ML23123A331
| ML23123A331 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/03/2023 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| Download: ML23123A331 (1) | |
Text
L-23-1 NRC EXAM SECURE INFORMATION Page 80 SRO Question # 76 Given the following conditions:
x Unit 3 experiences a small break LOCA.
x 3-EOP-ES-1.2, Post LOCA Cooldown and Depressurization, is in progress.
x Both RHR pumps are stopped.
x RCS pressure is 1500 psig and stable.
x Containment pressure is 6 psig and stable.
Subsequently:
x HHSI pumps flow rises rapidly.
x RCS subcooling is 10°F and lowering.
x Containment pressure is 21 psig and rising.
Which one of the following completes the statements below?
Unit 3 RHR Pumps are (1).
The US NEXT transition is required to be to (2).
A.
(1) expected to AUTOMATICALLY start (2) 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation B.
(1) expected to AUTOMATICALLY start (2) 3-EOP-ES-0.0, Rediagnosis C.
(1) required to be MANUALLY started (2) 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation D.
(1) required to be MANUALLY started (2) 3-EOP-ES-0.0, Rediagnosis ML23123A331
L-23-1 NRC EXAM SECURE INFORMATION Page 81 SRO Question # 77 Given the following conditions:
x Unit 3 is at 100% power and rising.
x ANN H8/6, CCW HEAD TANK HI/LO LEVEL alarms.
x ANN A4/6, VCT HI/LO LEVEL alarms.
x CCW Head Tank level is 0%.
x LI-3-115, VCT level is 81% and rising.
x Tavg is rising slowly.
x Control rods are automatically inserting.
x CCW Surge Tank level stabilizes with MOV-3-832, Component Cooling Water Surge Tank Makeup, fully opened.
Which one of the following completes the statement below?
The US will prioritize the implementation of (1) in order to isolate the (2).
A.
(1) H8/6 from 3-ARP-097.CR.H, Control Room Response - PANEL H (2) Seal Water Return Heat Exchanger B.
(1) H8/6 from 3-ARP-097.CR.H, Control Room Response - PANEL H (2) Non-Regen Heat Exchanger C.
(1) 3-ONOP-047.2, Shutdown of CVCS (2) Seal Water Return Heat Exchanger D.
(1) 3-ONOP-047.2, Shutdown of CVCS (2) Non-Regen Heat Exchanger
L-23-1 NRC EXAM SECURE INFORMATION Page 82 SRO Question # 78 Given the following conditions:
x Unit 3 is at 100% power.
Subsequently:
x Security notifies the SM that adversaries entered the power block and have taken two employees hostage.
x The RO is directed to MANUALLY trip the reactor and the Reactor fails to trip from the control room.
x 3-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS, is in progress.
x ANN B9/4, ROD CONTROL URGENT FAILURE, alarms.
x Reactor Power is 89%.
x CET temperature is 750°F and rising.
Which one of the following completes the statements below?
The EC is required to declare a(an) (1).
The crew is required to dispatch an operator to the (2) to LOCALLY trip the reactor.
REFERENCE PROVIDED A.
(1) Alert (2) 3B MCC B.
(1) Alert (2) 3B Load Center C.
(1) Site Area Emergency (2) 3B MCC D.
(1) Site Area Emergency (2) 3B Load Center
L-23-1 NRC EXAM SECURE INFORMATION Page 83 SRO Question # 79 Given the following:
x Unit 3 experiences a loss of all AC power.
x 3-EOP-ECA-0.0, Loss of All AC Power, is in progress.
x The RO is verifying proper AFW flow.
x NO AFW Pumps are running.
x ALL SG NR Levels are off-scale LOW.
Which one of the following completes the statements below?
The US is required to perform.
A.
3-EOP-FR-H.1, Loss of Secondary Heat Sink, while continuing with 3-EOP-ECA-0.0 B.
3-EOP-FR-H.1, Loss of Secondary Heat sink, and when a Feedwater Source is restored continue with 3-EOP-ECA-0.0 C.
3-ONOP-075, Auxiliary Feedwater System Malfunction, while continuing with 3-EOP-ECA-0.0 D.
3-ONOP-075, Auxiliary Feedwater System Malfunction, and when a Feedwater Source is restored continue with 3-EOP-ECA-0.0
L-23-1 NRC EXAM SECURE INFORMATION Page 84 SRO Question # 80 Given the following:
x Unit 3 is at 100%
Subsequently:
x Unit 3 PRMS Rack loses power.
Which of the following completes the statements below?
The crew is required to monitor containment radiation on (1).
IAW the ODCM, performing a Monitor Tank liquid release in this condition requires that (2).
A.
(1) ARMS RACK (2) at least two independent samples are analyzed B.
(1) ARMS RACK (2) grab samples are taken during the release C.
(1) QSPDS display on VPB (2) at least two independent samples are analyzed D.
(1) QSPDS display on VPB (2) grab samples are taken during the release
L-23-1 NRC EXAM SECURE INFORMATION Page 85 SRO Question # 81 Given the following:
x Unit 4 experiences a reactor trip and safety injection.
x The crew is on the last step of 4-EOP-ECA-1.2, LOCA Outside Containment, with the following conditions:
x 4A Charging Pump is running.
x RCS pressure is 1300 psig and rising.
x PRZ Level is off-scale low.
Which one of the following completes the statement below?
The US is required to transition NEXT to.
A.
4-EOP-ES-0.0, Rediagnosis B.
4-EOP-E-1, Loss of Reactor or Secondary Coolant C.
4-EOP-ES-1.2, Post LOCA Cooldown and Depressurization D.
4-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation
L-23-1 NRC EXAM SECURE INFORMATION Page 86 SRO Question # 82 Given the following:
x The crew is depressurizing All Intact Steam Generators to Inject Accumulators IAW 3-EOP-FR-C.2, Degraded Core Cooling.
Subsequently:
x The STA reports that there is a Red Path on Integrity.
x RCS pressure is 600 psig.
x Steam generator pressures are 500 psig.
Which one of the following describes the NEXT required action directed by the Unit Supervisor?
A.
Continue in 3-EOP-FR-C.2; Secure the SG depressurization when SG pressure is 140 psig B.
Continue in 3-EOP-FR-C.2; Secure the SG depressurization when Accumulator pressure is 140 psig C.
Secure the SG depressurization and then transition to 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition D.
Immediately transition to 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition
L-23-1 NRC EXAM SECURE INFORMATION Page 87 SRO Question # 83 Given the following conditions:
x Unit 4 is in MODE 6.
x The crew commenced rod unlatching.
Subsequently:
x Annunciator I4/6, CNTMT SUMP HI LEVEL, alarms.
x Reactor Cavity water level is 56 feet and lowering.
x 4-ONOP-041.3, Excessive Reactor Coolant System Leakage, is in progress.
Which ONE of the following completes the statement below?
The US is required to transition to (1), in accordance with which the US is required to direct to (2).
A.
(1) 4-ONOP-033.2, Refueling Cavity Seal Failure (2) monitor containment for airborne contamination B.
(1) 4-ONOP-033.2, Refueling Cavity Seal Failure (2) place PAHMS in service C.
(1) 4-ONOP-041.8, Shutdown LOCA [MODE 5 OR 6]
(2) monitor containment for airborne contamination D.
(1) 4-ONOP-041.8, Shutdown LOCA [MODE 5 OR 6]
(2) place PAHMS in service
L-23-1 NRC EXAM SECURE INFORMATION Page 88 SRO Question # 84 Given the following:
x Unit 3 experiences a reactor trip from 100% power.
x The crew is transitioning to 3-EOP-ES-0.1, Reactor Trip Response.
x 3A SG level is 82% NR x 3B SG level is 61% NR x 3C SG level is 72% NR x AFW flow indicates 180 GPM x 3A SG pressure indicates 1100 psig x 3B SG pressure indicates 1160 psig x 3C SG pressure indicates 1100 psig Which one of the following completes the statements below?
3-EOP-F-0 ENCLOSURE 3, CSF F-0.3 Heat Sink, directs to go to (1).
The US (2) required to immediately prioritize implementation of this FRP over the implementation of 3-EOP-ES-0.1.
A.
(1) 3-EOP-FR-H.2, Response to S/G Overpressure (2) is B.
(1) 3-EOP-FR-H.2, Response to S/G Overpressure (2) is NOT C.
(1) 3-EOP-FR-H.3, Response to High Steam Generator Level (2) is D.
(1) 3-EOP-FR-H.3, Response to High Steam Generator Level (1) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 89 SRO Question # 85 Given the following:
x 10:00 am Unit 3 experiences a LOCA from 100% power.
x 10:10 am RCS pressure is 450 psig and lowering.
x 10:10 am CET subcooling is 17°F and lowering.
x 10:10 am Containment pressure is 27 psig and rising slowly.
x 10:10 am CHRRMS read 5 x 10E3 R/hr.
x 10:15 am There is a report of a loud noise in the Aux Building.
x 10:15 am Containment pressure is 21 psig and rapidly lowering.
x 10:16 am ANN X4/1, ARMS HI RADIATION, alarms.
Which one of the following completes the statements below?
The highest classification for this event is (1)
The NRC is required to be notified a MAXIMUM of (2) minutes after the classification.
REFERENCE PROVIDED A.
(1) General Emergency (2) 15 B.
(1) General Emergency (2) 60 C.
(1) Site Area Emergency (2) 15 D.
(1) Site Area Emergency (2) 60
L-23-1 NRC EXAM SECURE INFORMATION Page 90 SRO Question # 86 Given the following:
x Unit 3 is at 100% power.
Subsequently:
x ANN A1/1, RCP THERMAL BARR COOLING WATER HI FLOW, alarms.
x ANN H1/4, PRMS HI RADIATION, alarms.
x R-3-17A, CCW Radiation Monitor, HIGH alarm is lit.
Which one of the following completes the statements below?
MOV-3-626, RCP Thermal Barrier CCW Outlet, (1) expected to AUTOMATICALLY close.
IAW 3-ONOP-041.1, Reactor Coolant Pump Off-Normal, the US is required to direct a (2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A.
(1) is (2) containment entry to verify CCW flows to the RCPs IAW 3-NOP-030, Component Cooling Water System, B.
(1) is (2) shutdown IAW 3-GOP-103, Power Operation to Hot Standby, and secure the affected RCP C.
(1) is NOT (2) containment entry to verify CCW flows to the RCPs IAW 3-NOP-030, Component Cooling Water System, D.
(1) is NOT (2) shutdown IAW 3-GOP-103, Power Operation to Hot Standby, and secure the affected RCP
L-23-1 NRC EXAM SECURE INFORMATION Page 91 SRO Question # 87 Given the following:
x Unit 4 is in MODE 3.
x SRNI indicates 230 cps.
Subsequently, a few minutes later:
x SRNI indicates 500 cps and rising on both channels.
Which one of the following completes the statement below?
US will NEXT direct to borate IAW (1).
IAW 0-ADM-115, Notification of Plant Events, the AOM (2) required to be notified.
A.
(1) 4-ONOP-046.1, Emergency Boration (2) is B.
(1) 4-ONOP-046.1, Emergency Boration (2) is NOT C.
(1) 4-ONOP-046.4, Malfunction of Boron Concentration Control System (2) is D.
(1) 4-ONOP-046.4, Malfunction of Boron Concentration Control System (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 92 SRO Question # 88 Given the following:
Sunday April 2:
x 13:00 3-OSP-50.2A begins for 3A RHR pump.
x 13:30 3A RHR Pump is declared INOPERABLE.
x 13:57 3B RHR Pump is declared INOPERABLE.
x 14:44 Shutdown starts x 15:51 3A RHR Pump is OPERABLE (Note: Risk Informed Completion Time not to be considered)
At 13:57, after the 3B RHR Pump was declared INOPERABLE, Tech Specs require the unit to be in Mode 3 by (1) on Sunday April 2.
At 15:51, after the 3A RHR Pump was declared OPERABLE, Tech Specs require the unit to be in Mode 3 by (2) on Sunday April 9 REFERENCE PROVIDED A.
(1) 19:57 (2) 19:30 B.
(1) 19:57 (2) 19:57 C.
(1) 20:57 (2) 19:30 D.
(1) 20:57 (2) 19:57
L-23-1 NRC EXAM SECURE INFORMATION Page 93 SRO Question # 89 Given the following:
x Unit 3 experienced a LOCA from 100% power. 3-EOP-E-1, Loss of Reactor or Secondary Coolant, is in progress.
Subsequently:
x ANN H 8/6, CCW HEAD TANK HI/LO LEVEL, alarms x ANN H 7/6, CCW SURGE TANK LOW LEVEL, alarms x Containment Recirculation Sump level is 450 inches and rising.
x Containment pressure is 15 psig.
Which of the following completes the statements below?
The US (1) required to transition NEXT to 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation.
The procedure that the crew NEXT transitions from 3-EOP-E-1, is designed to (2).
A.
(1) is NOT (2) protect the containment barrier B.
(1) is NOT (2) protect components needed for recovery C.
(1) is (2) protect the containment barrier D.
(1) is (2) protect components needed for recovery
L-23-1 NRC EXAM SECURE INFORMATION Page 94 SRO Question # 90 Which one of the following completes the statements below?
The TSC is NORMALLY powered from a (1).
IAW PTN EP, Turkey Point Plant Radiological Emergency Plan, as a MINIMUM the TSC is required to be activated for (2) or higher declaration classifications.
A.
(1) VITAL Power Source (2) UNUSUAL EVENT B.
(1) VITAL Power Source (2) ALERT C.
(1) NON-VITAL Power Source (2) UNUSUAL EVENT D.
(1) NON-VITAL Power Source (2) ALERT
L-23-1 NRC EXAM SECURE INFORMATION Page 95 SRO Question # 91 Given the following conditions:
x Unit 4 is in MODE 6 x
Refueling cavity water level is 57 feet 5 inches and stable.
x Preparations for a core off-load are in progress.
x Containment personnel air lock inner and outer doors are open and functional.
x The designated person for the containment personnel air lock door closure is on station.
Which one of the following completes the statements below?
Both SFP heat exchangers and pumps are required to be placed in parallel operation (1).
4-NOP-040.02 ATTACHMENT 3, Minimum Equipment Checklist During Core Shuffle, the SM will direct that Core off-load (2).
A.
(1) prior to core off load (2) is allowed with both personnel air lock doors open B.
(1) prior to core off load (2) will be delayed until a MINIMUM of one personnel air lock door is closed C.
(1) if SFP exceeds 140°F (2) is allowed with both personnel air lock doors open D.
(1) if SFP exceeds 140°F (2) will be delayed until a MINIMUM of one personnel air lock door is closed
L-23-1 NRC EXAM SECURE INFORMATION Page 96 SRO Question # 92 Given the following conditions:
x Both Units are at 100% power.
x Both Units MVAR load suddenly starts fluctuating.
x 3-ONOP-090, Abnormal Generator MW/MVAR Oscillation, is in progress.
Subsequently:
x Unit 3 Main Generator parameters are:
x 22 kV x
880 MWe x
350 MVAR in the LAG x
Hydrogen pressure is 60 psig Which one of the following completes the statements below?
The current MVAR reading (1) within the allowable Main Generator Limits.
If MVAR indication is outside the allowable limit, 0-ADM-211, Emergency and Off-Normal Operating Procedure Usage, (2) allow the use of Attachment 5 of 3-GOP-301, Guidance for Adjusting System Voltage and Main Generator Reactive Load.
REFERENCE PROVIDED A.
(1) is (2) does B.
(1) is (2) does NOT C.
(1) is NOT (2) does D.
(1) is NOT (2) does NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 97 SRO Question # 93 Given the following:
x Unit 3 is in the process of Reactor Vessel Head disassembly for Refueling activities.
x Area Radiation Monitor (ARMS) RD-1402B, 58 Elevation, has a broken dose rate indicator on the local monitor.
IAW 3-OP-038.1, Preparation for Refueling Activities, which one of the following identifies the action necessary to allow the Refueling Supervisor to perform core alterations?
A.
RP survey of the 58 elevation every 15 minutes.
B.
Dedicated operator to constantly monitor Control Room ARMS RD-1402B.
C.
Local indication for ARMS RD-1402B replaced with portable monitor with alarm.
D.
Control Room functions for ARMS RD-1402B verified OPERABLE every 15 minutes
L-23-1 NRC EXAM SECURE INFORMATION Page 98 SRO Question # 94 Which one of the following completes the statements below?
IAW OP-AA-100-1000, Conduct of Operations:
The STA/ WCS (1) required to complete a control board walkdown prior to taking the watch.
The SM (1) required to complete a control board walkdown prior to taking the watch.
A.
(1) is NOT (2) is B.
(1) is NOT (2) is NOT C.
(1) is (2) is D.
(1) is (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 99 SRO Question # 95 Given the following:
x Unit 3 is at 97% power and stable.
x A rod drops into the core.
x 3-ONOP-028.3, Dropped RCC, is in progress.
x QPTR is calculated to be 1.04.
Which one of the following completes the statements below?
QPTR is monitored in the control room on (1), and IAW TS a power reduction to (2) as a MINIMUM is required within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
A.
(1) DCS (2) 85%
B.
(1) DCS (2) 88%
C.
(1) QSPDS (2) 85%
D.
(1) QSPDS (2) 88%
L-23-1 NRC EXAM SECURE INFORMATION Page 100 SRO Question # 96 Which one of the following completes the statements below?
IAW OP-AA-101-1000, Clearance and Tagging:
The responsibility to ensure that required audits are performed on the clearance process resides with the (1).
The (2) is required to authorize a non-safety related component clearance for hanging.
A.
(1) Operations Director (2) OPS WCC supervisor B.
(1) Operations Director (2) Job Supervisor C.
(1) Nuclear Joint Safety Committee (2) OPS WCC supervisor D.
(1) Nuclear Joint Safety Committee (2) Job Supervisor
L-23-1 NRC EXAM SECURE INFORMATION Page 101 SRO Question # 97 Given the following:
x Unit 3 is operating at 100% power.
x It is discovered that 3A EDG monthly surveillance was LAST performed 33 days ago.
Which of the following completes the statements below?
The surveillance interval (2) allowed to be extended by 25% beyond the due date.
A.
(1) is NOT (2) is B.
(1) is NOT (2) is NOT C.
(1) is (2) is D.
(1) is (2) is NOT
L-23-1 NRC EXAM SECURE INFORMATION Page 102 SRO Question # 98 Which one of the following completes the statements below?
In order to approve a liquid release permit IAW 0-NCOP-003, Preparation of Liquid Release Permits, the SM is required to verify that the applicable tank has recirculated for a MINIMUM of (1) hours if pump discharge pressure is less than or equal to 70 psig.
IAW 3-ONOP-067, Radioactive Effluent Release, if a HIGH gas effluent alarm is received during a release, in order to recommence the release Chemistry is required to (2).
A.
(1) 2 (2) resample the affected gas decay tank B.
(1) 2 (2) establish continuous sample collection with auxiliary equipment C.
(1) 4 (2) resample the affected gas decay tank D.
(1) 4 (2) establish continuous sample collection with auxiliary equipment
L-23-1 NRC EXAM SECURE INFORMATION Page 103 SRO Question # 99 Given the following conditions:
x A Steam Generator Tube Rupture has occurred on Unit 3.
x The crew is performing 3-EOP-E-3, Steam Generator Tube Rupture, when a loss of vital instrument bus 3P07 occurs.
In accordance with 0-ADM-211, Emergency and Off-Normal Operating Procedure Usage, which one of the following identifies the use of 3-ONOP-003.7, Loss of 120 Volt Vital Bus 3P07, while performing 3-EOP-E-3?
A.
Continue in 3-EOP-E-3. Perform actions of 3-ONOP-003.7 only after exiting the EOP network.
B.
Stabilize the unit in 3-EOP-E-3. Perform actions to restore 3P07 in accordance with 3-ONOP-003.7 that will not interfere with the actions of 3-EOP-E-3, and then return to 3-EOP-E-3.
C.
At US discretion, perform steps of 3-ONOP-003.7 concurrently with the performance of 3-EOP-E-3 to mitigate both events.
D.
The US must obtain Assistant Operations Manager authorization prior to implementation of any part of 3-ONOP-003.7 while 3-EOP-E-3 is in effect.
L-23-1 NRC EXAM SECURE INFORMATION Page 104Page 104 SRO Question # 100 Which one of the following completes the statements below?
IAW 0-ADM-211, Emergency and Off-Normal Operating Procedure Usage:
The US (1) required to direct all ARP actions before transitioning into an ONOP procedure.
The US (2) required to perform an update when entering an ONOP procedure.
A.
(1) is (2) is B.
(1) is (2) is NOT C.
(1) is NOT (2) is D.
(1) is NOT (2) is NOT
L-23-1 NRC Exam Reference List RO & SRO References Steam Tables SRO Only References EAL Tables PCB Section 4 Figure 2 TS 3.5.2
L-23-1 NRC EXAM SECURE INFORMATION Question #
KEY RO 01 A
RO 02 A
RO 03 D
RO 04 B
RO 05 D
RO 06 B
RO 07 A
RO 08 B
RO 09 D
RO 10 A
RO 11 C
RO 12 B
RO 13 A
RO 14 C
RO 15 D
RO 16 C
RO 17 D
RO 18 B
RO 19 C
RO 20 B
RO 21 A
RO 22 B
RO 23 B
RO 24 D
RO 25 C
RO 26 B
RO 27 A
RO 28 A
RO 29 D
RO 30 D
RO 31 C
RO 32 D
RO 33 A
RO 34 C
RO 35 D
RO 36 D
RO 37 A
RO 38 B
RO 39 D
RO 40 C
RO 41 A
RO 42 B
RO 43 B
RO 44 C
RO 45 D
RO 46 A
RO 47 D
L-23-1 NRC EXAM SECURE INFORMATION RO 48 A
RO 49 D
RO 50 D
RO 51 C
RO 52 B
RO 53 C
RO 54 B
RO 55 D
RO 56 C
RO 57 D
RO 58 D
RO 59 C
RO 60 C
RO 61 A
RO 62 B
RO 63 B
RO 64 B
RO 65 A
RO 66 B
RO 67 C
RO 68 D
RO 69 A
RO 70 B
RO 71 C
RO 72 A
RO 73 C
RO 74 C
RO 75 D
SRO 1 / 76 C
SRO 2 / 77 A
SRO 3 / 78 C
SRO 4 / 79 C
SRO 5 / 80 A
SRO 6 / 81 B
SRO 7 / 82 A
SRO 8 / 83 A
SRO 9 / 84 B
SRO 10 / 85 D
SRO 11 / 86 B
SRO 12 / 87 A
SRO 13 / 88 C
SRO 14 / 89 B
SRO 15 / 90 D
SRO 16 / 91 A
SRO 17 / 92 C
SRO 18 / 93 C
SRO 19 / 94 A
SRO 20 / 95 B
L-23-1 NRC EXAM SECURE INFORMATION SRO 21 / 96 A
SRO 22 / 97 C
SRO 23 / 98 A
SRO 24 / 99 C
SRO 25 / 100 C