ML20148M368

ADAMS-2A-1 Vogtle-3 2020-301 Draft Items Public

ML20148M368
Person / Time
Site:	Vogtle
Issue date:	04/27/2020
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
Download: ML20148M368 (10)

Text

ES-401N AP-1000 Examination Outline Form ES-401N-2 Facility: Vogtle 3&4 Date of Exam: March 2020 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 3 3 3 18 3 3 6 Emergency 2 1 1 1 2 2 2 9 2 2 4 and Abnormal N/A N/A Plant Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10 1 3 2 3 3 3 2 2 2 3 3 2 28 2 3 5 2.

2 1 0 1 1 1 1 1 1 1 1 1 10 - 1 2 3 Plant Systems Tier Totals 4 2 4 4 4 3 3 3 4 4 3 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 3 1 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 section (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-401N 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-401N 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 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 above 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-401N-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

ES-401N 2 Form ES-401N-2 ES-401N AP-1000 Examination Outline Form ES-401N-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

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

1 2 3 1 E-0, Reactor Trip or Safeguards R R: EK2.06 Unavailability of either the startup 3.6 Actuation / 1, 2, 3, 4 feedwater pumps or Passive Residual Heat Removal System.

ES-0.1, Reactor Trip Response / 1, 2, 3, R R: EK3.16 Energizing the source range nuclear 3.2 4 instrumentation ES-1.3, ADS Stage 1-3 Actuation R R: EA1.03 Diverse Actuation System 3.4 Response / 3 ES-1.4, ADS Stage 4 Actuation R R: EA2.05 RNS alignment 2.9 Response / 3 A-313, Uncontrolled Cooldown / 4 R R: G2.1.7 Ability to evaluate plant performance 4.4 and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

A-336, Malfunction of Protection and S S: AA2.02 Diverse Actuation System 3.7 Safety Monitoring System / 7 indications E-1, Loss-of-Coolant Accident / 2, 3 R R: EK1.10 Passive Containment Cooling 3.9 System A-342, Reactor Coolant Pump R R: AK2.02 Reactor coolant pump trip in mode 3.1 Malfunction / 1, 2, 3, 4 3, 4, or 5 A-337, Passive RHR Heat Exchanger R R: AK3.07 Trending Passive Residual Heat 2.6 Leak / 4 Removal System inlet pressure over time A-343, Loss of Normal Residual Heat R R: AA1.06 Engineered Safeguards Actuation 4.0 Removal / 4 System A-317, Loss of Component Cooling Water S S: G2.2.17 Knowledge of limiting conditions for 4.7

/8 operations and safety limits.

ES-0.2, Natural Circulation Cooldown / 4 R R: EA2.02 Reactor Coolant System 3.4 temperature, pressure, and/or pressurizer level FR-S.1, Response to Nuclear Power R R: G2.4.9 Knowledge of operating crew 4.0 Generation / 1 responsibilities during emergency/abnormal operations.

E-3, Steam Generator Tube Rupture / 3 S EA2.02 Ruptured steam generator feedflow, 3.8 level, and/or pressure E-2, Faulted Steam Generator Isolation / R R: EK1.01 Steam Generator Blowdown System 2.9 4

A-301, Rapid Power Reduction / 1 R R: AK2.04 Failure of P-10, Power Range 3.3 Neutron Flux to reset A-307, DAS Operations at Local Cabinets NOT SELECTED

/7 FR-C.1, Response to Inadequate Core S S: G2.1.19 Ability to interpret and execute 4.6 Cooling / 4 procedure steps.

A-323, Loss of 6.9-kV, 4,160-V, or 480-V S S: AA2.03 Standby diesel generator load 3.4 Bus Power / 6 ES-1.1, Passive Safety System R R: EK3.11 Blocking Steamline / Feedwater 3.4 Termination / 3 Isolation Actuations and/or Safeguards Actuation below P-11, Pressurizer Pressure Below 1970 psig A-345, Loss of Nuclear Service Water / 4 R R: AA1.02 Compressed and Instrument Air 2.6 System A-329, Loss of Instrument Air / 8 S S: G2.2.30 Ability to interpret control room 4.4 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

ECA-1.1, Loss-of-Coolant Accident R R: EA2.02 Plant vent radiation 3.2 Outside Containment / 3

FR-H.1, Response to Loss of Heat Sink / R R: G2.4.39 Ability to verify system alarm 4.2 4 setpoints and operate controls identified in the Alarm Response Procedure.

SDP-1, Response to Loss of RCS R R: EK1.08 Passive Residual Heat Removal 3.4 Inventory During Shutdown / 2 System SDP-2 Response to Loss of RNS During NOT SELECTED Shutdown / 4 K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401N 3 Form ES-401N-2 ES-401N AP-1000 Examination Outline Form ES-401N-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

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

1 2 3 1 A-311, Rod Control System Malfunction / 1 NOT SELECTED A-308, Loss of Control Room AC / 8 NOT SELECTED R R: AA1.04 Cooling tower level 2.6 A-320, Loss of Circulating Water / 8 makeup and/or blowdown control A-302, Emergency Boration / 1 NOT SELECTED A-327, Startup Feedwater System Malfunction / 4 R R: AA2.01 Steam generator level 2.8 A-328, Malfunction of Feedwater Heaters and NOT SELECTED Extraction Steam / 4 FR-I.1 Response to High Pressurizer Level / 2 NOT SELECTED S S: AA2.01 Containment Bldg, fuel 3.4 A-314, Fuel-Handling Incident / 8 handling building, and/or plant vent radiation level R R: G2.2.23 Knowledge of conditions 3.6 A-304, Steam Generator Tube Leak / 3 and limitations in the facility license.

NOT SELECTED A-333, Main Turbine Malfunction / 4 FR-Z.1, Response to High Containment Pressure / NOT SELECTED 5

SDP-4, Response to Rising Nuclear Flux During NOT SELECTED Shutdown / 1 SDP-5, Response to RCS Cold Overpressure S S: G2.1.21 Ability to perform general 4.4 and/or normal operating procedures During Shutdown / 3 during any plant condition.

SDP-6 Response to Unexpected RCS R R: EK1.05 Service Water System 2.9 Temperature Changes During Shutdown / 4 S S: AA2.02 Chemical and Volume 2.9 A-306, Evacuation of Control Room / 8 Control System makeup system flows R R: AK2.05 Loss of cooling to gland 2.5 A-318, Condensate System Malfunctions / 4 sealing condenser FR-C-2, Response to Degraded Core Cooling / 4 NOT SELECTED FR-C.3, Response to Saturated Core Cooling / 4 NOT SELECTED FR-H.2, Response to Steam Generator R R: EK3.03 Verifying SG PORVs are 3.2 Overpressure / 4 not isolated FR-Z.2, Response to Containment Flooding / 5 NOT SELECTED FR-Z.3, Response to High Containment Radiation / NOT SELECTED 9

FR-Z.4, Response to Low Containment Pressure / R R: EA1.05 Engineering Safeguard 2.8 5 Actuation System A-332, Turbine Trip Without Reactor Trip / 4 R R: AA2.01 Reactor Coolant System 3.2 temperature ES-1.2, Post LOCA Cooldown and NOT SELECTED Depressurization / 4 A-321, Loss of Data Display and Processing NOT SELECTED System / 7 R R: G2.4.16 Knowledge of the 4.0 FR-P.1, Response to Imminent Pressurized parameters and logic used to assess the status of Emergency Operating Thermal Shock Condition / 3 Procedures Critical Safety Functions or Shutdown Critical Safety Functions.

A-340, Reactor Coolant Leak / 2 NOT SELECTED

FR-I.2, Response to Low Pressurized Level / 2 NOT SELECTED FR-I.3, Response to Voids in Reactor Vessel / 2 NOT SELECTED A-326, Feedwater System Malfunctions / 4 NOT SELECTED A-331, Loss of Plant DC Power or Batteries / 6 NOT SELECTED S S: G2.4.24 Knowledge of annunciator 4.1 A-348, Degraded Grid / 6 alarms, indications, or response procedures.

K/A Category Totals: 1 1 1 2 2/2 2/2 Group Point Total: 9/4

ES-401N 4 Form ES-401N-2 ES-401N AP-1000 Examination Outline Form ES-401N-2 Plant SystemsTier 2/Group 1 (RO/SRO)

K K K K K K A A A G*

System Name / Safety Function A2 K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 R S R: K1.03 Component Cooling 3.1 Water System Reactor Coolant / 2, 4 S: G2.1.17 Ability to use available 3.8 indications to evaluate system or component status.

R R R: K1.16 Steam Dump Control 3.2 System Steam Generator / 4 R: K2.11 Steam generator 2.9 blowdown isolation valves R S R: K3.02 Passive Core Cooling 3.6 System Normal Residual Heat Removal /

4 S: A2.08 Containment isolation 3.9 valves R R R: K2.01 Passive Residual Heat 3.2 Removal System heat exchanger Passive Residual Heat Removal inlet isolation valves

/4 R: K4.05 Passive Residual Heat 3.6 Removal System flow control R R R: K3.02 Normal Residual Heat 3.2 Removal System Passive Core Cooling / 2 R: K5.05 Post accident containment 3.4 pH control R R R: K4.05 Chemical and Volume 3.0 Control System makeup pump protection Component Cooling Water / 8 R: K6.28 Reactor coolant pump 3.2 external heat exchanger tube leak R R: A1.16 Pressurizer and Reactor 3.3 Pressurizer Pressure Control / 3 Coolant System boron Concentration R R: A2.02 Engineered Safeguards 4.1 Automatic Depressurization / 3 Actuation System R R: A3.02 Power Range Neutron 4.1 Reactor Trip System / 7 Flux High Positive Rate Reactor Trip R S R: A4.07 Startup Feedwater 3.9 Isolation Actuation Engineered Safeguards Actuation

/2 S: G2.2.22 Ability to determine 4.6 operability or availability of safety related equipment.

R R: G2.4.9 Knowledge of operating 4.0 Diverse Actuation / 7 crew responsibilities during emergency/abnormal operations.

R R: K1.08 Fire Protection System 2.7 Passive Containment Cooling / 5 R R: K5.03 Changing steam flow 3.7 Main Steam / 4 effect on reactor power R S R: K3.07 Reactor Coolant System 3.5 Main and Startup Feedwater / 4 S: A2.04 Engineered Safeguards 3.7 Actuation System R R: K4.02 Back feeding buses from 3.2 AC Electrical Distribution / 6 the grid

Class 1E and Non 1E DC and R R: K5.02 Loss of one or more Class 3.7 UPS / 6 1E instrument buses R R: K6.10 Lubrication Oil System 3.0 Onsite Standby Power System / 6 failure R R: A1.04 Service Water System 2.7 Service Water / 4 cooling tower basin level R R: A2.02 Transmission Switchyard 2.7 Compressed Air / 8 and Offsite Power System R S R: A3.01 Containment isolation 4.1 Containment System / 5 S: G2.4.9 Knowledge of operating 4.3 crew responsibilities during emergency/abnormal operations.

R R R: A3.01 Reactor Coolant Pump 3.6 Trip Actuation due to Engineered Safeguards Actuation Reactor Coolant Pump / 4 R: A4.02 Reactor coolant pump 2.9 shutdown R R R: A4.09 Containment Isolation 4.0 Actuation Chemical and Volume Control / 1, 2 R: G2.1.28 Ability to explain and 3.8 apply system precautions, limitations, notes, or cautions.

K/A Category Point Totals: 3 2 3 3 3 2 2 2/2 3 3 2/3 Group Point Total: 28/5

ES-401N 6 Form ES-401N-2 ES-401N AP-1000 Examination Outline Form ES-401N-2 Plant SystemsTier 2/Group 2 (RO/SRO)

K K K K K K A A A G*

System Name / Safety Function A2 K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 NOT SELECTED Digital Rod Control / 1 R R: A2.06 Reactor Coolant System 3.2 Pressurizer Level Control / 2 S S: G2.2.19 Knowledge of the bases in 4.2 Rod Position Indication / 1 Technical Specifications for limiting conditions for operations and safety limits.

NOT SELECTED In-Core Instrument System / 7 R R: A3.02 Containment Air Filtration 3.6 Containment Air Filtration / 8 System Isolation Actuation Containment Hydrogen Control / R R: A4.01 Containment hydrogen 3.6 5 monitor R R: G2.1.24 Knowledge of system 3.9 Main Control Room HVAC / 8 purpose and/or function.

NOT SELECTED Spent Fuel Pool Cooling / 8 R R: K1.11 Main and Startup Feedwater 2.8 Condensate / 4 System R R: A1.01 Main condenser vacuum 3.1 Condenser Air Removal / 4 Main Turbine and Main Turbine NOT SELECTED Control / 4 NOT SELECTED Fuel Handling / 8 S S: A2.10 Wetted activated carbon bed 2.6 Gaseous Radwaste / 9 R R: K3.03 Post Accident Monitoring 3.2 Radiation Monitoring / 7 System R R: K4.01 C-9, Condenser Available 3.1 Circulating Water / 8 S S: G2.4.7 Knowledge of how Abnormal 4.5 Fire Protection / 8 Operating Procedures are used in conjunction with Emergency Operating Procedures.

R R: K5.06 Changing steam flow effect on 3.5 Steam Dump Control System / 4 Reactor Coolant System temperature and/or cooldown rate Nuclear Instrumentation System / NOT SELECTED 7

R R: K6.07 Waste holdup tank inputs, 2.6 (such as; Containment sump, Auxiliary Liquid Radwaste System / 9 bldg sump, or Steam Generator blowdown)

K/A Category Point Totals: 1 0 1 1 1 1 1 1/1 1 1 1/2 Group Point Total: 10/3

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

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

Ability to use integrated control systems to operate plant systems 2.1.14 4.0 or components.

Ability to use On-Line Power Distribution Monitoring System 2.1.38 and/or procedures to determine the effects on reactivity of plant 4.1 changes, such as reactor coolant system temperature, secondary plant, or fuel depletion.

2.1.19 Ability to interpret and execute procedure steps. 4.6

1. Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, such as 3.9 minimum crew complement, or overtime limitations.

Knowledge of administrative requirements for temporary 2.1.13 management direction, such as standing orders, night orders, or 3.4 operations memos.

Subtotal 3 2 2.2.7 Knowledge of the process for conducting Infrequently Preformed 2.9 Tests or Evolutions.

Knowledge of the process for controlling equipment configuration 2.2.10 3.9 or status.

Knowledge of pre- and post-maintenance operability 2.2.16 2.9 requirements.

2. Equipment Control 2.2.9 Knowledge of tagging and clearance procedures. 4.3 Knowledge of the process for managing maintenance activities 2.2.12 during power operations, such as risk assessments, work 3.8 prioritization, and coordination with the transmission system operator.

Subtotal 3 2 2.3.1 Knowledge of radiation exposure limits under normal or 3.2 emergency conditions.

3. Radiation Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor Control 2.3.7 alarms, containment entry requirements, fuel handling 3.8 responsibilities, access to locked high-radiation areas, or aligning filters.

Subtotal 1 1 2.4.15 Knowledge of the operational implications of emergency / 3.8 abnormal operating procedures warnings, cautions, and notes.

2.4.17 Knowledge of the bases for prioritizing safety functions during 3.6 abnormal / emergency operations.

Knowledge of events related to system operation/status that 2.4.23 must be Reported to internal organizations or external agencies, 2.7

4. Emergency such as the State, the NRC, or the transmission system operator.

Procedures/Plan Knowledge of how Abnormal Operating Procedures are used in 2.4.7 4.5 conjunction with Emergency Operating Procedures.

Knowledge of emergency communications systems and 2.4.34 3.8 techniques.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401N Record of Rejected K/As Form ES-401N-4 Randomly Selected Tier/Group Reason for Rejection KA