ML16111A373

2016 Prairie Island Nuclear Generating Plant Initial License Examination Form ES-401-2 and Form ES-401-3

ML16111A373
Person / Time
Site:	Prairie Island
Issue date:	06/10/2016
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:	Northern States Power Company, Minnesota, Xcel Energy
References
Download: ML16111A373 (13)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Prairie Island Nuclear Generating Plant Date of Exam: June 10, 2016 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 2 4 3 3 3 18 3 3 6 Emergency &

Abnormal 2 1 1 1 N/A 2 2 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 4 3 5 5 5 5 27 5 5 10 1 2 3 2 3 2 2 3 2 3 3 3 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, 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 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 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 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

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

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

1 2 3 1 2 Ability to operate and monitor the following as 000007 Reactor Trip - Stabilization - 0 they apply to a reactor trip: MT/G trip; verification 4.3 1 Recovery / 1 7 that the MT/G has been tripped.

Ability to determine and interpret the following as 000008 Pressurizer Vapor Space 2 they apply to the Pressurizer Vapor Space Accident: Consequences of loss of pressure in 3.8 2 Accident / 3 2 RCS; methods for evaluating pressure loss.

2.1.7:Ability to evaluate plant performance and make operational judgments based on operating 000009 Small Break LOCA / 3 X characteristics, reactor behavior, and instrument 4.4 3 interpretation.

Knowledge of the operational implications of the 0 following concepts as they apply to the Large 000011 Large Break LOCA / 3 Break LOCA: Natural circulation and cooling, 4.1 4 1

including reflux Boiling.

Knowledge of the interrelations between the 0 Reactor Coolant Pump Malfunctions (Loss of RC 000015/17 RCP Malfunctions / 4 2.9 5 7 Flow) and the following: RCP seals.

000022 Loss of Rx Coolant Makeup / 2 Knowledge of the reasons for the following 0 responses as they apply to the Loss of Residual 000025 Loss of RHR System / 4 Heat Removal System: Shift to alternate 3.1 6 1

flowpath.

Ability to operate and/or monitor the following as 000026 Loss of Component Cooling 0 they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level 3.1 7 Water / 8 5 control and level alarms, and radiation alarm.

000027 Pressurizer Pressure Control System Malfunction / 3 Ability to determine or interpret the following as 0 they apply to a ATWS: Reactor nuclear 000029 ATWS / 1 4.4 8 1 instrumentation.

000038 Steam Gen. Tube Rupture / 3 W/E12 Steam Line Rupture - Excessive 2.4.21: Knowledge of general operating crew X responsibilities during emergency operations. 4.0 9 Heat Transfer / 4 Knowledge of the operational implications of the following concepts as they apply to Loss of Main 0 Feedwater (MFW): MFW line break 000054 Loss of Main Feedwater / 4 4.1 10 1 depressurizes the S/G (similar to a steam line break).

Knowledge of the reasons for the following 0 responses as they apply to the Station Blackout:

000055 Station Blackout / 6 Actions contained in EOP for loss of offsite and 4.3 11 2

onsite power.

Knowledge of the reasons for the following 0 responses as they apply to the Loss of Offsite 000056 Loss of Off-site Power / 6 Power: Order and time to initiation of power for 3.5 12 1

the load Sequencer.

Ability to operate and/or monitor the following as 0 they apply to the Loss of Vital AC Instrument Bus:

000057 Loss of Vital AC Inst. Bus / 6 Manual control of components for which 3.5 13 6

automatic control is lost.

000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 Ability to determine and interpret the following as 0 they apply to the Loss of Instrument Air: When to 000065 Loss of Instrument Air / 8 trip reactor if instrument air pressure is 3.6* 14 6

decreasing.

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

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

1 2 3 1 2 2.1.23: Ability to perform specific system and W/E04 LOCA Outside Containment / 3 X integrated plant procedures during all modes of 4.3 15 plant operation.

Knowledge of the operational implications of the following concepts as they apply to the (Loss of W/E11 Loss of Emergency Coolant Emergency Coolant Recirculation): Normal, 2 abnormal and emergency operating procedures 3.6 16 Recirc. / 4 associated with (Loss of Emergency Coolant Recirculation).

Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

Facilitys heat removal systems, including primary W/E05 Inadequate Heat Transfer - Loss coolant, emergency coolant, the decay heat 2 3.9 17 of Secondary Heat Sink / 4 removal systems, and relations between the proper operation of these systems to the operation of the facility.

Knowledge of the reasons for the following responses as they apply to Generator Voltage 000077 Generator Voltage and Electric 0 and Electric Grid Disturbances: Actions 3.6 18 Grid Disturbances / 6 2 contained in abnormal operating procedure for voltage and grid disturbances.

K/A Category Totals: 3 2 4 3 3 3 Group Point Total: 18

ES-401 4 Form ES-401-2 S-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

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

1 2 3 1 2 2.4.11: Knowledge of abnormal 000001 Continuous Rod Withdrawal / 1 X condition procedures. 4.0 19 000003 Dropped Control Rod / 1 Knowledge of the operational 0 implications of the following concepts as 000005 Inoperable/Stuck Control Rod / 1 they apply to Inoperable / Stuck Control 3.1 20 2

Rod: Flux tilt.

000024 Emergency Boration / 1 Knowledge of the interrelations between 0 the Pressurizer Level Control 000028 Pressurizer Level Malfunction / 2 2.3 21 4 Malfunctions and the following: Pumps.

Knowledge of the reasons for the following responses as they apply to the 0 Accidental Gaseous Radwaste:

000060 Accidental Gaseous Radwaste Rel. / 9 3.3* 22 2 Isolation of the auxiliary building ventilation.

000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 Ability to operate and/or monitor the following as they apply to the (High W/E14 Loss of CTMT Integrity / 5 2 Containment Pressure): Operating 3.3 23 behavior characteristics of the facility.

W/E06 & E07 Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 Ability to determine and interpret the following as they apply to the (SI Termination): Facility conditions and W/E01 & E02 Rediagnosis & SI Termination / 3 1 selection of appropriate procedures 3.3 24 during abnormal and emergency operations.

W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 2.4.3: Ability to identify post-accident W/E16 High Containment Radiation / 9 X instrumentation. 3.7 25 Ability to operate and/or monitor the following as they apply to the (LOCA Cooldown and Depressurization):

Components and functions of control W/E03 LOCA Cooldown - Depress. / 4 1 and safety systems, including 4.0 26 instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel W/E09 & E10 Natural Circ. / 4 1 with/without RVLIS): 3.2 27 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

W/E08 RCS Overcooling - PTS / 4 K/A Category Point Totals: 1 1 1 2 2 2 Group Point Total: 9

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to manually operate and/or 0 monitor in the control room: RCP lube 003 Reactor Coolant Pump 2.8 28 3 oil and lift pump motor controls.

2.1.31: Ability to locate control room 004 Chemical and Volume switches, controls, and indications, and X 4.6 29 Control to determine that they correctly reflect the desired plant lineup.

Knowledge of bus power supplies to the 0 following: RCS pressure boundary 005 Residual Heat Removal 2.7* 30 3 motor-operated valves.

Knowledge of the effect that a loss or 0 malfunction of the ECCS will have on the 006 Emergency Core Cooling 4.1* 31 1 following: RCS.

Knowledge of PRTS design feature(s) 007 Pressurizer Relief/Quench 0 and/or interlock(s) which provide for the following: 2.6 32 Tank 1 Quench tank cooling.

3.1 33 A1.04: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:

0 1 Surge tank level.

008 Component Cooling Water 3.1* 34 4 0 A4.10: Ability to manually operate and/or monitor in the control room:

Conditions that require the operation of two CCW coolers.

K5.01: Knowledge of the operational 3.2 35 implications of the following concepts as they apply to the PZR PCS:

Determination of condition of fluid in 0 0 PZR, using steam tables.

010 Pressurizer Pressure Control 1 3 3.5 36 K6.03: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: PZR sprays and heaters.

Ability to predict and/or monitor Changes in parameters (to prevent exceeding 0 design limits) associated with operating 012 Reactor Protection 2.9* 37 1 the RPS controls including:

Trip setpoint adjustment.

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those 013 Engineered Safety Features 0 predictions, use procedures to correct, 4.6 38 Actuation 1 control, or mitigate the consequences of those malfunctions or operations:

LOCA.

K2.01: Knowledge of power supplies to 3.0* 39 the following: Containment cooling fans.

0 0 A3.01:

022 Containment Cooling 4.1 40 1 1 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation.

ES-401 6 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to manually operate and/or 0 monitor in the control room: CSS 026 Containment Spray 4.5 41 1 controls.

2.1.19: Ability to use plant computers to 039 Main and Reheat Steam X evaluate system or component status. 3.9 42 K1.03: Knowledge of the physical 3.1 43 connections and/or cause effect relationships between the MFW and the following systems: S/GS.

0 0 A2.03: Ability to (a) predict the impacts 2.7 44 059 Main Feedwater of the following malfunctions or 3 3 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overfeeding event.

3.7* 45 K2.02: Knowledge of bus power supplies to the following: AFW electric drive pumps.

061 Auxiliary/Emergency 0 0 Feedwater 2 3 K5.03: Knowledge of the operational implications of the following concepts as 2.6 46 they apply to the AFW: Pump head effects when control valve is shut.

Knowledge of the effect that a loss or 0 malfunction of the ac distribution system 062 AC Electrical Distribution 4.1 47 2 will have on the following: ED/G.

Knowledge of DC electrical system 0 design feature(s) and/or interlock(s) 063 DC Electrical Distribution which provide for the following: 2.7 48 1

Manual/automatic transfers of control.

Knowledge of the effect of a loss or 0 malfunction of the following will have on 064 Emergency Diesel Generator the ED/G system: 2.7 49 7

Air receivers.

Knowledge of PRM system design feature(s) and/or interlock(s) which 0 provide for the following: Release 073 Process Radiation Monitoring 4.0 50 1 termination when radiation exceeds setpoint.

A1.02: Ability to predict and/or monitor 2.6* 51 changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:

Reactor and turbine building closed 0 cooling water temperatures.

076 Service Water X 2

2.2.3:

Knowledge of the design, procedural, and operational differences between 3.8 52 units.

0 Ability to monitor automatic operation of 078 Instrument Air the IAS, including: Air pressure 3.1 53 1

ES-401 7 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K1.03: Knowledge of the physical connections and/or cause effect 3.1* 54 relationships between the containment system and the following systems:

103 Containment 0 0 Shield Building Vent System.

3 1 A3.01: Ability to monitor automatic 3.9 55 operation of the containment system, including: Containment isolation.

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

ES-401 8 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Knowledge of the effect or a loss or 1 malfunction on the following RCS 002 Reactor Coolant 3.0 56 2 components: Code Safety valves.

011 Pressurizer Level Control Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, 0 use procedures to correct, control, or 014 Rod Position Indication 3.1 57 2 mitigate the consequences of those malfunctions or operations: Loss of power to the RPIS.

015 Nuclear Instrumentation 016 Non-nuclear Instrumentation Ability to monitor automatic operation of the 0 ITM system including: Measurement of in-017 In-core Temperature Monitor core thermocouple temperatures at panel 3.4* 58 2

outside control room.

028 Hydrogen Recombiner and Purge Control Ability to manually operate and/or monitor 0 in the control room: Containment purge 029 Containment Purge 2.5 59 1 flow rate.

2.1.25: Ability to interpret reference 033 Spent Fuel Pool Cooling X materials, such as graphs, curves, tables, 3.9 60 etc.

Knowledge of the physical connections 0 and/or cause effect relationships between 034 Fuel Handling Equipment the Fuel Handling System and the following 2.6 61 4

systems: NIS.

035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator Ability to monitor automatic operation of the 0 CARS, including: Automatic diversion of 055 Condenser Air Removal 2.5* 62 3 CARS exhaust.

056 Condensate Knowledge of the physical connections and/or cause effect relationships between 0 the Liquid Radwaste System and the 068 Liquid Radwaste 2.7 63 7 following systems: Sources of liquid wastes for LRS.

071 Waste Gas Disposal Knowledge of ARM system design 0 feature(s) and/or interlock(s) which provide 072 Area Radiation Monitoring 3.2* 64 3 for the following: Plant ventilation systems.

075 Circulating Water Knowledge of SAS design feature(s) and/or 0 interlock(s) which provide for the following:

079 Station Air 2.9 65 1 Cross-connect with IAS.

086 Fire Protection K/A Category Point Totals: 2 0 0 2 0 1 0 1 2 1 1 Group Point Total: 10

ES-401 9 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

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

1 2 3 1 2 Ability to determine or interpret the following as 1 they apply to a small break LOCA: RCS 000009 Small Break LOCA / 3 3.4 76 5 parameters.

000015/17 RCP Malfunctions / 4 X 2.2.12: Knowledge of surveillance procedures. 4.1 77 Ability to determine and interpret the following as 0 they apply to the Loss of Reactor Coolant 000022 Loss of Rx Coolant Makeup / 2 3.7 78 2 Makeup: Charging pump problems.

2.4.20: Knowledge of the operational implications 000055 Station Blackout / 6 X of EOP warnings, cautions, and notes. 4.3 79 Ability to determine and interpret the following as 0 they apply to the Loss of Offsite Power:

000056 Loss of Off-site Power / 6 Operational status of emergency feedwater pump 4.3 80 7

(motor driven).

2.2.36: Ability to analyze the effect of 000077 Generator Voltage and Electric maintenance activities, such as degraded power X sources, on the status of limiting conditions for 4.2 81 Grid Disturbances / 6 operations.

K/A Category Totals: 3 3 Group Point Total: 6

ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

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

1 2 3 1 2 Ability to determine and interpret the 0 following as they apply to the Emergency 000024 Emergency Boration / 1 Boration: Amount of boron to add to achieve 3.9 82 5

required SDM.

2.2.38: Knowledge of conditions and 000033 Loss of Intermediate Range NI / 7 X limitations in the facility license. 4.5 83 Ability to determine and interpret the 1 following as they apply to the Plant Fire on 000067 Plant Fire On-site / 8 Site: Requirements for establishing a fire 3.9 84 5

watch.

2.4.45: Ability to prioritize and interpret the W/E16 High Containment Radiation / 9 X significance of each annunciator or alarm. 4.3 85 K/A Category Point Totals: 2 2 Group Point Total: 4

ES-401 11 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.4.8: Knowledge of how abnormal 008 Component Cooling Water X operating procedures are used in 4.5 86 conjunction with EOPs.

Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those 0 predictions, use procedures to correct, 022 Containment Cooling 3.5 87 5 control, or mitigate the consequences of those malfunctions or operations:

Major leak in CCS.

Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those 061 Auxiliary/Emergency 0 predictions, use procedures to correct, 3.5 88 Feedwater 7 control, or mitigate the consequences of those malfunctions or operations: Air or MOV failure.

Ability to (a) predict the impacts of the following malfunctions or operations on the DC distribution system; and (b) 0 based on those predictions, use 063 DC Electrical Distribution procedures to correct, control, or 3.1 90 2

mitigate the consequences of those malfunctions or operations: Loss of ventilation during battery charging.

2.2.40: Ability to apply Technical 076 Service Water X Specifications for a system. 4.7 89 K/A Category Point Totals: 3 2 Group Point Total: 5

ES-401 12 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

K K K K K K A A A A System # / Name G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.2.22: Knowledge of limiting conditions 014 Rod Position Indication X for operations and safety limits. 4.7 91 Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) based on those predictions, 028 Hydrogen Recombiner 0 use procedures to correct, control or mitigate the consequences of those 3.9 92 and Purge Control 2 malfunctions or operations: LOCA condition and related concern over hydrogen.

Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on 0 those predictions, use procedures to 068 Liquid Radwaste 3.3 93 4 correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation.

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

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Prairie Island Nuclear Generating Plant Date of Exam: June 10, 2016 Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of facility requirements for controlling 2.1.13 vital/controlled access. 2.5 66 2.1.32 Ability to explain and apply system limits and precautions. 3.8 67 Knowledge of procedures and limitations involved in core

1. Conduct of 2.1.36 alterations. 3.0 68 Operations Ability to make accurate, clear, and concise logs, records, 2.1.18 status boards, and reports. 3.8 94 2.1.35 Knowledge of fuel handling responsibilities of SROs. 3.9 95 Subtotal 3 2 Ability to perform pre-startup procedures for the facility, 2.2.1 including operating those controls associated with plant 4.5 69 equipment that could affect reactivity.

2.2.12 Knowledge of surveillance procedures. 3.7 70 Knowledge of conditions and limitations in the facility

2. Equipment 2.2.38 license. 3.6 71 Control Knowledge of the process for managing maintenance 2.2.18 activities during shutdown operations, such as risk 3.9 96 assessments, work prioritization, etc.

Knowledge of the bases in Technical Specifications for 2.2.25 limiting conditions for operations and safety limits. 4.2 97 Subtotal 3 2 2.3.11 Ability to control radiation releases. 3.8 72 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation

3. Radiation 2.3.13 monitor alarms, containment entry requirements, fuel 3.8 98 Control handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 1 1 2.4.18 Knowledge of the specific bases for EOPs. 3.3 73 2.4.29 Knowledge of the emergency plan. 3.1 74 Knowledge of RO tasks performed outside the main

4. Emergency 2.4.34 control room during an emergency and the resultant 4.2 75 Procedures / operational effects.

Plan Knowledge of the emergency plan.

2.4.29 4.4 99 Knowledge of the emergency action level thresholds and 2.4.41 classifications. 4.6 100 Subtotal 3 2 Tier 3 Point Total 10 7