ML22318A013

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301 Final RO Written Exam (2 Year Delayed Release)(ADAMS-1A)
ML22318A013
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 11/10/2022
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Download: ML22318A013 (1)
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Question:

(1 point) 1 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Condition:

  • The plant is at 3% RTP
  • Plant startup is in progress IAW GP-003, NORMAL PLANT STARTUP FROM HOT STANDBY TO CRITICAL Current Condition:
  • A failure of the pressurizer pressure Master Controller, PC-444J, results in actual pressure lowering to 2185 psig and continuing to lower Technical Specification (TS) LCO 3.4.1 - RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Which ONE of the following correctly completes the statements below?

Entry into a TS LCO 3.4.1 CONDITION due to the current RCS pressure ____(1)____

required.

If RCS pressure continues to lower, then at a MAXIMUM pressure of ____(2)____

PSIG an automatic reactor trip will occur.

ASSUME NO OPERATOR ACTION A.

(1) is (2) 1715 B.

(1) is (2) 1844 C.

(1) is NOT (2) 1715 D.

(1) is NOT (2) 1844 Page 1 of 75 ML22318A013

Question:

(1 point) 2 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following initial plant conditions:

  • Unit is at 100% Rx Power
  • C SI pump was determined to be inoperable and unavailable, and its control power fuses were removed Current plant conditions:
  • Emergency Bus E-1 is deenergized
  • RCS Subcooling is 0°F Which ONE of the following correctly completes the statements below?

The RCPs are required to be ___________.

A.

tripped to reduce RCS coolant loss B.

tripped to stop RCP pump heat input C.

tripped because RCP motor cooling is lost D.

operated for core heat removal Page 2 of 75

Question:

(1 point) 3 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 9% power

o APP-001-D2, RCP#1 SEAL LEAKOFF HI FLOW o APP-001-C2, RCP#1 SEAL LEAKOFF HI TEMP o APP-001-B2, RCP LABYRINTH SEAL LO P o APP-001-E1, RCP THERM BAR COOL WTR HI TEMP o APP-001-F2, RCP SEAL WATER LO P

  • A RCP #1 Seal Leakoff Flow: 5.8 gpm
  • A RCP Thermal Barrier P: 0 inches
  • B and C RCP #1 Seal Leakoff Flows have lowered slightly Which ONE of the following describes the correct actions to be taken?

GP-006-1, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS EOP-E-0, REACTOR TRIP OR SAFETY INJECTION A.

Trip the A RCP and shutdown the plant IAW GP-006-1 ONLY.

B.

Trip the A RCP and shutdown the plant IAW GP-006-1 while continuing with AOP-018.

C.

Trip the reactor, trip A RCP, and go to EOP-E-0 ONLY.

D.

Trip the reactor, trip A RCP, and go to EOP-E-0 while continuing with AOP-018.

Page 3 of 75

Question:

(1 point) 4 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • The plant is at 50% power
  • All control systems are in normal alignments Subsequently:
  • RCP seal injection flows have lowered to 0 GPM
  • Charging flow has been rising and is currently at 70 GPM
  • CVC-200B, LTDN Orifice is OPEN
  • Letdown temperature downstream of the Regenerative Heat Exchanger has lowered slightly from its steady state value
  • VCT level is lowering
  • PZR level is lowering slowly
  • RCS temperature is stable Which ONE of the following correctly completes the statements below?

There is a leak on the charging line ____(1)____ of the Regenerative Heat Exchanger.

The correct procedure to mitigate this event is ____(2)____.

A.

(1) downstream (2) AOP-003-1, LOSS OF CHARGING OR LETDOWN B.

(1) upstream (2) AOP-003-1, LOSS OF CHARGING OR LETDOWN C.

(1) downstream (2) AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE D.

(1) upstream (2) AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE Page 4 of 75

Question:

(1 point) 5 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 100% RTP
  • PT-444, PZR Pressure, indicates 2220 PSIG and lowering
  • PT-445, PT-455, PT-456, and PT-457 all indicate PZR Pressure is 2250 PSIG and rising slowly
  • PZR control group heaters are full on Which ONE of the following correctly completes the statements below?

The crew will VERIFY immediate operator actions IAW ____(1)____.

The OATC will have to ____(2)____ demand on Pressure Controller PC-444J to restore PZR pressure to its normal band.

AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL AOP-025, RTGB INSTRUMENT FAILURE A.

(1) AOP-019 (2) lower B.

(1) AOP-019 (2) raise C.

(1) AOP-025 (2) lower D.

(1) AOP-025 (2) raise Page 5 of 75

Question:

(1 point) 6 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • An ATWS has occurred and is in progress after exceeding valid trip criteria
  • The RCS Pressure Safety Limit (SL) was momentarily exceeded In accordance with Technical Specifications, which ONE of the following correctly completes the statements below?

Based on the given conditions, operators must restore SL compliance within

____(1)____.

If the RCS Pressure SL was NOT exceeded until after the reactor was tripped, Operators would have to restore SL compliance within ____(2)____.

A.

(1) 30 minutes (2) 5 minutes B.

(1) 60 minutes (2) 5 minutes C.

(1) 30 minutes (2) 15 minutes D.

(1) 60 minutes (2) 15 minutes Page 6 of 75

Question:

(1 point) 7 ILT22 RNP RO NRC Examination Robinson Nuclear Plant The crew is implementing EOP-E-3, STEAM GENERATOR TUBE RUPTURE, due to a tube rupture on the A Steam Generator.

The following conditions currently exist:

  • All RCPs are stopped
  • SG NR Levels:

o A SG: 76%

o B SG: 50%

o C SG: 50%

  • SI has been reset
  • RCS Pressure is 1800 psig and lowering
  • A SG pressure is 1150 psig and slowly rising
  • The crew has just completed Step 7 to CHECK the MSIVs, MSIV Bypass Valves, SG PORVs, and Steam Driven AFW Pump Steam Shutoff Valves - CLOSED.

Which ONE of the following correctly completes the statement in accordance with EOP-E-3?

As the crew continues implementing EOP-E-3, a false RED/ORANGE Path is likely to occur because of the ___________.

A.

sensed AFW flow to A SG B.

current pressure in A SG C.

current RCS pressure D.

SI flow into the A RCS Loop Page 7 of 75

Question:

(1 point) 8 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant was operating at 100% power when a steamline break occurred

Which ONE of the following completes the statement below?

The basis for this CAUTION is to prevent a degradation of system conditions that would require transition to ___________.

A.

FRP-C.2, RESPONSE TO DEGRADED CORE COOLING B.

FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING C.

FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK D.

FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Page 8 of 75

Question:

(1 point) 9 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • RCS average temperature is 540°F and slowly lowering

- S/G "A" is 16% and slowly rising

- S/G "B" is 17% and slowly rising

- S/G "C" is 17% and slowly rising

  • The crew is performing the step in EOP-E-0 to, "Check AFW Pumps - RUNNING" Which ONE of the following correctly completes the statements below?

The SDAFW pump is ____(1)____.

IAW with EOP-E-0, the crew will ____(2)____.

A.

(1) OFF (2) manually start the SDAFW pump B.

(1) OFF (2) check AFW header section valves FULL OPEN C.

(1) ON (2) manually stop the SDAFW pump D.

(1) ON (2) check SDAFW pump discharge valves FULL OPEN Page 9 of 75

Question:

(1 point) 10 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Reactor Power was 100%
  • Based on discussions with offsite grid operations, the Shift Manager announces that an Extended Loss of AC Power (ELAP) does NOT need to be declared Which ONE of the following correctly completes the statement below?

EOP-ECA-0.0 directs operators to expeditiously perform the appropriate electrical load shed. Based on the current conditions, IAW a CAUTION in EOP-ECA-0.0, the applicable Load Shed must be ___________.

A.

completed within 44 minutes of the start of the LOOP event to extend the battery life to allow time for re-energizing battery chargers using a FLEX generator B.

completed within 60 minutes of the start of the LOOP event to extend the battery life to allow time for re-energizing battery chargers using a FLEX generator C.

prioritized since a loss of DC power may occur if the DC Busses are at maximum load AND the Battery Chargers are NOT restarted within 44 minutes of a loss of all AC Power for Batteries A and B D.

prioritized since a loss of DC power may occur if the DC Busses are at maximum load AND the Battery Chargers are NOT restarted within 60 minutes of a loss of all AC Power for Batteries A and B Page 10 of 75

Question:

(1 point) 11 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following conditions:

  • A EDG tripped on start and troubleshooting is in progress
  • Operators have just reset SPDS Current conditions as displayed on SPDS:

Which ONE of the following correctly completes the statements below?

Based on current conditions, the SUBCRITICALITY safety function status tree terminus is ____(1)____.

IAW FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION - ATWS, and based on conditions above, emergency boration will be initiated by opening

____(2)____.

MOV-350, BA TO CHARGING PMP SUCT LCV-115B, EMERG MU TO CHG SUCT A.

(1) ORANGE (2) MOV-350 B.

(1) ORANGE (2) LCV-115B C.

(1) RED (2) MOV-350 D.

(1) RED (2) LCV-115B Page 11 of 75

Question:

(1 point) 12 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The unit is at 100% RTP
  • 7.5 KVA Inverter A faults The crew is implementing AOP-024, LOSS OF INSTRUMENT BUS.

Which ONE of the following correctly completes the statements below?

Instrument Bus 2 will be re-energized from ____(1)____.

During restoration back to the normal power supply, ____(2)____ must be controlled in MANUAL.

A.

(1) MCC-5 (2) B FRV ONLY B.

(1) MCC-8 (2) B FRV ONLY C.

(1) MCC-5 (2) B and C FRVs D.

(1) MCC-8 (2) B and C FRVs Page 12 of 75

Question:

(1 point) 13 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The unit is at 10% power with GP-005, POWER OPERATIONS, in progress
  • The crew is in Section 6.3, Rolling the Turbine
  • Turbine Speed is 0 RPM
  • A battery cell in B battery bank experiences an internal electrical short
  • The B battery short results in a small fire damaging the affected and adjacent battery cells
  • Loss of the B DC Bus Voltage results in a reactor trip Which ONE of the following correctly completes the statements below?

2 minutes after reactor trip, 4KV Bus 4 ____(1)____ energized.

IAW DSP-019, SHUTDOWN FROM THE CONTROL ROOM WITH A FIRE IN THE BATTERY ROOM, Attachment 2, Electrical Operator Actions, DC Control Power can be restored using a safety switch in the ____(2)____.

A.

(1) is (2) 4KV Room B.

(1) is NOT (2) 4KV Room C.

(1) is (2) E1/E2 Room D.

(1) is NOT (2) E1/E2 Room Page 13 of 75

Question:

(1 point) 14 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

If an emergency diesel generator is operating in this condition, cooling water for the diesel will be aligned by which ONE of the following means?

AOP-022, LOSS OF SERVICE WATER EPP-28, LOSS OF ULTIMATE HEAT SINK A.

Alternate CCW cooling IAW EPP-28.

B.

Deepwell Pump D IAW EPP-28.

C.

Lake water through a portable pump IAW AOP-022.

D.

Via a Service Water Booster Pump IAW AOP-022.

Page 14 of 75

Question:

(1 point) 15 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Condition:

  • The crew entered AOP-017, LOSS OF INSTRUMENT AIR, and manually tripped the reactor as air pressure continued to lower Current Conditions:
  • RCS temperature is rising slowly

Which ONE of the following correctly completes the statements below?

With Nitrogen aligned to the Steam Line PORVs, PORV operation is available from the Secondary Control Panel ____(1)____.

IF a local PORV controller at the Secondary Control Panel is controlled in MANUAL, when an operator adjusts the white manual thumbwheel, they are adjusting

____(2)____.

A.

(1) ONLY (2) the PORV lift pressure setpoint B.

(1) ONLY (2) direct PORV valve positioner input C.

(1) OR the Main Control Room (2) the PORV lift pressure setpoint D.

(1) OR the Main Control Room (2) direct PORV valve positioner input Page 15 of 75

Question:

(1 point) 16 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • Reactor power is 58% during a return to power following a refueling outage
  • A grid low frequency condition causes the following annunciator to alarm:

o APP-009-B2, GEN HI EXCITATION TRIP

  • The generator Exciter Field Breaker remains closed
  • The Control Room Supervisor is referring to AOP-026, GRID INSTABILITY Which ONE of the following correctly completes the statement below?

In accordance with APP-009-B2, operators are required to ____(1)____ and the Load Dispatcher ____(2)____ required to be notified of this operation.

A.

(1) place the voltage regulator in manual and LOWER field current (2) is B.

(1) place the voltage regulator in manual and RAISE field current (2) is C.

(1) place the voltage regulator in manual and LOWER field current (2) is NOT D.

(1) place the voltage regulator in manual and RAISE field current (2) is NOT Page 16 of 75

Question:

(1 point) 17 ILT22 RNP RO NRC Examination Robinson Nuclear Plant IAW EOP-ECA-1.2, LOCA OUTSIDE CONTAINMENT, which ONE of the following correctly completes the following statements?

While performing the step to IDENTIFY AND ISOLATE Break, the crew is required to FIRST close the ____(1)____ valves.

The crew is required to monitor for ____(2)____ to determine if the break has been isolated.

A.

(1) SI-870 A & B, BIT OUTLET (2) RCS pressure rising B.

(1) RHR-744 A & B, RHR RETURN TO COLD LEGS (2) RCS pressure rising C.

(1) SI-870 A & B, BIT OUTLET (2) Pressurizer level rising D.

(1) RHR-744 A & B, RHR RETURN TO COLD LEGS (2) Pressurizer level rising Page 17 of 75

Question:

(1 point) 18 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

A LOCA outside Containment occurred The crew is implementing EOP-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION APP-002-A3, RWST HI/LO LVL, is extinguished Current Conditions:

Per EOP-ECA-1.1 Step 5, the CRS directs the OATC to add blended makeup to the RWST using Supplement P, EMERGENCY MAKEUP TO THE RWST Per EOP-ECA-1.1 Step 15, the CRS directs the BOP to establish minimum ECCS flow to remove decay heat by using BIT Outlet Valves SI-870A & B Which ONE of the following choices completes the statements below?

Supplement P will require the OATC to ____(1)____ to direct blended flow from the Boric Acid Blender to the RWST.

EOP-ECA-1.1 will have the BOP close one of the SI-870 valves, then take the other SI-870 valves handswitch to CLOSE and then ____(2)____ when the desired flowrate is achieved.

FCV-113B, Blended Makeup to Charging Pump Suction Valve LCV-115B, Emergency Makeup to Charging Suction A.

(1) open FCV-113B and LCV-115B from the RTGB (2) release the handswitch B.

(1) dispatch an AO to open manual valves in the CCW Heat Exchanger Room (2) release the handswitch C.

(1) open FCV-113B and LCV-115B from the RTGB (2) direct an AO to open the valves breaker D.

(1) dispatch an AO to open manual valves in the CCW Heat Exchanger Room (2) direct an AO to open the valves breaker Page 18 of 75

Question:

(1 point) 19 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • A and B EDGs are powering their respective E-Buses
  • EOP-ES-0.4, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS), is in progress
  • RCS pressure is 1635 psig
  • Pressurizer level is 30%

Subsequently:

  • Prior to depressurizing the RCS, PCV-456, Pressurizer PORV, fails open Which ONE of the following identifies the reason for the initial rapidly rising PZR level indication during this event?

A.

The steam space in the Pressurizer collapses allowing more makeup to be injected immediately into the RCS by the SI Pumps B.

Pressurizer level reference legs flash which results in a rise in indicated level C.

Safety Injection Accumulators inject into the RCS which raises Pressurizer level D.

Reactor upper head region voiding occurs which results in mass transfer from the Reactor Head to the Pressurizer Page 19 of 75

Question:

(1 point) 20 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Unit 2 is operating at 50% power
  • Vacuum Pump B is operating; Vacuum Pump A is not operating
  • APP-036-C7, R24 MONITOR HI has alarmed
  • R-15 (Cond Air Exhaust Monitor) and R-19 (SGBD Rad Monitor) are not in alarm Which ONE of the following correctly completes the statements below?

AOP-035, S/G TUBE LEAK entry conditions ____(1)____ met.

Subsequently, the crew is performing OP-504, CONDENSER AIR REMOVAL, Section 6.5, Using R-15 to Monitor for Low Level Primary to Secondary Leakage, as directed by the applicable procedure, and recorded a stabilized R-15 indication of 24 cpm.

IAW the PRIMARY-TO-SECONDARY LEAK RATE CONVERSION GRAPH, the action required by the determined leak rate is ____(2)____.

REFERENCE PROVIDED A.

(1) are (2) increased monitoring B.

(1) are NOT (2) increased monitoring C.

(1) are (2) a PSAL-1 declaration D.

(1) are NOT (2) a PSAL-1 declaration Page 20 of 75

Question:

(1 point) 21 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • A loss of coolant accident has occurred
  • The operators are transitioning to EOP-ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, from EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT The following plant conditions exist:
  • RCS subcooling is 0°F
  • RVLIS Full Range indicates 35% and lowering
  • RCS Pressure is 1100 psig
  • SI pumps are unavailable Which ONE of the following correctly completes the statements below?

Given the current plant conditions, the crew will transition to ____(1)____.

After the crew commences depressurization of the Steam Generators, the first source of ECCS flow into the RCS will be from ____(2)____.

A.

(1) FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING (2) RHR Pumps B.

(1) FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING (2) SI Accumulators C.

(1) FRP-C.2, RESPONSE TO DEGRADED CORE COOLING (2) RHR Pumps D.

(1) FRP-C.2, RESPONSE TO DEGRADED CORE COOLING (2) SI Accumulators Page 21 of 75

Question:

(1 point) 22 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Unit at 100% power
  • A fire started inside the RTGB, and efforts to extinguish it were unsuccessful Subsequent Conditions:
  • AOP-004, CONTROL ROOM INACCESSIBILITY, was entered
  • All control room actions of AOP-004 were completed
  • The Control Room was evacuated
  • A transition was made to DSP-002, SHUTDOWN WITH A FIRE IN THE CONTROL ROOM / HAGAN ROOM Based on the above conditions what is the procedurally-driven feed source to the steam generators?

A.

Main Feedwater Pump B.

Condensate Pump C.

Motor Driven AFW Pump D.

Steam Driven AFW Pump Page 22 of 75

Question:

(1 point) 23 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • Plant tripped from 100% RTP due to a SGTR in A SG
  • Operators are performing EOP-E-3, STEAM GENERATOR TUBE RUPTURE, Step 23, Check if ECCS Flow Should Be Terminated Current Conditions:
  • RCS Subcooling based on Core Exit T/Cs is 35ºF
  • Total feed flow to S/Gs is 400 gpm
  • RCS pressure is 1000 psig and stable
  • PZR level is 25% and rising Which ONE of the following correctly completes the statements below?

Based on the above conditions, in accordance with EOP-E-3, operators ____(1)____

required to stop SI Pumps.

In accordance with the CAUTION prior to Step 23, the purpose for terminating safety injection when termination criteria are met is to avoid overfilling the ____(2)____.

A.

(1) are (2) pressurizer B.

(1) are (2) ruptured S/G C.

(1) are NOT (2) pressurizer D.

(1) are NOT (2) ruptured S/G Page 23 of 75

Question:

(1 point) 24 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Condition:

  • A plant trip occurred
  • An auto-start of the fire pumps has been received
  • There are no indications of a fire in the CV
  • CV Pressure is 1 psig
  • CV Sump Level is 380 inches and rising
  • Pressurizer pressure and level are stable Which ONE of the following correctly completes the statements below?

The crew will enter procedure ____(1)____.

The procedure requires isolating the leak by closing FP-256 and FP-258 ____(2)____.

AOP-032, RESPONSE TO FLOODING FROM THE FIRE PROTECTION SYSTEM FRP-J.2, RESPONSE TO CONTAINMENT FLOODING FP-256, RCP PA SPRINKLERS & CV HOSE STATIONS OUTSIDE ISOL FP-258, RCP PA SPRINKLERS & CV HOSE STATIONS OUTSIDE ISOL FP-248, ELECTRICAL PEN PA SPRINKLERS SYS UPSTRM ISOL FP-249, ELECTRICAL PEN PA SPRINKLERS SYS UPSTRM ISOL A.

(1) AOP-032 (2) ONLY B.

(1) AOP-032 (2) with FP-248 and FP-249 C.

(1) FRP-J.2 (2) ONLY D.

(1) FRP-J.2 (2) with FP-248 and FP-249 Page 24 of 75

Question:

(1 point) 25 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The crew is at Step 7 to initiate RCS cooldown to cold shutdown, with the following conditions:

o Offsite power is NOT available o Both EDGs are supplying their respective Emergency Busses Which ONE of the following correctly completes the statements below?

The RCS cooldown will be performed with steam dumped via the ____(2)____.

The RCS depressurization will be conducted using ____(1)____.

A.

(1) Steam Dumps (2) Normal PZR Spray B.

(1) S/G PORVs (2) Normal PZR Spray C.

(1) Steam Dumps (2) one PZR PORV D.

(1) S/G PORVS (2) one PZR PORV Page 25 of 75

Question:

(1 point) 26 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Current conditions:

  • EOP-ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS), entered
  • RCS Tavg is 540°F In accordance with EOP-ES-0.3, which ONE of the following correctly completes the statements below?

The MAXIMUM RCS cooldown rate allowed in the RCS cold legs is LESS THAN

____(1)____ in an hour.

At a MINIMUM pressurizer level setpoint of ____(2)____ a manual initiation of safety injection is required.

A.

(1) 50°F (2) 7%

B.

(1) 50°F (2) 14%

C.

(1) 100°F (2) 7%

D.

(1) 100°F (2) 14%

Page 26 of 75

Question:

(1 point) 27 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is in Mode 3
  • APP-003-E2, VCT HI/LO PRESS, has alarmed
  • Actual VCT pressure is 15 psig Which ONE of the following correctly completes the statement below?

If VCT pressure continues to lower, RCP #1 Seal Leakoff flow will ____(1)____, and RCP #2 Seal Leakoff flow will ____(2)____.

A.

(1) lower (2) rise B.

(1) rise (2) lower C.

(1) rise (2) rise D.

(1) lower (2) lower Page 27 of 75

Question:

(1 point) 28 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial conditions:

  • RCS pressure is 340 psig and stable
  • HIC-142, PURIFICATION FLOW, is set at 50% demand
  • PC-145, LP LTDN PRESS controller, is in AUTO Subsequently:
  • HIC-142 demand fails to 100%
  • Attempts to close HCV-142, RHR TO LTDN LINE, from the RTGB using HIC-142 are unsuccessful Which ONE of the following correctly completes the statements below?

In accordance with OP-301, CHEMICAL AND VOLUME CONTROL SYSTEM, the maximum allowed flowrate through the Mixed Bed Demineralizers is ____(1)____.

Closing CVC-204A and/or CVC-204B, LETDOWN LINE ISO, ____(2)____ isolate the flowpath through HCV-142 from RHR to CVCS.

A.

(1) 120 gpm (2) does B.

(1) 140 gpm (2) does NOT C.

(1) 120 gpm (2) does NOT D.

(1) 140 gpm (2) does Page 28 of 75

Question:

(1 point) 29 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Plant startup activities following a refueling outage are in progress
  • The Pressurizer is solid
  • RCP A is running
  • PCV-145, LOW PRESSURE LETDOWN VALVE, has been placed in MANUAL
  • GP-002, COLD SHUTDOWN TO HOT SUBCRITICAL AT NO LOAD TAVG, Section 7.2, Instructions for Plant Heatup Up to 199ºF is in progress Current Conditions:
  • RCS temperature is 143º F and increasing Which ONE of the following correctly completes the statements below?

As the RCS heats up the operators will adjust PCV-145 by pushing the ____(1)____

button to control RCS pressure.

The operators will throttle ____(2)____ to control RCS heat up rate.

A.

(1) down (2) HCV-758, RHR HX DISCH FLOW B.

(1) down (2) FCV-605, RHR HX BYPASS VALVE C.

(1) up (2) HCV-758, RHR HX DISCH FLOW D.

(1) up (2) FCV-605, RHR HX BYPASS VALVE Page 29 of 75

Question:

(1 point) 30 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

Plant is in MODE 4 APP-002-C3, BIT HDR HI PRESS, has been received The crew is performing the APP actions to reduce BIT header pressure Which ONE of the following correctly completes the statements below?

IAW a CAUTION in the APP, the BIT header shall not be vented lower than 50 psig to avoid gas dissolution and minimize the potential for ____(1)____ upon system initiation.

The AO draining the header fully opens SI-963, SI PUMP B DRAIN THROTTLING VALVE, resulting in both Trains of Safety Injection being inoperable. To meet the applicable ITS LCO, ____(2)____ ECCS high head injection subsystem(s) must be restored to OPERABLE status.

A.

(1) water hammer (2) ONE B.

(1) pump cavitation (2) ONE C.

(1) water hammer (2) TWO D.

(1) pump cavitation (2) TWO Page 30 of 75

Question:

(1 point) 31 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

Unit is at 100% RTP Current Conditions:

The station is addressing gradually rising PRT temperature and level due to seat leakage from a pressurizer safety valve as a mitigating action until the unit is removed from service for repairs.

Which ONE of the following correctly completes the statements below?

In accordance with OP-103, PRESSURIZER RELIEF TANK CONTROL SYSTEM, actions to drain the PRT and make up with primary water ____(1)____ allowed to be performed simultaneously.

If the leaking pressurizer safety valve subsequently fails open, the Containment Pressure will begin to rise when the PRT pressure reaches ____(2)____ psig.

A.

(1) are NOT (2) 100 B.

(1) are NOT (2) 120 C.

(1) are (2) 100 D.

(1) are (2) 120 Page 31 of 75

Question:

(1 point) 32 ILT22 RNP RO NRC Examination Robinson Nuclear Plant IAW MST-021, REACTOR PROTECTION LOGIC TRAIN B AT POWER, which ONE of the following correctly completes the statements below?

When testing the B Reactor Protection Logic Train IAW MST-021, B train automatic reactor trip signals are simulated by opening a set of contacts to open the

____(1)____.

IAW MST-021 and ITS LCO 3.3.1, REACTOR PROTECTION (RPS)

INSTRUMENTATION, the B Reactor Trip Bypass Breaker is allowed to be in-service for no more than ____(2)____ continuous hours.

A.

(1) B Reactor Trip Breaker (2) 6 B.

(1) B Reactor Trip Bypass Breaker (2) 6 C.

(1) B Reactor Trip Breaker (2) 12 D.

(1) B Reactor Trip Bypass Breaker (2) 12 Page 32 of 75

Question:

(1 point) 33 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • The plant is at 100% power
  • Operators are in the field executing a clearance on portions of the Instrument Air system in preparation for maintenance
  • Charging Pump A is in service Current Conditions:
  • Valve IA-119, IA TO CHG PUMP B & PEN, was inadvertently closed and tagged Referencing the supplied P&ID, correctly complete the following statements:

TCV-144, NON-REGEN HX OUTLET TEMP will fail ____(1)_____.

The crew is required to ____(2)____.

REFERENCE PROVIDED A.

(1) closed (2) adjust reactor power level via turbine load reduction B.

(1) closed (2) divert letdown to the Hold Up Tank C.

(1) open (2) adjust reactor power level via turbine load reduction D.

(1) open (2) divert letdown to the Hold Up Tank Page 33 of 75

Question:

(1 point) 34 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

The plant is at 90% RTP A power loss occurs that causes the following to be observed:

Which ONE of the following correctly completes the statements below?

The loss of power is ____(1)____.

Pressurizer Spray Valve control is ____(2)____.

A.

(1) Instrument Bus 1 (2) NOT available by any means B.

(1) Instrument Bus 4 (2) NOT available by any means C.

(1) Instrument Bus 1 (2) STILL available by Manual control D.

(1) Instrument Bus 4 (2) STILL available by Manual control Page 34 of 75

Question:

(1 point) 35 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • RPS testing is in progress and Train "A" is in the Test Mode

Reactor Trip Breaker A (RTA) is currently closed Reactor Trip Bypass Breaker A (BYA) has been racked in and closed Reactor Trip Breaker B (RTB) is currently closed Reactor Trip Bypass Breaker B (BYB) is racked out.

Subsequently:

  • S/G "B" Feedwater Regulating valve (FCV-488) fails closed
  • The Reactor Operator MANUALLY trips the reactor as a reactor trip setpoint is being approached Which ONE of the following is correct regarding Reactor Trip Breaker and Bypass Breaker response to the manual reactor trip?

A.

RTA will remain CLOSED.

BYA will OPEN due to the shunt coil energizing ONLY.

RTB will OPEN due to the shunt coil energizing and the under voltage coil deenergizing.

B.

RTA will remain CLOSED.

BYA will OPEN due to the shunt coil energizing ONLY.

RTB will OPEN due to the shunt coil energizing ONLY.

C.

RTA will OPEN due to the shunt coil energizing and the under voltage coil deenergizing.

BYA will OPEN due to the under voltage coil de-energizing ONLY.

RTB will OPEN due to the shunt coil energizing and the under voltage coil deenergizing.

D.

RTA will OPEN due to the under voltage coils de-energizing ONLY.

BYA will remain CLOSED.

RTB will OPEN due to the under voltage coils de-energizing ONLY.

Page 35 of 75

Question:

(1 point) 36 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • The plant is operating at 100% power
  • An inadvertent actuation of the Feedwater Isolation Signal (FWIS) occurs due to the B SG HI-HI Level logic Current Conditions:
  • The EOP network has been exited and GP-004, POST TRIP STABILIZATION, has been entered
  • As part of the GP-004 actions, efforts to establish MFW flow per OP-403, FEEDWATER SYSTEM, are in progress Which ONE of the following correctly completes the statements below?

The Main Turbine ____(1)____ a trip signal directly from the FWIS.

OP-403, Sections 6.9 and 6.10 ____(2)____ allow the Feedwater Isolation Ovrd/Reset key switches to be placed and left in the OVRD/RESET position to support the establishment of feedwater flow on the bypass feed reg valves.

OP-403, Section 6.9, Resetting Feedwater Isolation Signal for Feed Regulating Bypass Valves / Main Feed Pump Trip OP-403, Section 6.10, Resetting Feedwater Isolation Signal for Main Feed Regulating Valves A.

(1) received (2) do B.

(1) received (2) do NOT C.

(1) did NOT receive (2) do D.

(1) did NOT receive (2) do NOT Page 36 of 75

Question:

(1 point) 37 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 100% RTP
  • Service Water Booster Pump (SWBP) A is running Subsequently, the A SW Pump trips Which ONE of the following correctly completes the statements below?

The SWBP is expected to trip when its suction pressure is less than a MAXIMUM of

____(1)____ for a specified time-delay.

In accordance with OP-903, SERVICE WATER SYSTEM, the SWBPs ____(2)____.

A.

(1) 4 psig (2) do not have ANY motor start limitations B.

(1) 12 psig (2) do not have ANY motor start limitations C.

(1) 4 psig (2) are limited to a maximum of 3 starts per hour D.

(1) 12 psig (2) are limited to a maximum of 3 starts per hour Page 37 of 75

Question:

(1 point) 38 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is in MODE 1
  • OP-921, CONTAINMENT AIR HANDLING, Section 6.4.9 Containment Temperature Applicability, is being implemented o Containment temperature is 117°F and very slowly rising Which ONE of the following completes both statements regarding Containment Cooling?

IAW Tech Spec LCO 3.6.6, Containment Spray and Cooling Systems,

____(1)____ fan cooler units are required to be operable.

OP-921 Section 6.4.9, Containment Temperature Applicability contains instructions to provide additional containment cooling by initiating ____(2)____.

A.

(1) TWO (2) CV purge ONLY B.

(1) TWO (2) supplemental HVH cooling by deepwell water injection AND CV purge C.

(1) FOUR (2) CV purge ONLY D.

(1) FOUR (2) supplemental HVH cooling by deepwell water injection AND CV purge Page 38 of 75

Question:

(1 point) 39 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 100% RTP Which ONE of the following correctly completes the statement below?

Sequentially depressing each Containment Spray pushbutton will initiate/actuate

1) CV Isolation Phase A
2) Main Steam Line Isolation A.

NEITHER 1 OR 2 B.

ONLY 1 C.

ONLY 2 D.

BOTH 1 AND 2 Page 39 of 75

Question:

(1 point) 40 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • A LOCA occurred Current Conditions:
  • The crew is implementing EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 9 RNO to manually actuate CV Spray
  • The operator adjusted SI-845C, Spray Additive Tank Throttling Valve, and FIT-949, Spray Additive Flow, now indicates 25 gpm Which ONE of the following correctly completes the statements below?

The current FIT-949 spray additive flow value ____(1)____ acceptable in accordance with EOP-E-0, Step 9 RNO.

This NaOH addition rate to the spray from the RWST ensures the pH value of the solution in the containment sump will be ____(2)____ during the recirculation phase.

A.

(1) is (2) approximately 7 B.

(1) is (2) between 8.5 and 11 C.

(1) is NOT (2) approximately 7 D.

(1) is NOT (2) between 8.5 and 11 Page 40 of 75

Question:

(1 point) 41 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following correctly completes the statements below concerning the Condenser Exhaust Hood Sprays?

Condenser exhaust hood sprays control high exhaust temperatures at ____(1)____

turbine loads.

Spray flow ____(2)____ provided by the head of the CST.

A.

(1) low (2) is B.

(1) high (2) is C.

(1) low (2) is NOT D.

(1) high (2) is NOT Page 41 of 75

Question:

(1 point) 42 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 80% power
  • Core is at EOL A 40% Turbine load rejection occurs.

Which ONE of the following correctly completes the statements below?

Steam Generator PORVs ____(1)____ open.

Steam Generator levels will initially ____(2)____.

A.

(1) will (2) shrink B.

(1) will NOT (2) shrink C.

(1) will (2) swell D.

(1) will NOT (2) swell Page 42 of 75

Question:

(1 point) 43 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Current Conditions:

  • The plant is at 100% power
  • All electrical buses are in their normal alignment Which ONE of the following correctly completes the statements below?

The power supply of Main Feedwater Pump A is ____(1)____.

The power supply of Main Feedwater Pump B is ____(2)____.

A.

(1) 4160 VAC Bus 1 (2) 4160 VAC Bus 4 B.

(1) 4160 VAC Bus 2 (2) 4160 VAC Bus 4 C.

(1) 4160 VAC Bus 2 (2) 4160 VAC Bus 5 D.

(1) 4160 VAC Bus 1 (2) 4160 VAC Bus 5 Page 43 of 75

Question:

(1 point) 44 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The crew has just finished immediate actions of EOP-ECA-0.0, LOSS OF ALL AC POWER
  • The SDAFW pump has tripped
  • S/G NR levels are:

A B

C 6%

15%

8%

Which ONE of the following correctly completes the statements below?

A RED path ____(1)____ exist for the HEAT SINK CSFST.

Under these conditions, AFW flow of ____(2)____ gpm by itself satisfies Heat Sink requirements.

A.

(1) does (2) 300 B.

(1) does NOT (2) 300 C.

(1) does (2) 600 D.

(1) does NOT (2) 600 Page 44 of 75

Question:

(1 point) 45 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following information regarding an important Robinson plant event and associated operating experience/lessons learned:

  • On March 28, 2010, a plant event occurred at Robinson involving fires in electrical equipment, a Reactor trip and subsequent Safety Injection actuation, and an ALERT emergency declaration.
  • During this event, two separate electrical fires occurred approximately four (4) hours apart.

Which ONE of the following correctly completes the below sentences based on the events that occurred during the March 28, 2010, Robinson plant event?

The first fire was caused, in part, by ____(1)____.

The second fire was caused when operators ____(2)____.

A.

(1) a failure of the Unit Auxiliary Transformer (UAT) sudden pressure trip to actuate as designed (2) manually re-closed the output breaker in Bus 4 that feeds Bus 5 (breaker 52/24)

B.

(1) a failure of the Unit Auxiliary Transformer (UAT) sudden pressure trip to actuate as designed (2) manually reset the generator lockout relay C.

(1) a failure of a cable between 4160 V Bus 4 and Bus 5 that did not meet many of the specifications for the design change that installed the cable (2) manually re-closed the output breaker in Bus 4 that feeds Bus 5 (breaker 52/24)

D.

(1) a failure of a cable between 4160 V Bus 4 and Bus 5 that did not meet many of the specifications for the design change that installed the cable (2) manually reset the generator lockout relay Page 45 of 75

Question:

(1 point) 46 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant was operating at 100% RTP
  • An Auxiliary Operator (AO) is performing OP-601, DC SUPPLY SYSTEM, Section 6.10, Shifting In-Service Battery Charger on MCC-A from A to A-1
  • The AO has just performed the step, Close breaker MCC-A (1M) (Feed from Battery Charger 'A-1') and Battery Charger A and A-1 are temporarily aligned supplying MCC-A
  • Battery Charger A is selected to IN SERVICE
  • Battery Charger A-1 is selected to STANDBY Subsequently:
  • The supply breaker to E-1 spuriously opens, there are no bus faults Which ONE of the following correctly completes the statement below?

5 minutes into the event, ___________ is(are) supplying MCC-A.

A.

A Battery B.

Battery Charger A C.

Battery Charger A-1 D.

Battery Chargers A AND A-1 Page 46 of 75

Question:

(1 point) 47 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • Operators have started the B EDG and paralleled it with the E2 bus at a no-load condition for a Maintenance PMT
  • After loading the B EDG to approximately 50%, the operators determine that it is necessary to lower E2 bus voltage
  • Section 6.1.4, EDG B Generator Operation, of procedure OP-604-2, DIESEL GENERATOR B OPERATIONS, directs the operators to UNLOCK AND LOWER the Automatic Voltage Control knob while maintaining a lagging Power Factor In accordance with OP-604-2, which ONE of the following correctly completes the below sentences?

EDG operation in a no-load condition should be minimized in order to ____(1)____.

Based on the given conditions, while the Automatic Voltage Control is lowered, the Generator will ____(2)____ of the reactive load.

A.

(1) prevent damage to the Field Excitation system due to excessive cyclic current caused by reactive load effects during no/low load (<500 kW) conditions (2) assume more B.

(1) prevent damage to the Field Excitation system due to excessive cyclic current caused by reactive load effects during no/low load (<500 kW) conditions (2) shed a portion C.

(1) preclude the potential for fires in the exhaust system and minimize consequence of equipment damage (2) assume more D.

(1) preclude the potential for fires in the exhaust system and minimize consequence of equipment damage (2) shed a portion Page 47 of 75

Question:

(1 point) 48 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The unit is operating at 100% RTP
  • B EDG is paralleled to the grid for surveillance testing
  • B EDG load is stable at 2450 KW Subsequently:
  • A loss of the normal power supply to E-2 occurred
  • B EDG remains running at 900 RPM
  • The crew is attempting to restore power to E-2 from B EDG by implementing OP-604-2, DIESEL GENERATOR B OPERATIONS, Section 6.4.1, Loss of Offsite Power (LOOP) While EDG B is Operating in Parallel with Site Power
  • The Control Room has confirmed that:

o The Blackout Sequencer has stopped o ALL E-2 480 VAC load breakers indicate OFF or STOPPED o The Appendix R isolation switch for breaker 52/27B remains in NORMAL Which ONE of the following correctly completes the statement below?

IAW OP-604-2, the B EDG Output Breaker (52/27B) can be reset from the ________.

A.

RTGB ONLY B.

output breaker ONLY C.

Generator Control Panel ONLY D.

RTGB OR Generator Control Panel OR output breaker Page 48 of 75

Question:

(1 point) 49 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions

  • 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 49 of 75

Question:

(1 point) 50 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is in MODE 3
  • A release is in progress from C Waste Gas Decay Tank
  • R-14C, PLANT VENT LOW RANGE GAS MONITOR, FAIL light illuminates due to low counts Which ONE of the following correctly completes the statements below?

RCV-014, WASTE GAS RELEASE ISOLATION will ____(1)____.

The R-14 Skid ____(2)____ shift to the Intermediate/Mid Range and provide R-14D and R-14E readings on the RTGB.

A.

(1) remain OPEN (2) will B.

(1) remain OPEN (2) will NOT C.

(1) automatically CLOSE (2) will D.

(1) automatically CLOSE (2) will NOT Page 50 of 75

Question:

(1 point) 51 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Condition

  • Plant is at 100% power Current Conditions
  • A loss of off-site power occurs
  • Fifteen seconds later an SI actuation occurs 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 51 of 75

Question:

(1 point) 52 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is at 100% RTP
  • Operating crew notes continued lowering of instrument air header pressure Subsequently, the crew enters AOP-017, LOSS OF INSTRUMENT AIR.

Which ONE of the following correctly completes the statements below?

IAW AOP-017, CRS direction to manually trip the reactor will be provided FIRST at an instrument air header pressure of ____(1)____.

CRS direction to trip the reactor at the pressure identified above is based on potential loss of ____(2)____.

A.

(1) 59 psig (2) Pressurizer Spray Valves B.

(1) 59 psig (2) Feedwater Regulating Valves C.

(1) 79 psig (2) Pressurizer Spray Valves D.

(1) 79 psig (2) Feedwater Regulating Valves Page 52 of 75

Question:

(1 point) 53 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant was operating at 100% RTP

Two minutes into the event, the ___________ Instrument Air Compressors have power available.

A.

A and B B.

A and D C.

B and Primary D.

D and Primary Page 53 of 75

Question:

(1 point) 54 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Robinson operators are performing a shutdown/cooldown in response to a Category 4 Hurricane named LINUS impacting the Carolinas
  • Operators were not able to start any Containment cooling systems after the LOOP Current Conditions:
  • The Shift Manager announces that the eye of Hurricane LINUS is directly over Hartsville
  • Tave is 410°F and lowering
  • Containment pressure is -1.0 psig
  • Containment average air temperature is 116°F Based on current conditions, which ONE of the following describes the status of LCO 3.6.4, CONTAINMENT PRESSURE, and LCO 3.6.5, CONTAINMENT AIR TEMPERATURE?

LCO 3.6.4 LCO 3.6.5 A.

Met Met B.

Met NOT Met C.

NOT Met Met D.

NOT Met NOT Met Page 54 of 75

Question:

(1 point) 55 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • Plant is at 40% RTP
  • The reactor operator notes that the control rod bank overlap requirement of LCO 3.1.6, CONTROL BANK INSERTION LIMITS, is NOT met, but all control rods were observed moving Which ONE of the following correctly completes the statements below?

Based on the conditions above, Technical Specification LCO 3.1.6 requires that within

____(1)____ SDM be verified within limits provided in the COLR -OR-boration to restore SDM to within limits.

Rod Control Bank Overlap ensures acceptable ____(2)____.

A.

(1) 15 minutes (2) shutdown margin B.

(1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) shutdown margin C.

(1) 15 minutes (2) power peaking during control bank motion D.

(1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) power peaking during control bank motion Page 55 of 75

Question:

(1 point) 56 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The Unit is in Mode 6 with core offload in progress
  • AOP-042, LOSS OF SPENT FUEL PIT COOLING, is in progress Which ONE of the following correctly completes the statement below?

When spent fuel pit temperature exceeds ____(1)____, immediate action is required to ____(2)____.

A.

(1) 125°F (2) transfer fuel assemblies back to containment B.

(1) 125°F (2) suspend movement of irradiated fuel assemblies in the fuel storage pool C.

(1) 150°F (2) transfer fuel assemblies back to containment D.

(1) 150°F (2) suspend movement of irradiated fuel assemblies in the fuel storage pool Page 56 of 75

Question:

(1 point) 57 ILT22 RNP RO NRC Examination Robinson Nuclear Plant In accordance with OWP-011, NUCLEAR INSTRUMENTATION (NI), which Nuclear Instruments (NIs) have the ability to BYPASS the reactor trip function via the LEVEL TRIP switch being placed in the BYPASS position?

A.

Source Range ONLY B.

Intermediate Range ONLY C.

Power Range ONLY D.

Source Range and Intermediate Range ONLY Page 57 of 75

Question:

(1 point) 58 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following correctly completes the statement below?

A Core Exit Thermocouple temperature indication of ____(1)____ degrees F indicates that fission product release from the ____(2)____ has likely occurred.

A.

(1) 700 (2) fuel pellet B.

(1) 700 (2) fuel cladding gap C.

(1) 1300 (2) fuel pellet D.

(1) 1300 (2) fuel cladding gap Page 58 of 75

Question:

(1 point) 59 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • A large break LOCA occurred
  • Containment pressure has returned to normal
  • Readings are still elevated on:

o R-11, CV AIR AND PLANT VENT PARTICULATE o R-12, CV AIR AND PLANT VENT RADIOACTIVE GAS Which ONE of the following correctly completes the statement below?

The primary reason for the elevated readings on R-11 and R-12 is increased levels of ____(1)____, which will be removed by the ____(2)____ system.

A.

(1) I-131 (2) Containment Purge B.

(1) I-131 (2) Containment Charcoal Filter C.

(1) Co-60 (2) Containment Purge D.

(1) Co-60 (2) Containment Charcoal Filter Page 59 of 75

Question:

(1 point) 60 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • The plant is in Mode 6
  • Core reload is in progress Current Conditions:
  • A fuel assembly that has previously been in the core is being lifted from the fuel storage rack in the Spent Fuel Pool
  • As the Spent Fuel Bridge starts to traverse to the Upender, a failure of the Spent Fuel Bridge Crane Hoist causes the hoist and the fuel assembly to rapidly lower
  • The fuel assembly makes contact with the fuel rack
  • Bubbles are observed from the assembly Which ONE of the following correctly completes the statements below?

For the event in progress, operators monitor radiation monitor ____(1)____ to determine if an unplanned release may be in progress.

Procedure ____(2)____ directs the control room to direct personnel to assemble at the Spent Fuel Pit landing.

A.

(1) R-21, FUEL HANDLING BUILDING UPPER LEVEL (2) AOP-013, FUEL HANDLING ACCIDENT B.

(1) R-21, FUEL HANDLING BUILDING UPPER LEVEL (2) AOP-005, RADIATION MONITORING SYSTEM C.

(1) R-14C, PLANT EFFLUENT NOBLE GAS-LOW RANGE (2) AOP-013, FUEL HANDLING ACCIDENT D.

(1) R-14C, PLANT EFFLUENT NOBLE GAS-LOW RANGE (2) AOP-005, RADIATION MONITORING SYSTEM Page 60 of 75

Question:

(1 point) 61 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • The unit is at full power
  • ISFSI cask loading is ongoing in the Spent Fuel Pool Current Conditions:
  • The Spent Fuel Crane Operator reports that he has dropped a spent fuel assembly and that bubbles are emerging from it
  • All Radiation Monitors have remained stable, indications are NOT rising Which ONE of the following correctly completes the statements below?

AOP-013, FUEL HANDLING ACCIDENT, will direct the operator to shift the Control Room Ventilation System to the Emergency ____(1)____ position.

In accordance with Section 6.4 of the UFSAR, the Control Room Ventilation System

____(2)____ designed to automatically protect the operators from toxic gases.

A.

(1) Recirculation (2) is B.

(1) Pressurization (2) is C.

(1) Recirculation (2) is NOT D.

(1) Pressurization (2) is NOT Page 61 of 75

Question:

(1 point) 62 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Current Conditions:

  • Unit is at 100% RTP
  • All electrical buses are in their normal alignment The electrical power supply of Condensate Pump A is ____(1)____, and Condensate Pump B is ____(2)____.

A.

(1) 4160 VAC Bus 1 (2) 4160 VAC Bus 4 B.

(1) 4160 VAC Bus 2 (2) 4160 VAC Bus 4 C.

(1) 4160 VAC Bus 1 (2) 4160 VAC Bus 5 D.

(1) 4160 VAC Bus 2 (2) 4160 VAC Bus 5 Page 62 of 75

Question:

(1 point) 63 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following correctly completes the statements below concerning Radiation monitors?

A high radiation alarm on the Control Room Area Monitor R-1 ____(1)____ result in the Control Room Ventilation System automatically shifting to Emergency Pressurization Mode.

A high radiation alarm on the Sampling Room Area Monitor R-6 ____(2)____ result in the Aux Building Charcoal Exhaust Fans automatically starting.

A.

(1) does (2) does B.

(1) does (2) does NOT C.

(1) does NOT (2) does D.

(1) does NOT (2) does NOT Page 63 of 75

Question:

(1 point) 64 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following correctly completes both statements in accordance with GP-003, NORMAL PLANT STARTUP FROM HOT STANDBY TO CRITICAL?

The first data point, Reference Count Rate (CR0), is required to be obtained

____(1)____ Shutdown Bank A and B have been fully withdrawn.

A minimum of ____(2)____ additional data points are required for the inverse count rate ratio (1/M) plot used during the approach to criticality.

A.

(1) before (2) four B.

(1) after (2) four C.

(1) before (2) five D.

(1) after (2) five Page 64 of 75

Question:

(1 point) 65 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given Conditions:

  • The plant shut down 5 days ago for a refueling outage
  • The plant is in Mode 6
  • The Upper Internals have been removed from the reactor vessel
  • Fuel movement has not started
  • Refueling Cavity Water level is 23 feet and 7 inches above the top of the reactor vessel flange Which ONE of the following correctly completes the statements below for the given conditions?

GP-010, REFUELING, requires One RHR Train to be OPERABLE and in operation. A second RHR Train is ____(1)____.

The Source Range Neutron Flux monitors are to be Channel Checked ____(2)_____

IAW with the applicable Operations Surveillance Test (OST).

A.

(1) not required (2) Daily B.

(1) required to be available (2) Daily C.

(1) not required (2) Shiftly D.

(1) required to be available (2) Shiftly Page 65 of 75

Question:

(1 point) 66 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The plant is in MODE 6, moving new fuel into the Reactor Vessel at the end of a scheduled outage In accordance with Technical Specifications, which of the following LCO(s) contain a REQUIRED ACTION statement with a COMPLETION TIME of Immediately?

LCO 3.8.2 is ELECTRICAL POWER SYSTEMS: AC Sources - Shutdown" LCO 3.9.1 is REFUELING OPERATIONS: Boron Concentration LCO 3.9.2 is REFUELING OPERATIONS: Nuclear Instrumentation A.

LCO 3.9.1 ONLY B.

LCO 3.9.2 ONLY C.

LCO 3.8.2 and LCO 3.9.2 ONLY D.

LCO 3.8.2, LCO 3.9.1, and LCO 3.9.2 Page 66 of 75

Question:

(1 point) 67 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following conditions requires ACTION statement entry IAW TS 3.4.3, RCS PRESSURE AND TEMPERATURE (P/T) LIMITS, at the designated operating points?

Assume rates provided are average values over the course of ANY one-hour period.

REFERENCES PROVIDED A.

Heatup Rate of 50oF/hr B.

Heatup Rate of 70oF/hr C.

Cooldown Rate of 50oF/hr D.

Cooldown Rate of 70oF/hr Page 67 of 75

Question:

(1 point) 68 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • Operators are required to position two components in a 200 mrem/hour radiation field
  • The first component requires independent verification (IV)
  • The second component requires concurrent verification (CV) and can be verified in 5 minutes In accordance with AD-HU-ALL-0005, HUMAN PERFORMANCE TOOLS, which ONE of the following correctly completes the statements below?

CV for the first component ____(1)____ satisfy the requirements for IV for ALARA purposes.

CV for the second component ____(2)____ be waived with appropriate supervisor approval and documentation.

A.

(1) can (2) can B.

(1) can (2) cannot C.

(1) cannot (2) can D.

(1) cannot (2) cannot Page 68 of 75

Question:

(1 point) 69 ILT22 RNP RO NRC Examination Robinson Nuclear Plant In accordance with AD-OP-RNP-1001, RNP CONDUCT OF ABNORMAL OPERATIONS, which ONE of the following correctly completes the statements below?

Concurrent use AOPs are contained in a ____(1)____ binder.

EOP Foldout Pages ____(2)____ continue to apply when implementing FRPs associated with YELLOW conditions.

A.

(1) red (2) do B.

(1) white (2) do C.

(1) red (2) do NOT D.

(1) white (2) do NOT Page 69 of 75

Question:

(1 point) 70 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The Plant has been at 100% power for 30 days
  • The crew has been directed to reduce power to 60% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
  • Control Rods are in Manual because Auto is unavailable Which ONE of the following correctly completes the statements below?

To maintain Tavg stable at 60% power for the hour following the power change, control rods will be ____(1)____.

Axial Flux Difference must be controlled by the operator following the downpower due to ____(2)____ concentration changes.

A.

(1) inserted (2) Samarium B.

(1) inserted (2) Xenon C.

(1) withdrawn (2) Samarium D.

(1) withdrawn (2) Xenon Page 70 of 75

Question:

(1 point) 71 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following is the reason for the shape of the Critical Boron Concentration vs. Burnup Curve from the middle of core life until the end of core life?

REFERENCE PROVIDED A.

Power defect B.

Fuel depletion C.

Burnable poisons D.

Samarium buildup Page 71 of 75

Question:

(1 point) 72 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial Conditions:

  • GP-003, NORMAL PLANT STARTUP FROM HOT STANDBY TO CRITICAL, is in progress
  • This is a Xenon-free Middle of Life (MOL) startup
  • Intermediate Range Nuclear Instruments are indicating 1 x 10-8 amps
  • Critical data has just been recorded Current conditions:
  • The Operator at the Controls (OATC) has just withdrawn control rods and established a 0.3 decade per minute (DPM) startup rate (SUR) to raise reactor power to the point of adding heat (POAH)
  • No other reactivity activities are in progress Which ONE of the following correctly completes the statements below?

After the initial rod withdrawal, the OATC ____(1)____ be required to perform additional control rod withdrawal to maintain SUR at 0.3 DPM until the POAH is reached.

Upon reaching the POAH, with no operator action, SUR will ____(2)____.

A.

(1) will (2) rise B.

(1) will (2) lower C.

(1) will not (2) rise D.

(1) will not (2) lower Page 72 of 75

Question:

(1 point) 73 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Given the following:

  • The RCS is solid at 140°F and 75 psig
  • A clearance error results in PZR Backup Group A heaters becoming energized Which ONE of the following correctly completes the statements below?

The FIRST (INITIAL) response is that letdown flow will ____(1)____ as ____(2)____

adjusts.

HCV-142, RHR TO LETDOWN & PURIFICATION FLOW CONTROL PCV-145, LOW PRESSURE LETDOWN PRESSURE CONTROL VALVE (ASSUME NO OPERATOR ACTIONS)

A.

(1) rise (2) HCV-142 B.

(1) rise (2) PCV-145 C.

(1) lower (2) HCV-142 D.

(1) lower (2) PCV-145 Page 73 of 75

Question:

(1 point) 74 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Initial conditions:

  • Operators are holding at 90% RTP for a 30-hour fuel conditioning per Reactor Engineering and Nuclear fuel vendor recommendation
  • All steam plant parameters are stable/in steady-state condition
  • Hotwell temperature is 3°F subcooled Current conditions:
  • Reactor Power is still 90% RTP
  • Condenser Vacuum is unchanged from the initial conditions
  • All steam plant parameters are stable/in steady-state condition
  • Hotwell temperature has lowered, and is now 10°F subcooled Which ONE of the following correctly completes the below sentences?

The Net Positive Suction Head (NPSH) delivered to the suction of the Condensate pumps under the current conditions (10°F subcooled) is ____(1)____ the NPSH at the suction of the Condensate pumps under the initial conditions (3°F subcooled).

The overall steam cycle thermal efficiency under the current conditions (10°F subcooled) is ____(2)____ the overall steam cycle thermal efficiency under the initial conditions (3°F subcooled).

A.

(1) GREATER than (2) LESS than B.

(1) LESS than (2) LESS than C.

(1) GREATER than (2) GREATER than D.

(1) LESS than (2) GREATER than Page 74 of 75

Question:

(1 point) 75 ILT22 RNP RO NRC Examination Robinson Nuclear Plant Which ONE of the following correctly completes the statement below?

At 100% RTP, control room operators directly and continuously monitor RTGB parameters and the ERFIS plant computer to verify conformance with ____(1)____ to ensure ____(2)____.

A.

(1) LCO 3.2.1, Heat Flux Hot Channel Factor (FQ(X,Y,Z))

(2) peak cladding temperature does not exceed 2200F during a design basis LOCA B.

(1) LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR)

(2) peak cladding temperature does not exceed 2200F during a design basis LOCA C.

(1) LCO 3.2.1, Heat Flux Hot Channel Factor (FQ(X,Y,Z))

(2) that control rods are capable of shutting down the reactor with the two highest worth control rods stuck fully withdrawn D.

(1) LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR)

(2) that control rods are capable of shutting down the reactor with the two highest worth control rods stuck fully withdrawn Page 75 of 75

NOTE:

Q P-

  • -IA-346A IDENTIFIED DRAWING):

OR NOT IT AFFECTS THE HIGHLIGHTED PORTIONS OF THE BLACKOUT SAFE-SHUTDOWN ANALYSIS DRAWING (WHETHER ON THE CORRESPONDING APPENDIX R AND STATION CHANGES TO THIS DRAWING MUST ALSO BE INCORPORATED HBR2-11390 SH.22 G-190200 2

10 SH. 9 (G-5)

G-190200 I&SA CONTAINMENT INSIDE IA-229

  • -IA-350B 1*-IA-350 ALLEY PIPE IA-525 33 Q

2 1716 PCV S-12 T

Q 2

SPARE 3054 IA-

  • -IA-350A
  • -IA-351A IA-228 SPARE SYSTEM INSTR. AIR f-IA-667 f-IA-666 IA-3739 IA-244A 1Xf 1X' 244 IA-Q IA-183 2-IA-35

-IA-680 fX 3738 IA-fX

-IA-678 SYSTEM RHR 3762 IA-Q IA-3759 IA-3763 IA-3760 F-96 F

616B PDR 616A PDR F

F-95 IA-3764 Q

3766 IA-PCV-1716 TO IA-236

  • -IA-348A IA-243
  • -IA-348B
  • X IA-3055 1*-IA-351 V12-10 TO IA-3082
  • X IA-267 TO RMS-1 IA-3081
  • X IA-3083 B

615 LT IA-3761 A

615 LT IA-3765 1*-IA-348 TO RC-550 TO FCV-1930A TO FCV-1930B

  • -IA-348C IA-3770 TO WD-1728 IA-238 IA-3769 IA-3056
  • X 1*-IA-349

-AC-235

-AC-233 SH. 1 (B-5) 5379-1484 RHR SYSTEM SH. 1 (B-3) 5379-1484 RHR SYSTEM ALLEY PIPE Q

Q IA-237

  • -IA-349A *X
  • X IA-3057 IA-3058 TO CVC-204B TO CVC-204A TO WD-1721 IA-3069
  • X
  • -IA-349C IA-239 ROOM PUMP CHARGING
  • X PUMP 'B' CHARGING SPEED CONTROL IA-3065 IA-3066 2-IA-35 IA-3897 IA-3896 IA-3893 IA-3895 IA-3894 TO TCV-144 IA-288
  • -IA-347B IA-178
  • -IA-347A 1-IA-347 IA-119 IA-3915 3916 IA-IA-3061
  • -IA-345B 3914 IA-I/P HCV-142 TO IA-3805 POS.

142 HCV-TO IA-3804

  • -IA-345A IA-289 IA-163A
  • X IA-3060 LCV-115B TO I/P HCV-121 POS.

HCV-121 3059 IA-

  • X IA-163
  • -IA-346
  • X IA-3067 IA-3068
  • -IA-346B PUMP 'C' CHARGING SPEED CONTROL
1. SEE SH. 1 FOR NOTES AND REFERENCE DRAWINGS.

TO HCV-758 IA-3913 IA-291

  • -IA-345C TO FCV-605

-IA-698 IA-292 (C-4)

THIS SHEET PANEL INSTRUMENT WASTE DISPOSAL TO FT-1007 (C-4)

THIS SHEET IA-3890 3891 IA-

-IA-693 IA-3889 IA-3888 IA-177

  • -IA-343 IA-3807 IA-180
  • -IA-344 IA-195 IA-3062 IA-3806 TO LT-1001 TO FC-1001 WHT ROOM RHR HX. ROOM 1X*

IA-290 IA-118 1-IA-345

  • -IA-344A 3902 IA-IA-3899 IA-3898 IA-3901 IA-3900

-IA-695 TO LCV-115A TO PCV-117

-IA-694 (C-4)

THIS SHEET IA-479 IA-219 (C-4)

THIS SHEET WET/DRY INDICATOR

  • -IA-347 IA-220 V.C.T. ROOM IA-179 TO WD-1794 TO RC-553 TO RC-516 TO RC-519B TO RC-519A TO WD-1722 1X*
  • -IA-347D
  • -IA-347C IA-3070
  • X
  • -IA-349D
  • X IA-3071
  • X IA-3072
  • X IA-3073 IA-3074
  • X
  • X
  • -IA-349F IA-241
  • -IA-349E IA-240 1*X1 IA-242
  • -IA-348F NOTE 3 IA-249 NOTE 3 IA-248
  • X IA-3080 TO SI-841B TO SI-841A IA-3079
  • X
  • -IA-348E IA-247 1*X1 IA-246 TO CC-739 1-IA-349 TO WD-1723 IA-3077 IA-3078
  • X
  • X IA-419
  • -IA-348D RMS-3 TO TO RMS-2 IA-3084
  • X
  • X IA-420
  • -IA-351B
  • X IA-3085 RMS-4 TO TO FCV-1932B TO FCV-1932A IA-224
  • -IA-351F TO FCV-1931A TO FCV-1931B PIPE ALLEY FT-601 TO IA-3087 ROOM WHT NOTE 3
  • X IA-3088
  • X IA-225 1X*
  • -IA-351E IA-223 1*X1
  • -IA-350C IA-230
  • -IA-350E IA-232 1*X1
  • -IA-350H IA-234
  • -IA-351C 1-IA-351 1-IA-350
  • -IA-350G IA-3101 IA-3104 TO FCV-1933B TO FCV-1934A IA-3105 TO FCV-1934B IA-3102 TO FCV-1935A TO FCV-1935B IA-3103
  • -IA-350F IA-233 IA-231
  • -IA-350D TO FCV-1933A IA-3100
  • X (TYP. 6) 4-IA-31 ATMOS.

F-24A F

'A' COMPRESSOR AIR INSTRUMENT S&CW

-IA-535 D

IA-3107 IA-3106

'A' CONTROL PANEL COMPRESSOR IA-471 A

1718 TS 1706 PI 4-IA-7 IA-235 WD-1786 TO TO WD-1787 IA-3090 IA-3091

  • X IA-226 S&CW

& SEPARATOR 'A' AFTERCOOLER T-52A T

IA-3 fX*

f-IA-338 3-IA-1 IA-1 IA-5

  • X IA-227 3089 IA-1710 PI TO PCV-1014 IA-270 TO V12-8
  • -IA-351D D
  • X SPARE TO RCV-018

'B' CONTROL PANEL COMPRESSOR IA-473

'A' CONTROL PANEL COMPRESSOR 4X3 IA-3112

  • -IA-537 IA-3111 IA-92B IA-3110 NOTE 3 IA-293 1700 PI IA-92

-IA-538 T-51A T

T 51B T-IA-476 RECEIVER AIR INSTRUMENT IA-92A TO WD-1789

  • X 2-IA-11

-IA-341 IA-3852 EV-11052 S

1712 PI 1740 FCV IA-11 IA-12 3-IA-13 AIR DRYER 'B' INSTRUMENT IA-3848 2-IA-11 IA-478 IA-23 3X2 3X2 3X2 IA-24 1702 AE 1702 PT

  • -IA-352 3X2 IA-97 IA-3113 AUX. BUILDING HALLWALL CHARGING PUMP ROOM 2-IA-35
  • X IA-3892 IA-3063 PUMP 'A' CHARGING CONTROL SPEED IA-3064 TO TCV-1628 2-IA-14 SH. 1 (E-2)

G-190200 I&SA SH. 7 (B-1)

G-190200 I&SA SH. 3 (B-3)

G-190200 I&SA-SA RECEIVER SA-5 2-IA-47 SH. 3 (B-2)

G-190200 I&SA-SA RECEIVER 3-SA-146 3-IA-4 IA-18 SA-221 IA-22 IA-477 2-IA-10 2-IA-10 IA-20 IA-3665 1-IA-541 IA-10 1"

3-IA-629 IA-3664 (E-1)

THIS SHEET

-IA-694

-IA-693 3-IA-4 IA-21 SH. 10 (E-1)

G-190200 COMPRESSOR 'D' I&SA-IA 1-IA-340A IA-14A (E-3)

THIS SHEET (F-1)

THIS SHEET (F-3)

THIS SHEET X*

-IA-698

-IA-695 IA-475 IA-14 D

IA-13 1X*

IA-9 T-51C T

1-IA-340B 1-IA-340 4-IA-3 4X3 IA-474 3-IA-2 IA-2 f-IA-339 IA-6

& SEPARATOR 'B' AFTERCOOLER 1721 PI IA-8 1711 PI S&CW

  • -IA-338A IA-4 4-IA-8 IA-472

'B' CONTROL PANEL COMPRESSOR

-IA-536 IA-3108 f-IA-338B B

1718 TS 1713 PI 4-IA-32 ATMOS.

F F-24B

'B' COMPRESSOR AIR INSTRUMENT S&CW IA-3109 D

f-IA-339B

  • -IA-339A IA-7 fX*

T-52B T

IA-3921 IA-3922 COMPRESSED AIR IA-3923 IA-3924 IA-3925 IA-3926 IA-3927 IA-3885 IA-3886 11121 PI 11122 PI IA-3884 IA-3903 IA-3887

  • -IA-692 EV-11051 IA-3851 S

IA-3928

-IA-342 AIR DRYER 'A' INSTRUMENT IA-3849

  • X TO PS-959 FOURTH TITLE DESCRIPTION REV DUKE ENERGY SCALE:

PLANT:

TITLE:

PLANT DWG NO.:

SHT:

QUALITY LEVEL:

ROBINSON NUCLEAR PLANT - UNIT 2 N/A 36 37 EC 291106 EAR 02272218 (CM-12)

INSTRUMENT &

STATION AIR SYSTEM FLOW DIAGRAM G-190200 00002 NON-SAFETY RELATED 5379-00581 5379-00581 EAR 02374569 (CM-12) 38

0 200 400 600 800 1000 1200 1400 1600 1800 0

100 200 300 400 500 600 700 HFP CRITICAL BORON CONCENTRATION (ppmb)

CYCLE BURNUP (EFPD)

Figure 5.2 HFP Critical Boron Concentration vs. Burnup (ARO, Eq. Xe, Eq. Sm; except 0 EFPD is at NoXe, PkSm)

ROBINSON UNIT 2 CYCLE 33 RNP - ROD MANUAL UNIT 2 Rev. 0 11/20/2020 REACTOR OPERATING DATA

ES 4.3, Page 7 of 7 EQUATIONS Q = m cpT N = S/(1 Keff)

Q = m h CR11 Keff1= CR21 Keff2 Q = UAT 1/M = CR1/CRx Q m Nat Circ 3

A = r2 T m Nat Circ 2

F = PA Keff = 1/(1 )

m = Av

= (Keff 1)/Keff W Pump = m P SUR = 26.06/

P = I2R

= eff eff P = IE PA = 3IE

=

+

eff 1 + eff PT = 3IEpf

= 1.0 x 104 sec PR = 3IEsin eff = 0.1 sec1 (for > 0)

Thermal Efficiency = Net Work Out/Energy In DRW tip 2 /avg 2

g(z2 z1) gc

+ (v2 2 v1 2) 2gc

+ (P2 P1) + (u2 u1) + (q w) = 0 P = Poet/

P = Po10SUR(t)

A = Aoet g = 32.2 ft/sec2 gc = 32.2 lbm-ft/lbf-sec2 CONVERSIONS 1 MW = 3.41 x 106 Btu/hr

= (5/9)(32) 1 ftwater 3

= 7.48 gal 1 hp = 2.54 x 103 Btu/hr

= (9/5)() + 32 1 galwater = 8.35 lbm 1 Btu = 778 ft-lbf 1 kg = 2.21 lbm 1 Curie = 3.7 x 1010 dps Form 4.3-1 Generic Fundamental Equations and Conversion Sheet

Examination KEY ILT22 RNP RO NRC Examination Q A Q A Q A Q A 1

C 26 C

51 D

2 D

27 B

52 B

3 D

28 C

53 A

4 A

29 A

54 C

5 D

30 A

55 D

6 B

31 A

56 C

7 D

32 C

57 D

8 C

33 C

58 D

9 B

34 A

59 B

10 D

35 C

60 C

11 B

36 B

61 D

12 B

37 D

62 A

13 A

38 D

63 B

14 B

39 A

64 B

15 D

40 D

65 C

16 A

41 C

66 D

17 B

42 B

67 B

18 D

43 A

68 A

19 D

44 B

69 A

20 B

45 D

70 D

21 D

46 B

71 B

22 D

47 D

72 D

23 B

48 D

73 B

24 D

49 B

74 A

25 D

50 D

75 B

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