ML20282A786

ST-2020-07 Draft Written Exam

ML20282A786
Person / Time
Site:	South Texas
Issue date:	07/29/2020
From:	Greg Werner Operations Branch IV
To:	South Texas
References
Download: ML20282A786 (232)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: STP Date of Exam: July 2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 2 3 3 3 4 3 18 3 3 6

1. 1 Emergency and 2 1 2 1 2 1 9 2 2 4 Abnormal Plant 2 Evolutions 4 4 5 4 6 4 27 5 5 10 Tier Totals 3 2 3 3 2 2 2 3 3 2 3 28 2 3 5 1

2. 1 0 1 1 1 1 1 1 1 1 1 10 1 1 1 3 Plant 2 Systems 4 2 4 4 3 3 4 3 4 3 4 38 4 4 8 Tier Totals

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

• These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

• • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2 Form ES-401-2 ES-401, Page 40 of 52

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

R EK1.06 Knowledge of the operational 74 000007 (EPE 7; BW E02&E10; CE E02) 3.7 Reactor Trip, Stabilization, Recovery / 1 implications of the following concepts as they apply Reactor Trip: relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip S AA2.26 Ability to determine or interpret the 77 000008 (APE 8) Pressurizer Vapor Space 3.4 Accident / 3 following as they apply to a PZR Vapor Space accident: Probable PZR steam space leakage paths other than PORV or code safety R EK3.21 Knowledge of the reasons for the 52 000009 (EPE 9) Small Break LOCA / 3 4.2 following responses as the apply to the Small Break LOCA: Actions contained in the EOPs for a small break LOCA R EK2.02 Knowledge of the interrelations 53 000011 (EPE 11) Large Break LOCA / 3 2.6 between a Large Break LOCA and the following: Pumps R AA1.02 Ability to operate and / or monitor the 45 000015 (APE 15) Reactor Coolant Pump 2.8 Malfunctions / 4 following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC flow): RCP oil reservoir level and alarm indicators R 2.1.19 Ability to use plant computers to 24 000022 (APE 22) Loss of Reactor Coolant 3.9 Makeup / 2 evaluate system or component status.

S 2.4.41 Knowledge of the emergency action 83 000025 (APE 25) Loss of Residual Heat 4.6 Removal System / 4 level thresholds and classifications.

R AA1.05 Ability to operate and / or monitor the 72 000026 (APE 26) Loss of Component 3.1 following as they apply to the Loss of Cooling Water / 8 Component Cooling Water: The CCWS Surge Tank, including level control and level alarms, and radiation alarms.

R AK3.03 Knowledge of the reasons for the 42 000027 (APE 27) Pressurizer Pressure 3.7 Control System Malfunction / 3 following responses as the apply to the PZR PCS Malfunction: Actions contained in EOP for PZR PCS malfunction.

R EK2.06 Knowledge of the interrelations 47 000029 (EPE 29) Anticipated Transient 2.9*

Without Scram / 1 between an ATWS and the following:

Breakers, relays, and disconnects S 2.2.25 Knowledge of the bases in Technical 99 000038 (EPE 38) Steam Generator Tube 4.2 Rupture / 3 Specifications for limiting conditions for operations and safety limits R 2.1.20 Ability to interpret and execute 54 000040 (APE 40; BW E05; CE E05; W E12) 4.6 Steam Line RuptureExcessive Heat procedure steps.

Transfer / 4 R AA2.03 Ability to determine or interpret the 27 000054 (APE 54; CE E06) Loss of Main 4.1 Feedwater /4 following as they apply to a Loss of Main Feedwater (MFW): Conditions and reasons for AFW pump startup R EK3.01 Knowledge of the reasons for the 000055 (EPE 55) Station Blackout / 6 2.7 55 following responses as the apply to the SBO: Length of time for which battery capacity is designed ES-401, Page 41 of 52

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

R G2.1.32 Ability to explain and apply system 000056 (APE 56) Loss of Offsite Power / 6 3.8 4 limits and precautions R AA1.04 Ability to operate and / or monitor the 000057 (APE 57) Loss of Vital AC 3.5 31 Instrument Bus / 6 following as they apply to the Loss of Vital AC Instrument Bus: RWST and VCT valves R AA2.02 Ability to determine and interpret the 000058 (APE 58) Loss of DC Power / 6 3.3* 19 following as they apply to the Loss of DC Power: 125V dc bus voltage, low/critical low, alarm R AA2.06 Ability to determine and interpret the 000062 (APE 62) Loss of Nuclear Service 2.8* 56 Water / 4 following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of SWS flow to a component before that component may be damaged R AA2.08 Ability to determine and interpret the 000065 (APE 65) Loss of Instrument Air / 8 2.9* 73 following as they apply to the loss of instrument air: Failure modes of air-operated equipment R AK1.03 Knowledge of the operational 000077 (APE 77) Generator Voltage and 3.3 25 Electric Grid Disturbances / 6 implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances: Under-excitation AA2.05 Ability to determine or interpret the S following as they apply to Generator Voltage 3.8 90 and Electric Grid Disturbances: Operational status of offsite circuit R EK2.1 Knowledge of the interrelations between 48 (W E04) LOCA Outside Containment / 3 3.5 the (LOCA outside Containment) and the following: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features S EA2.1 Ability to determine or interpret the 4.2 89 (W E11) Loss of Emergency Coolant Recirculation / 4 following as they apply to Loss of Emergency Coolant Recirculation: Facility conditions and selection of appropriate procedures during abnormal and emergency conditions S 2.4.21 Knowledge of the parameters and logic 4.6 78 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

2 3 3 3 4/3 3/3 K/A Category Totals: Group Point Total: 18/6 ES-401, Page 42 of 52

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 Not sampled 000003 (APE 3) Dropped Control Rod / 1 R AK3.08 Knowledge of the 3.1 41 reasons for the following responses as they apply to the (Dropped Control Rod):

Criteria for inoperable control rods 000005 (APE 5) Inoperable/Stuck Control Rod / 1 Not sampled 000024 (APE 24) Emergency Boration / 1 R AA2.02 Ability to determine 3.9 37 and interpret the following as they apply to the Emergency Boration: When use of manual boration valve is needed 000028 (APE 28) Pressurizer (PZR) Level Control R AA1.01 Ability to operate and / 3.8* 23 Malfunction / 2 or monitor the following as they apply to the PZR Level Control Malfunction: PZR level reactor protection bistables 000032 (APE 32) Loss of Source Range Nuclear Not sampled Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Not sampled Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 S AA2.03 Ability to determine 4.2* 86 and interpret the following as they apply to the Fuel Handling Incidents: Magnitude of potential release 000037 (APE 37) Steam Generator Tube Leak / 3 R AK1.02 Knowledge of the 3.5 35 operational implications of the following concepts as they apply to Steam generator Tube Leak: Leak rate versus pressure drop 000051 (APE 51) Loss of Condenser Vacuum / 4 Not sampled 000059 (APE 59) Accidental Liquid Radwaste Release / 9 S 2.4.30 Knowledge of events 4.1 82 related to system operation

/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission operator 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 Not sampled 000061 (APE 61) Area Radiation Monitoring System Alarms Not sampled

/7 ES-401, Page 43 of 52

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000067 (APE 67) Plant Fire On Site / 8 R AK3.04 Knowledge of the 3.3 40 reasons for the following responses as they apply to the plant fire on Site: Actions contained in EOP for plant fire on site 000068 (APE 68; BW A06) Control Room Evacuation / 8 R AK2.01 Knowledge of the 3.9 39 interrelations between the control room evacuation and the following: Auxiliary shutdown panel layout 000069 (APE 69; W E14) Loss of Containment Integrity / 5 S AA2.01 Ability to determine 4.4 94 and interpret the following as they apply to the Loss of Containment Integrity:

Verification of automatic and manual means of restoring integrity 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / Not sampled 4

000076 (APE 76) High Reactor Coolant Activity / 9 S 2.2.38 Knowledge of 4.5 97 conditions and limitations in the facility license.

000078 (APE 78*) RCS Leak / 3 2.2.42 Ability to recognize 3.9 38 R system parameters that are entry-level conditions for Technical Specifications (W E01 & E02) Rediagnosis & SI Termination / 3 R E02 EK1.2 Knowledge of the 3.4 5 operational implications of the following concepts as they apply to the (SI termination):

Normal, abnormal, and emergency operating procedures associated with SI termination.

(W E13) Steam Generator Overpressure / 4 Not sampled (W E15) Containment Flooding / 5 Not sampled (W E16) High Containment Radiation /9 Not sampled (BW A01) Plant Runback / 1 N/A for this design type (BW A02 & A03) Loss of NNI-X/Y/7 N/A for this design type (BW A04) Turbine Trip / 4 N/A for this design type (BW A05) Emergency Diesel Actuation / 6 N/A for this design type (BW A07) Flooding / 8 N/A for this design type (BW E03) Inadequate Subcooling Margin / 4 N/A for this design type (BW E08; W E03) LOCA CooldownDepressurization / 4 R EA2.2 Ability to determine and 3.5 57 interpret the following as they apply to the (LOCA Cooldown and Depressurization):

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 Not sampled ES-401, Page 44 of 52

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

(BW E13 & E14) EOP Rules and Enclosures N/A for this design type (CE A11**; W E08) RCS OvercoolingPressurized Thermal Not sampled Shock / 4 (CE A16) Excess RCS Leakage / 2 N/A for this design type (CE E09) Functional Recovery N/A for this design type (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 N/A for this design type K/A Category Point Totals: 2 1 2 1 2/2 1/2 Group Point Total: 9/4 ES-401, Page 45 of 52

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

R A3.03 Ability to monitor automatic 3.2 62 003 (SF4P RCP) Reactor Coolant operation of the RCP, including: Seal DP Pump R K4.01 Knowledge of CVCS design 2.8 75 004 (SF1; SF2 CVCS) Chemical and feature(s) and/or interlock(s)

Volume Control which provide for the following: Oxygen control in the RCS A2.11 Ability to (a) predict the impacts of the following malfunctions or operations R on the CVCS; and (b) based 3.6 46 on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of IAS R A1.02 Ability to predict and/or monitor 3.3 63 005 (SF4P RHR) Residual Heat changes in parameters (to prevent Removal exceeding design limits) associated with operating the RHR controls including:

RHR Flow rate R K3.01 Knowledge of the effect that a loss or malfunction of the RHRS 3.9 30 will have on the following: RCS R K6.18 Knowledge of the effect of a loss or 006 (SF2; SF3 ECCS) Emergency malfunction on the following will have on 3.6 58 Core Cooling the ECCS: Subcooling Margin indicators 2.2.25 Knowledge of the bases in S Technical Specifications for limiting 4.2 91 conditions for operations and safety limits R K5.02 Knowledge of the operational 3.1 29 007 (SF5 PRTS) Pressurizer implications of the following concepts Relief/Quench Tank as the apply to the PRTS: Method of forming a steam bubble in the PZR R K4.02 Knowledge of CCWS design 2.9 22 008 (SF8 CCW) Component Cooling feature(s) and/or interlock(s) which Water provide for the following: Operation of the surge tank, including the associated valves and controls R K3.02 Knowledge of the effect that a loss 4.0 21 010 (SF3 PZR PCS) Pressurizer or malfunction of the PZR PCS Pressure Control will have on the following: RPS R K2.01 Knowledge of bus power supplies 3.3 33 012 (SF7 RPS) Reactor Protection to the following: RPS channels, components, and interconnections R G2.1.28 Knowledge of the purpose and 4.1 20 function of major system components and controls ES-401, Page 46 of 52

ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

2.2.42 Ability to recognize system 013 (SF2 ESFAS) Engineered R parameters that are entry-level conditions 3.9 69 Safety Features Actuation for Technical Specifications.

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations 4.7 88 S on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rapid depressurization R K1.01 Knowledge of the physical 022 (SF5 CCS) Containment Cooling connections and/or cause-effect 3.5 34 relationships between the CCS and the following systems: SWS/cooling system A4.05 Ability to manually operate and/or R monitor in the control room: Containment readings, of temperature, pressure, and 3.8 18 humidity.

N/A for this design 025 (SF5 ICE) Ice Condenser S A2.08 Ability to (a) predict the impacts of 026 (SF5 CSS) Containment Spray the following malfunctions or operations 3.7 87 on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray, when it can be done.

2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand R how operator actions and directives affect 4.2 49 plant and system conditions R K1.02 Knowledge of the physical 3.3 17 039 (SF4S MSS) Main and Reheat connections and/or cause-effect Steam relationships between the MRSS and the following systems: atmospheric relief dump valves AA2.03 Ability to (a) predict the impacts of 3.4 59 R the following malfunctions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Indications and alarms for main steam and area radiation monitors (during SGTR)

ES-401, Page 47 of 52

ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

R K1.04 Knowledge of the physical 3.4 36 059 (SF4S MFW) Main Feedwater connections and/or cause-effect relationships between the MFW and the following systems: S/Gs water level control system R K3.01 Knowledge of the effect that a loss 4.4 16 061 (SF4S AFW) or malfunction of the AFW system Auxiliary/Emergency Feedwater will have on the following: RCS A3.02 Ability to monitor automatic 4.0 15 R operation of the AFW, including: RCS cooldown during AFW operations R K4.10 Knowledge of ED AC design 3.1 26 062 (SF6 ED AC) AC Electrical feature(s) and/or interlock(s) which Distribution provide for the following: Uninterruptible power sources.

S G2.2.40 Ability to apply Technical 4.7 95 Specifications for a system.

R A1.01 Ability to predict and/or monitor 2.5 14 063 (SF6 ED DC) DC Electrical changes in parameters associated with Distribution operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate R K6.07 Knowledge of the effect of a loss or 2.7 32 064 (SF6 EDG) Emergency Diesel malfunction on the following will have on Generator the EDG: Air receivers 2.2.37 Ability to determine operability S and/or availability of safety related 4.6 92 equipment R K5.03 Knowledge of the operational 2.9* 67 073 (SF7 PRM) Process Radiation implications as they apply to concepts for Monitoring the PRM system: Relationship between radiation intensity and exposure limits R A2.02 Ability to (a) predict the impacts of 2.7 13 076 (SF4S SW) Service Water the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure R K2.01 Knowledge of bus power supplies 2.7 71 078 (SF8 IAS) Instrument Air to the following: Instrument air compressor R A3.01 Ability to monitor automatic 3.9 12 103 (SF5 CNT) Containment operation of the CNT system, including:

Containment isolation R A4.03 Ability to manually operate and/or monitor in the control room: ESF slave 2.7 64 relays N/A for this Design 053 (SF1; SF4P ICS*) Integrated Control ES-401, Page 48 of 52

ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

3 2 3 3 2 2 2 3/2 3 2 3/3 K/A Category Point Totals: Group Point Total: 28/5 ES-401, Page 49 of 52

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive R K5.97, Knowledge of the following 3.3 11 operational implications as they apply to the CRDS: Relationship of Tave to Tref.

002 (SF2; SF4P RCS) Reactor Not sampled Coolant 011 (SF2 PZR LCS) Pressurizer R A2.03 Ability to (a) predict the impacts of Level Control the following malfunctions or operations 3.8 44 on the PZR LCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level 014 (SF1 RPI) Rod Position S 2.2.12 Knowledge of surveillance 4.1 93 Indication procedures 015 (SF7 NI) Nuclear Not sampled Instrumentation 016 (SF7 NNI) Nonnuclear R K1.12 Knowledge of the physical 3.5* 10 Instrumentation connections and/or cause effect relationships between the NNI system and the following systems: S/G 017 (SF7 ITM) In-Core Temperature R A4.02 Ability to manually operate and/or 3.8 60 Monitor monitor in the control room: Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values) 027 (SF5 CIRS) Containment Iodine Not sampled Removal 028 (SF5 HRPS) Hydrogen R 2.4.6 Knowledge of EOP mitigation 3.7 61 Recombiner and Purge Control strategies.

029 (SF8 CPS) Containment Purge Not sampled 033 (SF8 SFPCS) Spent Fuel Pool Not sampled Cooling 034 (SF8 FHS) Fuel-Handling S A2.01 Ability to (a) predict the impacts of Equipment the following malfunctions or operations 4.4 98 on the FHS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Dropped fuel element 035 (SF 4P SG) Steam Generator R K6.02 Knowledge of the effect of a loss or 3.1 9 malfunction on the following will have on the S/GS: secondary porv 041 (SF4S SDS) Steam R K3.04 Knowledge of the effect that a loss 3.5 8 Dump/Turbine Bypass Control or malfunction of the SDS system will have on the following: Reactor Power 045 (SF 4S MTG) Main Turbine Not sampled Generator 055 (SF4S CARS) Condenser Air Not sampled Removal ES-401, Page 50 of 52

ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

056 (SF4S CDS) Condensate Not sampled 068 (SF9 LRS) Liquid Radwaste S A2.04 Ability to (a) predict the impacts of 3.3 96 the following malfunctions or operations on the LRS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation 071 (SF9 WGS) Waste Gas R K4.04 Knowledge of the design features 2.9 2 Disposal and/or interlocks which provide for the following: Isolation of waste gas release tanks 072 (SF7 ARM) Area Radiation R A3.01 Ability to monitor automatic 2.9 7 Monitoring operation of the ARM system, including:

Changes in ventilation alignment 075 (SF8 CW) Circulating Water Not sampled 079 (SF8 SAS**) Station Air Not sampled 086 Fire Protection R A1.03 Ability to predict and/or monitor 3.0 6 changes in parameters to prevent exceeding design limits associated with operating the Fire Protection System controls, including: Fire water storage tank level 050 (SF 9 CRV*) Control Room N/A until rev3 of KA catalogs Ventilation K/A Category Point Totals: 1 0 1 1 1 1 1 1/2 1 1 1/1 Group Point Total: 10/3 ES-401, Page 51 of 52

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-only IR # IR #

68 2.1.40 Knowledge of refueling administrative requirements. 2.8 3.5 66 2.1.21 Ability to verify the controlled procedure copy

1. Conduct of Knowledge of individual licensed operator responsibilities 3.8 85 Operations 2.1.4 related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Knowledge of procedures and limitations involved in core 4.1 84 2.1.36 alterations Subtotal 2 2 1

2.2.3 Knowledge of the design, procedural, and operational 3.8 differences between units 3.0 3 2.2.6 Knowledge of the process for making changes to

2. Equipment procedures Control 2.9 51 2.2.7 Knowledge of the process for conducting special or infrequent tests 2.2.19 Knowledge of maintenance work order requirements 3.4 80 2.2.21 Knowledge of pre- and post-maintenance operability 4.1 100 requirements Subtotal 3 2 Ability to use radiation monitoring systems, such as fixed 2.9 28 2.3.5 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Ability to comply with radiation work permit requirements 3.5 65 2.3.7

3. Radiation during normal or abnormal conditions Control Knowledge of radiological safety procedures pertaining to 3.8 81 2.3.13 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Subtotal 2 1 Knowledge of EOP mitigation strategies. 3.7 50 2.4.6 Knowledge of low power/shutdown implications in accident 3.8 70 2.4.9 (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4. Emergency Procedures/Plan Ability to verify that the alarms are consistent with the plant 4.2 43 2.4.46 conditions.

Knowledge of SRO responsibilities in emergency plan 4.5 79 2.4.4 implementation.

Knowledge of the operational implications of EOP warnings, 4.3 76 2.4.20 cautions, and notes.

Subtotal 3 2 Tier 3 Point Total 10 10 7 7 ES-401, Page 52 of 52

ES-401 Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Reason for Rejection Selected K/A 1/1 APE 26 AA1.03 This KA tests the ability to operate and / or monitor the RO following as they apply to the Loss of Component Cooling Water: SWS as a backup to the CCWS. Essential Cooling Water does not act as a backup to Component Cooling Water at STP. Therefore, this KA was replaced with APE 26 AA1.05.

1/1 APE 27 AK3.01 This KA tests the knowledge of the reasons for the following RO responses as they apply to the PZR PCS Malfunction:

Isolation of PZR spray following loss of PZR heaters. This is neither an automatic feature nor an operator response if this occurs. Therefore, this KA was replaced with APE 27 AK3.03.

2/1 004 A2.20 This KA tests the ability to (a) predict the impacts of the RO following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or predations: Shifting demineralizer while the divert valve is lined up to VCT. When shifting demineralizers at STP, flushing to the RHUT is always accomplished first. There is no guidance when this is not done correctly. Therefore, this KA was replaced with 004 A2.11.

2/1 022 A4.03 This KA tests the ability to manually operate and/or monitor in RO the control room: Dampers in the CCS. We do not operate any RCFC dampers in the control room. Therefore, this KA was replaced with 022 A4.05.

2/1 062 K4.03 This KA tests the knowledge of ED AC design feature(s) and/or RO interlock(s) which provide for the following: Interlocks between automatic bus transfer and breakers. STP does not use automatic bus transfer devices. Therefore, this KA was replaced with 062 K4.10.

2/2 001 K5.12 This KA tests the knowledge of the following operational RO implications as they apply to the CRDS: Effects on power of inserting axial shaping rods. STP does not use axial shaping rods. Therefore, this KA was replaced with 001 K5.97.

2/1 006 K3.02 Changed to system 005 K3.01 because the program office is RO changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

2/1 013 K1.18 Changed to system 022 K1.01 because the program office is RO changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

ES-401, Page 53 of 52

Tier/Group Randomly Reason for Rejection Selected K/A 2/1 061 G2.2.40 Changed to system 062 G2.2.40 because the program office is SRO changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

2/1 026 A2.07 This KA tested the ability to predict the loss of CS pump SRO suction, possibly caused by clogged sump screen, pump inlet high temperature exceeded, cavitation, voiding, or sump level below cutoff (interlock) limit, and use a procedure to correct, control, or mitigate the consequences. STP does not have procedural guidance for these malfunctions on CS pump operation. Therefore, this KA was replaced with 026 A2.08.

2/2 034 A2.02 This KA tested the ability to predict the consequences of a SRO dropped cask, and use a procedure to correct, control, or mitigate the consequences. STP does not analyze for a dropped cask since a single failure proof crane is used.

Therefore, this KA was replaced with 034 A2.01.

ES-401, Page 54 of 52

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2883 Last used on an NRC exam: Never RO Sequence Number: 1

______(1)______ is responsible for making up to the ECW Pond and _____(2)____ is responsible for making up to the Main Reservoir.

A. (1) Unit 1 (2) Unit 1 B. (1) Unit 1 (2) Unit 2 C. (1) Unit 2 (2) Unit 1 D. (1) Unit 2 (2) Unit 2 Answer: B (1) Unit 1 (2) Unit 2 Page 1 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2883 Source: New Modified from K/A Catalog Number: G2.2.3 Knowledge of the design, procedural, and operational differences between units.

RO Importance: 3.8 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 203.21 Objective Number: 32403 Given a list of plant procedural differences, evaluate and explain any resulting operational differences

Reference:

LOT 203.21 Student Handout, page 3 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion over unit responsibilities.

B: CORRECT: Unit 1 personnel makeup to the ECW pond, Unit 2 personnel operate the RMPF.

C: INCORRECT: Plausible with confusion over unit responsibilities.

D: INCORRECT: Plausible with confusion over unit responsibilities.

Question Level: F Question Difficulty 2 Justification:

The student must know the differences in operations between the units.

Page 2 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2919 Last used on an NRC exam: Never RO Sequence Number: 2 In the GWPS, if _____(1)_____ Radiation Monitor, is in HIGH alarm, then the Bellows Compressor __________(2)__________.

A. (1) RT-8031, GWPS Inlet (2) starts B. (1) RT-8031, GWPS Inlet (2) trips C. (1) RT-8032, GWPS Outlet (2) starts D. (1) RT-8032, GWPS Outlet (2) trips Answer: D (1) RT-8032, GWPS Outlet (2) trips Page 3 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2919 Source: New Modified from K/A Catalog Number: 071 K4.04 Waste Gas Disposal: Knowledge of the design features and/or interlocks which provide for the following: Isolation of waste gas release tanks.

RO Importance: 2.9 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(13)

STP Lesson: LOT 203.14 Objective Number: 91649 Discuss the following operations (general): A. System Startup, B. System Shutdown, C. Abnormal Conditions.

Reference:

LOT 203.14 Student Handout, page 4 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion over the two radiation monitors in the system and with confusion over the function of the bellows compressor.

B: INCORRECT: Plausible with confusion over the two radiation monitors in the system. The bellows compressor does trip.

C: INCORRECT: Plausible as RT-8032, the outlet GWPS radiation monitor is correct and with confusion over the function of the bellows compressor.

D: CORRECT: When RT-8032, the outlet GWPS radiation monitor goes into HIGH alarm, the bellows compressor trips.

Question Level: F Question Difficulty 3 Justification:

The student must recall interlocks between the outlet radiation monitor and system shutdown features.

Page 4 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 790 Last used on an NRC exam: 2018 RO Sequence Number: 3 A Field Change (FC) is being written against a Plant Operating Procedure that does NOT require review by the Plant Operations Review Committee (PORC).

In accordance with 0PAP01-ZA-0102, Plant Procedures, when is the FC considered Effective?

As soon as it is approved by the A. Plant Manager.

B. Cognizant Manager.

C. Technical Reviewer.

D. Senior Reactor Operator.

Answer: D Senior Reactor Operator Page 5 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 790 Source: Bank Modified from K/A Catalog Number: G2.2.6 Knowledge of the process for making changes to procedures.

RO Importance: 3.0 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 507.01 Objective Number: 92183 Given the title of an administrative procedure, IDENTIFY the individuals (by job title) with specific responsibilities in the procedure.

Reference:

0PAP01-ZA-0102, Step 22.3.4 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible because if the procedure was required to be reviewed by PORC then the final signature would come from the Plant Manager.

B: INCORRECT: Plausible because the cognizant manager must give concurrence to the FC preparer and sign Form 7. This is done before it is sent for approval.

C: INCORRECT: Plausible because the Technical Reviewer is required to sign the FC but the FC is not effective until signed by the SRO.

D: CORRECT: The SRO approves the field change and this is when it is effective.

Question Level: F Question Difficulty 2 Justification:

Student must have fundamental knowledge of the plant procedure for field changes.

Page 6 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2881 Last used on an NRC exam: Never RO Sequence Number: 4 A loss of offsite power has occurred in the unit.

The crew is performing 0POP05-EO-ES02, Natural Circulation Cooldown.

While performing this procedure, CRDM fans are required to be in service in order to prevent

____(1)____.

If CRDM fans are NOT available, the crew is required to cooldown the RCS at a _____(2)_____

rate.

A. (1) damage to the CRDM coils (2) greater B. (1) damage to the CRDM coils (2) lower C. (1) voiding in the reactor vessel upper head (2) greater D. (1) voiding in the reactor vessel upper head (2) lower Answer: D (1) voiding in the reactor vessel upper head (2) lower Page 7 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2881 Source: New Modified from K/A Catalog Number: APE 056 G2.1.32 Loss of Offsite Power: Ability to explain system limits and precautions RO Importance: 3.8 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.25 Objective Number: 92234 Given a copy of a step from 0POP05-EO-ES02, state/identify how the action is performed and the basis for the action to include the action itself, its purpose, and the result.

Reference:

0POP05-EO-ES02, Note prior to Step 18, Step 18 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as fans do serve this purpose but not the reason here and if the student believes without fans, getting to lower temperatures in the RCS faster would be better.

B: INCORRECT: Plausible as fans do serve the purpose but not the reason here and a lower rate is desirable.

C: INCORRECT: Plausible as this is the correct reason why CRDM fans are desired and if the student believes without fans, getting to lower temperatures in the RCS faster would be better.

D: CORRECT: CRDM fans are desired to cool the upper head and prevent voiding. With none running, cooldown rate must be kept below 70F with checks made for upper head voiding and steps to remedy.

Question Level: F Question Difficulty 3 Justification:

The student must recall procedural requirements.

Page 8 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2891 Last used on an NRC exam: Never RO Sequence Number: 5 A Small Break LOCA has occurred in the unit.

Containment pressure is 6.0 psig and lowering.

RCS Subcooling is 48ºF and rising.

RCS pressure is 1815 psig and rising.

SG NR levels are all 31% and rising slowly.

AFW flow is 200 gpm to EACH SG.

Pressurizer level is 23% and rising.

The crew is performing 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, and determining if SI can be terminated.

SI termination criteria will be met when A. Pressurizer level rises above 44%.

B. SG levels rises above 34% NR.

C. RCS pressure exceeds 1857 psig.

D. Subcooling rises above 55ºF.

Answer: A Pressurizer level rises above 44%.

Page 9 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2891 Source: New Modified from K/A Catalog Number: E02 EK1.2 SI Termination: Knowledge of the operational implications of the following concepts as they apply to the SI Termination: Normal, abnormal, and emergency operating procedures associated with SI termination.

RO Importance: 3.4 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 504.09 Objective Number: 81187 DISCUSS the indications available to determine plant status during a loss of primary or secondary coolant accident.

Reference:

0POP05-EO-EO10, Step 15 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: With current containment conditions (adverse above 5 psig containment pressure),

bracketed values in the EOPs must be used so 44% pressurizer level is required to terminate SI in 0POP05-EO-ES11.

B: INCORRECT: Plausible because adverse containment conditions exist and 34% SG level is required as a bracketed value in the EOPs, but adequate AFW flow is established which is an alternative to the bracketed SG level value.

C: INCORRECT: Plausible as this is the value that SI actuates but is above the RCS pressure for SI termination value of 1745 psig.

D: INCORRECT: Plausible as 55F is a value in the EOPs for subcoolling but 48F is already above the adverse containment subcooling value of 45F.

Question Level: H Question Difficulty 3 Justification:

The student must recall SI termination criteria and make a determination if plant parameters allow termination.

Page 10 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2921 Last used on an NRC exam: Never RO Sequence Number: 6 The unit is at 100% power.

The Fresh Water System is OOS.

A large fire begins in the Protected Area.

Fire Water Storage Tank levels are dropping.

Recording a current Fire Water Storage Tank level can be done _________(1)________.

To prevent Fire Water Storage Tank levels from dropping below the required limit, makeup to the Fire Water Storage Tanks can be accomplished by using the ______(2)______ system.

A. (1) ONLY locally (2) Well Water B. (1) ONLY locally (2) Demineralized Water C. (1) locally AND in the Control Room (2) Well Water D. (1) locally AND in the Control Room (2) Demineralized Water Answer: A (1) ONLY locally (2) Well Water Page 11 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2921 Source: New Modified from K/A Catalog Number: 086 A1.03 Fire Protection: Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the Fire Protection System controls, including: Fire water storage tank level.

RO Importance: 3.0 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 201.29 Objective Number: 31247 State what the normal and backup sources of FWST makeup water are and how makeup is controlled.

Reference:

LOT201.29 Student Handout, page 2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: The Fire Water Storage Tanks have local instrumentation on the side of the tank but not in the control room. The normal makeup is Fresh Water, but if it is out of service, a bypass line from Well Water around the Fresh Water skid is available.

B: INCORRECT: Plausible as level may only be read locally, and the DWST is near the FWSTs and Demineralized Water is used to fill many tanks and systems.

C: INCORRECT: Plausible as other outdoor tanks have control room instrumentation such as the AFWST and SMUT level. Well Water is correct.

D: INCORRECT: Plausible as other outdoor tanks have control room instrumentation such as the AFWST and SMUT level and the DWST is near the FWSTs and Demineralized Water is used to fill many tanks and systems.

Question Level: F Question Difficulty 3 Justification:

The student must recall information about the Fire Protection system.

Page 12 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2920 Last used on an NRC exam: Never RO Sequence Number: 7 The unit is in a refueling outage.

RT-8036, FHB Exhaust Radiation Monitor, goes into HIGH alarm.

As a result of this condition, the FHB Exhaust Booster Fans will ______(1)______ and the FHB Relief Supply Dampers will ____(2)____.

A. (1) stop (2) close B. (1) stop (2) open C. (1) start (2) close D. (1) start (2) open Answer: D (1) start (2) open Page 13 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2920 Source: New Modified from K/A Catalog Number: 072 A3.01 Ability to monitor automatic operation of the ARM system, including: Changes in ventilation alignment RO Importance: 2.9 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 202.38 Objective Number: 3014 Given the name of a FHB Ventilation System component or control, describe any logic, actuation signals, coincidence, setpoints and interlocks associated with that component or control.

Reference:

LOT202.38 Student Handout, page 8 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion about system alignment on a high radiation signal.

B: INCORRECT: Plausible with confusion about system alignment on a high radiation signal.

C: INCORRECT: Plausible with confusion about system alignment on a high radiation signal.

D: CORRECT: Upon a high rad signal from RT-8035 or RT-8036, the exhaust booster fans will start and the relief supply dampers will open.

Question Level: F Question Difficulty 3 Justification:

The student must recall the automatic operation of FHB HVAC and where to monitor it.

Page 14 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2918 Last used on an NRC exam: Never RO Sequence Number: 8 Following a reactor trip near the End of Life, the crew is raising power:

Reactor power is 10%.

Control Rods are in manual.

Steam Dumps are in Steam Pressure Mode.

Header Pressure Controller PK-0557 is in AUTO with a setting of 8.47 on the potentiometer.

If the potentiometer on PK-0557 were to be changed to 7.00, RCS Tave would (1) and reactor power would (2) .

A. (1) lower (2) lower B. (1) rise (2) rise C. (1) lower (2) rise D. (1) rise (2) lower Answer: C (1) lower (2) rise Page 15 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2918 Source: Modified Modified from 2630 K/A Catalog Number: 041 K3.04 Knowledge of the physical connections and/or cause-effect relationships between the SDS and the following systems: Reactor Power RO Importance: 3.5 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 202.09 Objective Number: 22107 DISCUSS the operation of the Steam Dump System.

Reference:

LOT 202.09 Powerpoint Presentation, slide 49 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as Tave does lower, and if the student confuses the effect on reactor power.

B: INCORRECT: Plausible the student may think the potentiometer setting is similar to a demand signal. If that was the case then lowering this setting would cause dumps to close and raise Tave and if the student confuses the effect on reactor power..

C: CORRECT: At a setting of 8.46 the dumps maintain a no load value of 1185 psig. A pot setting of 7.00 would equate to a pressure of 980 psig. In order to lower pressure, the dumps would open to release more steam to the condenser. More steam flow would make RCS Tave go down. And since the reactor is at EOL it would have a negative MTC. With a negative MTC and a lowering of Tave, reactor power would go up.

D: INCORRECT: Plausible the student may think the potentiometer setting is similar to a demand signal. If that was the case then lowering this setting would cause dumps to close and raise Tave and lower power.

Question Level: H Question Difficulty 3 Justification:

The student must assess the conditions and determine the operation of the steam dump system.

Page 16 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2917 Last used on an NRC exam: Never RO Sequence Number: 9 The unit is at 100% power.

An inadvertent Main Steam Line Isolation occurs.

SG PORV 1A does NOT open.

With this condition, SG 1A pressure will rise to a maximum of A. 1185 psig.

B. 1225 psig.

C. 1265 psig.

D. 1285 psig.

Answer: D 1285 psig Page 17 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2917 Source: New Modified from K/A Catalog Number: 035 K6.02 Steam Generator: Knowledge of the effect of a loss or malfunction on the following will have on the SGs:

Secondary PORV.

RO Importance: 3.1 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.02 Objective Number: 12768 Given a plant or system condition, PREDICT the operation of the Main Steam System.

Reference:

LOT 202.02 Powerpoint Presentation, Slides 54, 58 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is normal no-load steam pressure following a reactor trip.

B: INCORRECT: Plausible as this is the PORV setpoint, and with confusion with the 5 safety setpoints on each SG.

C: CORRECT: Plausible as this is the pressure the PORV is adjusted to during a ruptured steam generator response.

D: CORRECT: With the PORV not working, pressure will rise to 1285 psig on a main steam line isolation.

Question Level: H Question Difficulty 3 Justification:

The student must assess the plant situation and understand the impact on the SGs and the plant.

Page 18 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2914 Last used on an NRC exam: Never RO Sequence Number: 10 The unit is at 4% power.

Main Steam Header Pressure Transmitter, PT-0557, fails HIGH.

As a result, steam dumps will fail ____(1)___ and steam generator ____(2)____ will occur.

A. (1) open (2) shrink B. (1) open (2) swell C. (1) closed (2) shrink D. (1) closed (2) swell Answer: B (1) open (2) swell Page 19 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2914 Source: New Modified from K/A Catalog Number: 016 K1.12 Non-nuclear instrumentation: Knowledge of the physical connections or cause/effect relationships between the NNI system and the following systems: S/G RO Importance: 3.5 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 202.02 Objective Number: 80261 Describe the instrumentation available to monitor and operate the Main Steam System.

Reference:

LOT 202.02 Powerpoint Presentation, slides 172 and 175 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with a misunderstanding on the steam pressure controller of steam dumps and steam generator behavior.

B: CORRECT: At 4% power, the steam dumps are operated in the steam pressure mode in automatic. The pot is set to attempt to maintain RCS Tave on program. At 4% power, Program Tave is approximately 568F and the potentiometer setting will be approximately 8.57 turns. If PT-557 fails high, the steam dumps will all open to attempt to lower pressure. Steam flow will rise and steam generators level will swell rapidly.

C: INCORRECT: Plausible with a misunderstanding on the steam pressure controller of steam dumps and steam generator behavior.

D: INCORRECT: Plausible with a misunderstanding on the steam pressure controller of steam dumps. Steam generator behavior is correct.

Question Level: H Question Difficulty 3 Justification:

The student must understand the impact of the instrument failure on the SG system.

Page 20 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2913 Last used on an NRC exam: Never RO Sequence Number: 11 The Unit is at 80% power with the following conditions:

Rod Control is in AUTO.

Due to a plant transient, Tave is reading 591º.

Control rods will step in at ___(1)___ steps per minute and will stop stepping when the Tave-Tref deviation is ___(2)___.

A. (1) 6 (2) 0°F B. (1) 6 (2) +1°F C. (1) 39 (2) 0°F D. (1) 39 (2) +1°F Answer: D (1) 39 (2) +1F Page 21 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2913 Source: New Modified from K/A Catalog Number: 001 K5.97 Control Rod Drive System: Knowledge of the following operational implications as they apply to the CRDS:

Relationship of Tave to Tref RO Importance: 3.3 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.18 Objective Number: 86061 Describe the instrumentation and controls available to monitor and operate the Rod Control System.

Reference:

LOT 201.18, Powerpoint Presentation, slide 60 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion over rod speeds or calculating Tave wrong and with a misunderstanding of the dead band in the circuit.

B: INCORRECT: Plausible with confusion over rod speeds or calculating Tave wrong. This is the correct deadband.

C: INCORRECT: Plausible as this rod speed is correct and with a misunderstanding of the dead band in the circuit.

D: CORRECT: Tref is linear from 567 to 592F, 0 to 100% power. At 80% then, Tref is 587F and the given Tave is 4F hot. Automatic rod control is 6 spm at 3F deviation, 39 spm at 4F deviation, and 72 spm at 5F deviation. Rod motion stops at +1F deviation.

Question Level: H Question Difficulty 3 Justification:

The student must determine rod motion based on given plant parameters.

Page 22 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2911 Last used on an NRC exam: Never RO Sequence Number: 12 Regarding a Phase A Containment Isolation, complete the following statements:

________(1)________ receives a Phase A Containment Isolation signal.

The position of the above Phase A valve may be verified on _____(2)_____.

A. (1) FV-0011, LTDN ORIF HDR ISOL (2) CP-002 B. (1) FV-0011, LTDN ORIF HDR ISOL (2) CP-004 C. (1) MOV-0059, RCFC 11A/12A CHWS SPLY OCIV (2) CP-002 D. (1) MOV-0059, RCFC 11A/12A CHWS SPLY OCIV (2) CP-004 Answer: B (1) FV-0011, LTDN ORIF HDR ISOL (2) CP-004 Page 23 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2911 Source: New Modified from K/A Catalog Number: 103 A3.01 Containment: Ability to monitor automatic operation of the Containment system including: Containment Isolation RO Importance: 3.9 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.21 Objective Number: 97774 Given a set of plant conditions, PREDICT the effect and/or response on the Containment Isolation system.

Reference:

LOT 201.21 Powerpoint Presentation Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as FV-0011 is the correct valve, and there are letdown heat exchanger related valves on other panels.

B: CORRECT: FV-0011 isolates letdown on a Phase A Containment Isolation signal and is located on CP-004.

C: INCORRECT: Plausible as MOV-0059 isolates on a SI signal which also causes a Phase A signal and it is on CP-002.

D: INCORRECT: Plausible as MOV-0059 isolates on a SI signal which also causes a Phase A signal and with confusion over location.

Question Level: F Question Difficulty 3 Justification:

The student must recall what isolates on a Phase A signal.

Page 24 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2910 Last used on an NRC exam: Never RO Sequence Number: 13 The unit is at 100% power.

ECW Trains A and C are in service.

CCW Train A is in service.

B Train ECW/CCW MODE SEL switch is in STANDBY Due to ECW pond debris accumulation, ECW Trains A and C discharge pressures both drop to 27 psig.

The crew enters 0POP04-EW-0001, Loss of Essential Cooling Water.

A minute later, a plant operator reports local CCW Train temperatures are 115ºF and rising.

Complete the following regarding this plant situation:

At this point, _____(1)_____ Pump(s) is(are) running.

The crew will _____________(2)______________.

A. (1) all 3 ECW (2) trip the reactor and trip the RCPs B. (1) all 3 ECW (2) place the PDP in service and place both CCPs in PTL C. (1) ONLY B ECW (2) trip the reactor and trip the RCPs D. (1) ONLY B ECW (2) place the PDP in service and place both CCPs in PTL Answer: A (1) all 3 ECW (2) trip the reactor and trip the RCPs Page 25 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2910 Source: New Modified from K/A Catalog Number: 076 A2.02 Service Water: Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure.

RO Importance: 2.7 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 505.01 Objective Number: 92109 GIVEN a plant condition, DESCRIBE and/or INTERPRET the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

0POP04-EW-0001, Step 14, NLO 100.29, Slide 69 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT If both running trains drop below 30 psig discharge pressure, the standby train will start. Above 110F CCW temperature, the reactor and RCPs must be tripped.

B: INCORRECT: Plausible if the student believes the running pumps would trip and these are the actions to be taken when 105F CCW temperature is exceeded.

C: INCORRECT: Plausible as B ECW pump will auto start and if the student believes low discharge pressure would trip the pump. These are the correct actions.

D: INCORRECT: Plausible as B ECW pump will auto start and if the student believes low discharge pressure would require a trip and these are the actions to be taken when 105F CCW temperature is exceeded.

Question Level: H Question Difficulty 4 Justification:

The student must assess plant conditions and determine the appropriate course of action.

Page 26 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2909 Last used on an NRC exam: Never RO Sequence Number: 14 125V DC Batteries E1A11 and E1B11 are both at the SAME terminal voltage and normally aligned.

Following a loss of power to their battery chargers, 125 VDC Batteries E1A11 AND E1B1 are discharging at the SAME rate.

The discharge rate is then RAISED on 125VDC Battery E1A11.

Complete the following statements:

The total capacity (ampere-hours) that 125VDC Battery E1A11 will be able to supply will be

_____(1)_____ 125VDC Battery E1B11.

After the discharge rate is raised, the voltage at any time for 125VDC E1A11 will be

_____(2)_____ that for 125 VDC Battery E1B11.

A. (1) less than (2) equal to B. (1) less than (2) less than C. (1) equal to (2) equal to D. (1) equal to (2) less than Answer: B (1) less than (2) less than Page 27 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2909 Source: New Modified from K/A Catalog Number: 063 A1.01 Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate.

RO Importance: 2.5 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 201.37 Objective Number: 82197 STATE the effects that varying the Class 1E 125 VDC System battery discharge rates will have on their capacity

Reference:

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as the battery will have a shorter life and with confusion about voltage values over battery life.

B: CORRECT: A battery that has a higher discharge rate has a shorter life and a lower voltage at any given time.

C: INCORRECT: Plausible if the student does not equate discharge rate with life and voltage.

D: INCORRECT: Plausible if the student does not equate discharge rate with battery life. The voltage will be lower.

Question Level: H Question Difficulty 3 Justification:

The student must assess the effect of discharge rate on voltage and battery life.

Page 28 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2908 Last used on an NRC exam: Never RO Sequence Number: 15 An inadvertent reactor trip from 100% power just occurred.

All automatic systems operated normally.

With NO operator action, the RCS will undergo a _______(1)_______ from no-load Tave.

The RATE (ºF/hour) of heatup or cooldown can be directly monitored from _____(2)____.

A. (1) significant cooldown (2) a chart recorder on CP-004 B. (1) small heatup (2) a chart recorder on CP-004 C. (1) significant cooldown (2) QDPS D. (1) small heatup (2) QDPS Answer: C (1) significant cooldown (2) QDPS Page 29 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2908 Source: New Modified from K/A Catalog Number: 061 A3.02 Auxiliary/Emergency Feedwater: Ability to monitor automatic operation of the AFW, including: RCS cooldown during AFW operations.

RO Importance: 4.0 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.05 Objective Number: 80483 Given a copy of a subsequent step or from memory an immediate action step form 0POP05-EO-EO00, state/identify how the action is performed and the basis for the action to include the action itself, its purpose and result.

Reference:

LOT 504.05 Powerpoint Presentation, slide 20 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as a significant cooldown will occur and Tave is displayed on a chart recorder on CP-005 B: INCORRECT: Plausible with a misconception about the operation of AFW following a reactor trip from this power level and Tave is displayed on a chart recorder on CP-005 C: CORRECT: From a reactor trip at 100% power, SG levels will rapidly lower to the AFW actuation setpoint of 20% SG level. AFW flow automatically initiates to each steam generator at 605 gpm, controlled by QDPS. With this flow rate left in place, the RCS will overcool. Cooldown rate is displayed on QDPS only.

D: INCORRECT: Plausible with a misconception about the operation of AFW following a reactor trip from this power level. QDPS is correct.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and determine the operation of the AFW system and its effect on the plant.

Page 30 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2907 Last used on an NRC exam: Never RO Sequence Number: 16 The crew is responding to a reactor trip in Unit 1.

The AFW system is functioning as designed.

AFW Pump 13 then TRIPS.

The Unit Supervisor directs the RO to cross-connect AFW Pump 12 to feed Steam Generators 1B and 1C.

Valve manipulations to complete this task will be performed _______(1)______ and AFW Pump 12 flow will be maintained at a MAXIMUM of ____(2)____ gpm.

A. (1) BOTH locally and in the control room (2) 576 B. (1) BOTH locally and in the control room (2) 675 C. (1) ONLY in the control room (2) 576 D. (1) ONLY in the control room (2) 675 Answer: D (1) ONLY in the control lroom (2) 675 gpm Page 31 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2907 Source: New Modified from K/A Catalog Number: 061 K3.01 Auxiliary/Emergency Feedwater: Knowledge of the effect that a loss or malfunction of the AFW system will have on the following: RCS RO Importance: 4.4 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 201.40 Objective Number: 91842 Given a set of plant parameters, analyze the situation, predict the results of the condition and state the action required to reset the system.

Reference:

0POP05-EO-EO00, step 23 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible because with a loss of power, some manipulations on the AFW system must be done locallly and operators in the simulator have requested local operations when control room operation was possible while responding in the simulator. 576 gpm is a value in the EOPs that must be maintained to ensure a proper heat sink is established.

B: INCORRECT: Plausible because with a loss of power, some manipulations on the AFW system must be done locallly and operators in the simulator have requested local operations when control room operation was possible while responding in the simulator. 675 gpm is correct.

C: INCORRECT: Plausible as these manipulations are only done in the control room and 576 gpm is a value in the EOPs that must be maintained to ensure a proper heat sink is established.

D: CORRECT: Cross-connecting AFW may be done with the AFW Feed Reg Valves and the Cross-Connect Valves, both of which may be operated from the control room. Flow is maintained less than 675 per pump at all times.

Question Level: H Question Difficulty 3 Justification:

The student must assess the plant condition and determine how to complete a task.

Page 32 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2905 Last used on an NRC exam: Never RO Sequence Number: 17 Complete the following regarding the SG PORVs:

The SG PORVs are located ___(1)___ of the Main Steam Safety Valves The TDAFWP 14 steam supply line is physically connected to the SG PORV ___(2)___ piping.

A. (1) UPSTREAM (2) 1C B. (1) UPSTREAM (2) 1D C. (1) DOWNSTREAM (2) 1C D. (1) DOWNSTREAM (2) 1D Answer: B (1) UPSTREAM (2) "1D" Page 33 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2905 Source: New Modified from K/A Catalog Number: 039 K1.02 Main and Reheat Steam: Knowledge of the physical connections and/or cause effect relationships between the MRSS and the following systems: Atmospheric relief dump valves.

RO Importance: 3.3 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.02 Objective Number: 12504 Describe the various flowpaths through the Main Steam System.

Reference:

LOT 202.02 Powerpoint Presentation, Slide 22 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as upstream is correct and with confusion over train connections.

B: CORRECT: The SG PORV is located in the IVC upstream of the safety valves. The TDAFWP 14 is tied physically to the SG PORV 1D line.

C: INCORRECT: Plausible with confusion over orientation of valves in the IVC and train connections.

D: INCORRECT: Plausible with confusion over orientation of valves in the IVC. TDAFWP 14 is connected to the SG PORV 1D line.

Question Level: F Question Difficulty 3 Justification:

The student must recall the physical configuration of the SG PORVs.

Page 34 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2903 Last used on an NRC exam: Never RO Sequence Number: 18 The control board indicator for Containment temperature is located on ______(1)______ and the control board indicator for Containment dewpoint is located on ______(2)______.

A. (1) CP-002 (2) CP-002 B. (1) CP-002 (2) CP-018 C. (1) CP-018 (2) CP-002 D. (1) CP-018 (2) CP-018 Answer: A (1) CP-002 (2) CP-002 Page 35 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2903 Source: New Modified from K/A Catalog Number: 022 A4.05 Containment Cooling: Ability to manually operate and/or monitor in the control room: Containment readings of temperature, pressure, and humidity.

RO Importance: 3.8 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.01 Objective Number: 91026 Describe the purpose of the following controls and instrumentation and their locations for monitoring and indications: Temperature and humidity

Reference:

LOT 201.01 Powerpoint Presentation, slide 83 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Both control board indicators are on CP-002.

B: INCORRECT: Plausible as there is a Containment section on CP-018 with recorders for pressure and radiation levels and with confusion over locations.

C: INCORRECT: Plausible as there is a Containment section on CP-018 with recorders for pressure and radiation levels and with confusion over locations.

D: INCORRECT: Plausible as there is a Containment section on CP-018 with recorders for pressure and radiation levels and with confusion over locations.

Question Level: F Question Difficulty 2 Justification:

The student must recall control board locations.

Page 36 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2878 Last used on an NRC exam: Never RO Sequence Number: 19 The unit is at 100% power.

3M02-A1, 125V DC SYSTEM E1A11 TRBL, alarms.

The in-service battery charger supply breaker has TRIPPED.

Complete the following regarding this plant condition:

125VDC E1A11 voltage can be determined _____(1)_____.

Battery E1A11 is _____(2)_____.

A. (1) locally ONLY (2) operable B. (1) locally ONLY (2) inoperable C. (1) BOTH from the control room and locally (2) operable D. (1) BOTH from the control room and locally (2) inoperable Answer: D (1) both from the control room and locally (2) inoperable Page 37 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2878 Source: New Modified from K/A Catalog Number: APE 058 AA2.02 Loss of DC Power: Ability to determine and interpret the following as they apply to the Loss of DC Power: 125VDC bus voltage, low/critical low, alarm.

RO Importance: 3.3 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.37 Objective Number: 92048 State the meaning of the Class 1E 125 VDC System alarms.

Reference:

LOT 201.37 Handout 1, Page 2 of 13; EOPT; 0POP04-AN-03M2-A-1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as there are other local switchboard and battery charger indications that are only available locally and if the student believes the battery, with satisfactory voltage, would still be operable.

B: INCORRECT: Plausible as there are other local switchboard and battery charger indications that are only available locally. The switchboard is inoperable.

C: INCORRECT: Plausible as battery voltage may be read at both locations and if the student believes the battery, with satisfactory voltage, would still be operable.

D: CORRECT: Battery voltage may be read on CP-001 in the control room, and also locally at the DC switchboard. Without an operating battery charger, the ARP states the battery is inoperable.

Question Level: H Question Difficulty 3 Justification:

The student must determine if a component meets the LCO based on given conditions.

Page 38 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2943 Last used on an NRC exam: Never RO Sequence Number: 20 A signal from _________(1)_________ will open ________(2)________.

A. (1) logic train R (2) reactor trip breaker S ONLY B. (1) logic train R (2) reactor trip breaker S and reactor trip bypass breaker R C. (1) logic train S (2) reactor trip breaker S ONLY D. (1) logic train S (2) reactor trip breaker S and reactor trip bypass breaker R Answer: D (1) logic train "S" (2) reactor trip breaker "S" and reactor trip bypass breaker "R" Page 39 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2943 Source: Modified Modified from 909 K/A Catalog Number: 012 G2.1.28 Reactor Protection: Knowledge of the purpose and function of major system components and controls.

RO Importance: 4.1 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(6)

STP Lesson: LOT 201.20 Objective Number: 34904 Describe the major components and instrumentation associated with the Solid State Protection System.

Reference:

LOT 201.20, Solid State Protection System, Powerpoint Presentation, slide 45 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as is similar to the correct answer in same train and opposite train relationship.

B: INCORRECT: Plausible as is similar to the correct answer in same train and opposite train relationship.

C: INCORRECT: Plausible as is similar to the correct answer in same train and opposite train relationship.

D: CORRECT: A Logic Train "S" Reactor Trip signal will open the same train reactor trip breaker and the opposite train reactor trip bypass breaker.

Question Level: F Question Difficulty 2 Justification:

The student must know the reactor trip breaker logic.

Page 40 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2899 Last used on an NRC exam: Never RO Sequence Number: 21 The unit is at 30% POWER.

The Pressurizer Master Pressure Controller fails upscale at 70%.

With NO operator action, A. an OTT Reactor Trip will occur.

B. a Low Pressurizer Pressure Reactor Trip will occur.

C. pressurizer pressure will lower, then rise and stabilize at 2235 psig.

D. pressurizer pressure will rise, then lower and stabilize at 2235 psig.

Answer: B a Low Pressurizer Pressure Reactor Trip will occur.

Page 41 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2899 Source: New Modified from K/A Catalog Number: 010 K3.02 Pressurizer Pressure Control: Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RPS.

RO Importance: 4.0 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.14 Objective Number: 92279 Given plant conditions, determine their effects on the pressurizer pressure and level control system.

Reference:

LOT 201.14 Powerpoint presentation, slide 39 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as an OTdeltaT trip will occur first at 100% power, but at 30% power, the OTdeltaT setpoint is nearly 150% and will not lower sufficiently as pressure lowers to cause a reactor trip.

B: CORRECT: With the Master Pressure Controller fixed at 70% output, the spray valves are nearly full open and will not change from that position. The pressurizer heaters will not energize.

Pressurizer pressure will drop quickly to the setpoint of 1870 psig.

C: INCORRECT: Plausible as pressurizer pressure will lower, and if there is a misunderstanding of controller and component functions.

D: INCORRECT: Plausible with a misunderstanding of controller and component functions.

Question Level: H Question Difficulty 3 Justification:

The student must determine the effect that a controller failure will have on the plant.

Page 42 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2898 Last used on an NRC exam: Never RO Sequence Number: 22 The unit is at 100% power.

A leak develops in the CCW system.

CCW Surge Tank level drops to 59%.

With these conditions CCW flow to the RCPs will _______(1)_______ and, CCW flow to the RHR system ____(2)____ initiate.

A. (1) remain in service (2) will NOT B. (1) remain in service (2) will C. (1) isolate (2) will NOT D. (1) isolate (2) will Answer: D (1) isolate (2) will Page 43 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2898 Source: New Modified from K/A Catalog Number: 008 K4.02 Component Cooling Water: Knowledge of CCWS design features and/or interlocks which provide for the following:

Operaton of the surge tank, including the associated valves and controls.

RO Importance: 2.9 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.12 Objective Number: 80198 DESCRIBE the Instrumentation and Controls available to monitor and operate the CCW System.

Reference:

LOT 201.12 Student Handout, page 14 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student believes that CCW flow is maintained to the RCPs (the RCPs are used in the EOPs) and if the student believes that flow to the RHR HXs is not train specific B: INCORRECT: Plausible if the student believes that CCW flow is maintained to the RCPs (the RCPs are used in the EOPs). RHR flow is initiated to all trains with a running CCW pump.

C: INCORRECT: Plausible as flow to the RCPs isolates and if the student believes that flow to the RHR HXs is not train specific.

D: CORRECT: When level drops below 61.5%, all flow to the RCPs isolates, and to maintain adequate flow for the CCW system, CCW flow to the RHR HXs initiates for any train with a running pump.

Question Level: H Question Difficulty 3 Justification:

The student assess plant conditions and determine the effect on the CCW system.

Page 44 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2887 Last used on an NRC exam: Never RO Sequence Number: 23 The unit is at 100%

Pressurizer level channel LT-468 fails HIGH.

Following this failure (1) A Pressurizer High Level Reactor Trip bistable on CP-005 ____(1)___ be lit.

(2) Actual Pressurizer level is _____(2)_____.

A. (1) will (2) lowering B. (1) will (2) unaffected C. (1) will NOT (2) lowering D. (1) will NOT (2) unaffected Answer: B (1) will (2) unaffected Page 45 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2887 Source: New Modified from K/A Catalog Number: APE 028 AA1.01 Ability to operate and or monitor the following as they apply to the PZR Level Control Malfunction: PZR level reactor protection bistables.

RO Importance: 3.8 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 505.01 Objective Number: 92109 Given a plant condition, describe and/or interpret the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

0POP04-RP-0002, Addendum 4, Page 1, LOT 201.20 Powerpoint presentation, page 166 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as a bistable will be lit, and if the student confuses the functions of the 4 pressurizer level transmitters for automatic level control.

B: CORRECT: A high failure of LT-468 will light a high pressurizer level reactor trip bistable on CP-005. LT-468 is not part of the control circuit for pressurizer level and is only used for letdown isolation, reactor trip, and alarms.

C: INCORRECT: Plausible as other parameters use 3 of 4 of the available transmitters (3 of 4 pressurizer pressure instruments are used to develop P-11, 3 of 4 containment pressure instruments are used to develop the SI signal) and if the student confuses the functions of the 4 pressurizer level transmitters for automatic level control.

D: INCORRECT: Plausible as other parameters use 3 of 4 of the available transmitters (3 of 4 pressurizer pressure instruments are used to develop P-11, 3 of 4 containment pressure instruments are used to develop the SI signal). Pressurizer level is unaffected.

Question Level: H Question Difficulty 3 Justification:

The student must assess the failure and determine the effect on plant systems.

Page 46 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2876 Last used on an NRC exam: Never RO Sequence Number: 24 With the unit at 100%, VCT Level Transmitter LT-112 fails and is removed from service.

Complete the following regarding this condition:

If level sensed by VCT Level Transmitter LT-113 falls below 28%, automatic makeup

____(1)____ occur.

Level indicated by LT-113 may be observed on ____(2)____.

A. (1) will (2) ICS B. (1) will (2) CP-004 C. (1) will NOT (2) ICS D. (1) will NOT (2) CP-004 Answer: C (1) will NOT (2) ICS Page 47 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2876 Source: New Modified from K/A Catalog Number: APE 022 G2.1.19 Loss of Reactor Coolant Makeup: Ability to use plant computers to evaluate system or component status.

RO Importance: 3.9 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(6)

STP Lesson: LOT 201.06 Objective Number: 03913 Describe the design features associated with the Chemical and Volume Control System and its major components.

Reference:

LOT 201.06 Powerpoint Presentation, Slide 56 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as some features that actuate on VCT level come from both transmitters or with confusion over which transmittter drives auto makeup. LT-113 may be seen on ICS only.

B: INCORRECT: Plausible as some features that actaute on VCT level come from both transmitters or with confusion over which transmittter drives auto makeup and if the student is confused about the location where these indications may be seen.

C: CORRECT: Auto makeup only is derived from LT-112 and LT-112 is the only tramsitter displayed on a gauge on CP-004. LT-113 does not control auto makeup and can only be seen on ICS.

D: INCORRECT: Plausible as LT-113 will not start an auto makeup and if the student is confused about the location where these indications may be seen.

Question Level: F Question Difficulty 3 Justification:

This question requires the student to recall the functions of the VCT level instruments and from where the current instrument readings may be obtained.

Page 48 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2643 Last used on an NRC exam: 2017 RO Sequence Number: 25 Following a grid disturbance, the Unit 1 Main Generator output is reading as follows:

1225 MW 200 MVAR IN The Unit 1 Main Generator is operating (1) the limits of the capability curve.

AND/BUT The operator would need to (2) Unit 1 Main Generator voltage to minimize operation in the VARS IN region.

A. (1) within (2) raise B. (1) within (2) lower C. (1) outside (2) raise D. (1) outside (2) lower Answer: C (1) outside (2) raise Page 49 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2643 Source: Bank Modified from K/A Catalog Number: APE 077 AK1.03 Generator Voltage and Electric Grid Disturbances:

Knowledge of the operational implications of the followint concepts as they apply to Generator Voltage and Electric Grid Disturbances: Under-excitation.

RO Importance: 3.3 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 202.17 Objective Number: 91965 Explain under and over excitation of the Main Generator and precautions.

Reference:

0POP03-ZG-0008, Step 4.8, 4.20 Attached Reference

Attachment:

Main Generator Capability Curve, PCB 107.01, Rev. 10 NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: With the given conditions, the generator is outside the limits. Plausible the student may misread the curve and its restrictions.

B: INCORRECT: With the given conditions, the generator is outside the limits. Plausible the student may misread the curve and its restrictions. Also plausible a student may think lowering voltage would minimize the VARS IN. However, when raising voltage in the VARS IN region the number actually lowers to get closer to zero.

C: CORRECT: With the given conditions the generator is outside the allowable limits of the capability curve. Raising voltage, or excitation, would lower VARS IN to above the capability limitation of 100 MVARS IN.

D: INCORRECT: Lowering voltage would put the Generator output to more MVARS IN. Plausible a student may think lowering current would minimize the VARS IN. However, when raising voltage in the VARS IN region the number actually lowers to get closer to zero.

Question Level: H Question Difficulty 3 Justification:

Student must read and interpret given curve and determine the operational limits.

Page 50 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2624 Last used on an NRC exam: Never RO Sequence Number: 26 Channel I 120VAC DP-1201 is normally supplied by its ______(1)______

AND If the normal power supply is lost, then DP-1201 will be transferred to its backup source

________(2)________.

A. (1) inverter (2) manually B. (1) inverter (2) automatically C. (1) voltage regulated transformer (2) manually D. (1) voltage regulated transformer (2) automatically Answer: B (1) inverter (2) automatically Page 51 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2624 Source: Bank Modified from K/A Catalog Number: 062 K4.10 Knowledge of the ac distribution system design feature(s) and/or interlock(s) which provide for the following:

Uninterruptable ac power sources.

RO Importance: 3.1 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.38 Objective Number: 91529 List the power supplies to the Class 1E Vital 120 VAC system components.

Reference:

0POP02-AE-0004 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible because the last design for DP-1201 required it to be transferred manually.

B: CORRECT: The inverter normally supplies DP-1201. With an overcurrent condition on the Inverter, the inverter will automatically transfer to the bypass source (VRT) with NO interruption of voltage.

C: INCORRECT: Plausible because the VRT is the bypass or backup source of power. Also plausible because the last design for DP-1201 required it to be transferred manually.

D: INCORRECT: Plausible because the VRT is the bypass or backup source of power.

Question Level: F Question Difficulty 3 Justification:

Student must have knowledge of the power supply for the 120VAC distribution panels and understand the design features.

Page 52 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2397 Last used on an NRC exam: 2015 RO Sequence Number: 27 The unit is at 4%.

SUFP 14 is providing feedwater flow.

SUFP 14 then trips.

Based on these plant conditions, the AFW pumps are A. running because an AMSAC actuation has occurred.

B. running due to an automatic Reactor Trip signal.

C. NOT running but will start when 2 of 4 level transmitters on ONE Steam Generator lowers to 20%.

D. NOT running but will start when 2 of 4 level transmitters on TWO Steam Generators lower to 20%.

Answer: C NOT running but will start when 2 of 4 level transmitters on ONE steam generator lowers to 20%.

Page 53 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2397 Source: Bank Modified from K/A Catalog Number: APE 054 AA2.03 Loss of Main Feedwater: Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Conditions and reasons for AFW pump startup RO Importance: 4.1 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.01 Objective Number: 101897 GIVEN a set of conditions, PREDICT the operation of or the effects on the Steam Generators.

Reference:

LOT 202.28 Powerpoint Presentation, Slide 51 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as the loss of feed event is the design basis for the AMSAC system but the system actually starts on lower steam generator levels above 30% turbine load.

B: INCORRECT: Plausible since loss of all feed is the design basis for the AMSAC system and if the student believes an auto AFW actuation will occur.

C: CORRECT: At 4% power, feed is supplied by the SUFP through the LPFRVs. The AFW pumps are in AUTO and required to automatically start for this mode of operation. The AFW pumps will start when 2 of 4 level transmitters on one SG lowers to 20%.

D: INCORRECT: Plausible as 2 of 4 can be confused between transmitters and steam generators.

Question Level: H Question Difficulty 3 Justification:

Must analyze the given conditions and determine the status of the AFW System.

Page 54 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2944 Last used on an NRC exam: Never RO Sequence Number: 28 Based on the picture below, complete the following statements:

The light blue color seen on the radiation monitor is due to a _________(1)_________.

A. loss of sample flow.

B. communications failure.

C. operate failure.

D. change in polling status.

Answer: A loss of sample flow.

Page 55 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2944 Source: New Modified from K/A Catalog Number: G2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

RO Importance: 2.9 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(11)

STP Lesson: LOT 202.33 Objective Number: 51334 DESCRIBE the interface between the Containment Supplementary Purge, ventilation stack and containment atmosphere radiation monitors.

Reference:

0PRP05-RA-0002, page 31-40 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Light blue (cyan) indicates a loss of sample flow.

B: INCORRECT: Plausible as this is a valid status but for a magenta color.

C: INCORRECT: Plausible as this is a valid status but for a dark blue color.

D: INCORRECT; Plausible as this is a valid status but for a white color.

Question Level: F Question Difficulty 3 Justification:

The student must recall information about radiation monitors.

Page 56 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1689 Last used on an NRC exam: 2016 RO Sequence Number: 29 The greatest likelihood of causing an observable PRT level change while forming a steam bubble in the Pressurizer would be during ______(1)______ because of the potential to lift a Pressurizer

_______(2)_______.

A. (1) Solid Plant Operations (2) PORV B. (1) a heatup in MODE 5 (2) PORV C. (1) Solid Plant Operations (2) Safety Valve D. (1) a heatup in MODE 5 (2) Safety Valve Answer: A (1) Solid Plant Operations (2) PORV Page 57 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1689 Source: Bank Modified from K/A Catalog Number: 007 K5.02 Knowledge of the operational implications of the following concepts as they apply to the PRTS:

Method of forming a steam bubble in the Pressurizer RO Importance: 3.1 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 201.04 Objective Number: 91039 DESCRIBE the procedure for formation of a pressurizer bubble.

Reference:

0POP03-RC-0100, RCS Vacuum Fill; 0POP03-ZG-0001, Plant Heatup Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: The greatest likelihood of causing a PRT level change would be from the Pressurizer PORV during solid plant conditions due to the lift setting for the Pressurizer PORV being lower due to COMS.

B: INCORRECT: Plausible if the student does not understand the temperature and condition of the pressurizer during a MODE 5 heatup.

C: INCORRECT: Plausible because Pressurizer Safety Valves could lift, however, during solid plant conditions, the Pressurizer PORVs have a lower setpoint through the COMS control, thus they will lift at a significantly lower pressure. The Pressurizer Safety valves will lift at much higher pressure so the potential for them lifting is not as great as that for the PORVs.

D: INCORRECT: Plausible if the student does not understand the temperature and condition of the pressurizer during a MODE 5 heatup.

Question Level: H Question Difficulty 4 Justification:

The student must be able to evaluate the different senarios given for forming a Pressurizer bubble and determine which method and case given would be the most likely to cause an observable level change in the PRT.

Page 58 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1656 Last used on an NRC exam: 2007 RO Sequence Number: 30 The unit is in MODE 5.

The crew is conducting Solid Plant Operations.

RHR Trains A and C are in service.

RCS pressure is 50 psig.

The RHR Pump A pump discharge relief valve fails fully OPEN.

Initially, the crew will observe A. Containment Normal Sump level rising.

B. PCV-0135, Letdown Pressure Control Valve, closing.

C. FCV-0205, Charging Flow Control Valve, opening.

D. RHR A Pump tripping.

Answer: B PCV-0135, Letdown Pressure Control Valve, closing.

Page 59 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1656 Source: Bank Modified from K/A Catalog Number: 005 K3.01 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: RCS RO Importance: 3.9 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 201.06 Objective Number: 48556 EXPLAIN the impact on RCS pressure, while using solid plant pressure control, if the following parameters are changed: 1. RCS temperature, 2. Letdown flow, 3. Charging flow, 4. Starting or stopping a RHR Pump, 5. Starting or stopping a RCP

Reference:

LOT201.06, CVCS; LOT201.09, RHR Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as a relief valve has opened, and some reliefs do discharge to local sumps, but the RHR discharge relief discharges to a tank.

B: CORRECT: Opening of the RHR discharge relief valve will result in a loss of RCS inventory causing a reduction in RCS pressure. PCV-0135 provides automatic pressure control by closing to reduce letdown flow C: INCORRECT - Plausible as charging is being controlled, but the valve is in manual in solid plant ops.

D: INCORRECT - Plausible as flow is being diverted, but the flow indicator is upstream of the discharge relief valve.

Question Level: H Question Difficulty 3 Justification:

The applicant must determine the effect of the event to the given plant conditions to determine the response of the plant.

Page 60 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1581 Last used on an NRC exam: Never RO Sequence Number: 31 The unit is at 100% power.

A loss of power to DP-1203 occurs.

Based on this event, complete the following statements:

Train __(1)__ Auto Recirc Swapover will fail to actuate.

RWST and VCT Outlet Valve position indication (red/green lights) will be _____(2)_____.

A. (1) B (2) de-energized B. (1) C (2) de-energized C. (1) B (2) unaffected D. (1) C (2) unaffected Answer: C (1) B (2) unaffected Page 61 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1581 Source: Bank Modified from K/A Catalog Number: APE 057 AA1.04 Ability to operate and/or monitor the following as they apply to the Loss of Vital AC Instrument Bus: RWST and VCT valves.

RO Importance: 3.5 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 505.01 Objective Number: 38635 Given an abnormal plant operating event, predict the symptoms expected to occur in accordance with the appropriate off normal operating procedure.

Reference:

0POP04-VA-0001, page 53; 9E0CV05#1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the correct train of instrumentation and if the student believes that a loss of vital 120V AC power will affect valve indication in the control room.

B: INCORRECT: Plausible if the student believes that DP-1201-1204 are A-D instrumentation and also if the student believes that a loss of vital 120V AC power will affect valve indication in the control room.

C: CORRECT: DP-1203 provides power to the "B" train instrumentation. With a failure of the "B" train RWST level transmitter, the auto swapover on Train B will NOT occur. The RWST and VCT suction valves to the CCPs are affected by failures of other instrumentation channels, but in all cases the light bulbs remain energized as they are powered from the MCC through a 480V/120V transformer.

D: INCORRECT: Plausible if the student believes that DP-1201-1204 are A-D instrumentation. It is true that indication is unaffected.

Question Level: H Question Difficulty 3 Justification:

The student must assess the effects of a loss of power on plant operations.

Page 62 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1474 Last used on an NRC exam: 2011 RO Sequence Number: 32 Due to corrective maintenance, one of the starting air receivers on ESF Diesel Generator #12 is isolated.

With this condition, a start signal for Diesel Generator #12 will result in ______(1)______ the cylinders receiving starting air. Engine acceleration to full speed will be __(2)__ seconds.

A. (1) ONLY HALF (2) <10 B. (1) ONLY HALF (2) >10 C. (1) ALL (2) <10 D. (1) ALL (2) >10 Answer: C (1) ALL (2) <10 Page 63 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1474 Source: Bank Modified from K/A Catalog Number: 064 K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G System: Air Receivers.

RO Importance: 2.7 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.39 Objective Number: 98476 Given a plant condition and/or various diesel modes of operation, PREDICT the response of the emergency diesels.

Reference:

LOT 201.39 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as there are two air flow paths and if the student believes each compressor and flowpath only services one side of the diesel. The diesel will start in less than 10 seconds.

B: INCORRECT: Plausible as there are two air flow paths and if the student believes each compressor and flowpath only services one side of the diesel and that the start time of <10 seconds requires 2 receivers.

C: CORRECT: A loss of one of two redundant air receivers will not impact the design performance of the ESF DG.

D: INCORRECT: Plausible as all cylinders receive starting air, but if the student believes the start time of <10 seconds requires 2 receivers Question Level: F Question Difficulty 3 Justification:

Student must know the design of the ESF DG starting air system.

Page 64 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1467 Last used on an NRC exam: Never RO Sequence Number: 33 The unit is at 100% power.

PR NI-0043 is OOS with all bistables tripped.

Power is then lost to Channel II (ESF Class 1E Vital 120V Instrumentation).

_____(1)____ is the affected panel. The reactor _______(2)______.

A. (1) DP-1202 (2) immediately trips B. (1) DP-1202 (2) does NOT immediately trip C. (1) DP-1203 (2) immediately trips D. (1)DP-1203 (2) does NOT immediately trip Answer: A (1) DP-1202 (2) immediately trips Page 65 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1467 Source: Bank Modified from K/A Catalog Number: 012 K2.01 Reactor Protection: Knowledge of bus power supplies to the following: RPS channels, components, and interconnections RO Importance: 3.3 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 505.01 Objective Number: 38635 Given an abnormal plant operating event, predict the symptoms expected to occur in accordance with the appropriate off normal operating procedure.

Reference:

LOT 201.38 Powerpoint Presentation, Slide 82; 0POP04-VA-0001, page 2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Channel II instrumentation is for "D" train equipment and is powered from DP-1202.

PR NI-0043 is powered from DP-1203. The reactor will trip immediately because 2/4 channels are tripped.

B: INCORRECT: Plausible as this is the correct power supply and with confusion over power supplies and channel numbers.

C: INCORRECT: Plausible with confusion over power supplies. The reactor does trip.

D: INCORRECT: Plausible with confusion over power supplies and channel numbers.

Question Level: H Question Difficulty 3 Justification:

The student must assess the conditions given, and determine how the plant responds.

Page 66 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1010 Last used on an NRC exam: 2010 RO Sequence Number: 34 The unit is at 100% power.

A Loss of Offsite Power occurs.

Following completion of the load sequence, the RCFCs are ____(1)____ with ____(2)____ flow established to the cooling coils.

A. (1) running (2) CCW B. (1) NOT running (2) CCW C. (1) running (2) NO D. (1) NOT running (2) NO Answer: C (1) running (2) NO Page 67 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1010 Source: Bank Modified from K/A Catalog Number: 022 K1.01 Containment Cooling: Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: SWS/Cooling system.

RO Importance: 3.5 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.33 Objective Number: 4967 STATE the sources of cooling water to the RCFC'S and when each is used.

Reference:

LOT 201.41 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as RCFC's will auto start and if the student believes the safety related water supply (CCW) would establish as it does on a Safety Injection (MODE 1) signal.

B: INCORRECT: Plausible if the student does not remember the sequence for a LOOP (MODE 2 and if the student believes the safety related water supply (CCW) would establish as it does on a Safety Injection (MODE 1) signal.

C: CORRECT: The RCFC's will be running because they are automatically loaded on a Sequencer Mode II signal (LOOP), however they will not have any cooling water because the CCW supply valves do not automatically open on a LOOP and the Chilled Water supply valves automatically close..

D: INCORRECT: Plausible if the student does not remember the sequence for a LOOP (MODE 2).

NO cooling water is established.

Question Level: H Question Difficulty 3 Justification:

Must know system design features and interlocks and be able to determine system response based on the given conditions.

Page 68 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 833 Last used on an NRC exam: Never RO Sequence Number: 35 The unit is at 100% power.

A 2 gpm steam generator tube leak develops.

If power is reduced to 50%, then tube leakage is _______(1)_______, because

_________(2)________.

A. (1) greater (2) RCS Tave has risen B. (1) greater (2) primary to secondary delta-P has risen C. (1) less (2) RCS Tave has lowered D. (1) less (2) primary to secondary delta-P has lowered Answer: D (1) less (2) primary to secondary delta-P has lowered Page 69 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 833 Source: Bank Modified from K/A Catalog Number: APE 037 AK1.02 Knowledge of the operational implicadtions of the following concepts as they apply to Steam Generator Tube Leak: Leak rate versus pressure drop.

RO Importance: 3.5 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(14)

STP Lesson: LOT 202.02 Objective Number: 12804 List the Main Steam system design and normal operating pressures, temperatures, and flows.

Reference:

Lesson Plan LOT202.02, Section 1.4.2.A Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion about the behavior of primary and secondary behaviors with power changes.

B: INCORRECT: Plausible with confusion about the behavior of primary and secondary behaviors with power changes.

C: INCORRECT: Plausible as tube leakage is less and RCS Tave will be lowered, RCS pressure remains constant.

D: CORRECT: With a drop in load of 50%, steam pressure will rise approximately 50 psig, thus lowering primary to secondary delta-P. This will in turn, lower tube leakage.

Question Level: H Question Difficulty 3 Justification:

The student must determine the change in SGTL with changes in plant conditions.

Page 70 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 65 Last used on an NRC exam: 1999 RO Sequence Number: 36 Unit 1 is at 70% power.

6M03-E-3, SG 1A STM/FW FLOW MSMTCH, alarms.

SG 1A FWRV demand signal is rising.

SG 1A level is rising.

SG 1B, 1C and 1D levels are lowering.

The reason for these indications is that the SG 1A A. Main Feedwater Regulating Valve has lost Class 1E control power.

B. controlling steam generator level channel has failed high.

C. steam pressure channel for the controlling steam flow channel has failed high.

D. controlling feedwater flow channel has failed high.

Answer: C steam pressure channel for the controlling steam flow channel has failed high.

Page 71 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 65 Source: Bank Modified from K/A Catalog Number: 059 K1.04 Knowledge of the physical connections and/or cause-effect relationships between the MFW and S/G water level control system RO Importance: 3.4 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 202.15 Objective Number: 21005 IDENTIFY the level controller, the manual/auto station, all input signals from the SGWLCS. STATE how a change in each input signal will affect the position of the Main Feed Regulating Valves.

Reference:

LOT202.15 Powerpoint Presentation, slides 76, 83 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT - Plausible as loss of class 1E control power will affect the FWRV, but causes it to close.

B: INCORRECT - Plausible with confusion over the operation of SGWLCS.

C: CORRECT - A failed high steam pressure channel will look like a failed high steam flow causing the regulating valve to open due to feed flow being less than steam flow (on the controlling channels).

D: INCORRECT - Plausible with confusion over the operation of SGWLCS.

Question Level: H Question Difficulty 3 Justification:

The candidate must be able to determine how each of the failures will affect the regulating valve and use this determination to compare against the given conditions in order to select the correct answer.

Page 72 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2886 Last used on an NRC exam: Never RO Sequence Number: 37 Following a downpower from 100%, the crew determines that emergency boration is required.

NO Boric Acid Transfer Pumps will start.

Per 0POP04-CV-0003, Emergency Boration, the crew will borate using _______(1)______.

This flowpath ___(2)___ be aligned from the Control Room.

A. (1) gravity feed (2) can NOT B. (1) gravity feed (2) can C. (1) the RWST (2) can NOT D. (1) the RWST (2) can Answer: A (1) gravity feed (2) can NOT Page 73 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2886 Source: New Modified from K/A Catalog Number: APE 024 AA2.02 Emergency Boration: Ability to determine and interpret the following as they apply to the Emergency Boration:

When use of manual boration valve is needed.

RO Importance: 3.9 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 505.01 Objective Number: 92109 Given a plant condition, describe and/or interpret the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

0POP04-CV-0003, Step 5.0 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: With no BAT pumps available, gravity feed to the charging pumps must be locally aligned.

B: INCORRECT: Plausible with confusion about procedural priorities and equipment necessary for boration.

C: INCORRECT: Plausible with confusion about procedural priorities and equipment necessary for boration.

D: INCORRECT: Plausible with confusion about procedural priorities and equipment necessary for boration.

Question Level: H Question Difficulty 3 Justification:

The student must assess the plant condition and determine the correct procedural actions.

Page 74 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2890 Last used on an NRC exam: Never RO Sequence Number: 38 The unit is at 100%.

The Unit Supervisor enters 0POP04-RC-0003, Excessive RCS Leakage.

0PSP03-RC-0006, Reactor Coolant Inventory, is performed with the following results:

o 1.3 gpm leakage to the PRT.

o 0.8 gpm leakage to unknown locations inside containment.

o 0.15 gpm leakage to Steam Generator 1A.

o 2.5 gpm leakage through XSI0007A, 6 Train A HHSI Cold Leg Injection Check Valve With these results, the crew will enter Technical Specification 3.4.6.2, Operational Leakage, for excessive _________________ from the Reactor Coolant System A. pressure boundary leakage.

B. primary to secondary leakage.

C. identified leakage.

D. leakage from XSI0007A.

Answer: B primary to secondary leakage.

Page 75 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2890 Source: New Modified from K/A Catalog Number: APE 078 G2.2.42 RCS Leak: Ability to recognize system parameters that are entry level conditions for Technical Specifications.

RO Importance: 3.9 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(3)

STP Lesson: LOT 503.01 Objective Number: 80056 Determine the applicable Technical Specification and/or TRM LCOs and the required actions to be taken.

Reference:

TS 3.4.6.2, 0POP04-RC-0003, Step 4.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student incorrectly equates SG leakage or pressurizer PORV leakage with pressure boundary leakage.

B: CORRECT: 0.15 gpm leakage exceeds 150 gpd for any one SG which is TS entry conditions.

C: INCORRECT: Plausible if the student confuses the limits for identified and unidentified leakage when assessing leakage to the PRT.

D: INCORRECT: Plausible if the student believes check valve leakage is required to be less than 1 gpm, rather than the actual 0.5 gpm for inch of valve size.

Question Level: H Question Difficulty 3 Justification:

The student must recall TS RCS leakage limits and assess the leaks in progress.

Page 76 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2889 Last used on an NRC exam: Never RO Sequence Number: 39 The control room has been evacuated.

The crew is performing 0POP04-ZO-0001, Control Room Evacuation.

Complete the following regarding the performance of this procedure.

1. Transfer of control to the ASP for TDAFWP 14 is performed at ______(1)______.

2. The RO will control SG levels from the ASP by supplying all SGs with flow from

________(2)________.

A. (1) the ASP (2) TDAFWP 14 ONLY B. (1) the ASP (2) ALL AFW pumps C. (1) ZLP-653 (ESF Train A Transfer Panel)

(2) TDAFWP 14 ONLY D. (1) ZLP-653 (ESF Train A Transfer Panel)

(2) ALL AFW pumps Answer: B (1) the ASP (2) ALL AFW pumps Page 77 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2889 Source: New Modified from K/A Catalog Number: APE 068 AK2.01 Knowledge of the interrelations between the control room evacuation and the following: Auxiliary shutdown panel layout.

RO Importance: 3.9 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 505.01 Objective Number: 92111 DESCRIBE the general sequence of operation in the referenced procedure.

Reference:

0POP04-ZO-0001, Steps 13 and 54 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as there are specific steps to transfer TDAFWP 14 at the ASP within the procedure, and if the student believes only the steam driven AFWP would be used for SG level control.

B: CORRECT: All AFW pumps would be transferred to the ASP (TDAFWP 14 has transfer switches at the ASP, all other AFW pumps have transfer switches in the respective ESF switchgear rooms).

Following transfer each AFW pump would supply its own steam generator.

C: INCORRECT: Plausible as the other 3 AFW pumps all have control transferred at ZLPs and if the student believes only the steam driven AFWP would be used for SG level control.

D: INCORRECT: Plausible as the other 3 AFW pumps all have control transferred at ZLPs. All AFWPs will provide flow.

Question Level: F Question Difficulty 3 Justification:

The student must know how to operate the AFW system from the ASP using the procedure.

Page 78 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2888 Last used on an NRC exam: Never RO Sequence Number: 40 A fire in the EAB has occurred.

The crew is performing 0POP04-ZO-0009, Fire/Explosion, Step 38.

The fire was reported 45 minutes ago and is NOT extinguished.

The performance of step 38 A. isolates all trains of EAB HVAC to prevent further spread of smoke and fire.

B. places all trains of EAB HVAC in smoke purge to dissipate smoke.

C. isolates all trains of CR HVAC to prevent further spread of smoke and fire.

D. places all trains of CR HVAC in smoke purge to dissipate smoke.

Answer: A isolates all trains of EAB HVAC to prevent further spread of smoke and fire.

Page 79 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2888 Source: New Modified from K/A Catalog Number: APE 067 AK3.04 Knowledge of the reasons for the following responses as they apply to the plant fire on site: Actions contained in EOP for plant fire on site.

RO Importance: 3.3 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 505.01 Objective Number: 92110 Given a precaution, note, or step(s) and the context in which it is used from the referenced procedure, describe its basis and any applicable limits.

Reference:

0POP04-ZO-0009, Step 37, 38 and bases.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: These switches close the supply, return, and exhaust dampers to EAB HVAC to prevent the further spread of smoke and fire.

B: INCORRECT: Plausible as EAB HVAC is operated and smoke purge is an option for clearing smoke after a fire is out.

C: INCORRECT: Plausible with confusion over CR vs. EAB HVAC. This is the action that occurs.

D: INCORRECT: Plausible with confusion over CR vs. EAB HVAC and smoke purge is an option for clearing smoke after a fire is out.

Question Level: F Question Difficulty 3 Justification:

The student must know the action accomplished by step 38 and the purpose of the step.

Page 80 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2885 Last used on an NRC exam: Never RO Sequence Number: 41 With the unit at 100%, Control Bank D Rod D12 dropped into the core.

The crew is performing 0POP04-RS-0001, Control Rod Malfunction, and preparing to recover Rod D12.

To recover Rod D12, the RO will open lift disconnect switches for the remaining 4 Control Bank D Rods in the ________(1)_______.

The remaining 4 Control Bank D Rods will remain OPERABLE because they are still

___________(2)_____________.

A. (1) Rod Drive room (2) trippable B. (1) Rod Drive room (2) above Rod Insertion Limits C. (1) Control Room (2) trippable D. (1) Control Room (2) above Rod Insertion Limits Answer: C (1) Control Room (2) trippable Page 81 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2885 Source: New Modified from K/A Catalog Number: 003 AK3.08 Dropped Control Rod: Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Criteria for inoperable control rods.

RO Importance: 3.1 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 505.01 Objective Number: 92109 Given a plant condition, describe and/or interpret the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

0POP04-RS-0001, Addendum 1, Page 1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as other features on the control rod drive system are operated from the Rod Drive Room. The rods do remain operable because they are trippable.

B: INCORRECT: Plausible as other features on the control rod drive system are operated from the Rod Drive Room and if the student believes operability is related to rod position only.

C: CORRECT: The rod lift disconnect switch panel is in the back of the control room. Opening lift disconnect switches prevents use but does not make the control rod inoperable because it is still trippable.

D: INCORRECT: Plausible as the rod lift disconnect switch panel is in the back of the control room and if the student believes that operability is related to rod position only.

Question Level: F Question Difficulty 3 Justification:

The student must know when a control rod is considered inoperable by having knowledge of an AOP.

Page 82 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2877 Last used on an NRC exam: Never RO Sequence Number: 42 The unit is at 3% reactor power.

The controlling Pressurizer Pressure transmitter PT-457 fails HIGH.

The crew responds with 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control.

The RO reports that the Loop A Spray Valve, PCV-0655C, is open and cannot be closed from CP-004.

Based on this event, the crew will ________(1)_______ in order to _____(2)_____.

A. (1) stop RCP 1A ONLY (2) stop flow through PCV-0655C B. (1) trip the reactor then stop RCP 1A and RCP 1D (2) stop flow through PCV-0655C C. (1) isolate Instrument Air to containment (2) fail PCV-0655C closed D. (1) open the Auxiliary Spray Valve, LV-3119 (2) route spray flow away from the pressurizer.

Answer: B (1) trip the reactor then stop RCP 1A and RCP 1D. (2) stop flow through PCV-0655C Page 83 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2877 Source: New Modified from K/A Catalog Number: APE 027 AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction RO Importance: 3.7 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 505.01 Objective Number: 92110 Given a precaution, note, or step(s) and the context in which it is used from the referenced procedure, describe its basis and any applicable limits.

Reference:

0POP04-RP-0002, Step 4 and basis Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this would slow down spray flow through the spray line but this action is not taken with the reactor critical.

B: CORRECT: With a spray valve failed open, the procedure directs the user to trip the reactor and then trip both RCPs that provide forced flow to the spray system. The reason for this action is to terminate flow through the spray line. The reactor is tripped because the reactor may not be critical without 4 RCPs in service.

C: INCORRECT: Plausible as the spray valves are air operated and they would fail closed on a loss of instrument air, but not a procedural action.

D: INCORRECT: Plausible as the auxiliary spray valve provides flow in a common line with the spray valves and if the student confuses the source of auxiliary spray. When auxiliary spray is in service under certain plant conditions, the rate of flow into the pressurizer is controlled by opening spray valves.

Question Level: H Question Difficulty 3 Justification:

The student must assess conditions and determine the proper course of action then recall the reason for the action taken.

Page 84 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2946 Last used on an NRC exam: Never RO Sequence Number: 43 In order to verify a current alarm is consistent with plant conditions, ________(1)________

requires that the RO validate the alarm by ___________(2)___________.

A. (1) 0PGP03-ZA-0010, Performing and Verifying Station Activities (2) comparing it with other indications B. (1) 0PGP03-ZA-0010, Performing and Verifying Station Activities (2) verifying the ICS point that drives the alarm is in the proper state C. (1) the Conduct of Operations (2) comparing it with other indications D. (1) the Conduct of Operations (2) verifying the ICS point that drives the alarm is in the proper state Answer: C (1) the Conduct of Operations (2) comparing it with other indications Page 85 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2946 Source: New Modified from K/A Catalog Number: G2.4.46 Ability to verify that the alarms are consisent with the plant conditions.

RO Importance: 4.2 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 505.01 Objective Number: 92107 Discuss automatic actions expected to occur on entry conditions for the reference procedure.

Reference:

Conduct of Operations, Chapter 2, Step 2.1.7 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as 0PGP03-ZA-0010 does contain requirements for operator activities.

This is the correct method to validate an alarm.

B: INCORRECT: Plausible as 0PGP03-ZA-0010 does contain requirements for operator activities and many alarms are driven from ICS but not the required actions to validate the alarm.

C: CORRECT: When an alarm is received, the Conduct of Operations requires the RO to validate the alarm by comparing it with other indications.

D: INCORRECT: Plausible as the Conduct of Operations is used for annunciator response and many alarms are driven from ICS but not the required actions to validate the alarm.

Question Level: F Question Difficulty 3 Justification:

The student must recall information from the Conduct of Operations.

Page 86 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2731 Last used on an NRC exam: Never RO Sequence Number: 44 The unit is at 100% power.

Pressurizer Level Control is selected to L465/466.

Pressurizer Level Channel LT-465 fails low.

The crew enters 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control.

The Pressurizer heaters will be ___(1)___

AND to maintain Pressurizer level, the crew will _______(2)_______.

A. (1) OFF (2) take manual control of charging ONLY B. (1) OFF (2) take manual control of charging AND place Excess Letdown in service C. (1) ON (2) take manual control of charging ONLY D. (1) ON (2) take manual control of charging AND place Excess Letdown in service Answer: B (1) OFF (2) take manual control of charging AND place Excess Letdown in service Page 87 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2731 Source: Bank Modified from K/A Catalog Number: 011 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate, the consequences of those malfunctions or operations: Isolation of letdown RO Importance: 3.8 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.14 Objective Number: 92779 GIVEN plant conditions, DETERMINE their effects on the Pressurizer pressure and level control system.

Reference:

0POP04-RP-0002; and LOT 201.14 Powerpoint Presentation, Slide 49 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: The heaters will be off and the crew will take manual control of charging. Incorrect because letdown isolates on a 465 failure so the POP04 will have the crew also place excess letdown in service. Plausible because letdown will not isolate if 466 or 467 fails low.

B: CORRECT: L465 failing low turns heaters off and isolates letdown. Therefore the POP04 will have the crew take manual control of charging and place excess letdown in service.

C: INCORRECT: The heaters will turn off. Plausible because the heaters will not turn off if 468 failed low. Also incorrect because letdown isolates on a 465 failure so the POP04 will have the crew also place excess letdown in service. Plausible because letdown will not isolate if 466 or 467 fails low.

D: INCORRECT: The heaters will turn off. Plausible because the heaters will not turn off if 468 failed low.

Question Level: H Question Difficulty 3 Justification:

Student must analyze given conditions and predict the operation of letdown.

Page 88 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2152 Last used on an NRC exam: 2013 RO Sequence Number: 45 The unit is at 100% power.

The crew is performing 0POP04-RC-0002, Reactor Coolant Pump Off Normal Step 2.0, CHECK RCP Motor Upper and Lower Thrust Bearing Temperatures - LESS THAN 195°F, is in progress.

The RO reports that RCP 1A Upper Thrust Bearing Temperature is 202°F and rising.

As part of the validation of the high temperature, the operator is asked to evaluate RCP upper oil reservoir levels. This action will be accomplished by checking __________(1)___________ on CP-005.

If the high thrust bearing temperature is validated, the crews action will be to

________(2)________.

A. (1) oil levels (2) place an additional train of CCW in service B. (1) oil levels (2) trip the reactor then stop RCP 1A C. (1) for the presence of an alarm (2) place an additional train of CCW in service D. (1) for the presence of an alarm (2) trip the reactor then stop RCP 1A.

Answer: D (1) for the presence of an alarm (2) trip the reactor then stop RCP 1A Page 89 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2152 Source: Bank Modified from K/A Catalog Number: APE 015 AA1.02 Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP oil reservoir level and alarm indicators RO Importance: 2.8 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(3)

STP Lesson: LOT 201.05 Objective Number: 4829 DESCRIBE the instrumentation available for the reactor coolant pumps in the control room and locally.

Reference:

0POP04-RC-0002, Step 2; 0POP04-AN-05M2, 5M02-C-1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as the RCP does have indications and controls on CP-005 but not oil levels and CCW is the cooling water the the oil reservoirs and is part of the validation process.

B: INCORRECT: Plausible as the RCP does have indications and controls on CP-005 but not oil levels. This is the correct action.

C: INCORRECT: Plausible as oil levels are checked via the presence of an alarm on CP-005 and CCW is the cooling water to the oil reservoirs and is part of the validation process.

D: CORRECT: Oil levels can only be checked via the presence of an RCP UPPR OIL RSVR HI/LO alarm on CP-005. Actual levels must be observed locally. If thrust bearing temperatures are validated to be over 195F, then the reactor is tripped and the RCP is stopped.

Question Level: F Question Difficulty 3 Justification:

The student must have knowledge of the annunciator location for RCP oil reservoir levels in the control room and a basic knowledge of containment conditions (radiologically) under these plant conditions.

Page 90 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1657 Last used on an NRC exam: 2007 RO Sequence Number: 46 The unit is at 100% power.

Instrument Air to the MAB has isolated.

Based on this event, charging flow will ______(1)______ and per 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control, the crew will secure charging and place the

_______(2)_______ in service.

A. (1) rise (2) alternate charging path B. (1) rise (2) PDP C. (1) lower (2) alternate charging path D. (1) lower (2) PDP Answer: A (1) rise (2) alternate charging path Page 91 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1657 Source: Bank Modified from K/A Catalog Number: 004 A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of IAS RO Importance: 3.6 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.06 Objective Number: 50297 Given a valve in the CVCS System, DESCRIBE the fail position of that valve and the reason.

Reference:

0POP04-CV-0004, Step 6 and Page 2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: On a loss of instrument air to the MAB, Charging Flow Control Valve FCV-205 will fail open. The crew will secure charging and then place the alternate charging path, which bypasses FCV-205 in service.

B: INCORRECT: Plausible as pressurizer level will rise, and the PDP could be used to supply charging, but not necessary here.

C: INCORRECT: Plausible with confusion about the effect of the loss of instrument air on the CVCS.

This is the correct action.

D: INCORRECT: Plausible with confusion about the effect of the loss of instrument air on the CVCS and the PDP could be used to supply charging, but not necessary here.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and determine what has occurred and the appropriate course of action.

Page 92 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1577 Last used on an NRC exam: 2015 RO Sequence Number: 47 With the unit at 100% power a condition that required a reactor trip arose.

The RO unsuccessfully attempted to trip the reactor from both reactor trip switches.

Next, per 0POP05-EO-EO00, Reactor Trip or Safety Injection, the RO is required to open

_____(1)_____.

Completing this action ______(2)_____ OPEN the reactor trip breakers.

A. (1) BOTH LC 1K1 and 1L1 feeder breakers (2) will B. (1) BOTH LC 1K1 and 1L1 feeder breakers (2) will NOT C. (1) EITHER LC 1K1 or 1L1 feeder breaker (2) will D. (1) EITHER LC 1K1 or 1L1 feeder breaker (2) will NOT Answer: B (1) BOTH LC 1K1 and 1L1 feeder breakers (2) will NOT Page 93 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1577 Source: Bank Modified from K/A Catalog Number: APE 029 EK2.06 Knowledge of the interrelations between the ATWS and the following: Breakers, relays and disconnects RO Importance: 2.9 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.18 Objective Number: 3069 IDENTIFY major components, system interfaces, interlocks and relative location of components and instrumentation by drawing and labeling a block diagram of the Rod Control System.

Reference:

0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS, Step 1 and basis Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the correct action to take and if the student believes that this action opens the reactor trip breakers instead of deenergizing the Rod Drive MG Sets.

B: CORRECT: Both breakers must be opened to cause the rods to drop by deenergizing the Rod Drive MG Sets. This will not cause the reactor trip breakers to open. A plant operator must be dispatched to open them locally.

C: INCORRECT: Plausible if the student does not realize that both Rod Drive MG Sets are in service at power and if the student believes that this action opens the reactor trip breakers instead of deenergizing the Rod Drive MG Sets.

D: INCORRECT: Plausible if the student does not realize that both Rod Drive MG Sets are in service at power. This action will not trip the reactor.

Question Level: F Question Difficulty 3 Justification:

Must analyze the given condition to determine the affect on the control rod system.

Page 94 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2107 Last used on an NRC exam: 2018 RO Sequence Number: 48 Due to a LOCA inside the FHB, the crew manually tripped the reactor and initiated Safety Injection.

0POP05-EO-EC12, LOCA Outside Containment is in progress.

RWST level is 150,000 gallons and dropping slowly.

The crew has reset SI and ESF Load Sequencers from the control room panels.

Complete the following regarding these circumstances:

(1) SI AUTO RECIRC has _____________(1)_____________.

(2) Resetting SI AUTO RECIRC will _____________(2)_____________.

A. (1) NOT occurred (2) allow the ECCS pumps to be manually stopped B. (1) NOT occurred (2) ensure the Emergency Sump Outlet Valves will remain closed C. (1) occurred (2) allow the ECCS pumps to be manually stopped D. (1) occurred (2) ensure the Emergency Sump Outlet Valves to remain closed Answer: B (1) NOT occurred (2) ensure the Emergency Sump Outlet Valves will remain closed Page 95 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2107 Source: Bank Modified from K/A Catalog Number: EPE W/E04 EK2.1 Knowledge of the interrelations between the (LOCA Outside Containment) and the following: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

RO Importance: 3.5 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.10 Objective Number: 29419 GIVEN a plant condition, PREDICT the operation of the ECCS to include automatic actuations, interlocks and/or trips.

Reference:

0POP05-EO-EC12; LOT 504.46, Powerpoint slide 18 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as SI AUTO RECIRC has not occurred, and if the student confuses resetting SI, which does allow the manual stopping of ECCS pumps, with resetting SI AUTO RECIRC.

B: CORRECT: SI AUTO RECIRC has not occurred since RWST level has not reached 75,000 gallons. This action is taken since establishing suction to containment with a LOCA outside containment would result in losing suction to the ECCS pumps.

C: INCORRECT: Plausible since there is a RWST LO LEVEL alarm illuminated by this point and if the operator confuses resetting SI, which does allow the manual stopping of ECCS pumps, with resetting SI AUTO RECIRC.

D: INCORRECT: Plausible since there is a RWST LO LEVEL alarm illuminated by this point and this is the correct reason for resetting SI AUTO RECIRC.

Question Level: H Question Difficulty 3 Justification:

Student must know the control features of the ECCS and be able to use them to predict their effect when used under the given plant conditions.

Page 96 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2310 Last used on an NRC exam: Never RO Sequence Number: 49 The crew is performing 0POP05-EO-FRZ1, Response to High Containment Pressure.

The RO is directed to verify At least one Containment Spray Pump - RUNNING.

To complete this step, the RO will use which indications?

A. Discharge valve OPEN and FLOW indication B. Discharge valve OPEN and Discharge PRESSURE indication C. Motor AMPS > 0 and FLOW indication D. Motor AMPS > 0 and Discharge PRESSURE indication Answer: A Discharge valve OPEN AND FLOW indication Page 97 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2310 Source: Bank Modified from K/A Catalog Number: 026 G2.2.44 Containment Spray: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

RO Importance: 4.2 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(8)

STP Lesson: LOT 504.40 Objective Number: 84127 Given a copy of a step, caution, or note from POP05-EO-FRZ1, STATE/IDENTIFY how the action is performed and the basis for the step, caution or note to include its purpose and the adverse impact of failure to comply with the step, caution or note

Reference:

0POP05-EO-FRZ1, Step 1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Indications used per procedure B: INCORRECT: Plausible because both would indicate pump operation and discharge pressure is provided for some pumps on the control boards but CS pumps do not. Discharge valve open is correct.

C: INCORRECT: Plausible because motor amps would indicate motor operation and some pumps do have this indication on the control board, but CS pumps do not. Flow indication is correct.

D: INCORRECT: Plausible because motor amps would indicate motor operation (and some pumps do have this indication on the control board) and discharge pressure is provided for some pumps on the control boards but not the CS pumps.

Question Level: F Question Difficulty 3 Justification:

Knowledge of procedures, system design required.

Page 98 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2601 Last used on an NRC exam: 2016 RO Sequence Number: 50 Which of the following procedures takes precedence over all Emergency Operating Procedures?

A. 0POP05-EO-FRS1, Response to Nuclear Generation - ATWS B. 0POP05-EO-EC00, Loss of All AC Power C. 0POP05-EO-EO00, Reactor Trip or Safety Injection D. 0POP05-EO-ES13, Transfer To Cold Leg Recirculation Answer: B 0POP05-EO-EC00, Loss of All AC Power Page 99 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2601 Source: Bank Modified from K/A Catalog Number: G2.4.6 Knowledge of EOP Mitigation Strategies RO Importance: 3.7 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.04 Objective Number: 92283 Given a set of conditions and the occurrence of a red, orange, or yellow path CSF, state the action required per 0POP01-ZA-0018, EOP Users Guide.

Reference:

0POP01-ZA-0018, Step 7.1.3 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible because it is the highest priority CSF. Incorrect because 0POP05-EO-EC00 takes priority over FRPs.

B: CORRECT: 0POP05-EO-EC00 takes precedence over the FRPs and all other EOPs due to specific initiating events per 0POP01-ZA-0018.

C: INCORRECT: Plausible because it is the first procedure you would enter after a reactor trip if there was not a complete loss of all AC power. Incorrect because 0POP05-EO-EC00 takes priority D: INCORRECT: Plausible because it takes priority over all other EOPs if swap over conditions exist.

Incorrect, because entry into 0POP05-EO-EC00 SHALL be entered during the performance of ANY other EOP.

Question Level: F Question Difficulty 3 Justification:

The student needs to have fundamental knowledge of Emergency Operating Procedure Mitigation Strategies.

Page 100 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2871 Last used on an NRC exam: Never RO Sequence Number: 51 Per 0PGP03-ZA-0506, Conduct of Tests or Evolutions Requiring Additional Controls, an example of a SPECIAL TEST would be A. Midloop Operations B. Vacuum Fill C. Standby Diesel 11 LOOP Test D. Standby Diesel Generator Governor Upgrade Acceptance Test Answer: D Standby Diesel Generator Governor Upgrade Acceptance Test Page 101 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2871 Source: New Modified from K/A Catalog Number: G2.2.7 Knowledge of the process for conducting special or infrequent tests.

RO Importance: 2.9 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 507.01 Objective Number: 92186 Given the title of an administrative procedure, discuss the requirements associated with the referenced procedure.

Reference:

0PGP03-ZA-0506, Section 3.0, Steps 3.4, 3.5, 3.7.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is an INFREQUENTLY PERFORMED EVOLUTION per ZA-0506 B: INCORRECT: Plausible as this is an INFREQUENTLY PERFORMED EVOLUTION per ZA-0506 C: INCORRECT: Plausible as this is an INFREQUENTLY PERFORMED TEST in ZA-0506.

D: INCORRECT: Correct.

Question Level: F Question Difficulty 3 Justification:

This question requires recall of information from two STP procedures governing infrequently performed tests and evolutions.

Page 102 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2874 Last used on an NRC exam: Never RO Sequence Number: 52 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, Step 2, requires the crew to depressurize intact SGs to less than 1000 psig.

Per the EOP basis document, this action is intended to mitigate the consequences of a

_____(1)_____ break LOCA. The reason for taking this action is to ensure

__________(2)__________.

A (1) small (2) peak clad temperature remains below 2200ºF B. (1) small (2) maximum heat transfer to the steam generators C. (1) large (2) peak clad temperature remains below 2200ºF D. (1) large (2) maximum heat transfer to the steam generators Answer: A (1) small (2) peak clad temperature remains below 2200F Page 103 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2874 Source: New Modified from K/A Catalog Number: EPE 009 EK3.21 Knowledge of the reasons for the following responses as they applly to the Small Break LOCA: Actions contained in the EOPs for a small break LOCA.

RO Importance: 4.2 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.09 Objective Number: 81084 Given a copy of a step from 0POP05-EO-EO10, state/identify how the action is performed and the basis for the action to include the action itself, its purose, and the result.

Reference:

LOT504.09 Powerpoint Presentation, slide 22, 0POP05-EO-EO10, Step 2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Step 2 is designed to lower steam generator pressures and assist the RCS in clearing the loop seal earlier so as to avoid a deeper core uncovery. This is an issue for SBLOCAs. The basis for this is to maintain peak clad temperatures below the 10CFR ECCS Acceptance Criteria limit.

B: INCORRECT: Plausible as this is the correct accident and that the student thinks that AFW flow would increase and is vital towards the response to a SBLOCA.

C: INCORRECT: Plausible if the student believes that core cooling or reflux flow on a LBLOCA would be enhanced by steaming the generators down in pressure. This is the correct reason for the response.

D: INCORRECT: Plausible if the student believes that core cooling or reflux flow on a LBLOCA would be enhanced by steaming the generators down in pressure and that AFW flow would increase.

Question Level: F Question Difficulty 3 Justification:

This question requires recall of an EOP step and its basis.

Page 104 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2875 Last used on an NRC exam: Never RO Sequence Number: 53 A Large Break LOCA has occurred in Unit 1.

The crew has completed 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

Containment pressure is 6 psig and slowly lowering.

The TSC has NOT been activated.

At this point, ____ Containment Spray Pumps are running.

A. 0 B. 1 C. 2 D. 3 Answer: C 2 Page 105 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2875 Source: New Modified from K/A Catalog Number: EPE 011 EK2.02 Knowledge of the interrelations between the following and a Large Break LOCA: Pumps RO Importance: 2.6 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.09 Objective Number: 81103 From memory, state/identify the criteria on the conditional information page of POP05-EO-EO10 to include operator response, initiating parameter(s) and values.

Reference:

0POP05-EO-EO00 CIP, 0POP05-EO-EO10, Step 16 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as below 6.5 psig, with TSC concurrence, all CS pumps may be stopped.

B: INCORRECT: Plausible as there are decision tables in other EOPS that allow stopping one or more SI or CS pumps.

C: CORRECT: One CS pump will be stopped in 0POP05-EO-EO00. In 0POP05-EO-EO10, the remaining CS pumps may be stopped if containment pressure is below 6.5 psig, but only with TSC concurrence.

D: INCORRECT: Plausible as 3 pumps automatically start on a large break LOCA.

Question Level: H Question Difficulty 3 Justification:

The student must assess the conditions and determine the plant configuration at a certain point in the EOP sequence.

Page 106 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2879 Last used on an NRC exam: Never RO Sequence Number: 54 The unit is at 100% power.

SG 1A Main Steam Line ruptures inside containment.

All systems function properly.

0POP05-EO-EO20, Faulted Steam Generator Isolation, is in progress.

o Containment pressure is 22.3 psig and lowering.

o SG 1A pressure is 122 psig and dropping.

o Pressurizer pressure is 1600 psig and rising.

Per 0POP05-EO-EO20, Step 4, to COMPLETE the isolation of SG 1A, the crew will close SG 1A A. AFW OCIV.

B. FWIV.

C. MSIV and MSIV Bypass Valve.

D. Sample and Blowdown Isolation Valves.

Answer: A AFW OCIV.

Page 107 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2879 Source: New Modified from K/A Catalog Number: APE 040 G2.1.20 Steam Line Rupture - Excessive Heat Transfer: Ability to interpret and execute procedure steps.

RO Importance: 4.6 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.13 Objective Number: 92146 State/identify the valves which must be shut to isolate a faulted steam generator.

Reference:

0POP05-EO-EO20, Step 4 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: With a Safety Injection signal, a Feedwater Isolation signal, and a Main Steam Line Isolation signal, all valves close automatically except for the AFW OCIV, which opened on an SI signal.

B: INCORRECT: Plausible with confusion over automatic features and the isolation sequence.

C: INCORRECT: Plausible with confusion over automatic features and the isolation sequence.

D: INCORRECT: Plausible with confusion over automatic features and the isolation sequence.

Question Level: H Question Difficulty 3 Justification:

The student is required to apply knowledge of faulted steam generator isolation and automatic features to a set of plant conditions and draw a conclusion about actions required.

Page 108 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2880 Last used on an NRC exam: Never RO Sequence Number: 55 The unit has lost all AC power.

The crew has just entered 0POP05-EO-EC00, Loss of All AC Power.

After an initial assessment, the crew determines that the time to restore one ESF 4160V Bus is estimated to be 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Complete the following regarding this event:

The performance of 0POP05-EO-EC00, Addendum 4, Vital DC Bus Monitoring, ____(1)____

required.

The purpose of Addendum 4 is to ensure battery capacity is sufficient to maintain ____(2)____.

A. (1) is (2) vital instrumentation channels available B. (1) is (2) the ability to operate Pressurizer PORVs C. (1) is NOT (2) vital instrumentation channels available D. (1) is NOT (2) the ability to operate Pressurizer PORVs Answer: A (1) is (2) vital instrumentation channels will be available Page 109 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2880 Source: New Modified from K/A Catalog Number: APE 055 EK3.01 Station Blackout: Knowledge of the reasons for the following responses as they apply to the SBO: Length of time for which battery capacity is designed.

RO Importance: 2.7 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.22 Objective Number: 82073 Given a copy of a step, caution, or note from 0POP05-EO-EC00, state/identify its basis, its purpose, and the result of a failure to comply with its requirements.

Reference:

Calculation 13-DJ-006, Page 6; 0POP05-EO-EC00, pages 1-12, Addendum 4 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: After a loss of all AC power, at step 7, the crew will shed DC loads to preserve battery capacity. The reason that this Addendum is performed if for instrumentation channels to be available to cope with the duration of the station blackout.

B: INCORRECT: Plausible as the performance of Addendum 4 is required. The Pressurizer PORVs are powered from Class 1E 125VDC power; are used in EC00; are mentioned in the calcuation of the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping strategy, but not the reason for the performance of Addendum 4.

C: INCORRECT: Plausible if the student does not understand the sequence of re-energization with the performance of other actions. This is the correct reason.

D: INCORRECT: Plausible if the student does not understand the sequence of re-energization with the performance of other actions.The Pressurizer PORVs are powered from Class 1E 125VDC power; are used in EC00; are mentioned in the calcuation of the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping strategy, but not the reason for the performance of Addendum 4.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and determine a course of action.

Page 110 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2882 Last used on an NRC exam: Never RO Sequence Number: 56 The unit is at 100% power.

A loss of offsite power occurs.

ECW Pump 1C will NOT start.

Complete the following regarding this situation:

The operator action that is required first is to ________(1)_______.

If this action is NOT taken, overheating could occur in as little as __(2)___ minutes.

A. (1) take ESF DG 13 to Pull-To-Stop (2) 8 B. (1) take ESF DG 13 to Pull-To-Stop (2) 2 C. (1) secure the Charging Pumps (2) 8 D. (1) secure the Charging Pumps (2) 2 Answer: B (1) take ESF DG 13 to Pull-To-Stop (2) 2 Page 111 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2882 Source: New Modified from K/A Catalog Number: APE 062 AA2.06 Loss of Nuclear Service Water: Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss after the loss of SWS flow to a component before that component may be damaged.

RO Importance: 2.8 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.05 Objective Number: 80483 Given a copy of a subsequent step or from memory an immediate action step from 0POP05-EO-EO00, state/identify how the action is performed and the basis for the action to include the action itself, its purpose and result.

Reference:

0POP01-ZA-0018, Page 17; 0POP04-CC-0002, Page 4; 5Q159MB1023 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the correct component, and 8 minutes is the time to damage a charging pump with no CCW flow to the lube oil cooler.

B: CORRECT: Without ECW flow to EDG components, the EDG could overheat in as little as 2 minutes. The EDG needs to be placed in PTS.

C: INCORRECT: Plausible as charging pumps can be damaged with no CCW flow and 8 minutes is the time to damage a charging pump with no CCW flow to the lube oil cooler.

D: INCORRECT: Plausible as charging pumps can be damaged with no CCW flow. This is the correct time.

Question Level: F Question Difficulty 3 Justification:

The student must recall actions required for plant conditions.

Page 112 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2892 Last used on an NRC exam: Never RO Sequence Number: 57 A Small Break LOCA has occurred in the unit.

The crew is performing 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization.

The next step is to cool down the RCS.

The cooldown will be performed at ________(1)________ in order to avoid thermal shock to the

_______(2)_______.

A. (1) maximum rate (2) reactor vessel B. (1) maximum rate (2) RCS to SG nozzles C. (1) less than 100ºF/hour (2) reactor vessel D. (1) less than 100ºF/hour (2) RCS to SG nozzles Answer: C (1) less than 100F/hour (2) reactor vessel Page 113 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2892 Source: Bank Modified from K/A Catalog Number: E03 EA2.2 Ability to determine and interpret the following as they apply to the LOCA Cooldown and Depressurization:

Ability to determine and interpret the following as they apply to the LOCA Cooldown and Depressurization:

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

RO Importance: 3.5 Tier: 1 Group/Category: 2 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.12 Objective Number: 92172 Given a step from 0POP05-EO-ES12, state/identify how the action is performed and the basis for the action to include the action itself, its purpose, and the result.

Reference:

0POP05-EO-ES12, Step 6' LOT 504.12 Powerpoint Presentation, Page 28 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as a max rate cooldown is used in other EOPs. Reactor vessel is correct.

B: INCORRECT: Plausible as a max rate cooldown is used in other EOPs and the SG nozzle is also a critical component but not the issue here.

C: CORRECT: Step 6 requires cooldown to be limited to less than 100F/hour in order to prevent pressurized thermal shock to the reactor vessel.

D: INCORRECT: Plausible as this is the correct cooldown rate limitation and the SG nozzle is also a critical component but not the issue here.

Question Level: F Question Difficulty 3 Justification:

The student must recall the required cooldown rate and the basis for the requirement.

Page 114 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2897 Last used on an NRC exam: Never RO Sequence Number: 58 With the unit at 100% power, a Loss of Offsite Power occurred.

The crew is performing 0POP05-EO-ES01, Reactor Trip Response.

The following conditions exist:

o RCS pressure is 1925 psig and lowering.

o CET temperatures are 605ºF and rising.

o S/G pressures are 1050 psig and lowering.

o RCS Thots are 600ºF and rising.

o RCS Tcolds are 595 ºF and rising.

o The QDPS Subcooling Margin indication is NOT available.

Per 0POP05-EO-ES01, Reactor Trip Response, the crew should A. raise the steam dumping rate.

B. raise AFW flow rate.

C. actuate SI.

D. energize pressurizer heaters.

Answer: C actuate SI.

Page 115 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2897 Source: Bank Modified from K/A Catalog Number: 006 K6.18 Emergency Core Cooling: Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Subcooling margin indicators.

RO Importance: 3.6 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 504.06 Objective Number: 81674 Given a step, note, or caution from 0POP05-EO-ES01, STATE/IDENTIFY the basis for the step, note or caution and the basis for the action to include the action itself, its purpose and result.

Reference:

0POP05-EO-ES01, CIP Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as natural circulation is not occurring, and improving the secondary heat sink would assist, but not the required action now.

B: INCORRECT: Plausible as natural circulation is not occurring, and improving the secondary heat sink would assist, but not the required action now.

C: CORRECT: With RCS pressure at 1925 psig (1940 psia), Tsat is 632F. Subcooling is 27F, less than the required 35F. The crew must actuate SI and return to 0POP05-EO-EO00.

D: INCORRECT: Plausible as subcooling is low and pressurizer heaters would raise subcooling, but not the action required here.

Question Level: H Question Difficulty 3 Justification:

The student must be able to calculate subcooling and relate it to the performance of a post-LOCA cooldown and depressurization.

Page 116 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2906 Last used on an NRC exam: Never RO Sequence Number: 59 The crew is responding to a tube rupture on SG C.

The cooldown is in progress per 0POP05-EO-EO30, Steam Generator Tube Rupture.

The following parameters are observed:

Pressure Level Main Steamline Radiation SG A 910 psig and lowering 17% NR and lowering 2.0E-2 and stable SG B 910 psig and lowering 23% NR and lowering 2.0E-2 and stable SG C 1190 psig and lowering 44% NR and stable 1.8E-1 and rising SG D 910 psig and lowering 23% NR and stable 1.2E-1 and rising With these conditions, the crew will A. continue the cooldown.

B. stop the cooldown and return to step 1 of 0POP05-EO-EO30.

C. transition to 0POP05-EO-EO20, Faulted Steam Generator Isolation.

D. transition to 0POP05-EO-EC31, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

Answer: B stop the cooldown and return to step 1 of 0POP05-EO-EO30.

Page 117 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2906 Source: Modified Modified from 2681 K/A Catalog Number: 039 AA2.03 Main and Reheat Steam: Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Indications and alarms for main steam and area radiation monitors (during SGTR).

RO Importance: 3.4 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.15 Objective Number: 92408 Given a copy of a step from 0POP05-EO-EO30, state/identify how the action is performed and the basis for the action to include the action itself, its purpose and the result.

Reference:

0POP05-EO-EO30, CIP Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student assesses the condition as normal and continues the cooldown for the "A" SG.

B: CORRECT: The indications show that 'C' SG is indicating a SGTR as well as 'D' SG. If a second SG is identified as ruptrured once a cooldown has been started, then the correct action to take is to stop the cooldown in progress and return to the beginning of EO30.

C: INCORRECT: Plausible because the CIP of EO30 states that if any SG pressure is lowering in an uncontrolled manner then transition to EO20. Plausible with the given SG pressure indications that the student may think that the SGs are depressing uncontrollably and would need to transition to EO20.

D: INCORRECT: Plausible because there are 10 different ways to transition out of EO30 to EC31. (i.e.

if a student believed there is no intact SG available for the cooldown)

Question Level: H Question Difficulty 3 Justification:

Student must be able to analyze given conditions and determine how to correctly apply the EOPs to mitigate the event.

Page 118 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2915 Last used on an NRC exam: Never RO Sequence Number: 60 A Large Break LOCA has occurred in the unit.

Due to multiple failures the crew has entered 0POP05-EO-FRC1, Response to Inadequate Core Cooling.

No ECCS flow is available.

A Steam Generator Depressurization to atmospheric pressure has been completed.

Complete the following:

CET temperatures in the control room may be obtained from ____(1)____.

If CET temperatures are still above ____(2)____ºF, then an RCP will be started.

A. (1) indicators on CP-005 (2) 708 B. (1) QDPS (2) 708 C. (1) indicators on CP-005 (2) 1200 D. (1) QDPS (2) 1200 Answer: D (1) QDPS (2) 1200 Page 119 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2915 Source: New Modified from K/A Catalog Number: 017 A4.02 Ability to manually operate and/or monitor in the control room: Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values)

RO Importance: 3.8 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 504.30 Objective Number: 82891 Given a step, note, or caution from POP05-EO-FRC1, STATE the basis.

Reference:

0POP05-EO-FRC1, Pages 19-20 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as several other RCS temperature indications are available on the control boards 708F is the entry condition temperature for 0POP05-EO-FRC2 and is also mentioned in FRC1 in a step and a note.

B: INCORRECT: Plausible as QDPS is correct and 708F is the entry condition temperature for 0POP05-EO-FRC2 and is also mentioned in FRC1 in a step and a note.

C: INCORRECT: Plausible as several other RCS temperature indications are available on the control boards. This is the correct temperature for the action.

D: CORRECT: Following a complete SG depressurization, a check is once again made for SI flow. If none can be established, and CETs are still over 1200F, RCPs can be started without support conditions established as a last resort. CET temperatures are availabe on QDPS or ICS.

Question Level: F Question Difficulty 3 Justification:

The student must recall steps from 0POP05-EO-FRC1.

Page 120 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2916 Last used on an NRC exam: Never RO Sequence Number: 61 A Large Break LOCA has occurred in the unit.

The crew is performing 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

They are currently monitoring Containment H2 Concentration.

If Containment H2 Concentration is __(1)__%, then the crew will _____(2)_____.

A. (1) 0.1 (2) place H2 Recombiners in service B. (1) 0.1 (2) consult TSC staff C. (1) 6.0 (2) place H2 Recombiners in service D. (1) 6.0 (2) consult TSC staff Answer: D (1) 6.0 (2) consult TSC staff Page 121 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2916 Source: New Modified from K/A Catalog Number: 028 G2.4.6 Hydrogen Recombiner and Purge Control: Knowledge of EOP mitigation strategies.

RO Importance: 3.7 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(8)

STP Lesson: LOT 504.09 Objective Number: 81084 Given a copy of a step from 0POP05-EO-EO10, state/identify how the action is performed and the basis for the action to include the action itself, its purpose, and the result.

Reference:

0POP05-EO-EO10, Step 12 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this does indicate H2 in containment but the levels are too low to require recombining.

B: INCORRECT: Plausible as this does indicate H2 in containment and the TSC staff does address concerns in this procedure.

C: INCORRECT: Plausible as this percent does exceed 0.5% but excessive to place recombiners in service.

D: CORRECT: The step first of all requires the crew to place the H2 Monitors in service. Then, if H2 concentraton if greater than or equal to 0.5%,and less than 4%, then H2 Recombiners are placed in service to prevent an explosive concentration in containment. Finally, if H2 concentration exceeds 4.0%, the TSC staff is consulted.

Question Level: F Question Difficulty 3 Justification:

The student must recall steps from 0POP05-EO-EO10.

Page 122 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2893 Last used on an NRC exam: Never RO Sequence Number: 62 Following a refueling outage, the crew is performing 0POP03-ZG-0006, Plant Heatup.

The unit is in MODE 4 RCS pressure is 430 psig.

All RCPs are in service.

Answer the following regarding this plant condition.

The RCP #1 Seal DP MINIMUM limit is ______(1)______.

As pressure is raised to 900-1000 psig the DP indication will rise and _______(2)_______.

A. (1) 250 (2) and stabilize at approximately 400 psid B. (1) 250 (2) and go off scale high C. (1) 220 (2) and stabilize at approximately 400 psid D. (1) 220 (2) and go off scale high Answer: D (1) 220 (2) and go off scale high Page 123 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2893 Source: New Modified from K/A Catalog Number: 003 A3.03 Reactor Coolant Pump: Ability to monitor automatic operation of the RCP including: Seal DP.

RO Importance: 3.2 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(3)

STP Lesson: LOT 506.01 Objective Number: 92161 Describe the general sequence of operaton of components in the referenced procedures.

Reference:

0POP02-RC-0002, Step 4.5; 0POP03-ZG-0001, Step 5.12.2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as 250 psid Seal DP is required to start an RCP in 0POP03-ZG-0006 and the top of the DP indicator scale is 400 psid.

B: INCORRECT: Plausible as 250 psid Seal DP is required to start an RCP in 0POP03-ZG-0006 and the indication will go off scale high.

C: INCORRECT: Plausible as this is the correct minimum DP for RCP operation and the top of the DP indicator scale is 400 psid.

D: CORRECT: The minimum DP to operate an RCP per procedure is 220 psid. When pressure is raised in 0POP03-ZG-0006, the control board indication will go off scale high and DP will continue to rise Question Level: H Question Difficulty 3 Justification:

The student must discern the DP behavior as the RCS is pressurized.

Page 124 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2895 Last used on an NRC exam: Never RO Sequence Number: 63 Unit is performing 0POP03-ZG-0009, Mid-Loop Operation.

RHR Trains A and B are in service.

RCS level is +10 and stable.

RCS temperature is 95ºF.

LP Letdown is aligned to RHR Train A.

A complete loss of instrument air occurs. Complete the following regarding this event.

At CP-001, the RO should observe RCS temperature _______(1)_______.

At CP-004, the RO should observe letdown flow ______(2)_____.

A. (1) lowering (2) lowering B. (1) lowering (2) rising C. (1) rising (2) lowering D. (1) rising (2) rising Answer: A (1) lowering (2) lowering Page 125 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2895 Source: New Modified from K/A Catalog Number: 005 A1.02 Residual Heat Removal: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHR controls including: RHR Flow rate.

RO Importance: 3.3 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 506.01 Objective Number: 921160 Given a plant condition, state whether it is in violation of a precaution or step as allowed by the referenced procedure and describe and/or interpret the requirements and/or limits of the precaution or step.

Reference:

0POP04-IA-0001, Basis page 87 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: With a complete loss of instrument air, full cooling flow will be established through the RHR Heat Exchanger with no bypass flow. The letdown pressure control valve, PCV-135 will also close.

B: INCORRECT: Plausible as RCS temperature does lower and if the student misunderstands the effect on LP letdown.

C: INCORRECT: Plausible with a misunderstanding of the loss of instrument air on RHR operations.

Letdown flow does lower.

D: INCORRECT: Plausible with a misunderstanding of the loss of instrument air on RHR operations and also a misunderstanding of the effect on letdown flow.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and determine the outcome and the impact on the plant.

Page 126 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2912 Last used on an NRC exam: Never RO Sequence Number: 64 The crew is performing 0PSP03-SP-0012A, Train A Slave Relay Test.

Actuating Slave Relay K845 will close all the Preheater Bypass Valves.

Actuating Slave Relay K807 will close all the Low Power Feedwater Regulating Valves.

Per 0PSP03-SP-0012A, when this step is performed, the operator will verify the position of the Low Power Feedwater Regulating Valves by _____________(1)____________

AND Preheater Bypass Valves by ____________(2)____________.

A. (1) Plant Computer point or physical valve position (2) Control Board indication B. (1) Plant Computer point or physical valve position (2) Plant Computer point or physical valve position C. (1) Control Board indication (2) Control Board indication D. (1) Control Board indication (2) Plant Computer point or physical valve position Answer: A (1) Plant Computer point or physical valve position (2) Control Board indication Page 127 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2912 Source: New Modified from K/A Catalog Number: 103 A4.03 Containment: Ability to manually operate and/or monitor in the control room: ESF slave relays.

RO Importance: 2.7 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 202.13 Objective Number: 83030 Describe the instrumentation and controls available to monitor and operate the Main Feedwater System

Reference:

CP-006 photographs, LOT202.13, Student Handout, pages 25-27, 0PSP03-SP-0012A, pages Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: The LPFRVs do not have position indication on the control board and must be verified via ICS point or locally. The preheater bypass valves have control board indication.

B: INCORRECT: Plausible with confusion over the numerous valves and indications on CP-006.

C: INCORRECT: Plausible with confusion over the numerous valves and indications on CP-006.

D: INCORRECT: Plausible with confusion over the numerous valves and indications on CP-006.

Question Level: F Question Difficulty 3 Justification:

The student must recall the available controls for valves on CP-006.

Page 128 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2884 Last used on an NRC exam: Never RO Sequence Number: 65 A plant operator is dispatched to the MAB 10, Room 064, to close 1-FC-0076, RWPP Discharge Test Valve Using the provided survey map and RWP, complete the following:

1. This valve is located in a ______(1)______.

2. The dress requirements are____________(2)____________.

A. (1) radiation area ONLY (2) normal work clothing and PPE B. (1) radiation area ONLY (2) one full set protective clothing C. (1) radiation area AND contaminated area (2) two full sets protective clothing D. (1) radiation area and contaminated area (2) one full set protective clothing Answer: D (1) radiation area and contaminated area (2) one full set of protective clothing Page 129 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2884 Source: New Modified from K/A Catalog Number: G2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

RO Importance: 3.5 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(12)

STP Lesson: LOT 507.01 Objective Number: 92186 Given the title of an administrative procedure, DISCUSS the requirements associated with the referenced procedure.

Reference:

RWP 2020-0-0003, 1-MAB +010-TG05 Survey Map Attached Reference

Attachment:

RWP 2020-0-0003, 1-MAB +010-TG05 Survey Map NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion over reading the survey map and RWP requirements.

B: INCORRECT: Plausible with confusion over reading the survey map and RWP requirements.

C: INCORRECT: Plausible with confusion over reading the survey map and RWP requirements.

D: CORRECT: FC-0076 is located in a RA/CA and requires one full set of protective clothing.

Question Level: H Question Difficulty 3 Justification:

The student must interpret the survey map and apply it to the operational situation given.

Page 130 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2415 Last used on an NRC exam: 2018 RO Sequence Number: 66 Per 0PGP03-ZA-0010, Performing and Verifying Station Activities, for continual use operational procedures, verifying the revision is current prior to use means A. each shift.

B. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. within 7 days.

D. when notified by Document Control.

Answer: A each shift Page 131 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2415 Source: Bank Modified from K/A Catalog Number: G2.1.21 Ability to verify the controlled procedure copy.

RO Importance: 3.5 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 507.01 Objective Number: 92186 GIVEN the title of an administrative procedure, DISCUSS the requirements associated with the referenced procedure.

Reference:

0PGP03-ZA-0010, Step 2.13 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: 0PGP03-ZA-0010, Performing and Verifying Station Activities directs continual use procedures must be verified each shift.

B: INCORRECT: Plausible based on common sense and normal frequency of evolutions conducted at power plants.

C: INCORRECT: Plausible based on common sense and normal frequency of evolutions conducted at power plants.

D: INCORRECT: Plausible based on common sense and normal frequency of evolutions conducted at power plants.

Question Level: F Question Difficulty 2 Justification:

Must have general knowledge of 0PGP03-ZA-0010.

Page 132 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1695 Last used on an NRC exam: 2007 RO Sequence Number: 67 RT-8039, Failed Fuel Monitor, has gone into HIGH Alarm.

Surveys indicate that a POINT SOURCE in the 29 MAB is emitting a radiation field of 600 mr/hr at 1-foot.

An individual with a to-date annual exposure (TEDE) of 4810 mr must perform a job in the area.

Which one of the following indicates a distance from the point source and job duration that will cause the individual to EXCEED the 10CFR20 Total Effective Dose Equivalent (TEDE) limit?

Distance - feet Time - hours A. 2 1 B. 3 3 C. 4 5 D. 5 7 Answer: B 3,3 Page 133 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1695 Source: Bank Modified from K/A Catalog Number: 073 K5.03 Knowledge of the operational implications of the following concepts as they apply to the PRM System: Relationship between radiation intensity and exposure limits RO Importance: 2.9 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(12)

STP Lesson: LOT 103.04 Objective Number: N91826 CALCULATE dose rates at different distances from point sources, line sources, plane sources, and tank sources.

Reference:

10CFR20.1201 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with math errors.

B: CORRECT: Based on a point source calculation, at a distance of 3 feet from the point source, the radiation intensity is 600/3X3 = 66.67 mr/hour. For a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period, the total dose is 200 mrem.

Added to the initial dose of 4810 mrem results in a total exposure of 5010 mr.

C: INCORRECT: Plausible with math errors.

D: INCORRECT: Plausible with math errors.

Question Level: H Question Difficulty 3 Justification:

The student must apply a knowledge of line source exposure to calculate what the dose rate will be at each distance and then calculate a total exposure based on the time frame given and compare it to the 10CFR20 limit to determine the correct response.

Page 134 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1101 Last used on an NRC exam: 2017 RO Sequence Number: 68 In accordance with 0POP08-FH-0009, Core Refueling, which of the following is a task for a Licensed Control Room Operator during refueling operations?

A. Inform the Core Load Supervisor of the next core location to have a fuel assembly loaded.

B. Operate the remote television monitoring equipment used to observe refueling activities.

C. Monitor the Core Monitoring NI channels during and following insertion of each fuel assembly.

D. Evaluate Inverse Count Rate Ratio (ICRR) data on loaded fuel assemblies.

Answer: C Monitor the Core Monitoring NI channels during and following insertion of each fuel assembly.

Page 135 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1101 Source: Bank Modified from K/A Catalog Number: G2.1.40 Knowledge of refueling administrative reqirements.

RO Importance: 2.8 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)()

STP Lesson: LOT 201.43 Objective Number: 66407 DESCRIBE the procedural requirements of the fuel handling equipment operating procedure(s) to include purpose, scope, precautions and limitations

Reference:

0POP08-FH-0009, Core Refueling, Step 6.2.10.3.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible because move sheets are available to and monitored by the RO during fuel movement, but not an assigned responsibility.

B: INCORRECT: Plausible because the equipment is available to the operator, but not an assigned responsibility C: CORRECT: per 0POP08-FH-0009, Core Refueling D: INCORRECT: Plausible because ICRR data is collected, but by Reactor Engineering in Step 6.2.10.4. NOTE: Reactor Operator is required to evaluate/perform an ICRR per the Task Analysis of LOT Training during their reactor startup certification..

Question Level: F Question Difficulty 2 Justification:

The student must be able to recall the administrative responsibilities for Licensed Operators during refueling.

Page 136 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2902 Last used on an NRC exam: Never RO Sequence Number: 69 The unit is at 100% power.

Which of the following requires entry into a Technical Specification action statement?

A. The FHB Train A Exhaust Radiation Monitor RT-8035 loses power.

B. The AMSAC Relay Panel 118VAC Neon Bulb is OFF.

C. RWST Level Channel LT-0931 is removed from service for maintenance.

D. The CP-006 MSIV A Handswitch will NOT operate.

Answer: C RWSTS Level Channel LT-0931 is removed from service for maintenance.

Page 137 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2902 Source: New Modified from K/A Catalog Number: 013 G2.2.42 Engineered Safety Features Actuation: Ability to recognize parameters that are entry-level conditions for Technical Specifications.

RO Importance: 3.9 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 503.01 Objective Number: 92102 Given the topic or title of a specification included in the Technical Specificatoins, or Technical Requirements Manual (TRM), describe the general requirements affected, limitations, major time frames involved, major surveillances in order to comploy, and the bases for the specification/requirement.

Reference:

TS 3.3.2 Functional Unit 7b, Action 19A Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as FHB HVAC and associated instrumentation used to be required and is in the TRM now.

B: INCORRECT: Plausible as AMSAC is important for reactor protection, but not required by TS.

C: CORRECT: Per TS 3.3.2, Functional Unit 7b, Action 19A.

D: INCORRECT: Plausible as the safety grade MSIV handswitches are required by TS.

Question Level: H Question Difficulty 3 Justification:

The student must assess different conditions and determine the impact on TS.

Page 138 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2945 Last used on an NRC exam: Never RO Sequence Number: 70 The crew is shutting down the unit for an outage.

RCS pressure 660 psig.

RCS temperature is 353ºF.

The RO reports the following:

RCS pressure is dropping.

Pressurizer level is dropping 5%/minute.

Containment radiation monitors are in HIGH alarm.

The crew will restore pressurizer level and stabilize plant conditions using A. 0POP05-EO-EO00, Reactor Trip or Safety Injection.

B. 0POP04-RC-0003, Excessive RCS Leakage.

C. 0POP04-RC-0006, Shutdown LOCA.

D. 0POP04-RC-0007, MODE 5 or MODE 6 LOCA With The Reactor Vessel Head On.

Answer: C 0POP04-RC-0006, Shutdown LOCA Page 139 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2945 Source: New Modified from K/A Catalog Number: G2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

RO Importance: 3.8 Tier: 3 Group/Category: 10CFR

Reference:

55.41(b)(10)

STP Lesson: LOT 201.10 Objective Number: 29419 Given a plant condition, predict the operation of the ECCS to include automatic actuations, interlocks and/or trips.

Reference:

0POP04 RC-0006, Shutdown LOCA, entry conditions Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this procedure is applicable in MODE 3, but only with RCS pressure above 1000 psig.

B: INCORRECT: Plausible as this would be the entry point for this event, but a transition would be made to 0POP04-RC-0006 because of the inability to maintain pressurizer level.

C: CORRECT: With pressurizer level dropping rapidly, charging flow cannot maintain it. The crew will restore level by isolating letdown and starting a HHSI pump in 0POP04-RC-0006.

D: INCORRECT: Plausible as this is a shutdown procedure that responds to leakage and if the student confuses modes of operation.

Question Level: H Question Difficulty 3 Justification:

Page 140 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 96 Last used on an NRC exam: 2016 RO Sequence Number: 71 If power is lost to 480V LC 1U, the BACKUP power supply to Instrument Air Compressor #14 is the A. TSC diesel generator which energizes 480V LC 1U.

B. TSC diesel generator which energizes 480V MCC 1G5.

C. BOP diesel generator which energizes 480V LC 1U.

D. BOP diesel generator which energizes 480V MCC 1G5.

Answer: D BOP diesel generator which energizes 480V MCC 1G5 Page 141 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 96 Source: Bank Modified from K/A Catalog Number: 078 K2.01 Knowledge of the bus power supplies to the following:

Emergency air compressor.

RO Importance: 2.7 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.26 Objective Number: 25610 LIST the systems that interface with the Instrument Air and Service Air systems and STATE the function of each interface.

Reference:

LOT201.35 Powerpoint Presentation, Slide 28; NLO 200.15 Student Handout, Page 20 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT -Plausible because LC 1U normally energizes MCC 1G5 (which is the supply to IA

1. 14);TSC DG is credible because it is another non-class DG which (despite its name) supplies power to plant components such as the CVCS PDP, transformer cooling fans, select plant lighting, etc.

B: INCORRECT - Plausible because it is another non-class DG which (despite its name) supplies power to plant components such as the CVCS PDP, transformer cooling fans, select plant lighting, etc.

C: INCORRECT - Plausible because the BOP DG supplies IA compressor #14, but it does so by energizing MCC 1G5 which is normally powered through LC 1U.

D: CORRECT - The BOP DG powers up MCC 1G5 (which supplies IA compressor 14) upon a loss of power to the MCC.

Question Level: F Question Difficulty 2 Justification:

The applicant must combine the knowledge of the instrument air system and the backup diesel generators to eliminate the incorrect distractors and select the correct answer.

Page 142 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2465 Last used on an NRC exam: Never RO Sequence Number: 72 A leak has developed in the CCW system. Based on the indications shown CCW Normal Makeup Valve, CC-LV-4501, should be _____(1)_____ and 2M03-F-6, CCW SURGE TK LVL LO, should be ______(2)______.

A. (1) Closed (2) Lit B. (1) Closed (2) Extinguished C. (1) Open (2) Lit D. (1) Open (2) Extinguished Answer: C (1) Open (2) Lit Page 143 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2465 Source: Bank Modified from K/A Catalog Number: APE 026 AA1.05 Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water:

The CCWS surge tank, including level control and level alarms, and radiation alarm.

RO Importance: 3.1 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.12 Objective Number: 80198 DESCRIBE the Instrumentation and Controls available to monitor and operate the CCW System.

Reference:

LOT 201.12 Powerpoint Slide 15; 0POP04-AN-02M3, page 50 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: All distractors are plausible given the fact the CCW Surge Tank high level alarm comes in above the green band. The student could also believe that the makeup does not occur until the red band and some level control signals occur at levels in the yellow band.

B: INCORRECT: All distractors are plausible given the fact that the CCW Surge Tank high level alarm comes in above the green band. The student could also believe that the makeup does not occur until the red band and some level control signals occur at levels in the yellow band.

C: CORRECT: The indicated CCW Surge Tank level is 65%. The normal makeup valve opens at <

68.75% and the low level alarm comes in at < 66.7%.

D: INCORRECT: All distractors are plausible given the fact that the CCW Surge Tank high level alarm comes in above the green band. The student could also believe that the makeup does not occur until the red band and some level control signals occur at levels in the yellow band.

Question Level: H Question Difficulty 2 Justification:

The student must be able to anlayze the given CCW Surge Tank level indication to determine the correct status of level controls and level alarms.

Page 144 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1557 Last used on an NRC exam: Never RO Sequence Number: 73 The unit is at 100% power.

Instrument Air pressure begins lowering rapidly.

The crew enters 0POP04-IA-0001, Loss of Instrument Air.

With NO operator action, on CP-004, the RO will note TOTAL seal injection flow

________(1)_______ because the position of _______(2)______.

A. (1) on the ICS screen has risen (2) HCV-0218, Seal Injection Flow Control Valve, is full OPEN B. (1) displayed on a panel indicator has risen (2) HCV-0218, Seal Injection Flow Control Valve, is full OPEN C. (1) on the ICS screen has lowered (2) HCV-0218, Seal Injection Flow Control Valve, is full CLOSED D. (1) displayed on a panel indicator has lowered (2) HCV-0218, Seal Injection Flow Control Valve, is full CLOSED Answer: A (1) on the ICS screen has risen (2) HCV-0218, Seal Injection Flow Control Valve, is full OPEN Page 145 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 1557 Source: Bank Modified from K/A Catalog Number: APE 065 AA2.08 Loss of Instrument Air: Ability to determine and interpret the following as they apply to the loss of instrument air:

Failure modes of air-operated equipment.

RO Importance: 2.9 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(7)

STP Lesson: LOT 201.06 Objective Number: 50297 Given a valve in the CVCS system, describe the fail position of that valve and the reason.

Reference:

0POP04-IA-0001, page 54 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Total seal injection flow is only displayed on the ICS screen on CP-004 and it has risen because HCV-0218 has failed OPEN.

B: INCORRECT: Plausible as many CVCS indications do have board indications but not total seal injection flow. HCV-0218 has failed OPEN.

C: INCORRECT: Plausible with confusion over failure positions and board locations.

D: INCORRECT: Plausible with confusion over failure positions and board locations.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and determine what occurs.

Page 146 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2872 Last used on an NRC exam: Never RO Sequence Number: 74 A reactor trip from 100% power has occurred. Complete the following statements:

The Auxiliary Feedwater System is designed to permit operation at hot standby for __(1)__

hours.

The Auxiliary Feedwater System design capability allows for a cooldown of the RCS at

____(2)____ °F/hour until the RHR system may be placed in service.

A. (1) 4 (2) 50 B. (1) 4 (2) 25 C. (1) 2 (2) 50 D. (1) 2 (2) 25 Answer: A (1) 4 (2) 50 Page 147 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2872 Source: New Modified from K/A Catalog Number: EPE 007 EK1.06 Knowledge of the operational implications of the following concepts as they apply to the Reactor Trip: Relationship of emergency feedwater flow to S/G and decay heat removal following a reactor trip.

RO Importance: 3.7 Tier: 1 Group/Category: 1 10CFR

Reference:

55.41(b)(4)

STP Lesson: LOT 202.28 Objective Number: 80167 State the relationship of AFW flow to the S/Gs and decay heat removal following a reactor trip.

Reference:

Auxiliary Feedwater DBD, page3-2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Following a reactor trip, the AFW system is capable of maintaining hot standby conditions for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by a cooldown at 50F/hour to RHR cut in conditions.

B: INCORRECT: Plausible as this is the correct time and 25F/hour is for natural circulation cooldown conditions.

C: INCORRECT: Plausible as 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> has been used in the design basis for battery life following a station blackout. 50F/hour is correct.

D: INCORRECT: Plausible as 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> has been used in the design basis for battery life following a station blackout and 25F/hour is for natural circulation cooldown conditions.

Question Level: F Question Difficulty 3 Justification:

The student must understand the relationship between decay heat removal and feedwater sources after a reactor trip from 100% power.

Page 148 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2894 Last used on an NRC exam: Never RO Sequence Number: 75 The unit is in MODE 1. Complete the following:

Oxygen levels in the RCS are controlled with a _____(1)_____ blanket on the VCT. Pressure in the VCT is maintained _________(2)________.

A. (1) nitrogen (2) manually by the crew B. (1) nitrogen (2) automatically with a pressure regulator C. (1) hydrogen (2) manually by the crew D. (1) hydrogen (2) automatically with a pressure regulator Answer: D (1) hydrogen (2) automatically with a pressure regulator Page 149 of 150

Print Date 5/5/2020 STP LOT-24 NRC RO EXAM Exam Bank No.: 2894 Source: New Modified from K/A Catalog Number: 004 K4.01 Chemical and Volume Control: Knowledge of CVCS design features and/or interlocks which provide for the following: Oxygen control in the RCS.

RO Importance: 2.8 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 201.06 Objective Number: 99238 Describe all the systems that interface with the CVCS to include the function of each interface.

Reference:

0POP03-ZG-0001, Section 5.0, Step 5.36 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as N2 is placed on the VCT while shutdown and Hydrogen is placed in service just prior to entering MODE 4. Other gas systems on site are operated manually (Hydrogen to the Main Generator).

B: INCORRECT: Plausible as N2 is placed on the VCT while shutdown and Hydrogen is placed in service just prior to entering MODE 4. Pressure is maintained automatically.

C: INCORRECT: Plausible as H2 is the correct gas in MODE 4. Other gas systems on site are operated manually (Hydrogen to the Main Generator).

D: CORRECT: H2 is placed in service prior to MODE 4 entry. H2 pressure is maintained automatically with a pressure regulator.

Question Level: F Question Difficulty 3 Justification:

The student must know when and how H2 gas is placed on the VCT.

Page 150 of 150

STP LOT-22 NRC RO EXAM This question was modified Print Date 4/21/2020 for the LOT 24 NRC RO Exam Bank No.: 2630 Exam. Last used on an NRC exam: 2018 RO Sequence Number: 30 Bank #2918 Question #8 A reactor startup is being performed at the End of Life (EOL) with the following conditions:

Reactor power is 10%.

Control Rods are in manual.

Steam Dumps are in Steam Pressure Mode.

Header Pressure Controller PK-0557 is in AUTO with a setting of 8.46 on the potentiometer.

If the potentiometer on PK-0557 were to be changed to 9.00, RCS Tave would (1) and reactor power would (2) .

A. (1) lower (2) lower B. (1) rise (2) rise C. (1) lower (2) rise D. (1) rise (2) lower Answer: D (1) rise (2) lower Page 59 of 150

Print Date 4/21/2020 STP LOT-22 NRC RO EXAM Exam Bank No.: 2630 Source: Bank Modified from K/A Catalog Number: 041 K3.04 Knowledge of the physical connections and/or cause-effect relationships between the SDS and the following systems: Reactor Power RO Importance: 3.5 Tier: 2 Group/Category: 2 10CFR

Reference:

55.41(b)(5)

STP Lesson: LOT 202.09 Objective Number: 22107 DISCUSS the operation of the Steam Dump System.

Reference:

LOT 202.09 Powerpoint Presentation, slides 54--56 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible the student may think the potentiometer setting is similar to a demand signal. If that was the case then raising this setting would cause dumps to open and lower Tave.

B: INCORRECT: Tave would rise. However, power would go down with a negative MTC. Plausible because if the reactor had a positive MTC at BOL then power would go up.

C: INCORRECT: Plausible the student may think the potentiometer setting is similar to a demand signal. If that was the case then raising this setting would cause dumps to open and lower Tave.

And if Tave were to lower with a negative MTC then reactor power would rise.

D: CORRECT: At a setting of 8.46 the dumps maintain a no load value of 1185 psig. A higher pot setting would equate to a higher pressure. In order to raise pressure, the dumps would close to release less steam to the condenser. Less steam flow would make RCS Tave go up. And since the reactor is at EOL it would have a negative MTC. With a negative MTC and a rise in Tave, reactor power would go down.

Question Level: H Question Difficulty 3 Justification:

Student must analyze the given conditions and predict the operation of the steam dump system.

Page 60 of 150

This question was modified Print Date 4/21/2020 STP LOT-22 NRC RO EXAM for the LOT 24 NRC RO Exam Bank No.: 909 Exam. Last used on an NRC exam: 2018 RO Sequence Number: 14 Bank #2943 Question #20 A signal from _________(1)_________ will open ________(2)________.

A. (1) logic train R (2) reactor trip breaker R ONLY B. (1) logic train R (2) reactor trip breaker R and reactor trip bypass breaker S C. (1) logic train S (2) reactor trip breaker R ONLY D. (1) logic train S (2) reactor trip breaker R and reactor trip bypass breaker S Answer: B (1) logic train "R" (2) reactor trip breaker "R" and reactor trip bypass breaker "S" Page 27 of 150

Print Date 4/21/2020 STP LOT-22 NRC RO EXAM Exam Bank No.: 909 Source: New Modified from K/A Catalog Number: 012 A3.07 Ability to monitor automatic operation of the RPS, including: Trip breakers RO Importance: 4.0 Tier: 2 Group/Category: 1 10CFR

Reference:

55.41(b)(6)

STP Lesson: LOT 201.20 Objective Number: 03832 Describe the reactor protection system control and permissive interlocks including inputs, setpoints, coincidence, and functions.

Reference:

LOT 201.20, Solid State Protection System, Powerpoint Presentation, slide 45 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student believes the bypass breaker is for testing only as it is normally kept racked out.

B: CORRECT: A Logic Train "R" Reactor Trip signal will open the same train reactor trip breaker and the opposite train reactor trip bypass breaker.

C: INCORRECT: Plausible if the student believes the bypass breaker is for testing only and if the logic train always gets the opposite train breaker.

D: INCORRECT: Plausible as is similar to the correct answer in same train and opposite train relationship.

Question Level: F Question Difficulty 2 Justification:

The student must know the reactor trip breaker logic.

Page 28 of 150

This question was modified Print Date 4/21/2020 STP LOT-21 NRC SRO EXAM for the LOT 24 NRC RO Exam Bank No.: 2681 Last used on an NRC exam: 2017 Exam.

SRO Sequence Number: 83 Bank #2906 Question #59 The crew was performing actions of 0POP04-RC-0004, Steam Generator Tube Leakage, in response to a tube leak on SG A.

Subsequently; The leak became larger and was approximately 250 gpm.

The crew performed a Reactor Trip and Safety Injection.

The crew is currently performing steps of 0POP05-EO-EO30, Steam Generator Tube Rupture.

SG A has been isolated and the RCS cooldown is in progress when the following parameters are observed:

Pressure Level Main Steamline Radiation SG A 1190 psig and lowering 44% NR and stable 1.8 E-1 and rising SG B 910 psig and lowering 22% NR and stable 9.2 E-2 and rising SG C 910 psig and lowering 17% NR and lowering 2.0 E-2 and stable SG D 910 psig and lowering 23% NR and lowering 2.0 E-2 and stable Based on these indications, the Unit Supervisor should A. stop the cooldown when the required CET temperature is reached and continue in 0POP05-EO-EO30.

B. stop the cooldown immediately and return to step 1 of 0POP05-EO-EO30.

C. transition to 0POP05-EO-EO20, Faulted Steam Generator Isolation.

D. transition to 0POP05-EO-EC31, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired.

Answer: B stop the cooldown immediately and return to step 1 of 0POP05-EO-EO30.

Page 15 of 50

Print Date 4/21/2020 STP LOT-21 NRC SRO EXAM Exam Bank No.: 2681 Source: New Modified From K/A Catalog Number: APE 037 A2.11 Ability to determine and interpret the following as they apply to a Steam Genrator Tube Leak: When to isolate one or more SGs SRO Importance: 3.8 Tier: 1 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed STP Lesson: LOT 504.15 Objective Number: 38635 Given a copy of a step from 0POP05-EO-EO30 state/identify how the action is performed and the basis for the action to include the action itself, its purpose and the result.

Reference:

0POP05-EO-EO30 Rev 26 and its WOG background document Rev 2 page 77 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: The cooldown should be stopped and the SRO should return to the beginning of EO30 so that the 'B' SG is isolated properly. Plausible, because the cooldown is a time critical operator action for response to a SGTR. It is plausible to think that the cooldown must be completed prior to addressing any new issues.

B: CORRECT: The given indications show that 'B' SG is indicating a SGTR as well as 'A' SG. It is implied in this question that the student identifies this since it is considered RO knowledge. If a second SG is identified as ruptrured once a cooldown has been started, then the correct action to take is to stop the cooldown in progress and return to the beginning of EO30. The WOG explains the cooldown should be stopped until the subsequent SG is isolated so there is no unnecessary releases.

C: INCORRECT: Plausible because the CIP of EO30 states that if any SG pressure is lowering in an uncontrolled manner then transition to EO20. Plausible with the given SG pressure indications that the student may think that the SGs are depressing uncontrollably and would need to transition to EO20.

D: INCORRECT: Plausible because there are 10 different ways to transition out of EO30 to EC31.

(i.e. if a student believed there is no intact SG available for the cooldown)

Question Level: H Question Difficulty 3 Justification:

Student must be able to analyze given conditions and determine how to correctly apply the EOPs to mitigate the event.

Page 16 of 50

A^'-vyn

^,\0 FIGURE 7.1 MAIN GENERATOR CAPABILITY CURVE (UNIT 1) PCB107.01 Rev. 10 Reference VTD-S1 25-0020 Page 2 SIEMENS ENERGY, INC CURVE NO. C22004340 CALCULATED CAPABIUTY CURVES AT 100 PERCEMT VOLTAGE (25.0 RV)

Wrm WATER COOLED STATQR HYDROGEM INNER-COOLED TURBINE CENERATQR 0

w~+/-

-r 400.0 i

lwt:'"^"';'i'~^^ ^^'-.i':^"ir:^^-'^ y't. * "y^^.t "*'*^-'-^"^'*'<. :.:'^;^.::-'-i:"'t?: :t-^;^;.f^-4'.'~:t^' t:

EEEEEEEEEE ;l;^;x2^iA4^^ ^'^^ai^^^x^t-.j;.

1200,0 ill43slili§ij^^ ^;.'^^t'^4^'^^t^^^^^

£::ElEi4^I$Si2Eff^945^S

^^.^L./.i^.l/.^^.^.

'^^sysssssssssxSss.

0 'l^:^l;;l;;l^lrt;cy^rHy^l^^l^^.:i^fct z

u 10TO.O 0 t-XU.;

^EF

~x.>p.^p^

ligd^i^SS

(^'-A'?'-^- "X. ^.J^^^i ^.^^^Z^^,.^.

a 800.0 fc£lai:'£iAr;a SBSBBS.

y-i l^gl^gn

>>.^..^..^^..^-.;^^

Q^QEj^QSi-y^

s 600.0

^S^SS'iSS:

K

§ f^^l3;Q::t;:l4::l:l:$[t: "J-"

• ^HfcrT^

Q. 40Q.Q

^ 200,0 IU

@ 0.0

'Q

-200.0 0'

-400.0 g ^psqgrr:^

I -600.0 Q

I -800.0

-1000.0 w

^

I

SSf.

'^^G^

-1200.0 0

2 Q ."rr.H~w^.i-t.4

-1400,^.r..r.r-.v...r"r.^^-.,...,.-v....-....^^...,..-r.....r.^^.~v^

uj MEGAWATTS 1504,8MVA PF 0.900 25.0 kV 34751 A 3 PHASE 60 Hz 1800 RPM SCR 0.63 75 PSIG RATED COLD GAS 46 degC RATED STWORVWERSOdegt ENGINEER - BIDHAN SAMAhTTA DAte - 2013-08-06 CURVM NO.

• C22004340 Confidential, Copyright 2013 Siemens; Energy, jnc. All Rtghts Reserved NOTES

1. OPERATE AS CLOSE TO UNITY POWER FACTOR (LOW MVAR) BUT SLIGHTLY LAGGING AS PRACTICAL WHILE OBSERVING PLANT AND GRID STABILITY FOR CONTRIBUTION TO LONG TERM HEALTH OF THE MAIN GENERATOR.

2. OBSERVE AN ADMINSTRATIVE LIMIT OF 450 MVAR (LAGGING) REACTIVE LOADING FOR CONTRIBUTION TO THE LONG TERM HEALTH OF THE MAIN GENERATOR. IF PLANT OR GRID CONDITIONS DICTATE OPERATION ABOVE THIS LIMIT THEN AN ENGINEERING EVALUATION IS TO BE PERFORMED FOLLOWING THE PERIOD OF INCREASED LOADING.

3. OBSERVE AN ADMINSTRATIVE LIMIT OF 90 MVAR (LEADING) REACTIVE LOADING TO PREVENT EXCEEDING THE GENERATOR REACTIVE CAPABILITY LIMITATION OF 100 MVAR (LEADING) AND/OR A MINIMUM GENERATOR VOLTAGE OF 95% (23.75 KV) OF RATED VOLTAGE DUE TO THE MAIN TRANSFORMER TURNS RATIO. REFERENCE CALCULATION EC05027.

^^

Prepared By: ate: ^^y/^Reviewed By._^^^^^ Date: ^// ^ // 9, Approved By: Date:  : ^/22/^

SOUTH TEXAS PROJECT PERMT/RWP ELECTRIC GENERATING STATION U10 RADIATION WORK PERMIT 2020-0-0003 ROUTINE REACTOR OPERATIONS FUNCTIONS Revision 0 WHITE RCA Entry Card Required ACTIVE: 01/01/2020 00:00 TERMINATION: 12/31/2020 23:59 JOB DESCRIPTION ROUTINE ROUNDS, TOURS, VALVE LINEUPS AND MISCELLANEOUS FUNCTIONS

_,,a(lSl RADIOLOGICAL DATA CONTAMINATION DOSE RATES ALARM SETPOINTS

'^iiSSSiiii:-

GA: <1,000-<200,000 dpm/100cm2

'^SSiSS^-

<80 mrem/hr ALARM SETPOINT: BY WAN WORK: <1,000-<200,000 dpm/1o0cm2 <80 mrem/hr ALARM RATE: BY WAN AIRBORNE: <0.3 DAC RESTRICTIONS

• NO ENTRY INTO POSTED LOCKED HIGH RADIA^BR <<A

• NO ENTRY INTO POSTED HIGH RADIATION AREAS^>>r"

• NO ENTRY INTO POSTED AIRBORNE RADIOACTMTY AREAS .flgiBlBlCTBfejpBLE GAS)

• NO ENTRY INTO REACTOR CONTAINMENT BUILDING IN HSSS 1 OR 2 REQUIREMENTS DOSIMETRY RESPIRATORY PROTECTION PAD. PROT. COVERAGE 3RD None Intermittent DLR SIGNATURES MORGAN,JONAH BOSWORTH 12/30/201907:38 Approved by Date/Time Terminated by Date/Time This document, when completed, SHALL be retained in accordance with the Document Types List. Page

SOUTH TEXAS PROJECT PERMT/RWP ELECTRIC GENERATING STATION U10 RADIATION WORK PERMIT 2020-0-0003 ROUTINE REACTOR OPERATIONS FUNCTIONS Revision 0 WHITE RCA Entry Card Required Entry Requirements PRIOR TO ENTRY INTO THE RCA, OBTAIN A COMPLETE UNDERSTANDING OF RADIOLOGICAL CONDITIONS UTILIZING SELF BRIEFINGS, CREW BRIEFINGS, DOCUMENTED SURVEYS AND/OR INFORMATION PRESENTED BY RADIATION PROTECTION If NOT self briefed, notify Radiation Protection prior to Initial entry into the RCA each shift Dress Requirements FOR ENTRY INTO A POSTED CONTAMINATED AREA:

• One full set lab coat protective clothing for work NOT involving climbing, kneeling, or crawling with permission from Radiation Protection or,

• Single set of protective clothing with skull cap

• Hood is required for climbing ladders/scaffolds, working above your head, situations where contaminated surfaces may come In contact with the neck or as prescribed by Radiation Protection FOR ENTRY INTO A POSTED HIGH CONTAMINATION AREA:

• Two full sets protective clothing OR a single set of protective clothing and double layer of protective clothing on area of body which may come into contact with highly contaminated surfaces (e.g., apron, knee pads, sleeved apron, etc.)

with permission from Radiation Protection

• A skull cap and hood

• Surgeon gloves may be worn as second set of gloves with permission from Radiation Protection

• Water resistant protective clothing should be worn as second set on area of body where protective clothing could become wet FOR REACHING INTO POSTED CONTAMINATED AREAS:

• Lab coat and surgeon gloves may be used with permission from Radiation Protection FOR REACHING INTO A POSTED HIGH CONTAMINATION AREA:

• Lab coat and two pair of surgeon gloves may be used with permission from Radiation Protection FOR DISCONNECTING CAPS, FITTINGS, TRANSMITTERS OR GAUGES ON CONTAMINATED SYSTEMS IN A NON-CONTAMINATED AREA:

• Lab coat and gloves (surgeon gloves allowed with permission from Radiation Protection)

FOR TRANSPORTING HOSES DESIGNATED FOR CONTAMINATED SYSTEMS:

• Lab coat and gloves (surgeon gloves allowed with permission from Radiation Protection)

Additional Requirements For work in contaminated areas involving laying, kneeling, sitting etc., ensure a protective barrier is placed between the worker and the contaminated surfaces For removal of hoses from drains in clean areas, ensure contamination is controlled as directed by Radiation Protection Notify Radiation Protection prior to accessing the overhead Notify Radiation Protection prior to disconnecting caps, fittings, transmitters and gauges on contaminated systems Make provisions to contain any residual liquids expected from opening a contaminated system This Radiation Work Permit does NOT allow the following work evolutions:

• Sluicing resin

• Transfer of resin

• Change out of process filters

• Top sweeping, back flushing or sluicing of ALPS Cautions / ALARA Notes Notify Radiation Protection prior to moving any radioactive material known or suspected to be >5 mrem/hr contact Accumulation of trash and debris can contribute to the spread of contamination. Workers should ensure that all debris is bagged, surveyed by Radiation Protection and removed from the work area at the end of each shift.

This document, when completed, SHALL be retained in accordance with the Document Types List. Page 2

SURVEY #: 109881 Page 1 of 4 STATUS: APPROVED U17 DATE/TIME: 04/10/2020 02:50 POWER: 0%

MAP CODE: 1-MAB+010-TG05 PURPOSE: Routine RWP: 2020-1-0071-0 ROUTINE: Task Group 5 Radiological Survey Report Package WAN: 1001 TPNS: N/A Task Group 05 HIGHEST CONTAMINATION

1. dpm/100cm² 1 <1 K 2 <1 K 3 <1 K 4 <1 K 5 <1 K 6 <1 K 7 <1 K 8 <1 K 9 <1 K 10 <1 K A <100 ccpm B <100 ccpm C <100 ccpm INSTRUMENTS LEGEND 400-00012-008 400-00047-017 400-00097-045 SURVEY COMMENTS See back page(s) for all contamination result details.

Routine TG5, permission granted by Unit 1 Supervisor to enter RM044 SURVEYOR: King,Jaleesa Danelle REVIEWER: Smith,Kimberly Rene DATE/TIME: 04/10/2020 03:39

SURVEY #: 109881 Page 2 of 4 STATUS: APPROVED U17 DATE/TIME: 04/10/2020 02:50 POWER: 0%

MAP CODE: 1-MAB+010-TG05 PURPOSE: Routine RWP: 2020-1-0071-0 ROUTINE: Task Group 5 Radiological Survey Report Package WAN: 1001 TPNS: N/A Task Group 05 HIGHEST CONTAMINATION

1. dpm/100cm² 11 <1 K 12 <1 K 13 <1 K 14 <1 K 15 <1 K 16 <1 K D <100 ccpm E <100 ccpm F <100 ccpm INSTRUMENTS LEGEND 400-00012-008 400-00047-017 400-00097-045 SURVEY COMMENTS See back page(s) for all contamination result details.

Routine TG5, permission granted by Unit 1 Supervisor to enter RM044 SURVEYOR: King,Jaleesa Danelle REVIEWER: Smith,Kimberly Rene DATE/TIME: 04/10/2020 03:39

SURVEY #: 109881 Page 3 of 4 STATUS: APPROVED U17 DATE/TIME: 04/10/2020 02:50 POWER: 0%

MAP CODE: 1-MAB+010-069 PURPOSE: Routine RWP: 2020-1-0071-0 ROUTINE: Task Group 5 Radiological Survey Report Package WAN: 1001 TPNS: N/A Task Group 05 HIGHEST CONTAMINATION

1. dpm/100cm² 17 <1 K 18 <1 K 19 <1 K 20 <1 K 21 <1 K 22 <1 K 23 <1 K 24 <1 K 25 <1 K G <100 ccpm INSTRUMENTS LEGEND 400-00012-008 400-00047-017 400-00097-045 SURVEY COMMENTS See back page(s) for all contamination result details.

Routine TG5, permission granted by Unit 1 Supervisor to enter RM044 SURVEYOR: King,Jaleesa Danelle REVIEWER: Smith,Kimberly Rene DATE/TIME: 04/10/2020 03:39

SURVEY #: 109881 Page 4 of 4 STATUS: APPROVED U17 DATE/TIME: 04/10/2020 02:50 POWER: 0%

MAP CODE: 1-MAB+010-069 PURPOSE: Routine RWP: 2020-1-0071-0 ROUTINE: Task Group 5 Radiological Survey Report Package WAN: 1001 TPNS: N/A SMEARS

1. dpm/100cm² dpm/100cm² Comments 1 <1 K N/A Sump Cover 2 <1 K N/A Stairs Handrail 3 <1 K N/A 1-CC-MOV-137 4 <1 K N/A SOP 5 <1 K N/A pump 07 6 <1 K N/A pump 06 7 <1 K N/A pump 05 8 <1 K N/A 1-FC-PA-103A 9 <1 K N/A Drain 10 <1 K N/A Trash Drum 11 <1 K N/A Drain 12 <1 K N/A Drain 13 <1 K N/A 1-WL-1059 14 <1 K N/A 1-WL-1079 15 <1 K N/A pipes 16 <1 K N/A panel 17 <1 K N/A pipes 18 <1 K N/A pump 19 <1 K N/A Drain 20 <1 K N/A Trash Drum 21 <1 K N/A 1-WL-0215 22 <1 K N/A 1-WL-0205 23 <1 K N/A Strainers 24 <1 K N/A inside CA 25 <1 K N/A SOP LARGE AREA WIPES

1. ccpm/LAW Particle Comments A <100 N/A Floor B <100 N/A Floor C <100 N/A Floor D <100 N/A Floor E <100 N/A Floor F <100 N/A Floor G <100 N/A Floor POSTING DEFINITIONS Abbreviation Definition RA Radiation Area CA Contaminated Area NHPPTE Notify HP Prior to Entry SURVEYOR: King,Jaleesa Danelle REVIEWER: Smith,Kimberly Rene DATE/TIME: 04/10/2020 03:39

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2942 Last used on an NRC exam: Never SRO Sequence Number: 76 Per 0POP01-ZA-0018, Emergency Operating Procedure Users Guide, complete the following:

A Caution in an EOP is used to ______________(1)_____________.

The Unit Supervisor is required to read cautions ALOUD to the crew _______(2)_______.

A. (1) provide explanatory information to assist in performing a task (2) ONLY when the information is needed B. (1) provide explanatory information to assist in performing a task (2) AT ALL TIMES C. (1) alert operators of conditions that could result in equipment damage (2) ONLY when the information is needed D. (1) alert operators of conditions that could result in equipment damage (2) AT ALL TIMES Answer: C (1) alert operators of conditions that could result in equipment damage (2)

ONLY when the information is needed Page 1 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2942 Source: New Modified From K/A Catalog Number: G2.4.20 Knowledge of the operational implicatons of EOP warnings, cautions, and notes.

SRO Importance: 4.3 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

STP Lesson: LOT 504.04 Objective Number: T50404 The student will be able to EXPLAIN the basic contents of the Emergency Operating Procedures.

Reference:

0POP01-ZA-0018, Step 2.7 and 4.3 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the definition of a note. This is the correct requirement.

B: INCORRECT: Plausible as this is a definition of a note and if the student confuses the different types of communications and requirements.

C: CORRECT: A caution alerts operators to serious conditions but the Unit Supervisor only reads them aloud when the situation warrants it.

D: INCORRECT: Plausible as this is the correct definition, and if the student confuses the different types of communications and requirements.

Question Level: F Question Difficulty 3 Justification:

The student must recall information from the procedure.

Page 2 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2922 Last used on an NRC exam: Never SRO Sequence Number: 77 The crew manually initiated Safety Injection due to a LOCA one minute ago.

The following conditions are noted:

o Pressurizer level is 70% and rising.

o RCS pressure is 1500 psig and lowering.

o Containment pressure is 1.2 psig and rising.

o Containment Normal Sump level is rising.

o Containment radiation monitors are in alarm.

This event is caused by a _________(1)________.

To respond properly to this event, the Unit Supervisor will direct the procedural flow path 0POP05-EO-EO00, Reactor Trip or Safety Injection, to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, to _________(2)__________.

A. (1) break in a Pressurizer Spray Bypass Line (2) 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization B. (1) break in a Pressurizer Spray Bypass Line (2) 0POP05-EO-ES13, Transfer to Cold Leg Recirculation C. (1) stuck open Pressurizer PORV (2) 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization D. (1) stuck open Pressurizer PORV (2) 0POP05-EO-ES13, Transfer to Cold Leg Recirculation Answer: A (1) break in a Pressurizer Spray Bypass Line (2) 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization.

Page 3 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2922 Source: New Modified From K/A Catalog Number: APE008 AA2.26 Ability to determine or interpret the following as they apply to a Pressurizer Vapor Space accident: Probable Pressurizer steam space leakage paths other than PORV or code safety.

SRO Importance: 3.4 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

This question requires the student to assess conditions and then select a procedure. It requires "knowledge of diagnostic steps and decision points in the emergency operating procedures (EOPs) that involve transitions to event-specific sub-procedures to emergency contingency procedures."

STP Lesson: LOT 201.21 Objective Number: 501215 Given a set of conditions or event description, be able to predict the sequence of events and trends of plant parameters for a transient or accident involving a decrease in Reactor Coolant Inventory.

Reference:

P&ID 5R149F05003#1, RCS Pressurizer; ; LOT 501.21 Student Handout, page 33 Attached Reference

Attachment:

Portion of P&ID 5R149F05003#1, RCS Pressurizer NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: The symptoms indicate a break into containment not a leak into the PRT. For this break size, the crew will cooldown and depressurize the plant below the LHSI injection pressure using 0POP05-EO-ES12.

B: INCORRECT: Plausible as this is the correct accident, and if the student confuses the recovery methods for different size LOCAs.

C: INCORRECT: Plausible as pressurizer level would be rising and pressurizer pressure lowering, but not the case here. This is the correct procedure.

D: INCORRECT: Plausible as pressurizer level would be rising and pressurizer pressure lowering, but not the case here and if the student confuses the recovery methods for different size LOCAs.

Question Level: H Question Difficulty 3 Justification:

This question requires the student to be able to interpret plant conditions, determine the accident in progress and select a course of action.

Page 4 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2925 Last used on an NRC exam: Never SRO Sequence Number: 78 With the unit at 100%, a loss of offsite power occurs.

The reactor could NOT be tripped from the control room.

The crew is performing 0POP05-EO-FRS1, Response to Nuclear Power Generation/ATWS.

The following indications are noted by the RO:

o SG NR levels are 5% and slowly lowering.

o Total AFW flow is 400 gpm.

With this information, the Unit Supervisor will direct the crew to A. immediately transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

B. transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, when 0POP05-EO-FRS1, Response to Nuclear Power Generation/ATWS, is exited.

C. transition back to 0POP05-EO-EO00, Reactor Trip or Safety Injection, perform a readthrough of the 1st 4 steps, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

D. transition back to 0POP05-EO-EO00, Reactor Trip or Safety Injection, and perform the procedure until directed to monitor CSFs, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

Answer: B transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, when 0POP05-EO-FRS1, Response to Nuclear Power Generation/ATWS, is exited.

Page 5 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2925 Source: New Modified From K/A Catalog Number: W/E05 G2.4.21 Loss of Secondary Heat Sink: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

SRO Importance: 4.6 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

STP Lesson: LOT 504.33 Objective Number: 92206 STATE the entry condition for 0POP05-EO-FRH1.

Reference:

0POP05-EO-F003; 0POP01-ZA-0018, Section 6.0 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible with confusion over the priority of FRPs.

B: CORRECT: When 0POP05-EO-EO00 is exited to perform 0POP05-EO-FRS1, CSFs are continually monitored and implemented from that point forward. Thus, when 0POP05-EO-FRS1 is complete, 0POP05-EO-FRH1 is the new highest priority and would be immediately entered.

C: INCORRECT: Plausible as in some cases, the user is directed back to 0POP05-EO-EO00 when a CSF is not met.

D: INCORRECT: Plausible as this would be the case if the user was performing 0POP05-EO-ES01 and an SI occurred.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and figure out when to implement CSFs and transition to 0POP05-EO-FRH1.

Page 6 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2668 Last used on an NRC exam: 2017 SRO Sequence Number: 79 In accordance with 0ERP01-ZV-SH01, Shift Manager, the Emergency Director is allowed to delegate approving A. press releases prior to issuance.

B. notifications to State and County.

C. departures from license conditions.

D. Protective Action Recommendations.

Answer: A press releases prior to issuance.

Page 7 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2668 Source: Bank Modified From K/A Catalog Number: G2.4.40 Knowledge of SRO responsibliities in emergency plan implementation.

SRO Importance: 4.5 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: Objective SRO Justification:

Task is unique to the SRO position.

STP Lesson: LOT 803.14 Objective Number: SRO-47030 DISCUSS the duties and responsibilities of the Shift Manager as delineated in 0ERP01-ZV-SH01, Shift Manager.

Reference:

0ERP01-ZV-SH01, Shift Manager, steps 4.4.1 and 4.4.2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Approving press releases prior to issuance is a Emergency Director responsibility that may be delegated.

B: INCORRECT: Plausible because all distractors are responsibilities of the Emergency Director listed in 0ERP01-ZV-SH01.

C: INCORRECT: Plausible because all distractors are responsibilities of the Emergency Director listed in 0ERP01-ZV-SH01.

D: INCORRECT: Plausible because all distractors are responsibilities of the Emergency Director listed in 0ERP01-ZV-SH01.

Question Level: F Question Difficulty 3 Justification:

Student must know the responsibilities of the Emergency Director.

Page 8 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2929 Last used on an NRC exam: Never SRO Sequence Number: 80 Per 0PGP03-ZA-0090, Work Process Program, complete the following:

Emergency Maintenance activities are performed at the discretion of the ______(1)______.

When Emergency Maintenance is performed on a safety related system, the Shift Manager

_______(2)_______.

A. (1) Shift Manager (2) may consider the system functional based on the knowledge of actions taken B. (1) Shift Manager (2) must declare the system inoperable C. (1) Plant Manager (2) may consider the system functional based on the knowledge of actions taken D. (1) Plant Manager (2) must declare the system inoperable Answer: A (1) Shift Manager (2) may consider the system functional based on the knowledge of actions taken Page 9 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2929 Source: New Modified From K/A Catalog Number: G2.2.19 Knowledge of maintenance work order requirements.

SRO Importance: 3.4 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: 55.43(b)(3)

SRO Justification:

Unique to the SRO position STP Lesson: LOT 802.33 Objective Number: SRO-1148 Distinguish between the following terms: B. Emergency Maintenance

Reference:

0PGP03-ZA-0090, step 2.7, step 4.1.1; WCG-0001, page 15 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Per ZA-0090, step 4.1.1 B: INCORRECT: Plausible as this is the right level of approval, and the serious nature of emergency maintenance may cause the student to draw the conclusion that the equipment must be declared inoperable.

C: INCORRECT: Plausible as the Plant Manager is required to approve HIGH Work Activity Risk Plan of Actions. This is the correct use.

D: INCORRECT: Plausible as the Plant Manager is required to approve HIGH Work Activity Risk Plan of Actions and the serious nature of emergency maintenance may cause the student to draw the conclusion that the equipment must be declared inoperable.

Question Level: F Question Difficulty 3 Justification:

The student must recall information about emergency maintenance.

Page 10 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2927 Last used on an NRC exam: Never SRO Sequence Number: 81 The Shift Manager maintains administrative control of the key to the Locked High Radiation Area key storage box.

Maintaining this key ___(1)___ required by Technical Specifications.

The Shift Manager ________(2)______ allowed to have a key to this storage box.

A. (1) is NOT (2) is the only individual B. (1) is NOT (2) and the RP Manager are C. (1) is (2) is the only individual D. (1) is (2) and the RP Manager are Answer: D (1) is (2) and the RP Manager are Page 11 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2927 Source: New Modified From K/A Catalog Number: G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

SRO Importance: 3.8 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: 55.43(b)(4)

SRO Justification:

This task is unique to the Shift Manager position.

STP Lesson: LOT 802.16 Objective Number: SRO-50157 Discuss the requirements of 0POP01-ZA-0019, Operations Key Control

Reference:

0POP01-ZA-0019, TS 6.12.2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is part of a plant procedure and in the plant procedure, the SM is identified as the only individual NORMALLY issued a key.

B: INCORRECT: Plausible as this is part of a plant procedure. These are the correct individuals.

C: INCORRECT: Plausible as this is required by TS, and in the plant procedure, the SM is identified as the only individual normally issued a key.

D: CORRECT: Per TS 6.12.2 Question Level: F Question Difficulty 3 Justification:

The student must recall information regarding key control and Technical Specifications.

Page 12 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2926 Last used on an NRC exam: Never SRO Sequence Number: 82 Due to an accidental release, a member of the public in a boat on the Colorado River under the FM521 bridge received whole body radiation dose in excess of limits.

Complete the following:

The radiation dose received by the individual occurred in a(an) ______(1)______ area.

Per the ODCM, a Special Report must be submitted to the NRC within ___(2)___ days.

A. (1) UNRESTRICTED (2) 30 B. (1) UNRESTRICTED (2) 14 C. (1) RESTRICTED (2) 30 D. (1) RESTRICTED (2) 14 Answer: A (1) UNRESTRICTED (2) 30 Page 13 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2926 Source: New Modified From K/A Catalog Number: APE 059 G2.4.30 Accidental Liquid Radwaste Release: Knowlede of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission operator.

SRO Importance: 4.1 Tier: 1 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(1)

SRO Justification:

Application of required actions (TS Section 3) and surveillance requirements (SR) (TS Section 4) in accordance with rules of appllicaoin requirements (TS, Section 1).

STP Lesson: LOT 503.03 Objective Number: 92103 Given the topic or title of a requirement in the Offsite Dose Calculation Manual (ODCM), describe the general requirements to include components or administrative requirements affected, limitations, and major time frames in order to comply and the bases for the requirement.

Reference:

ODCM 3.11.1.2, ODCM Figure 5.1-4 (partial)

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Per ODCM 3.11.1.2, if a member of the public, receives a dose of 1.5 mrem or greater at an UNRESTRICTED location, then a Special Report must be submitted within 30 days.

B: INCORRECT: Plausible as this is an UNRESTRICTED AREA and this is the number of days in the ODCM that releases may continue with OOS radiation monitoring equipment.

C: INCORRECT: Plausible with confusion over the OCA, UNRESTRICTED AREA, PROTECTED AREA, etc. This is the correct action.

D: INCORRECT: Plausible with confusion over the OCA, UNRESTRICTED AREA, PROTECTED AREA, etc. and this is the number of days in the ODCM that releases may continue with OOS radiation monitoring equipment.

Question Level: H Question Difficulty 3 Justification:

The student must assess what happened and decide if the action is required.

Page 14 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2923 Last used on an NRC exam: Never SRO Sequence Number: 83 The unit is in a refueling outage.

The crew is performing 0POP03-ZG-0007, Plant Cooldown.

RCS temperature is 191ºF and lowering.

RHR Trains A and C are in service.

At 0900, both RHR pumps trip.

The crew enters 0POP04-RH-0001, Loss of Residual Heat Removal.

At 0910, RCS temperature is 200ºF and rising.

NO RHR pumps are ready to be placed in service.

At 1005, RCS temperature is 242ºF and rising.

With this information, the Shift Manager will classify this situation as an _____(1)_____.

If NO RHR pump can be restarted, the mitigative strategy the crew will employ at this time is to establish _______(2)_______.

A. (1) UNUSUAL EVENT (2) RCS feed and bleed B. (1) UNUSUAL EVENT (2) a secondary heat sink C. (1) ALERT (2) RCS feed and bleed D. (1) ALERT (2) a secondary heat sink Answer: D (1) ALERT (2) a secondary heat sink Page 15 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2923 Source: New Modified From K/A Catalog Number: APE 025 G2.4.41 Loss of Residual Heat Removal System: Knowledge of the emergency action level thresholds and classifications.

SRO Importance: 4.6 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

SRO Specific Task: Classifying plant events.

Knowledge of the content of the procedure versus knowledge of the procedure's overall mitigative strategy or purpose.

STP Lesson: LOT 803.14 Objective Number: 74926 Given an emergency condition and a copy of the emergency classification tables from 0ERP01-ZV-IN01, Emergency Classification, classify the emergency condition.

Reference:

0POP04-RH-0001, Cold Shutdown/Refueling System Malfunctions EAL Chart Attached Reference

Attachment:

Cold Shutdown/Refueling System Malfunctiuons EAL Chart NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student does not correctly interpret the more complicated ALERT requirements. The UNUSUAL EVENT requirements are met but are not the highest level at this time and RCS feed and bleed is a mitigative strategy in 0POP04-RH-0001, but for a higher temperature.

B: INCORRECT: Plausible if the student does not correctly interpret the more complicated ALERT requirements. The UNUSUAL EVENT requirements are met but are not the highest level at this time. This is the correct mitigative strategy.

C: INCORRECT: Plausible as this is the correct classification and RCS feed and bleed is a mitigative strategy in 0POP04-RH-0001, but for a higher temperature.

D: CORRECT: With the given conditions, EAL CA3-1 is met. The RCS has been over 200F for 55 minutes and temperature is still rising. NO RHR pumps are ready to be restored. With an intact RCS, the heatup duration can be no longer than 60 minutes. Since it is likely 60 minutes will be exceeded, an ALERT should be declared. With the RCS over 200F but NOT over 300F, the specific mitigative strategy is to establish a secondary heat sink. Over 350F, RCS Feed and Bleed will be established.

Question Level: H Question Difficulty 4 Justification:

The student is required to assess plant conditions and determine the appropriate EAL and the mitigative strategy that will be employed.

Page 16 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2431 Last used on an NRC exam: 2015 SRO Sequence Number: 84 The unit is in a refueling outage and performing 0POP08-FH-0009, Core Refueling.

Date / Time Activity 9/5 00:00 Plant Shutdown commenced 9/5 06:30 Mode 3 Entry 9/5 13:20 Mode 4 Entry 9/5 22:10 Mode 5 Entry 9/7 22:00 First Reactor Vessel Head Stud detensioned 9/8 09:00 Reactor Vessel Head removed As the Core Loading Supervisor, the EARLIEST time that you would allow irradiated fuel movements to commence would be on A. 9/9 at 10:30 B. 9/10 at 02:10 C. 9/12 at 02:00 D. 9/12 at 13:00 Answer: A 9/9 at 10:30 Page 17 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2431 Source: Bank Modified From K/A Catalog Number: G2.1.36 Knowledge of procedures and limitations involved in core alterations.

SRO Importance: 4.1 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: 55.43(b)(6)

SRO Justification:

Unique to the SRO position.

STP Lesson: LOT 201.43 Objective Number: 66407 Describe the procedural requirements of the fuel handling equipment operating procedure(s) to include purpose, scope, precautions and limitations.

Reference:

0POP08-FH-0009, Core Refueling, page 27 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: Reactor must be subcritical for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to irradiated fuel movement. Mode 3 trip breakers open is the moment of subcriticality.

B: INCORRECT: Plausible because it is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from a milestone in the shutdown to Refueling. In this case, Mode 5 conditions. Applicant may consider 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> from beginning of other plant conditions, such as Mode 5 (Water temperature is below boiling), Mode 6 (first head stud detensioned), and vessel head removed.

C: INCORRECT: Plausible because it is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from a milestone in the shutdown to Refueling. In this case, Mode 6 conditions. Applicant may consider 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> from beginning of other plant conditions, such as Mode 5 (Water temperature is below boiling), Mode 6 (first head stud detensioned), and vessel head removed.

D: INCORRECT: Plausible because it is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from a milestone in the shutdown to Refueling. In this case, Mode 6 conditions in preparation for cavity fill. Applicant may consider 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> from beginning of other plant conditions, such as Mode 5 (Water temperature is below boiling), Mode 6 (first head stud detensioned), and vessel head removed.

Question Level: H Question Difficulty 3 Justification:

Must be able to analyze the given conditions to determine the requirements for the start of fuel off-load.

Page 18 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2933 Last used on an NRC exam: Never SRO Sequence Number: 85 It is 4/1/2020 at 1730. BOTH units are at 100%. The oncoming shift on site has the following individuals available to take the watch.

1 SM, 2 US, 1 STA, 4 ROs One of the ROs has the following watchstanding record in the 1st quarter.

January 2020 February 2020 March 2020 3/20 Nights -12 hours Primary 3/21 Nights - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Secondary No hours No hours 3/22 Nights - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Extra 3/23 Nights - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Extra 3/27 Days - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Primary 3/28 Days - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Secondary 3/29 Days - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Extra Per 0POP01-ZA-0014, Initial Operator License and Licensed Operator Programs, the Shift Manager should determine that the ROs license is _______(1)______, AND should determine that night shift staffing is ______(1)______.

A. (1) active (2) adequate B. (1) active (2) inadequate C. (1) NOT active (2) adequate D. (1) NOT active (2) inadequate Answer: D (1) NOT active (2) inadequate Page 19 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2933 Source: New Modified From K/A Catalog Number: G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

SRO Importance: 3.8 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Unique to the SRO position.

STP Lesson: LOT 507.01 Objective Number: 92186 Given the title of an administrative procedure, discuss the requirements associated with the referenced procedure.

Reference:

0POP01-ZA-0014, Section 4.3; 10CFR50.54M Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student does not realize that EXTRA does not count for active license maintenance and if they confuse the requirements for ROs with other positions on the 10CFR chart.

B: INCORRECT: Plausible if the student does not realize that EXTRA does not count for active license maintenance and the student confuses requirements on the 10CFR chart.

C: INCORRECT: Plausible as NOT active is correct, and if the student confuses requirements on the 10CFR chart.

D: CORRECT: At power, 4 ROs are required to staff 2 units with 2 control rooms. Since the RO has not stood 5-12 hour Primary OR Secondary watches, the RO is inactive.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant staffing, determine its adequacy and then the proper actions to implement.

Page 20 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2519 Last used on an NRC exam: 2019 SRO Sequence Number: 86 The unit is in Mode 6 with Core Offload in progress.

The following occurs:

A spent fuel assembly is damaged while removing it from the reactor vessel.

Area radiation monitors in the RCB are alarming.

For the damaged spent fuel assembly, the potential for a radiological release is _____(1)_____

compared to if the incident occurred during Core Reload.

The Unit Supervisor should direct the performance of _____(2)_____ per 0POP04-FH-0001, Fuel Handling Accident.

A. (1) GREATER (2) Addendum 1, Establishing CRE HVAC in Emergency Mode B. (1) GREATER (2) Addendum 2, Establishing FHB HVAC in Emergency Mode C. (1) LESS (2) Addendum 1, Establishing CRE HVAC in Emergency Mode D. (1) LESS (2) Addendum 2, Establishing FHB HVAC in Emergency Mode Answer: A (1) GREATER (2) Addendum 1, Establishing CRE HVAC in Emergency Mode Page 21 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2519 Source: Bank Modified From K/A Catalog Number: APE 036 AA2.03 Ability to determine and interpret the following as they apply to the Fuel Handling Incidents:

Magnitude of potential radioactive release.

SRO Importance: 4.2 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Knowledge of when to implement attachments and appendices, including how to coordinate these items with procedure steps.

STP Lesson: LOT 501.22 Objective Number: 501226 Given a set of conditions or event description, be able to CATEGORIZE projected radiological consequences as either minimal or potentially significant for a transient or accident involving a radioactive release from a subsystem or component.

Reference:

LOT 501.22 Lesson Plan on Transient and Accident Analysis and 0POP04-FH-0001, Fuel Handling Accident.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: In comparison, a damaged Spent Fuel Assembly that has just been removed from the reactor vessel would have a radiological release of a greater magnitude than one having spent time in the SFP and being placed back in the reactor vessel.. The correct action listed is to perform Addendum 1.

B: INCORRECT: Plausible as the radiological release is greater and the FHB and RCB are connected during refueling.

C: INCORRECT: Plausible with confusion over offload and reload. This is the correct action.

D: INCORRECT: Plausible with confusion over offload and reload and the FHB and RCB are connected during refueling.

Question Level: H Question Difficulty 3 Justification:

The student must be able to analyze the given conditions to determine the correct procedure steps to perform and have fundamental knowledge of the magnitude of potential radiological releases.

Page 22 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2940 Last used on an NRC exam: Never SRO Sequence Number: 87 The unit is at 100% power. A LOCA then occurs.

The RO reports RWST level is 75,000 gallons and dropping slowly.

Containment pressure is 6 psig and dropping slowly.

The crew enters 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.

Complete the following regarding this situation.

If NO trains can be aligned for recirculation, the Unit Supervisor will direct the securing of

___(1)___ Containment Spray Pumps AND direct a transition to _______(1)_______

A. (1) ALL (2) 0POP05-EO-ES14, Transfer to Hot Leg Recirculation B. (1) ONE (2) 0POP05-EO-ES14, Transfer to Hot Leg Recirculation C. (1) ALL (2) 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation D. (1) ONE (2) 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation Answer: C (1) ALL (2) 0POP05-EO-EC11, Loss of Emergency Coolant Recirculaton Page 23 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2940 Source: New Modified From K/A Catalog Number: 026 A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray - when it can be done.

SRO Importance: 3.7 Tier: 2 Group/Category: 1 10CFR Reference or SRO Objective: Objective SRO Justification:

Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event-specific sub-procedures or emegency contingency procedures. Knowledge of a specific mitigative strategy.

STP Lesson: LOT 504.27 Objective Number: 82524 Describe the readings and indications which confirm that a Safety Injection or Containment Spray pump should be stopped.

Reference:

0POP05-EO-ES13, Steps 5 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as all pumps will be stopped and with confusion over the recirculation flow paths.

B: INCORRECT: Plausible since there is a lower RWST level setpoint in the CIP at 32,500 gallons at which all pumps must be stopped and with confusion over the recirculation flow paths.

C: CORRECT: With no trains aligned, all pumps taking suction from the RWST must be stopped.

The crew will transition to 0POP05-EO-EC11.

D: INCORRECT: Plausible since there is a lower RWST level setpoint in the CIP at 32,500 gallons at which all pumps must be stopped. The pumps would have already been stopped on step 1 however.

Question Level: H Question Difficulty 4 Justification:

The student must assess conditions and then determine a course of action.

Page 24 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2931 Last used on an NRC exam: Never SRO Sequence Number: 88 The unit is at 3% POWER following a refueling outage.

A Main Steam Line ruptures OUTSIDE containment.

A Main Steam Line Isolation does NOT occur and NO MSIVs can be closed Complete the following regarding these conditions:

An automatic reactor trip signal would have been generated from a ______(1)______.

The Unit Supervisor will achieve cold shutdown conditions by directing actions in

_______(1)_______.

A. (1) low Pressurizer Pressure Reactor Trip signal (2) 0POP05-EO-ES02, Natural Circulation Cooldown B. (1) low Pressurizer Pressure SI signal (2) 0POP05-EO-ES02, Natural Circulation Cooldown C. (1) low Pressurizer Pressure Reactor Trip signal (2) 0POP05-EO-EC21, Uncontrolled Depressurization of All Steam Generators D. (1) Low Pressurizer Pressure SI signal (2) 0POP05-EO-EC21, Uncontrolled Depressurization of All Steam Generators Answer: D (1) Low Pressurizer Pressure SI signal (2) 0POP05-EO-EC21, Uncontrolled Depressurization of All Steam Generators Page 25 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2931 Source: New Modified From K/A Catalog Number: 013 A2.03 Engineered Safety Features Actuation: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Rapid depressurization.

SRO Importance: 4.7 Tier: 2 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Knowledge of a specific mitigative strategy of an EOP. Knowledge of the content of an EOP.

STP Lesson: LOT 504.14 Objective Number: 82689 Given a copy of a step from 0POP05-EO-EC21, state/identify how the action is performed and the bases for the action to include the action itself, its purpose, and the result.

Reference:

0POP05-EO-EC21, 0POP05-EO-ES02 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible since natural circulation would be required as all RCPs would have to be tripped and if the student does not remember when the reactor trip is active.

B: INCORRECT: Plausible since natural circulation would be required as all RCPs would have to be tripped. This is the correct reactor trip signal from SI.

C: INCORRECT: Plausible as this is the correct procedure and if the student does not remember when the reactor trip is active.

D: CORRECT: With no MSIVs closed, the cooldown will rapidly reduce pressurizer pressure to the SI setpoint. Since power is below 10%, the low pressurizer pressure reactor trip is not active. The crew will go to 0POP05-EO-EC21 to achieve cold shutdown conditions.

Question Level: H Question Difficulty 3 Justification:

The student must determine the effect of a failure on the plant, and then respond using the correct procedure strategy.

Page 26 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2924 Last used on an NRC exam: Never SRO Sequence Number: 89 The Unit has experienced a LOCA outside containment with the following conditions:

RCS temperature is rising.

RCS pressure is lowering.

MAB sump levels and radiation levels are rising.

Subsequently, The crew is performing 0POP05-EO-EC12, LOCA Outside Containment, Step 5, CHECK For LOCA In MAB.

The crew performed Step 5 but was NOT successful in isolating the leak.

RCS pressure continues to lower.

At this point, the Unit Supervisor should direct the crew to A. return to Step 1 of 0POP05-EO-EC12, LOCA Outside Containment.

B. transition to 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation.

C. transition to 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization.

D. transition to 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.

Answer: B transition to 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation Page 27 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2924 Source: Modified Modified From 2688 K/A Catalog Number: W/E11 EA2.1 Loss of Emergency Coolant Recirculation: Ability to determine and interpret the following as they apply to Loss of Emergency Coolant Recirculation: Facility conditions and selection of appropriate procedures during abnormal and emergency conditions.

SRO Importance: 4.2 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Knowledge of diagnostic steps and decision points in the emergency operating procedures (EOPs) that involve transitions to event-specific sub-procedures or emeregency contingency procedures.

STP Lesson: LOT 504.46 Objective Number: 82657 From Memory STATE/IDENTIFY indications and trends used to determine that the break is isolated in accordance with POP05-EO-EC12.

Reference:

0POP05-EO-EC12, Steps 5 and 6 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as other EOPs require re-performance after a certain point is reached.

B: CORRECT: Following the completion of Step 5, the crew has done everything possible to stop the leak in the FHB or MAB and the transition is made to 0POP05-EO-EC11, in order to conserve RWST inventory and cool down and depressurize the plant.

C: INCORRECT: Plausible as a cooldown and depressurization is to be conducted, but in 0POP05-EO-EC11 not 0POP05-EO-ES12.

D: INCORRECT: Plausible if the student believes that long term recirc will fill the containment sump and provide a long term solution to this issue.

Question Level: H Question Difficulty 3 Justification:

The student must assess the conditions and determine a course of action.

Page 28 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2947 Last used on an NRC exam: Never SRO Sequence Number: 90 Both units are at 100%. A disturbance on the grid is in progress.

The RO reports that BOTH North and South Bus voltages are reading 335 KV.

Per Technical Specifications, the Shift Manager has ___(1)___ hours to restore voltages prior to shutting the plant down.

Per 0POP04-AE-0005, Offsite Power System Degraded Voltage, while awaiting voltage restoration, the Shift Manager will direct the crew to A. (1) 24 (2) place the 4160V ESF Buses on the Standby Diesel Generators B. (1) 24 (2) transfer the 13.8KV Standby Buses to the UAT C. (1) 72 (2) place the 4160V ESF Buses on the Standby Diesel Generators D. (1) 72 (2) transfer the 13.8KV Standby Buses to the UAT Answer: B (1) 24 (2) transfer the 13.8KV Standby Buses to the UAT Page 29 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2947 Source: New Modified From K/A Catalog Number: APE 077 AA2.05 Ability to determine and interpret the following as they apply to Generator Voltage And Electric Grid Disturbances: Operational status of offsite circuit.

SRO Importance: 3.8 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

Application of required actions (TS Section 3) and specific mitigative strategies within a procedure.

STP Lesson: LOT 505.01 Objective Number: 32443 Given a plant condition, describe and/or interpret the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

0POP04-AE-0005, Step 11.0, TS 3.8.1.1 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the correct time and if the student believes that removing the ESF buses from the grid is the best action to take now.

B: CORRECT: With Switchyard voltage less than 339 KV, all offsite sources are inoperable and this is a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action statement prior to beginning a shutdown (TS 3.8.1.1e). In the meantime, one action in the AOP is to transfer all 13.8KV buses to the UAT.

C: INCORRECT: Plausible as this is the action time for one offsite source inoperable and if the student believes that removing the ESF buses from the grid is the best action to take now.

D: INCORRECT: Plausible as this is the action time for one offsite source inoperable and this is the correct action.

Question Level: H Question Difficulty 4 Justification:

The student must assess plant conditions and determine the correct actions to take.

Page 30 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2930 Last used on an NRC exam: Never SRO Sequence Number: 91 Complete the following regarding the basis of Technical Specification 3.5.2, Emergency Core Cooling Systems.

Following a design basis LOCA, ___(1)___ train(s) of ECCS is(are) assumed to provide core cooling, because __________(2)__________.

A. (1) 1 (2) 1 train of ECCS is OOS for maintenance and 1 train of ECCS fails to operate B. (1) 1 (2) 1 train of ECCS discharges through the pipe break and 1 train of ECCS fails to operate C. (1) 2 (2) 1 train of ECCS discharges through the pipe break D. (1) 2 (2) 1 train of ECCS fails to operate Answer: B (1) 1 (2) 1 train of ECCS discharges through the pipe break and 1 train of ECCS fails to operate Page 31 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2930 Source: New Modified From K/A Catalog Number: 006 G2.2.25 Emergency Core Cooling: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

SRO Importance: 4.2 Tier: 2 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

Knowledge of TS bases that are reuiqred to analyze TS-requiried actions and terminology.

STP Lesson: LOT 503.01 Objective Number: 92102 Given the topic or title of a specification included in the TS, or TRM, describe the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillance in order to comply, and the basis for the specification

Reference:

TS 3.5.2 and 3.5.3 Basis Document (B3/4 5-2)

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the correct number of trains and with confusion about LCOs, actions, and single failure criteria.

B: CORRECT: The TS basis assumes a single failure and also 1 train pours out the break.

C: INCORRECT: Plausible as there is an action statement for 1 train OOS, and the basis is built around single failure criteria.

D: INCORRECT: Plausible as there is an action statement for 1 train OOS, and the basis is built around single failure criteria.

Question Level: F Question Difficulty 3 Justification:

The student must recall information about Technical Specifications and the Basis Document.

Page 32 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2934 Last used on an NRC exam: Never SRO Sequence Number: 92 Both units are at 100% power.

A 345KV Switchyard North Bus outage is in progress.

The EAB Operator contacts the control room and informs them of the following:

Standby Diesel Generator #11 Jacket Water Temperature is 95ºF.

Based on this information, the Shift Manager will ensure that A. within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, restore either Standby Diesel Generator #11 OR restore from the North Bus outage.

B. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore either Standby Diesel Generator #11 OR restore from the North Bus outage.

C. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, restore from the North Bus outage ONLY.

D. actions of the CRMP are applied AND be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Answer: A within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, restore either Standby Diesel Generator #11 OR restore from the North Bus outage.

Page 33 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2934 Source: New Modified From K/A Catalog Number: 064 G2.2.37 Emergency Diesel Generator: Ability to determine operability and/or availability of safety related equipment.

SRO Importance: 4.6 Tier: 2 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

Application of required actions (TS Section 3)

STP Lesson: LOT 503.01 Objective Number: 92102 Given the topic or title of a specification included in the TS, or TRM, describe the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillance in order to comply, and the basis for the specification

Reference:

0PSP03-EA-0002, page 27, TS 3.8.1.1, 0POP02-DG-0001, page 18 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: CORRECT: The North Bus outage represents the loss of ONE offsite source. Jacket water temperature below 100F makes DG 11 inoperable. This results in entering TS 3.8.1.1, action c, which allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore either the DG or the offsite source.

B: INCORRECT: Plausible as this is the action time for 3.8.1.1e.

C: INCORRECT: Plausible if the student does not realize the realignment for the North Bus outage results in the loss of an offsite source. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is the allowed time for 1 DG OOS.

D: INCORRECT: Plausible as the CRMP may be used, but if it is, the plant stays on line for the time indicated.

Question Level: H Question Difficulty 3 Justification:

The student must assess the conditions and apply Technical Specifications.

Page 34 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2936 Last used on an NRC exam: Never SRO Sequence Number: 93 The unit is at 100% power.

The crew is performing 0PSP03-RS-0001, Control Rod Operability.

Control Bank D is inserted from 256 to 242 steps.

During insertion, the DRPI indication for rod D4 does NOT change.

The Control Bank D step counters indicated properly.

Control Bank D is then withdrawn to 256 steps.

Complete the following regarding this occurrence.

Based on the results above, the MOST restrictive applicable Technical Specification action requires the crew to A. be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ONLY.

B. determine the position of rod D4 every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> using incore detectors.

C. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiate action to be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. ensure adequate SHUTDOWN MARGIN exists within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Answer: D ensure adequate SHUTDOWN MARGIN exists within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Page 35 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2936 Source: New Modified From K/A Catalog Number: 014 G2.2.12 Rod Position Indication: Knowledge of surveillance procedures.

SRO Importance: 4.1 Tier: 2 Group/Category: 2 10CFR Reference or SRO Objective: Objective SRO Justification:

Application of required actions (TS Section 3)

STP Lesson: LOT 503.01 Objective Number: 92102 Given the topic or title of a specification included in the Technical Specifications, or the Technical Requirements Manual (TRM), DESCRIBE the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillance in order to comply, and the bases for the specification.

Reference:

0PSP03-RS-0001; TS 3.1.3.1, 3.1.3.2 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is part of the required action and if the student forgets the shutdown margin TS also applies.

B: INCORRECT: Plausible as this is an action from TS 3.1.3.2.a for DRPI.

C: CORRECT: Plausible since this is the required action for TS 3.0.3 and similar to the action of TS 3.1.3.1.a D: CORRECT: Until I&C can assist, the rod will be assumed to be sutck and untrippable and TS action 3.1.3.1.a applies.

Question Level: H Question Difficulty 3 Justification:

The student must assess the occurrence, and determine how to apply Technical Specifications.

Page 36 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2937 Last used on an NRC exam: Never SRO Sequence Number: 94 The unit is in a refueling outage. Containment closure has been established per 0PSP03-XC-0001, Refueling Containment Penetration Status.

A fuel assembly has been damaged in the RCB.

The crew enters 0POP04-FH-0001, Fuel Handling Accident.

Complete the following statements:

To comply with TRM 3.9.4, Containment Building Penetrations, the Shift Manager will direct the closure of _______________(1)______________, as necessary. The Personnel Airlock must have ________(2)_________

A. (1) the Equipment Hatch and the Personnel Airlock ONLY (2) a minimum of ONE door closed B. (1) the Equipment Hatch and the Personnel Airlock ONLY (2) BOTH doors closed with Instrument Air established to the door seals C. (1) the Equipment Hatch, Personnel Airlock, and Auxiliary Airlock (2) a minimum of ONE door closed D. (1) the Equipment Hatch, Personnel Airlock, and Auxiliary Airlock (2) BOTH doors closed with Instrument Air established to the door seals Answer: C (1) the Equipment Hatch, Personnel Airlock, and Auxiliary Airlock (2) a minimum of ONE door closed.

Page 37 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2937 Source: New Modified From K/A Catalog Number: 069 AA2.01 Loss of Containment Integrity: Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

SRO Importance: 4.4 Tier: 1 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(7)

SRO Justification:

Application of required actions (TS Section 3)

STP Lesson: LOT 201.43 Objective Number: 33172 Describe the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillances in order to comply, and the bases for the specification/requirement.

Reference:

0POP03-ZG-0010, Addendum 6, TRM 3.9.4, POP04-FH-0001, page 5 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as the student may think this is a small opening on the 37' elevation, well below the elevation where the broken fuel assembly bubbles would be rising into containment. A minimum of one door must be closed.

B: INCORRECT: Plausible as the student may think this is a small opening on the 37' elevation, well below the elevation where the broken fuel assembly bubbles would be rising into containment and these are the actual steps to perform for the PAL in Addendum 6.

C: CORRECT: All 3 openings must be closed. The airlocks only require one door closed per TRM 3.9.4 D: INCORRECT: All 3 openings must be closed and these are the actual steps to perform for the PAL in Addendum 6 Question Level: F Question Difficulty 3 Justification:

The student must know the requirements for containment during a fuel handling accident.

Page 38 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 1421 Last used on an NRC exam: Never SRO Sequence Number: 95 The unit is at 100% power.

The online Battery Charger for 125V DC Bus E1C11 deenergizes.

The crew aligns the standby Battery Charger to 125V DC Bus E1C11 in 10 MINUTES.

The standby Battery Charger is operating satisfactorily.

Complete the following statements regarding this occurrence:

BEFORE the standby Battery Charger was aligned, the most restrictive Technical Specification was to ________(1)________.

IMMEDIATELY after the Battery Charger is aligned, Battery E1C11 is _____(2)_____.

A. (1) reenergize 120V AC Vital Distribution Panel DP1204 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (2) STILL INOPERABLE B. (1) reenergize 120V AC Vital Distribution Panel DP1204 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2) OPERABLE C. (1) align a Battery Charger to 125V DC Bus E1C11 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (2) still INOPERABLE D. (1) align a Battery Charger to 125V DC Bus E1C11 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2) OPERABLE Answer: D (1) align a Battery Charger to 125V DC Bus E1C11 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2)

OPERABLE Page 39 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 1421 Source: Bank Modified From K/A Catalog Number: 062 G2.4.40 AC Electrical Distribution: Ability to apply Technical Specifications for a system.

SRO Importance: 4.7 Tier: 2 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

STP Lesson: LOT 201.31 Objective Number: 62351 GIVEN a plant or system condition, PREDICT the operation of the Non-Class 1E 13.8 to 4.16 volt AC distribution system.

Reference:

TS 3.8.2.1d; 0POP04-AE-0001, Page 4 NOTE Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible if the student is confused about what occurs with no battery charger supplying a bus and if the student confuses times (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is allowed to restore a 4.16KV ESF Bus). The battery would still be inoperable if it took greater than 15 minutes to restore the bus.

B: INCORRECT: Plausible if the student is confused about what occurs with no battery charger supplying a bus. This is the correct time and the bus is OPERABLE.

C: INCORRECT: Plausible as this is the most restrictive action and if the student confuses times (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is allowed to restore a 4.16KV ESF Bus). The battery would still be inoperable if it took greater than 15 minutes to restore the bus.

D: CORRECT: Per TS 3.8.2.1d. With no charger supplying the battery, the battery is considered inoperable and must be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. IF a battery charger is realigned withiin 15 minutes, the battery is operable at that point.

Question Level: H Question Difficulty 3 Justification:

The student must assess conditions and apply Technical Specifications and procedural requirements.

Page 40 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2938 Last used on an NRC exam: Never SRO Sequence Number: 96 The crew is releasing Waste Monitor Tank 1E.

The RO reports that RT-8038, LWPS Monitor #1, is indicating RED on the RM-11.

The release continues.

With this condition, the Shift Manager will direct the crew to take actions of _______(1)_____

and ______(2)______.

A. (1) 0POP02-WL-0100, Liquid Effluent Release (2) stop WMT Pump 1E B. (1) 0POP02-WL-0100, Liquid Effluent Release (2) place WL-FV-4077, WMT Discharge Divert Valve, in the RECIRC position C. (1) 0POP04-RA-0001, Radiation Monitoring System Alarm Response (2) stop WMT Pump 1E D. (1) 0POP04-RA-0001, Radiation Monitoring System Alarm Response (2) place WL-FV-4077, WMT Discharge Divert Valve, in the RECIRC position Answer: D (1) 0POP04-RA-0001, Radiaton Monitoring System Alarm Response (2) place WL-FV-4077, WMT Discharge Divert Valve, in the RECIRC position Page 41 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2938 Source: New Modified From K/A Catalog Number: 068 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation.

SRO Importance: 3.3 Tier: 2 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Unique to the SRO position.

STP Lesson: LOT 203.11 Objective Number: 92084 Given an abnormal plant condition concerning equipment associated with the Liquid Waste Processing System (LWPS), determine the probable cause of the condition and any corrective actions necessary (if applicable).

Reference:

0POP04-RA-0001, Addendum 12 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this is the release procedure and this would stop the release but not the action here.

B: INCORRECT: Plausible as this is the release procedure and actions for a trip of RT-8038 are included but not for a HIGH alarm.

C: INCORRECT: Plausible as this would stop the release, but not the procedurally directed action.

D: CORRECT: Per 0POP04-RA-0001, if RT-8038 goes into a HIGH alarm status, the crew will ensure FV-4077 is in the RECIRC position.

Question Level: H Question Difficulty 3 Justification:

The student must assess plant conditions and decide upon a course of action.

Page 42 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2928 Last used on an NRC exam: Never SRO Sequence Number: 97 With the unit at 100% power, RT-8039, CVCS Letdown Failed Fuel Monitor, goes into HIGH alarm.

Chemistry reports Dose Equivalent Iodine is 120 microcuries/gram.

The specific activity limits in Technical Specification 3.4.8 are based on ensuring that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose at the site boundary will not exceed a small fraction of the 10CFR100 limits in conjunction with _______(1)_______.

AND For the given plant conditions above, the Shift Manager will ensure ________(2)_______.

A. (1) a 25 gpm RCS leak outside containment (2) that when Dose Equivalent Iodine exceeds 100 uCi/gram for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the plant is in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500°F B. (1) 150 gpd steam generator tube leakage (2) that when Dose Equivalent Iodine exceeds 100 uCi/gram for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the plant is in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500°F C. (1) a 25 gpm RCS leak outside containment (2) the plant is in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500°F D. (1) 150 gpd steam generator tube leakage (2) the plant is in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500°F Answer: D (1) 150 gpd steam generator tube leakage (2) the plant is in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500F Page 43 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2928 Source: New Modified From K/A Catalog Number: APE 076 G2.2.38 High Reactor Coolant Activity: Knowledge of conditions and limitations in the facility license.

SRO Importance: 4.5 Tier: 1 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

Knowledge of Technical Specificaton bases that are required to anallyze TS required actions and terminology. Applicaton of required actions (TS Section 3).

STP Lesson: LOT 505.01 Objective Number: 92109 GIVEN a plant condition, DESCRIBE and/or INTERPRET the requirements and/or limits of a precaution or step of a referenced procedure.

Reference:

TS 3.4.8 and basis Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as this value of RCS leakage is an EAL for a UE and if the student mistakenly thinks the DEI limit is 100 Uci/gram instead of 1 Uci/gram.

B: INCORRECT: Plausible as this is the correct event and if the student mistakenly thinks the DEI limit is 100 Uci/gram instead of 1 Uci/gram.

C: INCORRECT: Plausible as this value of RCS leakage is an EAL for a UE. This is the correct action.

D: CORRECT: Per the TS basis, this is the event that the specific activity limit is based upon. With DEI at 120 Uci/gram it exceeds the limit line on Figure 3.4-1 so the plant must be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with Tave less than 500F.

Question Level: F Question Difficulty 3 Justification:

The student must recall procedural and licensing information.

Page 44 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2939 Last used on an NRC exam: Never SRO Sequence Number: 98 The unit is in a refueling outage.

A fuel assembly is dropped in the RCB.

The cladding on 3 fuel rods is breached.

The crew enters 0POP04-FH-0001, Fuel Handling Accident.

As a result of this event, radiation levels in the RCB from _____(1)_____ will rise significantly.

The Unit Supervisor will direct the performance of ____________(2)____________.

A. (1) Iodine and Krypton (2) 0POP02-HC-0003, Supplementary Containment Purge, to place Supplementary Containment Purge in service B. (1) Iodine and Krypton (2) 0POP02-HC-0001, Containment HVAC, to place the Containment Carbon Filter Units in service C. (1) Cesium and Strontium (2) 0POP02-HC-0003, Supplementary Containment Purge, to place Supplementary Containment Purge in service D. (1) Cesium and Strontium (2) 0POP02-HC-0001, Containment HVAC, to place the Containment Carbon Filter Units in service Answer: B (1) Iodine and Krypton (2) 0POP02-HC-0001, Containment HVAC, to place the ontainment Carbon Filter Units in service Page 45 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2939 Source: New Modified From K/A Catalog Number: 034 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling Equipment and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped fuel element.

SRO Importance: 4.4 Tier: 2 Group/Category: 2 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

Assessment of plant conditions and then selection of a procedure. Knowledge of the content of the procedure.

STP Lesson: LOT 505.01 Objective Number: 92110 Given a precaution, note, or step(s) and the context in which it is used from the referenced procdure, describe its basis and any applicable limits.

Reference:

0POP04-FH-0001, page 5; LOT 501.22 Student Handout, page 9.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as these are the correct gases, and purging containment would lower activity levels, but the purge flowpath has no filtration installed and is not used here.

B: CORRECT: With breaks in the cladding of fuel rods, the gas gap will be released into the water.

The gases are largely iodine and krypton. The carbon filter units are designed to remove iodine activity from containment.

C: INCORRECT: Plausible if the student confuses isotopes from fuel damage with isotopes from cladding damage and purging containment would lower activity levels, but the purge flowpath has no filtration installed and is not used here.

D: INCORRECT: Plausible if the student confuses isotopes from fuel damage with isotopes from cladding damage. This is the correct action.

Question Level: H Question Difficulty 3 Justification:

The student must respond to a dropped fuel assembly and direct actions based on plant conditions.

Page 46 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2948 Last used on an NRC exam: Never SRO Sequence Number: 99 Per the basis of Technical Specifications, complete the following:

MANUAL control of the Pressurizer PORVs is required for the _________(1)_______ accident.

MANUAL control is required in order to _________(2)________.

A. (1) Main Steam Line Break (2) provide a safety related method of depressurizing the RCS to allow SI termination B. (1) Main Steam Line Break (2) close the Pressurizer PORV to prevent an inadvertent depressurization C. (1) Steam Generator Tube Rupture (2) provide a safety related method of depressurizing the RCS to allow SI termination D. (1) Steam Generator Tube Rupture (2) close the Pressurizer PORV to prevent an inadvertent depressurization Answer: C (1) Steam Generator Tube Rupture (2) provide a safety related method of depressurizing the RCS to allow SI termination Page 47 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2948 Source: New Modified From K/A Catalog Number: EPE038 G2.2.25 Steam Generator Tube Rupture: Knowledge of the basis in the Technical Specifications for limiting conditions and safety limits SRO Importance: 4.2 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(2)

SRO Justification:

Knowledge of TS bases that is required to analyze TS-required actions and terminology.

STP Lesson: LOT 503.01 Objective Number: 92102 Given the topic or title of a specification included in the Technical Specifications, or the Technical Requirements Manual (TRM), describe the general requirements of the specification to include components or administrative requirements affected, limitations, major time frames involved, major surveillance in order to comply, and the bases for the specification.

Reference:

TS 3.4.4 and basis.

Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: Plausible as the main steam line break is discussed in the TS basis document.

This is the correct reason.

B: INCORRECT: Plausible as the main steam line break is discussed in the TS basis document and often manual control is used by the operator to control a failed automatic valve.

C: CORRECT: The manual control of the PORV is used to control RCS pressure during a SGTR. It is the safety related option to depressurize the RCS during the SGTR. The spray and aux spray valves can also be used, but they are not safety related.

D: INCORRECT: Plausible as this is the correct accident, and often manual control is used by the operator to control a failed automatic valve.

Question Level: F Question Difficulty 3 Justification:

The student must recall information from the TS basis document.

Page 48 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2935 Last used on an NRC exam: Never SRO Sequence Number: 100 The crew is performing an inservice test on a safety related pump.

One of the vibration readings falls into the ALERT range high.

Per 0PGP03-ZE-0022, Inservice Testing Program for Pumps, the Shift Manager will determine that the pump will _________(1)_________.

Testing frequency of the pump will _________(2)_________.

A. (1) remain OPERABLE (2) remain the same B. (1) remain OPERABLE (2) be doubled C. (1) be declared INOPERABLE (2) remain the same D. (1) be declared INOPERABLE (2) be doubled Answer: B (1) remain OPERABLE (2) be doubled Page 49 of 50

Print Date 4/21/2020 STP LOT-24 NRC SRO EXAM Exam Bank No.: 2935 Source: New Modified From K/A Catalog Number: G2.2.21 Knowledge of pre- and post-maintenance operability requirements.

SRO Importance: 4.1 Tier: 3 Group/Category:

10CFR Reference or SRO Objective: Objective SRO Justification:

Unique to the SRO position STP Lesson: Objective Number: CRO00061 Perform the Auxiliary Feedwater Pump 14 Inservice Test

Reference:

0PGP03-ZE-0022, steps 4.1.4, 0PSP03-AF-0007 Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: This is the correct operability decision, and if the student believes that ALERT, although serious, does not warrant doubling the frequency.

B: CORRECT: With vibration in the ALERT range, the pump will still remain operable, but be subject to increased frequency testing.

C: INCORRECT: Plausible as ALERT indicates a degraded condition that could cause the student to believe this equates with inoperability, and if the student believes that further testing is not necessary as maintenance will be performed.

D: INCORRECT: Plausible as ALERT indicates a degraded condition that could cause the student to believe this equates with inoperability. The testing will be at an increased frequency.

Question Level: F Question Difficulty 3 Justification:

The student must recall procedural requirements.

Page 50 of 50

This question was modified Print Date 4/21/2020 STP LOT-21 NRC SRO EXAM for the LOT 24 NRC SRO Exam Bank No.: 2688 Exam. Last used on an NRC exam: 2017 SRO Sequence Number: 82 Bank #2924 Question #89 The Unit has experienced a LOCA outside containment with the following conditions:

RCS temperature is rising.

RCS pressure is lowering.

Train A FHB SI/CS pump sump level is in alarm.

Subsequently; The crew is performing actions of 0POP05-EO-EC12, LOCA Outside Containment.

The crew isolated Train A ECCS and Containment Spray per step 4.

RCS pressure continues to lower.

The crew restores Train A ECCS and Containment Spray.

In accordance with 0POP05-EO-EC12, the Unit Supervisor should A. remain in 0POP05-EO-EC12 and continue with step 5 to check for a LOCA inside the MAB.

B. remain in 0POP05-EO-EC12 and repeat step 4 to isolate B or C ECCS and Containment Spray.

C. transition to 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation, to cool down and depressurize to Cold Shutdown conditions.

D. transition to 0POP05-EO-ES12, Post LOCA Cooldown and Depressurization, to cool down and depressurize to Cold Shutdown conditions.

Answer: B remain in 0POP05-EO-EC12 and repeat step 4 to isolate B or C ECCS and Containment Spray.

Page 13 of 50

Print Date 4/21/2020 STP LOT-21 NRC SRO EXAM Exam Bank No.: 2688 Source: Modified Modified From 1398 K/A Catalog Number: EPE E04 EA2.1 Ability to determine and interpret the following as they apply to LOCA Outside Containment: Facility conditions and selection of appropriate procedures during abnormal and emergency conditions.

SRO Importance: 4.3 Tier: 1 Group/Category: 1 10CFR Reference or SRO Objective: 55.43(b)(5)

SRO Justification:

assessment of plant conditions (normal, abnormal, or emergency) and then selection of a procedure or section of a procedure to mitigate or recover, or with which to proceed STP Lesson: LOT 504.46 Objective Number: 82657 From Memory STATE/IDENTIFY indications and trends used to determine that the break is isolated in accordance with POP05-EO-EC12.

Reference:

0POP05-EO-EC12 Rev 10 step 4j RNO Attached Reference

Attachment:

NRC Reference Req'd

Attachment:

Distractor Justification A: INCORRECT: RCS pressure is still lowering so the procedure will have the crew repeat step 4 for the other trains before moving on to step 5 to check for a LOCA in the MAB. Plausible, because the crew isolated the train with the sump level alarm in. Therefore the student may think it is appropriate to move on to the next step of the procedure.

B: CORRECT: Since the crew has only isolated one train of ECCS and RCS pressure is still lowering the procedure will have the crew repeat step 4 for the other trains before moving on to step 5 to check for a LOCA in the MAB.

C: INCORRECT: The crew should remain in EC12. Plausible because at step 6 of EC12 the crew would transition to EC11 to cool down if RCS pressure is still lowering. Also plausible to think that step 5 would not be perfomed (check for LOCA in MAB) since the indications are only for a LOCA in the FHB.

D: INCORRECT: The crew should remain in EC12. Plausible because at step 6 of EC12 the crew would transition to cool down if RCS pressure is still lowering. However they would transition to EC11 and not ES12 to perform the cooldown.

Question Level: H Question Difficulty 3 Justification:

Student must analyze the plant conditions and determine the appropriate actions to take to mitigate the event.

Page 14 of 50