ML18240A427

301 Exam Draft Items 2A - Delay Release 2 Yrs

ML18240A427
Person / Time
Site:	Turkey Point
Issue date:	08/28/2018
From:	Southern Nuclear Company
To:	NRC/RGN-II
References
Download: ML18240A427 (15)

Text

ES-401N, Rev. 10 PWR Examination Outline Form ES-401N-2 Facility: Vogtle Date of Exam: February 2017 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 3 2 3 3 18 18 3 3 66 Emergency &

2 2 1 2 1 2 1 99 2 2 44 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 3 5 4 27 27 5 5 1010 1 3 3 2 2 3 3 3 2 2 3 2 28 28 2 3 55 2.

2 1 1 1 1 1 1 1 0 1 1 1 10 10 1 2 33 Plant Systems Tier Totals 4 4 3 3 4 4 4 2 3 4 3 38 38 5 88

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 2 3 1 2 2 2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A 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 associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems 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 KAs.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (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 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.

ES-401N, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO A-301AA2.02 Rapid Power Reduction 3 3.1 Reactor Coolant System boron addition volume and rate A-313AA1.03 Uncontrolled Cooldown 3.5 SG PORVs A-323AK1.08 Loss of 6.9KV, 4160 Volt, or 480 3.2 Main Control Room Emergency Habitability System Volt Bus Power A-336AG2.1.14 Malfunction of Protection and 4 3.3 Ability to use integrated control systems to operate plant Safety Monitoring System systems or components.

A-337AK3.06 Passive Residual Heat Removal 2.7 Trending Passive Residual Heat Removal System inlet Heat Exchanger Leak temperatures and pressures A-342AG2.4.36 Reactor Coolant Pump Malfunctions 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.

A-343AK2.02 Loss of Normal Residual Heat 3.5 Transferring Reactor Coolant System heat load to the Removal Passive Residual Heat Removal System heat exchanger E-1EK1.01 Loss of Reactor or Secondary 4.3 Automatic Depressurization System Coolant E-2EK3.04 Faulted Steam Generator Isolation 3.4 Checking Passive Residual Heat Removal System is available prior to isolating the startup feedwater lines to the faulted steam generators ECA-1.1EA1.02 Loss of Coolant Accident Outside 3.6 Diverse Actuation System Containment ES-0.1EK2.10 Reactor Trip Response 3.3 Inability to stabilize Reactor Coolant System at no load Tcold temperature Page 1 of 2 01/11/2016 7:41 AM

ES-401N, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO ES-1.1EK1.12 Passive Safety System Termination 2.8 Pressurizer Pressure Control System ES-1.3EA1.14 ADS Stage 1-3 Actuation Response 3.6 0 ADS Stage 4 ES-1.4EA2.01 ADS Stage 4 Actuation Response 3.6 3.8 ADS Stage 4 proper alignment FR-C.1EG2.4.1 Response to Inadequate Core 4.6 4.8 Knowledge of Emergency/Abnormal Operating Procedure Cooling entry conditions.

FR-H.1EK3.14 Response to Loss of Heat Sink 4.4 Automatic Depressurization System Actuation FR-S.1EK2.03 Response to Nuclear Power 4.1 Failure to recognize the need and failure to manually trip Generation - ATWS the reactor through the Protection and Safety Monitoring System, given anticipated transient without scram (PRA related)

SDP-1EA2.03 Response to Loss of RCS 3.6 3.6 Core exit temperature Inventory During Shutdown Page 2 of 2 01/11/2016 7:41 AM

ES-401N, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO A-304AK2.08 Steam Generator Tube Leak 3.2 Using Passive Residual Heat Removal System for Reactor Coolant System cooldown A-311AK3.02 Rod Control System Malfunctions 3.3 Checking On-line Power Distribution Monitoring System is operable A-320AK1.09 Loss of Circulating Water 2.6 Circulating Water trash screens A-327AA2.01 Startup Feedwater System 2.8 3.5 Steam generator level Malfunctions A-328AK1.03 Malfunction of Feedwater Heaters 2.6 Main and Startup Feedwater System and Extraction Steam A-333AA1.01 Main Turbine Malfunctions 3.4 Main turbine load and trip controls FR-Z.1EK3.06 Response to High Containment 3.4 Main Steam Isolation Actuation Pressure FR-Z.2EG2.4.25 Response to Containment Flooding 3.6 4 Knowledge of operator response to a loss of all annunciators.

FR-Z.4EA2.01 Low Containment Pressure 2.8 3 Containment pressure Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTION IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO ADSA4.04 Automatic Depressurization System 4.1 Reactor Cooling System pressure ADSK6.01 Automatic Depressurization System 4.2 Diverse Actuation System CASA1.01 Compressed Air System 2.6 Instrument air compressor package parameters CCSK4.02 Component Cooling Water System 3 Normal Reactor Coolant System cooldown CNSK1.20 Containment System 3.3 Steam Generator System CNSK3.01 Containment System 4 Containment integrity CVSK2.04 Chemical and Volume Control 3.7 Containment isolation valves System DASA2.05 Diverse Actuation System 3.4 3.3 Containment isolation ECSG2.2.17 AC Electrical Distribution Systems 4 4.7 Knowledge of limiting conditions for operations and safety limits.

ESASK6.23 Engineered Safeguards Actuation 3.6 P-12, Pressurizer Level System FWSA4.05 Main and Startup Feedwater System 3.3 Main feedwater control valve Page 1 of 3 01/11/2016 7:41 AM

ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTION IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO IDSK2.09 Class 1E and Non 1E DC and UPS 2.5 Non class 1E instrument bus inverters (OE-related)

Systems IDSK4.06 Class 1E and Non 1E DC and UPS 2.6 System ground detection Systems MSSA3.05 Main Steam System 3.5 Steam Line Isolation Actuation PCSA2.13 Passive Containment Cooling 3.8 4.1 Loss of coolant accident System PCSK5.03 Passive Containment Cooling 2.5 Heat transfer via radiation System PPCSG2.4.39 Pressurizer Pressure Control 4.2 4 Ability to verify system alarm setpoints and operate controls System identified in the Alarm Response Procedure.

PRHRA1.03 Passive Residual Heat Removal 3.5 Passive Residual Heat Removal System heat exchanger System temperature PXSK3.02 Passive Core Cooling System 3.2 Normal Residual Heat Removal System RCPK5.04 Reactor Coolant Pump System 3.2 Reactor coolant pump start effect on reactivity/boron (OE-related)

RCSA1.17 Reactor Coolant System 3.9 Reactor Coolant System Automatic Depressurization System discharge temperature RCSK1.18 Reactor Coolant System 3.6 Normal Residual Heat Removal System Page 2 of 3 01/11/2016 7:41 AM

ES-401N, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTION IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO RNSA4.07 Normal Residual Heat Removal 3.5 Post loss of coolant accident containment makeup System RNSK6.04 Normal Residual Heat Removal 2.7 Pump flow rate instrument System RTSK2.02 Reactor Trip System 3.6 Reactor Trip System Instrumentation SGSK5.14 Steam Generator System 2.6 Chemistry and corrosion control SWSK1.03 Service Water System 2.7 Circulating Water System ZOSA3.01 Onsite Standby Power System 3.2 Standby Diesel Generator starting and loading Page 3 of 3 01/11/2016 7:41 AM

ES-401N, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO CDSK4.07 Condensate System 2.6 Feedwater heater automatic isolation and bypass DRCSG2.2.28 Digital Rod Control System 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

FHSK5.06 Fuel Handling System 2.7 3.0 Loss of Containment Air Filtration System IISK1.07 Incore Instrumentation System 2.5 Special Monitoring System NISA3.03 Nuclear Instrumentation System 3.6 P-17, Negative Flux Rate Alert PLCSA1.08 Pressurizer Level Control System 3.1 Code safety tailpipe temperature RMSK2.01 Radiation Monitoring System 3.1 Radiation monitors that provide Engineered Safeguards Actuation System Actuations VFSK6.01 Containment Air Filtration System 2.5 Compressed Air System VLSA4.02 Containment Hydrogen Control 3.6 Containment hydrogen igniter System WGSK3.01 Gaseous Radwaste System 2.6 Plant Gas Systems Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G.2.3.9 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.

G2.1.5 Conduct of operations 2.9 3.9 Ability to use procedures related to shift staffing, such as minimum crew complement, or overtime limitations.

G2.1.8 Conduct of operations 3.4 4.1 Ability to coordinate personnel activities outside the control room.

G2.2.15 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.

G2.2.22 Equipment Control 4.6 Ability to determine operability or availability of safety related equipment.

G2.2.24 Equipment Control 3.9 4.5 Knowledge of less than or equal to one hour Technical Specification action statements. (This K/A does not include Action Statements of one hour or less that follow the expiration of a completion time for a Technical Specification condition for which an A G2.3.4 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

G2.4.16 Emergency Procedures/Plans 4 4.6 Knowledge of the parameters and logic used to assess the status of Emergency Operating Procedures Critical Safety Functions or Shutdown Critical Safety Functions.

G2.4.38 Emergency Procedures/Plans 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material G2.4.8 Emergency Procedures/Plans 3.8 4.2 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

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ES-401N, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO A-323AG2.2.21 Loss of 6.9KV, 4160 Volt, or 480 Volt 3.1 4.2 Ability to analyze the effect of maintenance activities, such Bus Power as degraded power sources, on the status of limiting conditions for operations.

A-329AG2.1.14 Loss of Instrument Air 4 3.3 Ability to use integrated control systems to operate plant systems or components.

A-336AA2.02 Malfunction of Protection and Safety 4 3.7 Diverse Actuation System indications Monitoring System E-1EA2.04 Loss of Reactor or Secondary Coolant 3.4 3.4 Passive Residual Heat Removal System flow FR-C.1EG2.2.19 Response to Inadequate Core Cooling 0 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

FR-H.1EA2.02 Response to Loss of Heat Sink 3.8 3.7 Reactor Coolant System pressure and/or temperature Page 1 of 1 01/11/2016 7:41 AM

ES-401N, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO A-308AA2.02 Loss of Control Room Air 2.3 2.8 Nuclear Island Nonradioactive Ventilation System flow Conditioning A-318AG2.2.22 Condensate System Malfunctions 0 4.6 Ability to determine operability or availability of safety related equipment.

ES-1.2EA2.07 Post Loss of Coolant Accident 3.2 3.7 Containment pressure Cool Down and Depressurization FR-C.3EG2.4.14 Response to Saturated Core 3.4 4.1 Knowledge of Emergency/Abnormal Operating Cooling Procedures layout, symbols, and icons.

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ES-401N, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO CASA2.06 Compressed Air System 3 2.7 Loss of instrument air supply pressure CNSA2.03 Containment System 3.7 3.6 Normal Residual Heat Removal System containment isolation ESASG2.4.3 Engineered Safeguards Actuation 3.7 3.9 Ability to identify post-accident instrumentation.

System FWSG2.1.21 Main and Startup Feedwater 4.3 4.4 Ability to perform general and/or normal operating System procedures during any plant condition.

RTSG2.4.1 Reactor Trip System 4.6 4.8 Knowledge of Emergency/Abnormal Operating Procedure entry conditions.

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ES-401N, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO FPSG2.4.39 Fire Protection System 4.2 4 Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.

SDCSA2.08 Steam Dump Control System 2.7 2.9 Main steam header pressure VESG2.4.24 Main Control Room HVAC 4.2 4.1 Knowledge of annunciator alarms, indications, or response procedures.

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ES-401N, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 KA NAME / SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G.2.3.9 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.

G2.1.30 Conduct of operations 3 Knowledge of the fuel-handling responsibilities of SROs.

G2.2.11 Equipment Control 3.9 4.3 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, or tag-outs.

G2.2.27 Equipment Control 3.5 3.9 Ability to obtain and/or interpret station electrical and mechanical drawings.

G2.3.5 Radiation Control 3.8 4.3 Ability to control radiation releases.

G2.4.39 Emergency Procedures/Plans 4.2 4 Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.

G2.4.6 Emergency Procedures/Plans 3.7 4.7 Knowledge of Emergency/Abnormal Operating Procedures major action categories.

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Draft ES-301-1, ES-301-2, RO Written Exam, SRO Written Exam, Simulator Scenarios, Simulator JPMs, In-Plant JPMs, and Administrative JPMs are located in Non-Public ADAMS due to being Proprietary information.