ML16061A457

301 SRO As-Given Written Exam

ML16061A457
Person / Time
Site:	Robinson
Issue date:	03/01/2016
From:	NRC/RGN-II
To:	Carolina Power & Light Co
References
Download: ML16061A457 (124)

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Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 1 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 2 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 3 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 4 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 5 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 6 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 7 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 8 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 9 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 10 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 11 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 12 (1 point)

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/Gs 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 13 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 14 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 15 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 16 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 17 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 18 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 19 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 20 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 21 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 22 (1 point)

Given the following:

• A Reactor startup is in progress

• The following indications are observed:

• N31/32 = 900 cps

-11

• N35/36 = 5 x 10 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 23 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 24 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 25 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 26 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 27 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 28 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 29 (1 point)

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

1. 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 30 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 31 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 32 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 33 (1 point)

Given the following:

• The plant is at 100% RTP

• The following timeline is observed:

TIME A SI accumulator pressure A SI accumulator level 1108 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 34 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 35 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 36 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 37 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 38 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 39 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 40 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 41 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 42 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 43 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 44 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 45 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 46 (1 point)

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 minute after 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 47 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 48 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 49 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 50 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 51 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 52 (1 point)

Given the following:

• The plant is operating at 100% power

• R-19A, STM GEN BLOW DN SG-A, enters the alarm condition Which 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-1930A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-1930A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-1930A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B)

(2) will D. (1) Blowdown Isolation Valves (FCV-1930A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B)

(2) will NOT Page 52 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 53 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 54 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 55 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 56 (1 point)

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) PP-61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP-61, 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 57 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 58 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 59 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 60 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 61 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 62 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 63 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 64 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 65 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 66 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 67 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 68 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 69 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 70 (1 point)

Given the following:

• The plant is at 100% power

• It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band.

Which ONE of the following correctly completes the statement below?

IAW Technical Specification LCO 3.2.3 ACTION.

Restore AFD to within target band within ___(1)___.

If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___.

A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Page 70 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 71 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 72 (1 point)

Given the following:

• An operator has been assigned work in the radiologically controlled area

• The dose rate in the area is 500 mR/hr

• The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Page 72 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 73 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 74 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 75 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 76 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 77 (1 point)

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, POST-SGTR COOLDOWN USING BLOWDOWN B. (1) is (2) EOP-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP C. (1) is NOT (2) EOP-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN D. (1) is NOT (2) EOP-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP Page 77 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 78 (1 point)

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 RC-567, HEAD VENT RC-568, HEAD VENT RC-569, PZR VENT RC-570, PZR VENT RC-571, PRT ISO RC-572, 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 79 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 80 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 81 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 82 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 83 (1 point)

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 go to 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 84 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 85 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 86 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 87 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 88 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 89 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 90 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 91 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 92 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 93 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 94 (1 point)

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/Gs 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> B. (1) R-15 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C. (1) R-24 (2) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. (1) R-24 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Page 94 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 95 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 96 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 97 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 98 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 99 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 100 (1 point)

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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> B. (1) high level (2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. (1) low level (2) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. (1) low level (2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Page 100 of 100

RCS P/T Limits 3.4.3 MATERIALS PROPERTIES BASE Curves applicable for heatup rates up to 60 ºF/Hr for CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Service period up to 35 EFPY.

Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Heatup Curves include +10ºF and 60 psig allowance For instrumentation error.

2750 2500 2250 2000 Leak Test Limit 1750 Unacceptable Operation Indicated Pressure (psig)

Acceptable Operation 1500 Heatup Rate to 60 °F/Hr 1250 1000 Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 75 35 EFPY 50 25 0

0 5 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F)

Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-7 Amendment No.218

RCS P/T Limits 3.4.3 MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Curves applicable for cooldown rates up to and Girth Weld 10-273 100°F/Hr for the service period up to 35 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F EFPY. Curves include +10°F and -60 PSIG 3/4T, 147°F and 172°F allowance for instrument error.

2750 2500 0°F/Hr.

2250 2000 Unacceptable Operation 20°F/ Hr Indicated Pressure (PSIG) 1750 40°F/ Hr 1500 Acceptable Operation 60°F/ Hr 1250 1000 Cooldown Rates

(°F/Hr) 100°F/ Hr 750 0 and 20 500 40 60 100 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F)

Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-8 Amendment No. 218

RNP Cycle 30 Curve Book RNP-F/NFSA-0237, Rev. 0 Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve Book Page A46 of A86 CURVE 1.14 REV. 218 HBR2 CYCLE 30 BORON CONCENTRATION REQUIRED TO MAINTAIN A MINIMUM OF 2.6% SHUTDOWN MARGIN (ARI-MRR) 1700 1500 SHUTDOWN MARGIN BORON (PPM) 1300 1100 900 38 F 700 200 F 300 F 350 F 500 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 22000 CYCLE EXPOSURE (MWD/MTU)

REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR

Rev. 7 EOPE3 STEAM GENERATOR TUBE RUPTURE Page 47 of 52 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Attachment 3 RCS Pressure And Charging Flow Control Handout (Page 1 of 1)

CAUTION RCS AND Ruptured S/G(s) pressures must be maintained LESS THAN 1060 PSIG.

1. CONTROL RCS Pressure AND Charging Flow To MINIMIZE RCSToSecondary Leakage:

a. PERFORM appropriate action(s) from table below:

RUPTURED S/G(s) LEVEL PZR Level RISING LOWERING OFF SCALE HIGH LESS THAN OR RAISE Charging RAISE Charging RAISE Charging EQUAL TO 27% flow flow flow

[44%] DEPRESSURIZE MAINTAIN RCS RCS using Step 1.c AND Ruptured S/G(s) pressures equal BETWEEN 27% DEPRESSURIZE TURN ON PZR MAINTAIN RCS AND

[44%] AND 50% RCS using Step 1.c Heaters Ruptured S/G(s) pressures equal BETWEEN 50% DEPRESSURIZE TURN ON PZR MAINTAIN RCS AND AND 73% [66%] RCS using Step 1.c Heaters Ruptured S/G(s)

REDUCE Charging pressures equal flow GREATER THAN REDUCE Charging TURN ON PZR MAINTAIN RCS AND OR EQUAL TO flow Heaters Ruptured S/G(s) 73% [66%] pressures equal

b. CHECK Ruptured S/G Pressure b. CONTROL Ruptured S/G LESS THAN 1060 PSIG pressure LESS THAN 1060 psig using Step 1.a.

c. USE Normal PZR Spray as c. IF Letdown is in service, THEN necessary to depressurize RCS USE Aux PZR Spray per per Table in Step 1.a Supplement G, Establishing Aux PZR Spray.

IF Aux PZR Spray is NOT available OR effective, THEN USE one PZR PORV.

- END -

Rev. 15 AOP-026 GRID INSTABILITY Page 18 of 23 ATTACHMENT 1 MAXIMUM GENERATOR MVA OUTPUT vs SYSTEM FREQUENCY (Page 1 of 1)

ATTACHMENT 10.1 Page 12 of 13 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%).

FMP-001 Rev. 31 Page 23 of 25

ATTACHMENT 11.1 Page 1 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Emergency HBRSEP shall notify the NRC of the Declaration of an Unusual Event, Alert, Site Unusual Event declaration of any of the Emergency Classes Area Emergency, or General Emergency.

Alert specified in the Emergency Plan.

Site Area Discovery of an event that should have Emergency (See EPNOT-01) resulted in an Emergency Classification, but General no emergency was declared.

Emergency Discovery that a declared emergency 10 CFR 50.72(a)(i)

ISFSI exceeded the Emergency Action Levels for a 10 CFR 30.32(i)(3)(viii) higher emergency declaration, but the higher 10 CFR 40.31(i)(3)(viii) classification was not declared.

10 CFR 72.75(a)

ERDS ACTIVATION ERDS HBRSEP shall activate the ERDS as soon as An Alert, Site Area Emergency, or General Emergency possible but not later than one hour after Emergency is declared.

declaring an Alert, Site Area Emergency, or General Emergency.

10 CFR 50.72(a)(4)

DEVIATION FROM TS (10 CFR Deviation Any deviation from the TS authorized Intentional deviation from an approved plant 50.54(X)) Departure pursuant to 10 CFR 50.54(x). procedure in order to preserve plant safety 10 License CFR 50.54(x).

10 CFR 50.72(b)(1) Condition AP-030 Rev. 52 Page 16 of 66

ATTACHMENT 11.1 Page 2 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Safety Limit If any safety limit is exceeded, shut down The limits of TS Figure 2.1.1-1 are exceeded.

SYSTEM SETTING EXCEEDED Limiting Safety the reactor. HBRSEP shall notify the NRC System Setting [within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> via ETS per 10 CFR 50.72(a)(1), See Emergency Plan Procedures]. Operation must not be resumed until authorized by the NRC.

10 CFR 50.36(c)(1)(i)(A) NRC Region II must also be notified within 1 UFSAR Section 17.3A, Paragraph hour and the Vice President - Robinson 3.1.a Nuclear Plant within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SAFETY SYSTEM DOES NOT ESF HBRSEP shall notify the NRC if the A failure mechanism is discovered that FUNCTION AS REQUIRED RPS automatic safety system [to correct an indicates that the RPS will not function to trip Limiting Safety abnormal situation before a safety limit is the reactor under certain required conditions.

System Setting exceeded] has been determined not to 10 CFR 50.36(c)(1)(ii)(A) function as required.

AP-030 Rev. 52 Page 17 of 66

ATTACHMENT 11.1 Page 3 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Any discovery of the loss of any shipment of Shipment Emergency Event SNM OR SPENT FUEL SHIPMENT Spent Fuel SNM or spent fuel, and within one hour after Security recovery of or accounting for such lost Safeguards shipment 10 CFR 73.71(a)(1)

THEFT/UNLAWFUL DIVERSION OF Theft of SNM Any event in which there is reason to Shipment Emergency Event SNM Diversion believe that a person has committed or Security caused, or attempted to commit or cause, or Safeguards has made a credible threat to commit or 10 CFR 73.71(b)(1) cause:

10 CFR 73, Appendix G, I(a)(1) (1) A theft or unlawful diversion of SNM SABOTAGE OF PLANT Sabotage [Any event in which there is reason to Shipment Emergency Event EQUIPMENT Damage to Plant believe that a person has committed or Security Event (AD-SY-ALL-0150)

SNM caused, or attempted to commit or cause, or Spent Fuel has made a credible threat to commit or Security cause:]

Safeguards (2) Significant physical damage to a power reactor...or its equipment or carrier equipment transporting nuclear fuel or spent 10 CFR 73.71(b)(1) nuclear fuel, or to the nuclear fuel or spent 10 CFR 73, Appendix G, I(a)(2) fuel a facility or carrier possesses.

• 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)

AP-030 Rev. 52 Page 18 of 66

ATTACHMENT 11.1 Page 4 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Unauthorized [Any event in which there is reason to Security Event (AD-SY-ALL-0150)

WITH PLANT EQUIPMENT Use believe that a person has committed or Tampering caused, or attempted to commit or cause, or Security System has made a credible threat to commit or Safeguards cause:]

(3) Interruption of normal operation of HBRSEP through the unauthorized use of or tampering with its machinery, components, or controls including the 10 CFR 73, Appendix G, I(a)(3) security system.

ENTRY OF UNAUTHORIZED Unauthorized An actual entry of an unauthorized person Security Event (AD-SY-ALL-0150)

PERSON INTO PROTECTED OR Entry into a protected area, material access area, VITAL AREA Security controlled access area, vital area, or 10 CFR 73, Appendix G, I(b) Safeguards transport.

FAILURE, DEGRADATION, OR Degradation Any failure, degradation, or the discovered Procedure AD-SY-ALL-0150 DISCOVERED VULNERABILITY OF Vulnerability vulnerability in a safeguard system that SAFEGUARD SYSTEM Safeguards could allow unauthorized or undetected Unauthorized access to a protected area, material access Undetected area, controlled access area, vital area or Access transport for which compensatory measures 10 CFR 73, Appendix G, I(c) Security have not been employed.

INTRODUCTION OF Contraband The actual or attempted introduction of Contraband applies to items that could be CONTRABAND INTO VITAL OR Unauthorized contraband into a protected area, material used to commit radiological sabotage as PROTECTED AREA Security process area, vital area, or transport. defined in 10 CFR 73.2.

10 CFR 73, Appendix G, I(d) Safeguards

• 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.

AP-030 Rev. 52 Page 19 of 66

ATTACHMENT 11.1 Page 5 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Notwithstanding any other requirements for BYPRODUCT, SOURCE, OR SNM Source notification, immediately notify the NRC of any (5X ANNUAL LIMIT) SNM event involving byproduct, source, or SNM Exposure possessed by HBRSEP that may have caused or Dose threatens to cause any of the following Release conditions:

Occupational 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the 10 CFR 20.2202(a)(1) individual could have received an intake five times the occupational annual limit on intake.

AP-030 Rev. 52 Page 20 of 66

ATTACHMENT 11.1 Page 6 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Intake The release of radioactive material, inside or BYPRODUCT, SOURCE, SNM (>5X Ingestion outside the restricted area, so that, had an OCCUPATIONAL LIMIT) Release individual been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Source individual could have received an intake five times Byproduct the occupational annual limit on intake.

10 CFR 20.2202(a)(2) SNM 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 ISFSI The licensee shall notify the NRC Operations Unusually high radiation readings OR LOSS OF SNM Criticality Center via ETS within one hour of discovery of discovered in the vicinity of the ISFSI that 10 CFR 72.74 SNM accidental criticality or any loss of SNM. could indicate possibility of a criticality Loss 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 HBRSEP shall notify the NRC Operations Center Shipment Emergency Event SHIPMENT OF SNM Loss via the ETS within one hour after discovery of any Security Event (AD-SY-ALL-0150)

SNM loss of any shipment of SNM or spent fuel or any Spent Fuel incident in which an attempt has been made, or is Diversion believed to have been made, to commit a theft or 10 CFR 70.52(b) Safeguards unlawful diversion of SNM.

10 CFR 73.71(a)(1) Security LOST OR UNACCOUNTED Recovery HBRSEP shall notify the NRC Operations Center SHIPMENT OF SNM - RECOVERY Accounting via the ETS within one hour after recovery of, or Shipment accounting for, any lost shipment of SNM.

SNM Security 10 CFR 73.71(a)(1) Safeguards AP-030 Rev. 52 Page 21 of 66

ATTACHMENT 11.1 Page 7 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Degradation (i) any further degradation in the level of Refer to EPNOT-01 Emergency Class safety of the plant or ISFSI or other Change worsening conditions, including those that Update require the declaration of any of the Termination Emergency Classes, if such a declaration ISFSI has not been previously made, or (ii) any change from one Emergency Class 10 CFR 50.72(c)(1) to another, or (iii) a termination of the 10 CFR 72.75(f)(1) Emergency Class.

FOLLOW-UP NOTIFICATION Result (i) the results of ensuing evaluations or Evaluation assessments of plant or ISFSI conditions, Effectiveness (ii) the effectiveness of response or Unknown protective measures taken, and 10 CFR 50.72(c)(2) ISFSI (iii) information related to plant or ISFSI 10 CFR 72.75(f)(2) behavior that is not understood.

FOLLOW-UP NOTIFICATION Open Maintain an open, continuous Refer to EPNOT-01 Continuous communication channel with the NRC 10 CFR 50.72(c)(3) Communication Operations Center upon request by the 10 CFR 50.72.75(f)(3) ISFSI NRC.

AP-030 Rev. 52 Page 22 of 66

ATTACHMENT 11.1 Page 8 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Incident Any incident in which an attempt has been 10 Curies of tritium discovered missing from TRITIUM Theft made or is believed to have been made to the Chemistry Laboratory, and reason exists to Tritium commit a theft of more than 10 curies of suspect that the tritium was stolen Attempt tritium (outside of spent fuel) at any one Security time or more than 100 curies of tritium in 10 CFR 30.55(c) Safeguards one calendar year THEFT/UNLAWFUL DIVERSION OF Incident Any incident in which an attempt has been A source assembly is discovered missing SOURCE MATERIAL Attempt made or is believed to have been made to from a new fuel shipment.

Theft commit a theft or unlawful diversion of more Diversion than 15 pounds of Source Material at any Source one time or 150 pounds of Source Material 10 CFR 40.64(c) Security in any one calendar year Safeguards SHIPPING PACKAGE Contamination Removable radioactive surface New or Spent Fuel Shipment Cask arrives RADIOACTIVELY CONTAMINATED Shipment contamination exceeds the limits of with surface contamination in excess of limits.

10 CFR 20.1906(d)(1) 10 CFR 71.87 SHIPPING PACKAGE EXCEEDING Radiation External radiation levels exceeds of the New or Spent Fuel Shipment Cask arrives EXTERNAL DOSE RATE LIMITS Dose Rate limits of 10 CFR 71.47 with external radiation levels in excess of 10 CFR 20.1906(d)(2) Shipment limits.

AP-030 Rev. 52 Page 23 of 66

ATTACHMENT 11.1 Page 9 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Alcohol If HBRSEP has a reasonable belief that an DUTY Influence NRC employee or NRC contractor may be Substance under the influence of any substance, or is NRC employee otherwise unfit for duty, the licensee or FFD other entity may not deny access but shall 10 CFR 26.77(c) Fitness for Duty 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 IAEA HBRSEP shall immediately communicate If the IAEA representatives credentials have OFFICIAL International by telephone, within one hour with respect not been confirmed by the NRC, the licensee Atomic to the credentials of any person who claims shall not admit the person until the NRC has Energy to be an IAEA representative and shall confirmed the persons credentials. The Agency accept written or electronic confirmation of licensee, shall notify the Commission 10 CFR 75.8(c) Credential the credentials from the NRC. promptly, by telephone, whenever an IAEA representative arrives at a facility or location without advance notification.

AP-030 Rev. 52 Page 24 of 66

ATTACHMENT 11.2 Page 1 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 Shutdown The initiation of any shutdown required by Reactor is in MODEs 1 or 2 and the TS Shutdown the TS. Control Room takes action to reduce Power power (i.e., negative reactivity insertion)

Reduction 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 10 CFR 50.72(b)(2)(i) 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 ECCS Any event that results or should have Manual or automatic Safety Injection System Actuation resulted in emergency core cooling system actuation in response to a valid signal that Safety (ECCS) discharge into the reactor coolant resulted in or should have resulted in Injection system as a result of a valid signal except discharge into the reactor coolant system.

when the actuation results from and is part of a pre-planned sequence during testing 10 CFR 50.72(b)(2)(iv)(A) or reactor operation.

RPS INITIATION RPS Actuation Any event or condition that results in Manual or automatic reactor trip from critical (MANUAL/AUTOMATIC) Reactor actuation of the reactor protection system through RTP of 100%. Trips which occur as DURING OPERATION Protection (RPS) when the reactor is critical except part of planned evolutions in accordance with System when the actuation results from and is part procedures are not reportable.

RPS of a pre-planned sequence during testing 10 CFR 50.72(b)(2)(iv)(B) Reactor Trip or reactor operation.

AP-030 Rev. 52 Page 25 of 66

ATTACHMENT 11.2 Page 2 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 News Release Any event or situation, related to the health Any News release concerning GOVERNMENT NOTIFICATIONS Press and safety of the public or on-site - A fatality, Radio personnel, or protection of the - Inadvertent release of radioactively Television environment, for which a news release is contaminated materials to public areas Fatality planned or notification to other government - unusual or abnormal releases of radioactive Environment agencies has been or will be made. Such effluents (See Attachment 11.14), or Public an event may include an on-site fatality or - Information associated with an Emergency Health and Safety inadvertent release of radioactively Event except when the ERO is activated Release contaminated materials. (EPNOT-01).

ISFSI Licensees are required to notify the NRC Notification to other government agencies within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of whichever of the following concerning:

occurs first: - A fatality on site,

- A plan to report to either the press or - Health and safety of the public or site another government agency is personnel, approved by an individual authorized to - Inadvertent release of radioactively 10 CFR 50.72(b)(2)(xi) make the final decision, or contaminated materials to public areas, 10 CFR 72.75(b)(2) - A report has actually been made to the - Discovered endangered species kill.

press or another government agency. - Notifications to the National Response Center (EPA) related to Lake Robinson AP-030 Rev. 52 Page 26 of 66

ATTACHMENT 11.2 Page 3 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 Loss Immediately notify the NRC, after its A radiography source is discovered missing. The MATERIAL (>1000X 10 CFR 20 Theft occurrence becomes known, any lost, stolen, source is licensed to the radiography contractor.

LIMITS) Missing or missing licensed material in an aggregate If the contractor does not make the required Licensed quantity equal to or greater than 1,000 times notification, HBRSEP should notify the NRC Radioactive the quantity specified in [10 CFR 20] Operations Center via ETS.

Material Appendix C under such circumstances that it Recovery appears to HBRSEP that an exposure could result to persons in unrestricted areas.

10 CFR 20.2201 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of any subsequent recovery of the source.

ISFSI - DEPARTURE FROM ISFSI An action taken in an emergency that Action taken in an emergency that departs from LICENSE CONDITION Emergency departs from a condition or a technical procedure that is deemed necessary to prevent Departure specification contained in a license or releases or radiation doses to the public in Deviation certificate of compliance issued under excess of 10 CFR 20 limits Health and 10 CFR 72 when the action is immediately (See AD-HU-ALL-0004).

Safety needed to protect the public health and License safety and no action consistent with license Condition conditions or technical specifications that can 10 CFR 72.75(b)(1) provide adequate or equivalent protection is immediately apparent.

AP-030 Rev. 52 Page 27 of 66

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 1 B 2 D 3 C 4 C 5 B 6 B 7 B 8 B 9 D 10 C 11 A 12 D 13 D 14 B 15 A 16 A 17 B 18 B 19 C 20 A 21 B 22 D 23 D 24 D 25 C Printed 2/11/2016 2:50:36 PM Page 1 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 26 A 27 D 28 C 29 B 30 C 31 B 32 B 33 C 34 B 35 B 36 A 37 D 38 D 39 C 40 C 41 B 42 C 43 C 44 C 45 C 46 C 47 B 48 A 49 A 50 D Printed 2/11/2016 2:50:37 PM Page 2 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 51 D 52 C 53 D 54 D 55 C 56 C 57 B 58 B 59 C 60 D 61 A 62 B 63 A 64 B 65 C 66 C 67 D 68 B 69 A 70 A 71 B 72 B 73 A 74 D 75 B Printed 2/11/2016 2:50:37 PM Page 3 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 76 A 77 C 78 D 79 B 80 B 81 A 82 C 83 D 84 C 85 A 86 D 87 A 88 C 89 A 90 D 91 C 92 B 93 C 94 A 95 D 96 B 97 D 98 B 99 B 100 B Printed 2/11/2016 2:50:37 PM Page 4 of 4

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 1 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 2 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 3 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 4 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 5 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 6 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 7 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 8 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 9 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 10 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 11 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 12 (1 point)

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/Gs 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 13 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 14 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 15 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 16 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 17 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 18 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 19 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 20 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 21 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 22 (1 point)

Given the following:

• A Reactor startup is in progress

• The following indications are observed:

• N31/32 = 900 cps

-11

• N35/36 = 5 x 10 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 23 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 24 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 25 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 26 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 27 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 28 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 29 (1 point)

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

1. 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 30 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 31 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 32 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 33 (1 point)

Given the following:

• The plant is at 100% RTP

• The following timeline is observed:

TIME A SI accumulator pressure A SI accumulator level 1108 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 34 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 35 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 36 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 37 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 38 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 39 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 40 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 41 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 42 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 43 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 44 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 45 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 46 (1 point)

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 minute after 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 47 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 48 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 49 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 50 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 51 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 52 (1 point)

Given the following:

• The plant is operating at 100% power

• R-19A, STM GEN BLOW DN SG-A, enters the alarm condition Which 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-1930A/B), ONLY (2) will B. (1) Blowdown Isolation Valves (FCV-1930A/B), ONLY (2) will NOT C. (1) Blowdown Isolation Valves (FCV-1930A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B)

(2) will D. (1) Blowdown Isolation Valves (FCV-1930A/B) and Blowdown Sample Isolation Valves (FCV-1933A/B)

(2) will NOT Page 52 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 53 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 54 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 55 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 56 (1 point)

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) PP-61, Circuit 1 breaker, ROD POSITION INDICATION SYSTEM, (2) is NOT C. (1) PP-61, 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 57 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 58 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 59 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 60 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 61 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 62 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 63 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 64 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 65 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 66 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 67 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 68 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 69 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 70 (1 point)

Given the following:

• The plant is at 100% power

• It has been determined that LCO 3.2.3, Axial Flux Difference is outside the target band.

Which ONE of the following correctly completes the statement below?

IAW Technical Specification LCO 3.2.3 ACTION.

Restore AFD to within target band within ___(1)___.

If AFD cannot be restored within target band within the allowable time, Reduce THERMAL POWER to < 90% RTP or 0.9 APL, whichever is less, within an additional ___(2)___.

A. (1) 15 minutes (2) 15 minutes B. (1) 15 minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 30 minutes (2) 15 minutes D. (1) 30 Minutes (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Page 70 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 71 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 72 (1 point)

Given the following:

• An operator has been assigned work in the radiologically controlled area

• The dose rate in the area is 500 mR/hr

• The operator has a current yearly dose of 0.5 Rem TEDE Which ONE of the following identifies the MAXIMUM time that the operator can perform work BEFORE reaching the Duke Energy Annual Administrative Dose Limit without receiving an extension?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Page 72 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 73 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 74 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 75 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 76 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 77 (1 point)

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, POST-SGTR COOLDOWN USING BLOWDOWN B. (1) is (2) EOP-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP C. (1) is NOT (2) EOP-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN D. (1) is NOT (2) EOP-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP Page 77 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 78 (1 point)

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 RC-567, HEAD VENT RC-568, HEAD VENT RC-569, PZR VENT RC-570, PZR VENT RC-571, PRT ISO RC-572, 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 79 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 80 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 81 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 82 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 83 (1 point)

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 go to 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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 84 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 85 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 86 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 87 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 88 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 89 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 90 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 91 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 92 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 93 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 94 (1 point)

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/Gs 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> B. (1) R-15 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C. (1) R-24 (2) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. (1) R-24 (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Page 94 of 100

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 95 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 96 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 97 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 98 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 99 (1 point)

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

Robinson Nuclear Plant ILC15 RNP SRO NRC Examination Question: 100 (1 point)

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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> B. (1) high level (2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. (1) low level (2) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. (1) low level (2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Page 100 of 100

RCS P/T Limits 3.4.3 MATERIALS PROPERTIES BASE Curves applicable for heatup rates up to 60 ºF/Hr for CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Service period up to 35 EFPY.

Limiting ART Values at 35 EFPY: 1/4T, 167°F 3/4T, 147°F Heatup Curves include +10ºF and 60 psig allowance For instrumentation error.

2750 2500 2250 2000 Leak Test Limit 1750 Unacceptable Operation Indicated Pressure (psig)

Acceptable Operation 1500 Heatup Rate to 60 °F/Hr 1250 1000 Criticality Limit based on Inservice Hydrostatic test Temperature (226°F) for the service period up to 75 35 EFPY 50 25 0

0 5 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F)

Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-7 Amendment No.218

RCS P/T Limits 3.4.3 MATERIALS PROPERTY BASE CONTROLLING MATERIAL: Upper Shell Plate W10201-1 Curves applicable for cooldown rates up to and Girth Weld 10-273 100°F/Hr for the service period up to 35 Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F EFPY. Curves include +10°F and -60 PSIG 3/4T, 147°F and 172°F allowance for instrument error.

2750 2500 0°F/Hr.

2250 2000 Unacceptable Operation 20°F/ Hr Indicated Pressure (PSIG) 1750 40°F/ Hr 1500 Acceptable Operation 60°F/ Hr 1250 1000 Cooldown Rates

(°F/Hr) 100°F/ Hr 750 0 and 20 500 40 60 100 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F)

Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-8 Amendment No. 218

RNP Cycle 30 Curve Book RNP-F/NFSA-0237, Rev. 0 Appendix A - RNP Cycle 30 Neutronic Curves for Updating Station Curve Book Page A46 of A86 CURVE 1.14 REV. 218 HBR2 CYCLE 30 BORON CONCENTRATION REQUIRED TO MAINTAIN A MINIMUM OF 2.6% SHUTDOWN MARGIN (ARI-MRR) 1700 1500 SHUTDOWN MARGIN BORON (PPM) 1300 1100 900 38 F 700 200 F 300 F 350 F 500 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 22000 CYCLE EXPOSURE (MWD/MTU)

REVIEWS ARE DOCUMENTED ELECTRONICALLY IN THE PRR

Rev. 7 EOPE3 STEAM GENERATOR TUBE RUPTURE Page 47 of 52 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Attachment 3 RCS Pressure And Charging Flow Control Handout (Page 1 of 1)

CAUTION RCS AND Ruptured S/G(s) pressures must be maintained LESS THAN 1060 PSIG.

1. CONTROL RCS Pressure AND Charging Flow To MINIMIZE RCSToSecondary Leakage:

a. PERFORM appropriate action(s) from table below:

RUPTURED S/G(s) LEVEL PZR Level RISING LOWERING OFF SCALE HIGH LESS THAN OR RAISE Charging RAISE Charging RAISE Charging EQUAL TO 27% flow flow flow

[44%] DEPRESSURIZE MAINTAIN RCS RCS using Step 1.c AND Ruptured S/G(s) pressures equal BETWEEN 27% DEPRESSURIZE TURN ON PZR MAINTAIN RCS AND

[44%] AND 50% RCS using Step 1.c Heaters Ruptured S/G(s) pressures equal BETWEEN 50% DEPRESSURIZE TURN ON PZR MAINTAIN RCS AND AND 73% [66%] RCS using Step 1.c Heaters Ruptured S/G(s)

REDUCE Charging pressures equal flow GREATER THAN REDUCE Charging TURN ON PZR MAINTAIN RCS AND OR EQUAL TO flow Heaters Ruptured S/G(s) 73% [66%] pressures equal

b. CHECK Ruptured S/G Pressure b. CONTROL Ruptured S/G LESS THAN 1060 PSIG pressure LESS THAN 1060 psig using Step 1.a.

c. USE Normal PZR Spray as c. IF Letdown is in service, THEN necessary to depressurize RCS USE Aux PZR Spray per per Table in Step 1.a Supplement G, Establishing Aux PZR Spray.

IF Aux PZR Spray is NOT available OR effective, THEN USE one PZR PORV.

- END -

Rev. 15 AOP-026 GRID INSTABILITY Page 18 of 23 ATTACHMENT 1 MAXIMUM GENERATOR MVA OUTPUT vs SYSTEM FREQUENCY (Page 1 of 1)

ATTACHMENT 10.1 Page 12 of 13 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%).

FMP-001 Rev. 31 Page 23 of 25

ATTACHMENT 11.1 Page 1 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Emergency HBRSEP shall notify the NRC of the Declaration of an Unusual Event, Alert, Site Unusual Event declaration of any of the Emergency Classes Area Emergency, or General Emergency.

Alert specified in the Emergency Plan.

Site Area Discovery of an event that should have Emergency (See EPNOT-01) resulted in an Emergency Classification, but General no emergency was declared.

Emergency Discovery that a declared emergency 10 CFR 50.72(a)(i)

ISFSI exceeded the Emergency Action Levels for a 10 CFR 30.32(i)(3)(viii) higher emergency declaration, but the higher 10 CFR 40.31(i)(3)(viii) classification was not declared.

10 CFR 72.75(a)

ERDS ACTIVATION ERDS HBRSEP shall activate the ERDS as soon as An Alert, Site Area Emergency, or General Emergency possible but not later than one hour after Emergency is declared.

declaring an Alert, Site Area Emergency, or General Emergency.

10 CFR 50.72(a)(4)

DEVIATION FROM TS (10 CFR Deviation Any deviation from the TS authorized Intentional deviation from an approved plant 50.54(X)) Departure pursuant to 10 CFR 50.54(x). procedure in order to preserve plant safety 10 License CFR 50.54(x).

10 CFR 50.72(b)(1) Condition AP-030 Rev. 52 Page 16 of 66

ATTACHMENT 11.1 Page 2 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Safety Limit If any safety limit is exceeded, shut down The limits of TS Figure 2.1.1-1 are exceeded.

SYSTEM SETTING EXCEEDED Limiting Safety the reactor. HBRSEP shall notify the NRC System Setting [within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> via ETS per 10 CFR 50.72(a)(1), See Emergency Plan Procedures]. Operation must not be resumed until authorized by the NRC.

10 CFR 50.36(c)(1)(i)(A) NRC Region II must also be notified within 1 UFSAR Section 17.3A, Paragraph hour and the Vice President - Robinson 3.1.a Nuclear Plant within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SAFETY SYSTEM DOES NOT ESF HBRSEP shall notify the NRC if the A failure mechanism is discovered that FUNCTION AS REQUIRED RPS automatic safety system [to correct an indicates that the RPS will not function to trip Limiting Safety abnormal situation before a safety limit is the reactor under certain required conditions.

System Setting exceeded] has been determined not to 10 CFR 50.36(c)(1)(ii)(A) function as required.

AP-030 Rev. 52 Page 17 of 66

ATTACHMENT 11.1 Page 3 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Any discovery of the loss of any shipment of Shipment Emergency Event SNM OR SPENT FUEL SHIPMENT Spent Fuel SNM or spent fuel, and within one hour after Security recovery of or accounting for such lost Safeguards shipment 10 CFR 73.71(a)(1)

THEFT/UNLAWFUL DIVERSION OF Theft of SNM Any event in which there is reason to Shipment Emergency Event SNM Diversion believe that a person has committed or Security caused, or attempted to commit or cause, or Safeguards has made a credible threat to commit or 10 CFR 73.71(b)(1) cause:

10 CFR 73, Appendix G, I(a)(1) (1) A theft or unlawful diversion of SNM SABOTAGE OF PLANT Sabotage [Any event in which there is reason to Shipment Emergency Event EQUIPMENT Damage to Plant believe that a person has committed or Security Event (AD-SY-ALL-0150)

SNM caused, or attempted to commit or cause, or Spent Fuel has made a credible threat to commit or Security cause:]

Safeguards (2) Significant physical damage to a power reactor...or its equipment or carrier equipment transporting nuclear fuel or spent 10 CFR 73.71(b)(1) nuclear fuel, or to the nuclear fuel or spent 10 CFR 73, Appendix G, I(a)(2) fuel a facility or carrier possesses.

• 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)

AP-030 Rev. 52 Page 18 of 66

ATTACHMENT 11.1 Page 4 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Unauthorized [Any event in which there is reason to Security Event (AD-SY-ALL-0150)

WITH PLANT EQUIPMENT Use believe that a person has committed or Tampering caused, or attempted to commit or cause, or Security System has made a credible threat to commit or Safeguards cause:]

(3) Interruption of normal operation of HBRSEP through the unauthorized use of or tampering with its machinery, components, or controls including the 10 CFR 73, Appendix G, I(a)(3) security system.

ENTRY OF UNAUTHORIZED Unauthorized An actual entry of an unauthorized person Security Event (AD-SY-ALL-0150)

PERSON INTO PROTECTED OR Entry into a protected area, material access area, VITAL AREA Security controlled access area, vital area, or 10 CFR 73, Appendix G, I(b) Safeguards transport.

FAILURE, DEGRADATION, OR Degradation Any failure, degradation, or the discovered Procedure AD-SY-ALL-0150 DISCOVERED VULNERABILITY OF Vulnerability vulnerability in a safeguard system that SAFEGUARD SYSTEM Safeguards could allow unauthorized or undetected Unauthorized access to a protected area, material access Undetected area, controlled access area, vital area or Access transport for which compensatory measures 10 CFR 73, Appendix G, I(c) Security have not been employed.

INTRODUCTION OF Contraband The actual or attempted introduction of Contraband applies to items that could be CONTRABAND INTO VITAL OR Unauthorized contraband into a protected area, material used to commit radiological sabotage as PROTECTED AREA Security process area, vital area, or transport. defined in 10 CFR 73.2.

10 CFR 73, Appendix G, I(d) Safeguards

• 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.

AP-030 Rev. 52 Page 19 of 66

ATTACHMENT 11.1 Page 5 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Notwithstanding any other requirements for BYPRODUCT, SOURCE, OR SNM Source notification, immediately notify the NRC of any (5X ANNUAL LIMIT) SNM event involving byproduct, source, or SNM Exposure possessed by HBRSEP that may have caused or Dose threatens to cause any of the following Release conditions:

Occupational 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the 10 CFR 20.2202(a)(1) individual could have received an intake five times the occupational annual limit on intake.

AP-030 Rev. 52 Page 20 of 66

ATTACHMENT 11.1 Page 6 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Intake The release of radioactive material, inside or BYPRODUCT, SOURCE, SNM (>5X Ingestion outside the restricted area, so that, had an OCCUPATIONAL LIMIT) Release individual been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Source individual could have received an intake five times Byproduct the occupational annual limit on intake.

10 CFR 20.2202(a)(2) SNM 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 ISFSI The licensee shall notify the NRC Operations Unusually high radiation readings OR LOSS OF SNM Criticality Center via ETS within one hour of discovery of discovered in the vicinity of the ISFSI that 10 CFR 72.74 SNM accidental criticality or any loss of SNM. could indicate possibility of a criticality Loss 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 HBRSEP shall notify the NRC Operations Center Shipment Emergency Event SHIPMENT OF SNM Loss via the ETS within one hour after discovery of any Security Event (AD-SY-ALL-0150)

SNM loss of any shipment of SNM or spent fuel or any Spent Fuel incident in which an attempt has been made, or is Diversion believed to have been made, to commit a theft or 10 CFR 70.52(b) Safeguards unlawful diversion of SNM.

10 CFR 73.71(a)(1) Security LOST OR UNACCOUNTED Recovery HBRSEP shall notify the NRC Operations Center SHIPMENT OF SNM - RECOVERY Accounting via the ETS within one hour after recovery of, or Shipment accounting for, any lost shipment of SNM.

SNM Security 10 CFR 73.71(a)(1) Safeguards AP-030 Rev. 52 Page 21 of 66

ATTACHMENT 11.1 Page 7 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Degradation (i) any further degradation in the level of Refer to EPNOT-01 Emergency Class safety of the plant or ISFSI or other Change worsening conditions, including those that Update require the declaration of any of the Termination Emergency Classes, if such a declaration ISFSI has not been previously made, or (ii) any change from one Emergency Class 10 CFR 50.72(c)(1) to another, or (iii) a termination of the 10 CFR 72.75(f)(1) Emergency Class.

FOLLOW-UP NOTIFICATION Result (i) the results of ensuing evaluations or Evaluation assessments of plant or ISFSI conditions, Effectiveness (ii) the effectiveness of response or Unknown protective measures taken, and 10 CFR 50.72(c)(2) ISFSI (iii) information related to plant or ISFSI 10 CFR 72.75(f)(2) behavior that is not understood.

FOLLOW-UP NOTIFICATION Open Maintain an open, continuous Refer to EPNOT-01 Continuous communication channel with the NRC 10 CFR 50.72(c)(3) Communication Operations Center upon request by the 10 CFR 50.72.75(f)(3) ISFSI NRC.

AP-030 Rev. 52 Page 22 of 66

ATTACHMENT 11.1 Page 8 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Incident Any incident in which an attempt has been 10 Curies of tritium discovered missing from TRITIUM Theft made or is believed to have been made to the Chemistry Laboratory, and reason exists to Tritium commit a theft of more than 10 curies of suspect that the tritium was stolen Attempt tritium (outside of spent fuel) at any one Security time or more than 100 curies of tritium in 10 CFR 30.55(c) Safeguards one calendar year THEFT/UNLAWFUL DIVERSION OF Incident Any incident in which an attempt has been A source assembly is discovered missing SOURCE MATERIAL Attempt made or is believed to have been made to from a new fuel shipment.

Theft commit a theft or unlawful diversion of more Diversion than 15 pounds of Source Material at any Source one time or 150 pounds of Source Material 10 CFR 40.64(c) Security in any one calendar year Safeguards SHIPPING PACKAGE Contamination Removable radioactive surface New or Spent Fuel Shipment Cask arrives RADIOACTIVELY CONTAMINATED Shipment contamination exceeds the limits of with surface contamination in excess of limits.

10 CFR 20.1906(d)(1) 10 CFR 71.87 SHIPPING PACKAGE EXCEEDING Radiation External radiation levels exceeds of the New or Spent Fuel Shipment Cask arrives EXTERNAL DOSE RATE LIMITS Dose Rate limits of 10 CFR 71.47 with external radiation levels in excess of 10 CFR 20.1906(d)(2) Shipment limits.

AP-030 Rev. 52 Page 23 of 66

ATTACHMENT 11.1 Page 9 of 9 IMMEDIATE (ONE HOUR) NOTIFICATIONS TO THE NRC 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 Alcohol If HBRSEP has a reasonable belief that an DUTY Influence NRC employee or NRC contractor may be Substance under the influence of any substance, or is NRC employee otherwise unfit for duty, the licensee or FFD other entity may not deny access but shall 10 CFR 26.77(c) Fitness for Duty 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 IAEA HBRSEP shall immediately communicate If the IAEA representatives credentials have OFFICIAL International by telephone, within one hour with respect not been confirmed by the NRC, the licensee Atomic to the credentials of any person who claims shall not admit the person until the NRC has Energy to be an IAEA representative and shall confirmed the persons credentials. The Agency accept written or electronic confirmation of licensee, shall notify the Commission 10 CFR 75.8(c) Credential the credentials from the NRC. promptly, by telephone, whenever an IAEA representative arrives at a facility or location without advance notification.

AP-030 Rev. 52 Page 24 of 66

ATTACHMENT 11.2 Page 1 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 Shutdown The initiation of any shutdown required by Reactor is in MODEs 1 or 2 and the TS Shutdown the TS. Control Room takes action to reduce Power power (i.e., negative reactivity insertion)

Reduction 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 10 CFR 50.72(b)(2)(i) 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 ECCS Any event that results or should have Manual or automatic Safety Injection System Actuation resulted in emergency core cooling system actuation in response to a valid signal that Safety (ECCS) discharge into the reactor coolant resulted in or should have resulted in Injection system as a result of a valid signal except discharge into the reactor coolant system.

when the actuation results from and is part of a pre-planned sequence during testing 10 CFR 50.72(b)(2)(iv)(A) or reactor operation.

RPS INITIATION RPS Actuation Any event or condition that results in Manual or automatic reactor trip from critical (MANUAL/AUTOMATIC) Reactor actuation of the reactor protection system through RTP of 100%. Trips which occur as DURING OPERATION Protection (RPS) when the reactor is critical except part of planned evolutions in accordance with System when the actuation results from and is part procedures are not reportable.

RPS of a pre-planned sequence during testing 10 CFR 50.72(b)(2)(iv)(B) Reactor Trip or reactor operation.

AP-030 Rev. 52 Page 25 of 66

ATTACHMENT 11.2 Page 2 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 News Release Any event or situation, related to the health Any News release concerning GOVERNMENT NOTIFICATIONS Press and safety of the public or on-site - A fatality, Radio personnel, or protection of the - Inadvertent release of radioactively Television environment, for which a news release is contaminated materials to public areas Fatality planned or notification to other government - unusual or abnormal releases of radioactive Environment agencies has been or will be made. Such effluents (See Attachment 11.14), or Public an event may include an on-site fatality or - Information associated with an Emergency Health and Safety inadvertent release of radioactively Event except when the ERO is activated Release contaminated materials. (EPNOT-01).

ISFSI Licensees are required to notify the NRC Notification to other government agencies within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of whichever of the following concerning:

occurs first: - A fatality on site,

- A plan to report to either the press or - Health and safety of the public or site another government agency is personnel, approved by an individual authorized to - Inadvertent release of radioactively 10 CFR 50.72(b)(2)(xi) make the final decision, or contaminated materials to public areas, 10 CFR 72.75(b)(2) - A report has actually been made to the - Discovered endangered species kill.

press or another government agency. - Notifications to the National Response Center (EPA) related to Lake Robinson AP-030 Rev. 52 Page 26 of 66

ATTACHMENT 11.2 Page 3 of 3 FOUR HOUR NOTIFICATIONS TO THE NRC 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 Loss Immediately notify the NRC, after its A radiography source is discovered missing. The MATERIAL (>1000X 10 CFR 20 Theft occurrence becomes known, any lost, stolen, source is licensed to the radiography contractor.

LIMITS) Missing or missing licensed material in an aggregate If the contractor does not make the required Licensed quantity equal to or greater than 1,000 times notification, HBRSEP should notify the NRC Radioactive the quantity specified in [10 CFR 20] Operations Center via ETS.

Material Appendix C under such circumstances that it Recovery appears to HBRSEP that an exposure could result to persons in unrestricted areas.

10 CFR 20.2201 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of any subsequent recovery of the source.

ISFSI - DEPARTURE FROM ISFSI An action taken in an emergency that Action taken in an emergency that departs from LICENSE CONDITION Emergency departs from a condition or a technical procedure that is deemed necessary to prevent Departure specification contained in a license or releases or radiation doses to the public in Deviation certificate of compliance issued under excess of 10 CFR 20 limits Health and 10 CFR 72 when the action is immediately (See AD-HU-ALL-0004).

Safety needed to protect the public health and License safety and no action consistent with license Condition conditions or technical specifications that can 10 CFR 72.75(b)(1) provide adequate or equivalent protection is immediately apparent.

AP-030 Rev. 52 Page 27 of 66

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 1 B 2 D 3 C 4 C 5 B 6 B 7 B 8 B 9 D 10 C 11 A 12 D 13 D 14 B 15 A 16 A 17 B 18 B 19 C 20 A 21 B 22 D 23 D 24 D 25 C Printed 2/11/2016 2:50:36 PM Page 1 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 26 A 27 D 28 C 29 B 30 C 31 B 32 B 33 C 34 B 35 B 36 A 37 D 38 D 39 C 40 C 41 B 42 C 43 C 44 C 45 C 46 C 47 B 48 A 49 A 50 D Printed 2/11/2016 2:50:37 PM Page 2 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 51 D 52 C 53 D 54 D 55 C 56 C 57 B 58 B 59 C 60 D 61 A 62 B 63 A 64 B 65 C 66 C 67 D 68 B 69 A 70 A 71 B 72 B 73 A 74 D 75 B Printed 2/11/2016 2:50:37 PM Page 3 of 4

Examination KEY for: ILC15 RNP SRO NRC Examin Question Answer Number 76 A 77 C 78 D 79 B 80 B 81 A 82 C 83 D 84 C 85 A 86 D 87 A 88 C 89 A 90 D 91 C 92 B 93 C 94 A 95 D 96 B 97 D 98 B 99 B 100 B Printed 2/11/2016 2:50:37 PM Page 4 of 4