____. A. (1) Section 3.1, Monitor Alarm Setpoint Determination, of the Offsite Dose Calculation Manual (ODCM) (2) must be suspended immediately B. (1) the Setpoint Change and Log Record of OMM-014, Radiation Monitor Setpoints (2) must be suspended immediately C. (1) the Setpoint Change and Log Record of OMM-014, Radiation Monitor Setpoints (2) may continue, provided that continuous HP Technician coverage and a Portable Area Radiation Monitor are provided D. (1) Section 3.1, Monitor Alarm Setpoint Determination, of the Offsite Dose Calculation Manual (ODCM) (2) may continue, provided that continuous HP Technician coverage and a Portable Area Radiation Monitor are provided Page 84 of 100 Question:(1 point)85ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A LOCA has occurred and NO ECCS Pumps are operating

The crew is implementing FRP-C.2, RESPONSE TO DEGRADED CORE COOLING

While depressurizing all intact S/G's they receive a RED condition on CSF-4, Integrity

RCS pressure is 200 psig Which ONE of the following identifies the required implementation of procedures for this event?

FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK A. Remain in FRP-C.2 until completed, THEN transition to FRP-P.1 B. Transition to FRP-P.1 and perform until completed, THEN transition to FRP-C.2 C. Transition to FRP-P.1 and when it is determined that RCS Integrity does not exist at Step 2, return to FRP-C.2 D. Transition to FRP-P.1 and initiate a soak, THEN perform FRP-C.2 actions that do not cooldown or raise RCS pressure until the soak is complete Page 85 of 100 Question:(1 point)86ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 25% power

A plant shutdown is in progress

The following timeline of events occur: 0800 Pressurizer Level Transmitter LT-460 starts to fluctuate rapidly characterized by abrupt spiking in the high and low direction 0800 A channel check indicates that all other Pressurizer level indications indicate on program and stable 0800 ITS LCO 3.3.1, REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION, action statement for LT-460, PZR level, was entered 0802 The lowest spike on the LT-460 indication reaches 13% 0804 The highest spike on the LT-460 indication reaches 92% 0810 The crew completes removing the instrument from service IAW OWP-030, PRESSURIZER LEVEL TRANSMITTERS (PLT) 0830 Plant down-power is initiated 1000 Reactor Power is stabilized at 8% and REACTOR TRIP BLOCK P-7 status light is ILLUMINATED Which ONE of the following correctly completes the statements below? The EARLIEST time that a single Reactor Protection Bistable will illuminate due to the erratic behavior of LT-460 is ____(1)____.

At 1000, IAW ITS LCO 3.3.1, the action statement for LT-460, PZR level ____(2)____ applicable. A. (1) 0802 (2) is NOT B. (1) 0802 (2) is C. (1) 0804 (2) is D. (1) 0804 (2) is NOT Page 86 of 100 Question:(1 point)87ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following initial plant conditions:

The plant was at 100% power when a reactor trip and safety injection occurred

R-31C, STEAM LINE RADIATION MONITOR, is in alarm and rising

The crew is implementing EOP-E-3,STEAM GENERATOR TUBE RUPTURE with the following conditions:

ALL MSIVs are closed

Containment pressure 0.8 psig

RWST level is 50% and lowering due to a leak in the RWST

S/G Parameters: Pressure NR Level A 960 psig and lowering slowly 22% and rising B 960 psig and lowering slowly 7% and rising C 450 psig and lowering rapidly 7% and lowering Which ONE (1) of the following correctly completes the statements below? IAW EOP-E-3 the crew will continue to feed ____(1)____ . When the CRS is transitioning from EOP-E-3, a transition to EOP-ECA-3.1 ____(2)____ required PRIOR to entering EOP-ECA-3.2. EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EOP-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT: SUBCOOLED RECOVERY DESIRED EOP-ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT: SATURATED RECOVERY DESIRED A. (1) "A" AND "B" Steam Generators ONLY (2) is B. (1) ALL Steam Generators (2) is C. (1) "A" AND "B" Steam Generators ONLY (2) is NOT D. (1) ALL Steam Generators (2) is NOT Page 87 of 100 Question:(1 point)88ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power

The crew has just completed swapping Service Water Booster Pumps from "A" to "B" IAW OP-903, SERVICE WATER SYSTEM

The following data was obtained after the pump swap:

HVH FI-1698A: 830 gpm

HVH FI-1698B: 810 gpm

HVH FI-1698C: 745 gpm

HVH FI-1689D: 805 gpm Which ONE of the following correctly completes the statements below? Entry into Technical Specification LCO 3.6.6, Containment Spray and Cooling Systems ____(1)____ required. OP-903 states that the electrical analysis for the Service Water Booster Pump motors may be exceeded if total HVH Unit Service Water Flow exceeds ____(2)____. A. (1) is NOT (2) 4000 gpm B. (1) is NOT (2) 4220 gpm C. (1) is (2) 4220 gpm D. (1) is (2) 4000 gpm Page 88 of 100 Question:(1 point)89ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A plant cooldown is in progress

RCS temperature is 380°F * "B" Instrument Air Compressor is in AUTO with the "B" Instrument Air Dryer in service * "D" Instrument Air Compressor is operating * "A" Instrument Air Compressor and "A" Instrument Air Dryer are out of service Subsequently:

The "D" Instrument Air Compressor trips, followed by the "B" Instrument Air Dryer clogging

The crew has entered AOP-017, LOSS OF INSTRUMENT AIR

RCS temperature is slowly rising

IA header pressure is 40 psig and rising slowly Which ONE of the following correctly completes the statements below? Based upon current conditions, FCV-1740, Air Dryer Hi DP Flow Control valve ____(1)____ be open. IAW AOP-017, the CRS will direct use of ____(2)____ as the preferred method to control RCS temperature. Attachment 2, Nitrogen Alignment to Steam Line PORVs Attachment 3, Manual Steam Dump of S/Gs A. (1) will (2) Attachment 2 B. (1) will NOT (2) Attachment 2 C. (1) will (2) Attachment 3 D. (1) will NOT (2) Attachment 3 Page 89 of 100 Question:(1 point)90ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following plant conditions:

The plant is operating at 100% power Subsequently:

A Large Break LOCA and loss of offsite power has occurred

The "A" EDG has failed to start

HVH-3, CV RECIRC FAN C, failed to AUTO start on the SI actuation

SI-880D, CV SPRAY PUMP "B" DISCHARGE, failed to automatically OPEN

Containment pressure is 13 psig and rising The Shift Manager is evaluating whether or not the EAL Threshold "Containment pressure > 10 psig with < one full train of depressurizing equipment," is met.

Which ONE of the following assesses whether or not one full train of depressurizing equipment is operating, and if not, identifies the MINIMUM action that must be taken from the Control Room to ensure that one full train is running? A. One full train of depressurization equipment is operating. B. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started. C. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started OR SI-880D must be OPENED. D. One full train of depressurization equipment is NOT operating; HVH-3 must be manually started AND SI-880D must be OPENED. Page 90 of 100 Question:(1 point)91ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 100% when Control Rod H-12 dropped

The crew lowered reactor power to 68% IAW AOP-001

During this load reduction AFD stabilized at -19 Which ONE of the following correctly completes the statements below? NI-41 and NI-43 will indicate ____(1)____ than NI-42 and NI-44 due to the Rod H-12 drop.

IAW AOP-001, the CRS ____(2)____ required to use Attachment 1 to reduce power to less than or equal to 50% within 30 minutes. AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM AOP-001, ATTACHMENT 1, TURBINE LOAD ADJUSTMENT (REFERENCE PROVIDED)A. (1) higher (2) is B. (1) lower (2) is NOT C. (1) lower (2) is D. (1) higher (2) is NOT Page 91 of 100 Question:(1 point)92ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

Monitor Tank "A" is being prepared for release

Tank pH was sampled and found to be too low Which ONE of the following correctly completes the statements below? IAW OP-705, WASTE LIQUID RELEASE AND RECIRCULATION Monitor Tank "A" is recirculated for a MINIMUM period of time to ensure ____(1)____. IAW EMP-023, LIQUID WASTE RELEASE AND SAMPLING, pH must be adjusted to a MINIMUM of ____(2)____ before the tank is released. A. (1) representative samples are obtained (2) > 5.0 B. (1) representative samples are obtained (2) > 6.0 C. (1) radioactive hot spots do not occur during the release (2) > 5.0 D. (1) radioactive hot spots do not occur during the release (2) > 6.0 Page 92 of 100 Question:(1 point)93ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Which ONE of the following correctly completes the statements below?

The TRM limitation on the quantity of radioactivity permitted in ____(1)____ Waste Gas Decay Tank(s) is < 1.9 X 104 Curies noble gas. The bases for TRM 3.21 is concerned with exposure to ____(2)____. A. (1) each (2) personnel in the Control Room B. (1) ALL (2) personnel in the Control Room C. (1) each (2) members of the public at the site boundary D. (1) ALL (2) members of the public at the site boundary Page 93 of 100 Question:(1 point)94ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant was at 35% power when a valid alarm on R-19 occurred

The crew has just entered AOP-035, S/G TUBE LEAK

Chemistry is sampling S/G's to determine primary to secondary leakage rate Which ONE of the following correctly completes the statements below? IAW AOP-035 the crew will use ____(1)____ as a reliable diverse indication to confirm the S/G tube leak.

Subsequently, Chemistry reports that the "B" S/G tube leakage rate is 0.071 gpm IAW AOP-035, the CRS is required to initiate a plant shutdown and place the unit in MODE 3 within ____(2)____. R-15, CONDENSER AIR EJECTOR GAS R-19, A, B, C STEAM GENERATOR BLOWDOWN R-24, A, B, C, MAIN STEAM LINE N-16 A. (1) R-15 (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months B. (1) R-15 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. (1) R-24 (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. (1) R-24 (2) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Page 94 of 100 Question:(1 point)95ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power.

The crew has tested SW-PMP-A, "SERVICE WATER PUMP A" on the previous shift per OST-302-1, SERVICE WATER PUMPS A & B INSERVICE TEST" and recorded elevated vibration level readings that are in the REQUIRED ACTION range.

Maintenance now has a plan to repair the pump. Subsequently, the following sequence of events occur:

SW-PMP-A is shutdown, placed under clearance, and repairs completed.

SW-PMP-A is re-energized and realigned in preparation for retesting.

SW-PMP-A is retested IAW OST-302-1 and vibrations are now found in the ALERT range. Based on the above information, Which ONE of the following correctly completes the statements below? IAW OST-302-1, SW-PMP-A is required to be declared INOPERABLE when ____(1)____. Based on the retest of SW-PMP-A, the pump is ____(2)____. A. (1) the pump is placed under clearance (2) INOPERABLE B. (1) the pump is placed under clearance (2) OPERABLE C. (1) when OST 302-1 was completed on the previous shift (2) INOPERABLE D. (1) when OST 302-1 was completed on the previous shift (2) OPERABLE Page 95 of 100 Question:(1 point)96ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power Subsequently, the following timeline of events occurs: 0200 EDG "A" is declared inoperable due to wrong oil being added during maintenance 0400 EDG "B" is declared inoperable due to mechanical issues 0400 The crew enters Technical Specification LCO 3.0.3 0500 A downpower is initiated 0900 Mode 3 is entered Which ONE of the following correctly completes the statements below? IAW Technical Specifications LCO 3.8.1, the operator must verify the correct breaker alignment and indicated power availability for the offsite circuit (offsite power checks) no later than ____(1)____. Based on this, the LATEST time that the plant must be placed in Mode 4 is ____(2)____. A. (1) 0300 (2) 1500 B. (1) 0300 (2) 1700 C. (1) 0500 (2) 1500 D. (1) 0500 (2) 1700 Page 96 of 100 Question:(1 point)97ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The Inside AO needs to enter a room during EOP implementation

The TSC and OSC are NOT activated

General dose rate levels in the room range from 25-45 mr/hr

The survey map shows the following on contact readings:

Point 1 is 100 mr/hr at 30 cm

Point 2 is 500 mr/hr at 30 cm

Point 3 is 1100 mr/hr at 30 cm Which ONE of the following correctly completes the statements below? Based on the plant indications, the radiological posting required is ____(1)____. Under the stated plant conditions, the Shift Manager ____(2)____ grant access to this area. A. (1) Very High Radiation Area (2) may B. (1) Very High Radiation Area (2) may NOT C. (1) Locked High Radiation Area (2) may NOT D. (1) Locked High Radiation Area (2) may Page 97 of 100 Question:(1 point)98ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

A General Emergency has been declared

The Dose Rate in Pipe Alley is 105 R/hr

A 10-minute evolution in Pipe Alley is necessary to conduct repair and re-entry activities

Two two-person teams have been briefed and are prepared to enter Pipe Alley to complete the task Which ONE of the following correctly completes the statement below?

IAW EPOSC-04, EMERGENCY WORK CONTROL, the ____(1)____ can authorize performance of the evolution in Pipe Alley.

The MINIMUM number of two-person teams needed to be dispatched to complete the 10-minute evolution in Pipe Alley without exceeding any emergency exposure limits is ____(2)____. A. (1) Site Emergency Coordinator (2) one B. (1) Site Emergency Coordinator (2) two C. (1) Radiological Control Director (2) one D. (1) Radiological Control Director (2) two Page 98 of 100 Question:(1 point)99ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is operating at 100% power.

At 0100, LCO 3.4.13, RCS OPERATIONAL LEAKAGE, was entered due to an 15 gpm leak from a crack on the spray line penetration weld at the PZR

The crew commenced a shutdown at 0200

The plant reached MODE 3 at 0545 when the OATC manually tripped the Rx as part of the plant shutdown per GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN. Which ONE of the following identifies the LATEST time at which the NRC must be notified? (REFERENCES PROVIDED) A. 0130 B. 0215 C. 0315 D. 0600 Page 99 of 100 Question:(1 point)100ILC15 RNP SRO NRC ExaminationRobinson Nuclear Plant Given the following:

The plant is at 100% power when the following annunciators alarm:

APP-001-C5, RCP Standpipe HI/LO LVL

APP-001-E2, RCP #1 SEAL LEAKOFF LO FLOW

The crew has entered AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS Which ONE of the following correctly completes the statements below? APP-001-C5, RCP Standpipe HI/LO LVL is due to ____(1)____. Subsequently:

Indicated "B" RCP #1 seal leakoff flow: 0.6 gpm

The BOP performed Attachment 2 of AOP-018, RCP #2 SEAL LEAK RATE CALCULATION,and calculates Total "B" RCP #1 seal leakoff flow at 6.5 gpm * "B" RCP Bearing Temperatures are 130°F and stable * "B" RCP #1 Seal Leakoff Temperature is 125°F and stable IAW AOP-018 the CRS will direct the crew to continue to monitor RCP parameters and place the plant in MODE 3 within ____(2)____ using GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN. A. (1) high level (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months B. (1) high level (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. (1) low level (2) 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. (1) low level (2) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Page 100 of 100 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

ATTACHMENT 10.1 Page 12 of 13 FMP-001 Rev. 31 Page 23 of 25 HBRSEP UNIT NO. 2, CYCLE 30 CORE OPERATING LIMITS REPORT REVISION 0 NOTE: For power levels above 90%, power operation is allowed within the target bands (+3% and +5%).

ATTACHMENT 11.1 Page 1 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 16 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 10 CFR 50.72 states that immediate reports shall be made to the NRC Operations Center of these Emergency Events via the NRC Emergency Telecommunications System (ETS) as specified in the Emergency Plan. 10 CFR 50.72 additionally identifies Non-Emergency Events which are to be reported within one-hour, four-hours, or eight hours to the NRC. ETS Telephones, which are identified, are located in the Control Room, the TSC, and the EOF. In the event that the ETS is not available, 10 CFR 50.72(a)(2) permits the use of commercial telephone. EVENT KEY WORDS REQUIREMENT EXAMPLES NOTE: 10 CFR 50.72 recognizes the Emergency Plan and its four Emergency Classes of Unusual Event, Alert, Site Area Emergency and General Emergency. EMERGENCIES 10 CFR 50.72(a)(i) 10 CFR 30.32(i)(3)(viii) 10 CFR 40.31(i)(3)(viii) 10 CFR 72.75(a) Emergency Unusual Event Alert Site Area Emergency General Emergency ISFSI HBRSEP shall notify the NRC of the declaration of any of the Emergency Classes specified in the Emergency Plan. (See EPNOT-01) Declaration of an Unusual Event, Alert, Site Area Emergency, or General Emergency. Discovery of an event that should have resulted in an Emergency Classification, but no emergency was declared. Discovery that a declared emergency exceeded the Emergency Action Levels for a higher emergency declaration, but the higher classification was not declared. ERDS ACTIVATION 10 CFR 50.72(a)(4) ERDS Emergency HBRSEP shall activate the ERDS as soon as possible but not later than one hour after declaring an Alert, Site Area Emergency, or General Emergency. An Alert, Site Area Emergency, or General Emergency is declared. DEVIATION FROM TS (10 CFR 50.54(X)) 10 CFR 50.72(b)(1) Deviation Departure License Condition Any deviation from the TS authorized pursuant to 10 CFR 50.54(x). Intentional deviation from an approved plant procedure in order to preserve plant safety 10 CFR 50.54(x).

ATTACHMENT 11.1 Page 2 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 17 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC HBRSEP shall immediately notify the NRC Operations Center via ETS as soon as practical and in all cases within one hour of the occurrence of any of the following: EVENT KEY WORDS REQUIREMENT EXAMPLES SAFETY LIMIT, LIMITING SAFETY SYSTEM SETTING EXCEEDED 10 CFR 50.36(c)(1)(i)(A) UFSAR Section 17.3A, Paragraph 3.1.a Safety Limit Limiting Safety System Setting If any safety limit is exceeded, shut down the reactor. HBRSEP shall notify the NRC [within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months via ETS per 10 CFR 50.72(a)(1), See Emergency Plan Procedures]. Operation must not be resumed until authorized by the NRC. NRC Region II must also be notified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and the Vice President - Robinson Nuclear Plant within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months The limits of TS Figure 2.1.1-1 are exceeded. SAFETY SYSTEM DOES NOT FUNCTION AS REQUIRED 10 CFR 50.36(c)(1)(ii)(A) ESF RPS Limiting Safety System Setting HBRSEP shall notify the NRC if the automatic safety system [to correct an abnormal situation before a safety limit is exceeded] has been determined not to function as required. A failure mechanism is discovered that indicates that the RPS will not function to trip the reactor under certain required conditions.

ATTACHMENT 11.1 Page 3 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 18 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SECURITY SAFEGUARDS EVENTS HBRSEP shall notify the NRC Operations Center via the ETS within one hour* after discovery of the safeguards events described as follows (10 CFR 73.71(b)(1)): EVENT KEY WORDS REQUIREMENT EXAMPLES THEFT/UNLAWFUL DIVERSION OF SNM OR SPENT FUEL SHIPMENT 10 CFR 73.71(a)(1) SNM Spent Fuel Security Safeguards Any discovery of the loss of any shipment of SNM or spent fuel, and within one hour after recovery of or accounting for such lost shipment Shipment Emergency Event THEFT/UNLAWFUL DIVERSION OF SNM 10 CFR 73.71(b)(1) 10 CFR 73, Appendix G, I(a)(1) Theft of SNM Diversion Security Safeguards Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause: (1) A theft or unlawful diversion of SNM Shipment Emergency Event SABOTAGE OF PLANT EQUIPMENT 10 CFR 73.71(b)(1) 10 CFR 73, Appendix G, I(a)(2) Sabotage Damage to Plant SNM Spent Fuel Security Safeguards [Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause:] (2) Significant physical damage to a power reactor...or its equipment or carrier equipment transporting nuclear fuel or spent nuclear fuel, or to the nuclear fuel or spent fuel a facility or carrier possesses. Shipment Emergency Event Security Event (AD-SY-ALL-0150)

In response to NRC Bulletin 2005-02, RNP committed to make an accelerated call to the NRC within approximately 15 minutes following discovery of an imminent threat or attack against the station. The primary purpose is to allow for the NRC to timely notify other licensees of a potential common threat. The accelerated call should not be allowed to interfere with plant or personnel safety, physical security response, or notification of local law enforcement agencies. The information provided in the accelerated call can be limited to: Site name Emergency Classification - if already determined - do not delay call for the purpose of classifying Nature of the threat - briefly described, if known, including the type of attack (e.g., armed assault by land, water or aircraft) and the attack status (e.g., imminent, in progress, or repelled)

ATTACHMENT 11.1 Page 4 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC AP-030 Rev. 52 Page 19 of 66 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC - SECURITY SAFEGUARDS EVENTS HBRSEP shall notify the NRC Operations Center via the ETS within one hour* after discovery of the safeguards events described as follows (10 CFR 73.71(b)(1)): EVENT KEY WORDS REQUIREMENT EXAMPLES UNAUTHORIZED TAMPERING WITH PLANT EQUIPMENT 10 CFR 73, Appendix G, I(a)(3) Unauthorized Use Tampering Security System Safeguards [Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause:] (3) Interruption of normal operation of HBRSEP through the unauthorized use of or tampering with its machinery, components, or controls including the security system. Security Event (AD-SY-ALL-0150) ENTRY OF UNAUTHORIZED PERSON INTO PROTECTED OR VITAL AREA 10 CFR 73, Appendix G, I(b) Unauthorized Entry Security Safeguards An actual entry of an unauthorized person into a protected area, material access area, controlled access area, vital area, or transport. Security Event (AD-SY-ALL-0150) FAILURE, DEGRADATION, OR DISCOVERED VULNERABILITY OF SAFEGUARD SYSTEM 10 CFR 73, Appendix G, I(c) Degradation Vulnerability Safeguards Unauthorized Undetected Access Security Any failure, degradation, or the discovered vulnerability in a safeguard system that could allow unauthorized or undetected access to a protected area, material access area, controlled access area, vital area or transport for which compensatory measures have not been employed. Procedure AD-SY-ALL-0150 INTRODUCTION OF CONTRABAND INTO VITAL OR PROTECTED AREA 10 CFR 73, Appendix G, I(d) Contraband Unauthorized Security Safeguards The actual or attempted introduction of contraband into a protected area, material process area, vital area, or transport. Contraband applies to items that could be used to commit radiological sabotage as defined in 10 CFR 73.2.

See footnote on the previous page regarding a goal for a 15 minute call to the NRC in regard to an imminent security threat or attack.